10.1. SCALE Cross Section Libraries

J. M. Brown, A. Holcomb, D. Wiarda, C. Celik, K. S. Kim, M. L. Williams, M. E. Dunn, B. T. Rearden

ABSTRACT

The cross section data libraries available in the SCALE code system are briefly described in this section. All libraries were processed from ENDF/B-VII.1 and -VIII.0 evaluated data files using the AMPX code system. Continuous-energy libraries as well as several multigroup libraries for a variety of applications are included in SCALE. Several fine-group and broad-group structures are available so that a user may select the nuclear data library based on considerations of application, accuracy, and execution time.

ACKNOWLEDGMENTS

We would like to acknowledge all those who participated in developing and implementing the SCALE cross section libraries for their assistance in preparing previous versions of this document. Special thanks go to S. Goluoglu, N. M. Greene, and L. M. Petrie for their contributions to SCALE data processing efforts, and to C. R. Daily and W. J. Marshall for their extensive validation testing of the libraries described here.

10.1.1. Introduction

SCALE includes both multigroup (MG) and pointwise continuous energy (CE) nuclear data libraries, which were processed using the AMPX code system [XSLibWWCD15b]. Libraries are available for neutron and for coupled neutron-photon transport calculations. The CE libraries are used for Monte Carlo calculations with CE-KENO (criticality) and CE-Monaco (shielding), and are also used by the pointwise (PW) discrete ordinates code CENTRM to obtain PW flux spectra for computing self-shielded MG cross sections. The MG libraries are used in the MG-KENO and MG-Monaco Monte Carlo codes, and in the deterministic transport codes XSDRNPM, NEWT, and DENOVO. All cross section libraries in SCALE 6.3 and later versions are based strictly on ENDF/B-VII.1 [XSLibCHO+11] and ENDF/B-VIII.0 [XSLibDAB18], while earlier SCALE releases included libraries processed from ENDF/B-VI.8, V, and IV. The ENDF/B-VII.1 CE and MG libraries include 423 nuclides shown in Table 10.1.1, and the ENDF/B-VIII.0 CE and MG libraries contain data for 556 nuclides (Note that while ENDF/B-VIII.0 contains data for neutron-as-a-target, this data is not useful for SCALE calculations and is thus the processed data is not released with SCALE.). ENDF/B-VII.1 does not have evaluated data for several isotopes in the SCALE Standard Composition Data, which are listed in Table 10.1.2. If one of these isotopes is explicitly requested or if the natural element containing the isotope is requested in the SCALE input, a warning message is written saying that the nuclide is being omitted from the calculations. The most commonly encountered example of this is O-18 which has an abundance of approximately 0.2% in elemental oxygen (Note that O-18 data are available in ENDF/B-VIII.0, but not ENDF/B-VII.1.).

The ENDF/B-VII.1 libraries include 21 thermal-scattering moderators for which bound-scattering kernels [e.g., S(\(\alpha\),\(\beta\))] are provided as given in Table 10.1.4. This table also lists the temperatures available in MG and CE libraries for the materials with bound kernels. The ENDF/B-VIII.0 libraries include 34 thermal-scattering moderators for which bound-scattering kernels are provided; of particular interest are updated thermal scatter laws for HinH2O and multiple graphite compositions, these are given in Table 10.1.3. The thermal scattering kernels for all other materials are based on the free-gas kernel. On the MG libraries, these nuclides have 2D scattering matrices processed from the free-gas kernel evaluated at the temperatures of 293 K, 565 K, 600 K, 900 K, 1200 K, 2000 K, and 2400 K. SCALE 6.3 includes routines that automatically interpolate the CE cross section data, as well as thermal scattering kernels to any arbitrary temperature for Monte Carlo calculations [XSLibHCML16]. Analogous procedures are available for MG data. The CE libraries do not include free gas kernel data because the transport codes internally evaluate the free gas scattering information at the specified temperature.

For each reaction and nuclide, CE data were processed from ENDF/B in the manner described in Sect. 10.1.2.6. The CE data were further processed into several generic MG libraries focused on different applications. CE data are stored as individual files for each nuclide, and an associated cross section directory file contains the names of the individual files. Furthermore, the MG libraries each contain data for all nuclides. AMPX master libraries are very general and contain essentially all reaction data available in ENDF/B, as well as several specialized cross sections used in SCALE. The master libraries also include Bondarenko shielding factors tabulated as a function of background cross section and temperature for all nuclides and groups, and the master libraries may contain intermediate resonance parameters for self-shielding. A much improved methodology in AMPX was used to process more accurate shielding factors for the most important resonance absorbers.1

The CE and MG libraries available in SCALE 6.3 are given in Table 10.1.5, which also lists the main source of data for each library. The desired MG or CE library for a computation is typically selected by specifying the appropriate mnemonic name from Table 10.1.5. The CE library mnemonic corresponds to the actual name of the cross section directory file, and the MG mnemonic is an alias for the file containing the actual master library, shown in the third column of Table 10.1.5. SCALE control modules recognize the mnemonics in the first column, or the standard MG library name in the third columns of the table. Users also may supply their own MG library by specifying the file name as the library name in the control module input (only lower case alphanumeric characters are allowed in the filename, and the filename must be eight characters or less in length). The library must be an AMPX master library and must be located in the SCALE data directory or the temporary working directory where the problem is run.

The CE data libraries do not require additional processing prior to their use in transport computations. However, the MG libraries distributed with the SCALE code system contain problem-independent cross sections processed with generic weighting functions appropriate for a specified type of application (e.g., criticality safety, shielding, etc.). These data must be further processed into problem-dependent libraries by performing resonance self-shielding and other modifications. This is done by the XSProc module during the execution of a SCALE control sequence prior to executing a transport solver.

For data in Table 10.1.1, note that: (a) Yield data are only available in coupled MG libraries and in the CE libraries, (b) narrow and/or intermediate resonance factors are only available for MG libraries, and (c) incident gamma cross sections are only available for coupled MG libraries (a separate incident gamma CE library is available).

Table 10.1.1 Nuclides in CE and MG ENDF/B-VII.1 and -VIII.0 libraries.

SCALE-ID

Name

Gamma Prod.

Bond. Factors

Photo-atomic Eval.

ENDF/B Lib.

8001001

hfreegas

yes

yes

h

e80, e71

8001002

dfreegas

no

yes

h

e80, e71

1003

h-3

no

yes

h

e80, e71

2003

he-3

no

yes

he

e80, e71

2004

he-4

no

yes

he

e80, e71

3006

li-6

no

yes

li

e80, e71

3007

li-7

no

yes

li

e80, e71

4007

be-7

no

yes

be

e80, e71

4009

be-9

yes

yes

be

e80, e71

5010

b-10

yes

yes

b

e80, e71

5011

b-11

yes

yes

b

e80, e71

6012

c-12

yes

yes

c

e80

6013

c-13

no

yes

c

e80

7014

n-14

yes

yes

n

e80, e71

7015

n-15

no

yes

n

e80, e71

8016

o-16

yes

yes

o

e80, e71

8017

o-17

no

yes

o

e80, e71

8018

o-18

no

yes

o

e80

9019

f-19

yes

yes

f

e80, e71

10020

ne-20

yes

yes

ne

e80

10021

ne-21

yes

yes

ne

e80

10022

ne-22

yes

yes

ne

e80

11022

na-22

no

yes

na

e80, e71

11023

na-23

no

yes

na

e80, e71

12024

mg-24

no

yes

mg

e80, e71

12025

mg-25

no

yes

mg

e80, e71

12026

mg-26

no

yes

mg

e80, e71

1013026

al-26m1

yes

yes

al

e80

13027

al-27

yes

yes

al

e80, e71

14028

si-28

yes

yes

si

e80, e71

14029

si-29

yes

yes

si

e80, e71

14030

si-30

yes

yes

si

e80, e71

14031

si-31

yes

yes

si

e80

14032

si-32

yes

yes

si

e80

15031

p-31

yes

yes

p

e80, e71

16032

s-32

no

yes

s

e80, e71

16033

s-33

no

yes

s

e80, e71

16034

s-34

no

yes

s

e80, e71

16035

s-35

yes

yes

s

e80

16036

s-36

no

yes

s

e80, e71

17035

cl-35

yes

yes

cl

e80, e71

17036

cl-36

yes

yes

cl

e80

17037

cl-37

yes

yes

cl

e80, e71

18036

ar-36

no

yes

ar

e80, e71

18037

ar-37

yes

yes

ar

e80

18038

ar-38

no

yes

ar

e80, e71

18039

ar-39

yes

yes

ar

e80

18040

ar-40

yes

yes

ar

e80, e71

18041

ar-41

yes

yes

ar

e80

19039

k-39

no

yes

k

e80, e71

19040

k-40

no

yes

k

e80, e71

19041

k-41

no

yes

k

e80, e71

20040

ca-40

yes

yes

ca

e80, e71

20041

ca-41

yes

yes

ca

e80

20042

ca-42

yes

yes

ca

e80, e71

20043

ca-43

yes

yes

ca

e80, e71

20044

ca-44

yes

yes

ca

e80, e71

20045

ca-45

yes

yes

ca

e80

20046

ca-46

yes

yes

ca

e80, e71

20047

ca-47

yes

yes

ca

e80

20048

ca-48

yes

yes

ca

e80, e71

21045

sc-45

no

yes

sc

e80, e71

22046

ti-46

yes

yes

ti

e80, e71

22047

ti-47

yes

yes

ti

e80, e71

22048

ti-48

yes

yes

ti

e80, e71

22049

ti-49

yes

yes

ti

e80, e71

22050

ti-50

yes

yes

ti

e80, e71

23049

v-49

yes

yes

v

e80

23050

v-50

yes

yes

v

e80, e71

23051

v-51

yes

yes

v

e80, e71

24050

cr-50

yes

yes

cr

e80, e71

24051

cr-51

yes

yes

cr

e80

24052

cr-52

yes

yes

cr

e80, e71

24053

cr-53

yes

yes

cr

e80, e71

24054

cr-54

yes

yes

cr

e80, e71

25054

mn-54

yes

yes

mn

e80

25055

mn-55

yes

yes

mn

e80, e71

26054

fe-54

yes

yes

fe

e80, e71

26055

fe-55

yes

yes

fe

e80

26056

fe-56

yes

yes

fe

e80, e71

26057

fe-57

yes

yes

fe

e80, e71

26058

fe-58

yes

yes

fe

e80, e71

27058

co-58

yes

yes

co

e80, e71

1027058

co-58m1

no

yes

co

e80, e71

27059

co-59

yes

yes

co

e80, e71

28058

ni-58

yes

yes

ni

e80, e71

28059

ni-59

yes

yes

ni

e80, e71

28060

ni-60

yes

yes

ni

e80, e71

28061

ni-61

yes

yes

ni

e80, e71

28062

ni-62

yes

yes

ni

e80, e71

28063

ni-63

yes

yes

ni

e80

28064

ni-64

yes

yes

ni

e80, e71

29063

cu-63

yes

yes

cu

e80, e71

29064

cu-64

yes

yes

cu

e80

29065

cu-65

yes

yes

cu

e80, e71

30064

zn-64

yes

yes

zn

e80, e71

30065

zn-65

yes

yes

zn

e80, e71

30066

zn-66

yes

yes

zn

e80, e71

30067

zn-67

yes

yes

zn

e80, e71

30068

zn-68

yes

yes

zn

e80, e71

30069

zn-69

yes

yes

zn

e80

30070

zn-70

yes

yes

zn

e80, e71

31069

ga-69

no

yes

ga

e80, e71

31070

ga-70

yes

yes

ga

e80

31071

ga-71

no

yes

ga

e80, e71

32070

ge-70

yes

yes

ge

e80, e71

32071

ge-71

yes

yes

ge

e80

32072

ge-72

yes

yes

ge

e80, e71

32073

ge-73

yes

yes

ge

e80, e71

32074

ge-74

yes

yes

ge

e80, e71

32075

ge-75

yes

yes

ge

e80

32076

ge-76

yes

yes

ge

e80, e71

33073

as-73

yes

yes

as

e80

33074

as-74

yes

yes

as

e80, e71

33075

as-75

yes

yes

as

e80, e71

34074

se-74

no

yes

se

e80, e71

34075

se-75

yes

yes

se

e80

34076

se-76

no

yes

se

e80, e71

34077

se-77

no

yes

se

e80, e71

34078

se-78

no

yes

se

e80, e71

34079

se-79

no

yes

se

e80, e71

34080

se-80

no

yes

se

e80, e71

34081

se-81

yes

yes

se

e80

34082

se-82

no

yes

se

e80, e71

35079

br-79

no

yes

br

e80, e71

35080

br-80

yes

yes

br

e80

35081

br-81

no

yes

br

e80, e71

36078

kr-78

yes

yes

kr

e80, e71

36079

kr-79

yes

yes

kr

e80

36080

kr-80

no

yes

kr

e80, e71

36081

kr-81

yes

yes

kr

e80

36082

kr-82

no

yes

kr

e80, e71

36083

kr-83

no

yes

kr

e80, e71

36084

kr-84

no

yes

kr

e80, e71

36085

kr-85

yes

yes

kr

e80, e71

36086

kr-86

no

yes

kr

e80, e71

37085

rb-85

no

yes

rb

e80, e71

37086

rb-86

yes

yes

rb

e80, e71

37087

rb-87

no

yes

rb

e80, e71

38084

sr-84

yes

yes

sr

e80, e71

38085

sr-85

yes

yes

sr

e80

38086

sr-86

no

yes

sr

e80, e71

38087

sr-87

no

yes

sr

e80, e71

38088

sr-88

no

yes

sr

e80, e71

38089

sr-89

no

yes

sr

e80, e71

38090

sr-90

no

yes

sr

e80, e71

39089

y-89

yes

yes

y

e80, e71

39090

y-90

yes

yes

y

e80, e71

39091

y-91

no

yes

y

e80, e71

40090

zr-90

yes

yes

zr

e80, e71

40091

zr-91

yes

yes

zr

e80, e71

40092

zr-92

yes

yes

zr

e80, e71

40093

zr-93

yes

yes

zr

e80, e71

40094

zr-94

yes

yes

zr

e80, e71

40095

zr-95

yes

yes

zr

e80, e71

40096

zr-96

yes

yes

zr

e80, e71

41093

nb-93

yes

yes

nb

e80, e71

41094

nb-94

no

yes

nb

e80, e71

41095

nb-95

no

yes

nb

e80, e71

42092

mo-92

no

yes

mo

e80, e71

42093

mo-93

yes

yes

mo

e80

42094

mo-94

no

yes

mo

e80, e71

42095

mo-95

yes

yes

mo

e80, e71

42096

mo-96

no

yes

mo

e80, e71

42097

mo-97

no

yes

mo

e80, e71

42098

mo-98

no

yes

mo

e80, e71

42099

mo-99

no

yes

mo

e80, e71

42100

mo-100

no

yes

mo

e80, e71

43098

tc-98

yes

yes

tc

e80

43099

tc-99

yes

yes

tc

e80, e71

44096

ru-96

no

yes

ru

e80, e71

44097

ru-97

yes

yes

ru

e80

44098

ru-98

no

yes

ru

e80, e71

44099

ru-99

no

yes

ru

e80, e71

44100

ru-100

no

yes

ru

e80, e71

44101

ru-101

yes

yes

ru

e80, e71

44102

ru-102

no

yes

ru

e80, e71

44103

ru-103

no

yes

ru

e80, e71

44104

ru-104

no

yes

ru

e80, e71

44105

ru-105

no

yes

ru

e80, e71

44106

ru-106

no

yes

ru

e80, e71

45103

rh-103

yes

yes

rh

e80, e71

45104

rh-104

yes

yes

rh

e80

45105

rh-105

no

yes

rh

e80, e71

46102

pd-102

yes

yes

pd

e80, e71

46103

pd-103

yes

yes

pd

e80

46104

pd-104

yes

yes

pd

e80, e71

46105

pd-105

yes

yes

pd

e80, e71

46106

pd-106

yes

yes

pd

e80, e71

46107

pd-107

no

yes

pd

e80, e71

46108

pd-108

yes

yes

pd

e80, e71

46109

pd-109

yes

yes

pd

e80

46110

pd-110

yes

yes

pd

e80, e71

47107

ag-107

no

yes

ag

e80, e71

47108

ag-108

yes

yes

ag

e80

47109

ag-109

yes

yes

ag

e80, e71

1047110

ag-110m1

no

yes

ag

e80, e71

47111

ag-111

yes

yes

ag

e80, e71

47112

ag-112

yes

yes

ag

e80

47113

ag-113

yes

yes

ag

e80

47114

ag-114

yes

yes

ag

e80

47115

ag-115

yes

yes

ag

e80

47116

ag-116

yes

yes

ag

e80

47117

ag-117

yes

yes

ag

e80

1047118

ag-118m1

yes

yes

ag

e80

48106

cd-106

no

yes

cd

e80, e71

48107

cd-107

yes

yes

cd

e80

48108

cd-108

no

yes

cd

e80, e71

48109

cd-109

yes

yes

cd

e80

48110

cd-110

no

yes

cd

e80, e71

48111

cd-111

no

yes

cd

e80, e71

48112

cd-112

no

yes

cd

e80, e71

48113

cd-113

no

yes

cd

e80, e71

48114

cd-114

no

yes

cd

e80, e71

1048115

cd-115m1

yes

yes

cd

e80, e71

48116

cd-116

no

yes

cd

e80, e71

49113

in-113

no

yes

in

e80, e71

49114

in-114

yes

yes

in

e80

49115

in-115

no

yes

in

e80, e71

50112

sn-112

no

yes

sn

e80, e71

50113

sn-113

yes

yes

sn

e80, e71

50114

sn-114

no

yes

sn

e80, e71

50115

sn-115

no

yes

sn

e80, e71

50116

sn-116

no

yes

sn

e80, e71

50117

sn-117

no

yes

sn

e80, e71

50118

sn-118

no

yes

sn

e80, e71

50119

sn-119

no

yes

sn

e80, e71

50120

sn-120

yes

yes

sn

e80, e71

1050121

sn-121m1

yes

yes

sn

e80

50122

sn-122

no

yes

sn

e80, e71

50123

sn-123

no

yes

sn

e80, e71

50124

sn-124

no

yes

sn

e80, e71

50125

sn-125

yes

yes

sn

e80, e71

50126

sn-126

no

yes

sn

e80, e71

51121

sb-121

no

yes

sb

e80, e71

51122

sb-122

yes

yes

sb

e80

51123

sb-123

no

yes

sb

e80, e71

51124

sb-124

no

yes

sb

e80, e71

51125

sb-125

no

yes

sb

e80, e71

51126

sb-126

yes

yes

sb

e80, e71

52120

te-120

no

yes

te

e80, e71

52121

te-121

yes

yes

te

e80

1052121

te-121m1

yes

yes

te

e80

52122

te-122

no

yes

te

e80, e71

52123

te-123

no

yes

te

e80, e71

52124

te-124

no

yes

te

e80, e71

52125

te-125

no

yes

te

e80, e71

52126

te-126

no

yes

te

e80, e71

1052127

te-127m1

no

yes

te

e80, e71

52128

te-128

no

yes

te

e80, e71

1052129

te-129m1

no

yes

te

e80, e71

52130

te-130

no

yes

te

e80, e71

52131

te-131

yes

yes

te

e80

1052131

te-131m1

yes

yes

te

e80

52132

te-132

yes

yes

te

e80, e71

53127

i-127

yes

yes

i

e80, e71

53128

i-128

yes

yes

i

e80

53129

i-129

no

yes

i

e80, e71

53130

i-130

yes

yes

i

e80, e71

53131

i-131

no

yes

i

e80, e71

53132

i-132

yes

yes

i

e80

1053132

i-132m1

yes

yes

i

e80

53133

i-133

yes

yes

i

e80

53134

i-134

yes

yes

i

e80

53135

i-135

no

yes

i

e80, e71

54123

xe-123

no

yes

xe

e80, e71

54124

xe-124

yes

yes

xe

e80, e71

54125

xe-125

yes

yes

xe

e80

54126

xe-126

no

yes

xe

e80, e71

54127

xe-127

yes

yes

xe

e80

54128

xe-128

no

yes

xe

e80, e71

54129

xe-129

no

yes

xe

e80, e71

54130

xe-130

no

yes

xe

e80, e71

54131

xe-131

yes

yes

xe

e80, e71

54132

xe-132

no

yes

xe

e80, e71

54133

xe-133

no

yes

xe

e80, e71

54134

xe-134

no

yes

xe

e80, e71

54135

xe-135

no

yes

xe

e80, e71

54136

xe-136

no

yes

xe

e80, e71

55133

cs-133

yes

yes

cs

e80, e71

55134

cs-134

no

yes

cs

e80, e71

55135

cs-135

no

yes

cs

e80, e71

55136

cs-136

no

yes

cs

e80, e71

55137

cs-137

no

yes

cs

e80, e71

56130

ba-130

no

yes

ba

e80, e71

56131

ba-131

yes

yes

ba

e80

56132

ba-132

no

yes

ba

e80, e71

56133

ba-133

yes

yes

ba

e80, e71

56134

ba-134

no

yes

ba

e80, e71

56135

ba-135

no

yes

ba

e80, e71

56136

ba-136

no

yes

ba

e80, e71

56137

ba-137

no

yes

ba

e80, e71

56138

ba-138

no

yes

ba

e80, e71

56139

ba-139

yes

yes

ba

e80

56140

ba-140

no

yes

ba

e80, e71

57138

la-138

no

yes

la

e80, e71

57139

la-139

no

yes

la

e80, e71

57140

la-140

yes

yes

la

e80, e71

58136

ce-136

yes

yes

ce

e80, e71

58137

ce-137

yes

yes

ce

e80

1058137

ce-137m1

yes

yes

ce

e80

58138

ce-138

yes

yes

ce

e80, e71

58139

ce-139

yes

yes

ce

e80, e71

58140

ce-140

no

yes

ce

e80, e71

58141

ce-141

no

yes

ce

e80, e71

58142

ce-142

no

yes

ce

e80, e71

58143

ce-143

yes

yes

ce

e80, e71

58144

ce-144

no

yes

ce

e80, e71

59141

pr-141

yes

yes

pr

e80, e71

59142

pr-142

yes

yes

pr

e80, e71

59143

pr-143

no

yes

pr

e80, e71

60142

nd-142

yes

yes

nd

e80, e71

60143

nd-143

yes

yes

nd

e80, e71

60144

nd-144

yes

yes

nd

e80, e71

60145

nd-145

yes

yes

nd

e80, e71

60146

nd-146

yes

yes

nd

e80, e71

60147

nd-147

yes

yes

nd

e80, e71

60148

nd-148

yes

yes

nd

e80, e71

60149

nd-149

yes

yes

nd

e80

60150

nd-150

yes

yes

nd

e80, e71

61143

pm-143

yes

yes

pm

e80

61144

pm-144

yes

yes

pm

e80

61145

pm-145

yes

yes

pm

e80

61146

pm-146

yes

yes

pm

e80

61147

pm-147

no

yes

pm

e80, e71

61148

pm-148

no

yes

pm

e80, e71

1061148

pm-148m1

no

yes

pm

e80, e71

61149

pm-149

no

yes

pm

e80, e71

61150

pm-150

yes

yes

pm

e80

61151

pm-151

yes

yes

pm

e80, e71

62144

sm-144

yes

yes

sm

e80, e71

62145

sm-145

yes

yes

sm

e80

62146

sm-146

yes

yes

sm

e80

62147

sm-147

yes

yes

sm

e80, e71

62148

sm-148

yes

yes

sm

e80, e71

62149

sm-149

yes

yes

sm

e80, e71

62150

sm-150

yes

yes

sm

e80, e71

62151

sm-151

yes

yes

sm

e80, e71

62152

sm-152

yes

yes

sm

e80, e71

62153

sm-153

yes

yes

sm

e80, e71

62154

sm-154

yes

yes

sm

e80, e71

63151

eu-151

no

yes

eu

e80, e71

63152

eu-152

no

yes

eu

e80, e71

63153

eu-153

yes

yes

eu

e80, e71

63154

eu-154

no

yes

eu

e80, e71

63155

eu-155

no

yes

eu

e80, e71

63156

eu-156

no

yes

eu

e80, e71

63157

eu-157

yes

yes

eu

e80, e71

64152

gd-152

yes

yes

gd

e80, e71

64153

gd-153

yes

yes

gd

e80, e71

64154

gd-154

yes

yes

gd

e80, e71

64155

gd-155

yes

yes

gd

e80, e71

64156

gd-156

yes

yes

gd

e80, e71

64157

gd-157

yes

yes

gd

e80, e71

64158

gd-158

yes

yes

gd

e80, e71

64159

gd-159

yes

yes

gd

e80

64160

gd-160

yes

yes

gd

e80, e71

65158

tb-158

yes

yes

tb

e80

65159

tb-159

no

yes

tb

e80, e71

65160

tb-160

yes

yes

tb

e80, e71

65161

tb-161

yes

yes

tb

e80

66154

dy-154

yes

yes

dy

e80

66155

dy-155

yes

yes

dy

e80

66156

dy-156

yes

yes

dy

e80, e71

66157

dy-157

yes

yes

dy

e80

66158

dy-158

yes

yes

dy

e80, e71

66159

dy-159

yes

yes

dy

e80

66160

dy-160

yes

yes

dy

e80, e71

66161

dy-161

yes

yes

dy

e80, e71

66162

dy-162

yes

yes

dy

e80, e71

66163

dy-163

yes

yes

dy

e80, e71

66164

dy-164

yes

yes

dy

e80, e71

67165

ho-165

no

yes

ho

e80, e71

1067166

ho-166m1

yes

yes

ho

e80, e71

68162

er-162

no

yes

er

e80, e71

68163

er-163

yes

yes

er

e80

68164

er-164

no

yes

er

e80, e71

68165

er-165

yes

yes

er

e80

68166

er-166

no

yes

er

e80, e71

68167

er-167

no

yes

er

e80, e71

68168

er-168

no

yes

er

e80, e71

68169

er-169

yes

yes

er

e80

68170

er-170

no

yes

er

e80, e71

69168

tm-168

yes

yes

tm

e80, e71

69169

tm-169

yes

yes

tm

e80, e71

69170

tm-170

yes

yes

tm

e80, e71

69171

tm-171

yes

yes

tm

e80

70168

yb-168

no

yes

yb

e80

70169

yb-169

yes

yes

yb

e80

70170

yb-170

no

yes

yb

e80

70171

yb-171

no

yes

yb

e80

70172

yb-172

no

yes

yb

e80

70173

yb-173

no

yes

yb

e80

70174

yb-174

no

yes

yb

e80

70175

yb-175

yes

yes

yb

e80

70176

yb-176

no

yes

yb

e80

71175

lu-175

no

yes

lu

e80, e71

71176

lu-176

no

yes

lu

e80, e71

72174

hf-174

yes

yes

hf

e80, e71

72175

hf-175

yes

yes

hf

e80

72176

hf-176

yes

yes

hf

e80, e71

72177

hf-177

yes

yes

hf

e80, e71

72178

hf-178

yes

yes

hf

e80, e71

72179

hf-179

yes

yes

hf

e80, e71

72180

hf-180

yes

yes

hf

e80, e71

72181

hf-181

no

yes

hf

e80

72182

hf-182

no

yes

hf

e80

73180

ta-180

no

yes

ta

e80, e71

73181

ta-181

no

yes

ta

e80, e71

73182

ta-182

no

yes

ta

e80, e71

74180

w-180

yes

yes

w

e80, e71

74181

w-181

yes

yes

w

e80

74182

w-182

yes

yes

w

e80, e71

74183

w-183

yes

yes

w

e80, e71

74184

w-184

yes

yes

w

e80, e71

74185

w-185

yes

yes

w

e80

74186

w-186

yes

yes

w

e80, e71

75185

re-185

no

yes

re

e80, e71

1075186

re-186m1

yes

yes

re

e80

75187

re-187

no

yes

re

e80, e71

76184

os-184

yes

yes

os

e80

76185

os-185

yes

yes

os

e80

76186

os-186

yes

yes

os

e80

76187

os-187

yes

yes

os

e80

76188

os-188

yes

yes

os

e80

76189

os-189

yes

yes

os

e80

76190

os-190

yes

yes

os

e80

76191

os-191

yes

yes

os

e80

76192

os-192

yes

yes

os

e80

77191

ir-191

yes

yes

ir

e80, e71

77192

ir-192

yes

yes

ir

e80

77193

ir-193

yes

yes

ir

e80, e71

1077194

ir-194m1

yes

yes

ir

e80

78190

pt-190

yes

yes

pt

e80

78191

pt-191

yes

yes

pt

e80

78192

pt-192

yes

yes

pt

e80

78193

pt-193

yes

yes

pt

e80

78194

pt-194

yes

yes

pt

e80

78195

pt-195

yes

yes

pt

e80

78196

pt-196

yes

yes

pt

e80

78197

pt-197

yes

yes

pt

e80

78198

pt-198

yes

yes

pt

e80

79197

au-197

no

yes

au

e80, e71

80196

hg-196

yes

yes

hg

e80, e71

80197

hg-197

yes

yes

hg

e80

1080197

hg-197m1

yes

yes

hg

e80

80198

hg-198

yes

yes

hg

e80, e71

80199

hg-199

yes

yes

hg

e80, e71

80200

hg-200

yes

yes

hg

e80, e71

80201

hg-201

yes

yes

hg

e80, e71

80202

hg-202

yes

yes

hg

e80, e71

80203

hg-203

yes

yes

hg

e80

80204

hg-204

yes

yes

hg

e80, e71

81203

tl-203

yes

yes

tl

e80, e71

81204

tl-204

yes

yes

tl

e80

81205

tl-205

yes

yes

tl

e80, e71

82204

pb-204

yes

yes

pb

e80, e71

82205

pb-205

yes

yes

pb

e80

82206

pb-206

yes

yes

pb

e80, e71

82207

pb-207

yes

yes

pb

e80, e71

82208

pb-208

yes

yes

pb

e80, e71

83209

bi-209

yes

yes

bi

e80, e71

1083210

bi-210m1

yes

yes

bi

e80

84208

po-208

yes

yes

po

e80

84209

po-209

yes

yes

po

e80

84210

po-210

yes

yes

po

e80

88223

ra-223

no

yes

ra

e80, e71

88224

ra-224

no

yes

ra

e80, e71

88225

ra-225

no

yes

ra

e80, e71

88226

ra-226

no

yes

ra

e80, e71

89225

ac-225

yes

yes

ac

e80, e71

89226

ac-226

yes

yes

ac

e80, e71

89227

ac-227

yes

yes

ac

e80, e71

90227

th-227

yes

yes

th

e80, e71

90228

th-228

yes

yes

th

e80, e71

90229

th-229

yes

yes

th

e80, e71

90230

th-230

yes

yes

th

e80, e71

90231

th-231

yes

yes

th

e80, e71

90232

th-232

yes

yes

th

e80, e71

90233

th-233

yes

yes

th

e80, e71

90234

th-234

yes

yes

th

e80, e71

91229

pa-229

yes

yes

pa

e80, e71

91230

pa-230

yes

yes

pa

e80, e71

91231

pa-231

yes

yes

pa

e80, e71

91232

pa-232

yes

yes

pa

e80, e71

91233

pa-233

yes

yes

pa

e80, e71

92230

u-230

yes

yes

u

e80, e71

92231

u-231

yes

yes

u

e80, e71

92232

u-232

yes

yes

u

e80, e71

92233

u-233

yes

yes

u

e80, e71

92234

u-234

no

yes

u

e80, e71

92235

u-235

yes

yes

u

e80, e71

92236

u-236

no

yes

u

e80, e71

92237

u-237

no

yes

u

e80, e71

92238

u-238

yes

yes

u

e80, e71

92239

u-239

no

yes

u

e80, e71

92240

u-240

no

yes

u

e80, e71

92241

u-241

no

yes

u

e80, e71

93234

np-234

yes

yes

np

e80, e71

93235

np-235

yes

yes

np

e80, e71

93236

np-236

yes

yes

np

e80, e71

1093236

np-236m1

yes

yes

np

e80

93237

np-237

no

yes

np

e80, e71

93238

np-238

yes

yes

np

e80, e71

93239

np-239

yes

yes

np

e80, e71

94236

pu-236

yes

yes

pu

e80, e71

94237

pu-237

yes

yes

pu

e80, e71

94238

pu-238

no

yes

pu

e80, e71

94239

pu-239

yes

yes

pu

e80, e71

94240

pu-240

no

yes

pu

e80, e71

94241

pu-241

no

yes

pu

e80, e71

94242

pu-242

yes

yes

pu

e80, e71

94243

pu-243

no

yes

pu

e80, e71

94244

pu-244

yes

yes

pu

e80, e71

94245

pu-245

yes

yes

pu

e80

94246

pu-246

yes

yes

pu

e80, e71

95240

am-240

yes

yes

am

e80, e71

95241

am-241

yes

yes

am

e80, e71

95242

am-242

no

yes

am

e80, e71

1095242

am-242m1

no

yes

am

e80, e71

95243

am-243

no

yes

am

e80, e71

95244

am-244

no

yes

am

e80, e71

1095244

am-244m1

no

yes

am

e80, e71

96240

cm-240

yes

yes

cm

e80, e71

96241

cm-241

yes

yes

cm

e80, e71

96242

cm-242

yes

yes

cm

e80, e71

96243

cm-243

yes

yes

cm

e80, e71

96244

cm-244

yes

yes

cm

e80, e71

96245

cm-245

yes

yes

cm

e80, e71

96246

cm-246

yes

yes

cm

e80, e71

96247

cm-247

yes

yes

cm

e80, e71

96248

cm-248

yes

yes

cm

e80, e71

96249

cm-249

yes

yes

cm

e80, e71

96250

cm-250

yes

yes

cm

e80, e71

97245

bk-245

yes

yes

bk

e80, e71

97246

bk-246

yes

yes

bk

e80, e71

97247

bk-247

yes

yes

bk

e80, e71

97248

bk-248

yes

yes

bk

e80, e71

97249

bk-249

yes

yes

bk

e80, e71

97250

bk-250

yes

yes

bk

e80, e71

98246

cf-246

yes

yes

cf

e80, e71

98247

cf-247

yes

yes

cf

e80

98248

cf-248

yes

yes

cf

e80, e71

98249

cf-249

yes

yes

cf

e80, e71

98250

cf-250

yes

yes

cf

e80, e71

98251

cf-251

yes

yes

cf

e80, e71

98252

cf-252

yes

yes

cf

e80, e71

98253

cf-253

yes

yes

cf

e80, e71

98254

cf-254

yes

yes

cf

e80, e71

99251

es-251

yes

yes

es

e80, e71

99252

es-252

yes

yes

es

e80, e71

99253

es-253

yes

yes

es

e80, e71

99254

es-254

yes

yes

es

e80, e71

1099254

es-254m1

yes

yes

es

e80, e71

99255

es-255

yes

yes

es

e80, e71

100255

fm-255

yes

yes

fm

e80, e71

1013027

albound

yes

yes

al

e80, e71

1026056

fe56-bound

yes

yes

fe

e80, e71

3004009

bebound

yes

yes

be

e80, e71

5004009

be-beo

yes

yes

be

e80, e71

6001001

h-benzene

yes

yes

h

e80, e71

5006012

c12-benzene

yes

yes

h

e80

5006013

c13-benzene

yes

yes

h

e80

5106012

c12_3c_sic

yes

yes

c

e80

5106013

c13_3c_sic

yes

yes

c

e80

3006012

c12-graphite

yes

yes

c

e80

3006013

c13-graphite

yes

yes

c

e80

1002

h-2

yes

yes

h

e80, e71

9101001

h-lucite

yes

yes

h

e80

9001001

h-poly

yes

yes

h

e80, e71

1001

h-1

yes

yes

h

e80, e71

1101001

h-ice_ih

yes

yes

h

e80

1201001

h-yh2

yes

yes

h

e80

7001001

h-zrh2

yes

yes

h

e80, e71

1001001

h-liquid_ch4

yes

yes

h

e80, e71

1007014

n14-un

yes

yes

n

e80

1007015

n15-un

yes

yes

n

e80

5008016

o16-beo

yes

yes

o

e80, e71

2008016

o16-d2o

yes

yes

o

e80

1108016

o16-ice_ih

yes

yes

o

e80

1008016

o16-uo2

yes

yes

o

e80, e71

4001002

d-cryo_ortho

yes

yes

h

e80, e71

4001001

h-cryo_ortho

yes

yes

h

e80, e71

5001002

d-cryo_para

yes

yes

h

e80, e71

5001001

h-cryo_para

yes

yes

h

e80, e71

3106012

c12-10_graph

yes

yes

c

e80

3106013

c13-10_graph

yes

yes

c

e80

3206012

c12-30_graph

yes

yes

c

e80

3206013

c13-30_graph

yes

yes

c

e80

2001001

h-solid_ch4

yes

yes

h

e80, e71

2014028

si28-3c_sic

yes

yes

si

e80

2014029

si29-3c_sic

yes

yes

si

e80

2014030

si30-3c_sic

yes

yes

si

e80

1014028

si28-sio2

yes

yes

si

e80, e71

1014029

si29-sio2

yes

yes

si

e80, e71

1014030

si30-sio2

yes

yes

si

e80, e71

1018016

o16-sio2

yes

yes

si

e80

1114028

si28-sio2_b

yes

yes

si

e80

1114029

si29-sio2_b

yes

yes

si

e80

1114030

si30-sio2_b

yes

yes

si

e80

1118016

o16-sio2_b

yes

yes

si

e80

1039089

y89-yh2

yes

yes

y

e80

1039090

y90-yh2

yes

yes

y

e80

1039091

y91-yh2

yes

yes

y

e80

1040090

zr90-zr5h8

yes

yes

zr

e80, e71

1040091

zr91-zr5h8

yes

yes

zr

e80, e71

1040092

zr92-zr5h8

yes

yes

zr

e80, e71

1040093

zr93-zr5h8

yes

yes

zr

e80, e71

1040094

zr94-zr5h8

yes

yes

zr

e80, e71

1040095

zr95-zr5h8

yes

yes

zr

e80, e71

1040096

zr96-zr5h8

yes

yes

zr

e80, e71

6000

c

yes

yes

c

e71*

5006000

c-benzene

yes

yes

c

e71*

3006000

c-graphite

yes

yes

c

e71*

* natural carbon evaluation is unique to ENDF/B-VII.1, but the name can be used with ENDF/B-VIII.0 and SCALE will expand to isotopic evaluations

Table 10.1.2 Isotopes with no ENDF/B-VII.1 nuclear data.

Element

SCALE standard composition ID

Missing Isotopes

ZA numbers

% Abundance

oxygen

8000

18

8018

0.20

neon

10000

21, 22

10021, 10022

0.27, 9.25

ytterbium

70000

All(1)

(1)

osmium

76000

All(2)

(2)

platinum

78000

All(3)

(3)

tantalum

73000

180m

1073180

0.01

  1. no data for any of the 7 naturally-occurring ytterbium isotopes

  2. no data for any of the 7 naturally-occurring osmium isotopes

  3. no data for any of the 6 naturally-occurring platinum isotopes

Some notes regarding the use of TSLs in SCALE should be addressed. The naming convention for these materials is traditionally {isotope}-{material name} (e.g., C12-graphite). Similar to the isotopic nuclear data files, elemental versions of these materials can also be called that will appropriately weight the isotopes according to SCALE Standard Composition Library (e.g., si-sio2 will call all si28-sio2, si29-sio2, and si30-sio2). Some materials do not have a corresponding isotopic distribution for all of their isotopes (e.g., o-sio2). Therefore, calling o-sio2 will only pull o16-sio2 data and the o17 and o18 isotopic data (if available).

There are some exceptions to these guidelines, most notably that h-1 defaults to the H in H2O TSL file (as opposed to the H-1 isotopic nuclear data file) and h-2 defaults to the D in D2O TSL file. Additionally, some of the material names might be confusing to users, as they can be related to material science properties that are not well known outside of the material science community. The most notable example of this is 3c_sic, which is silicon carbide. Furthermore, certain materials are released with SCALE but are not recommended for use by the general practitioner. These cases are highlighted in the “Notes” column in the following table, with an explanation below the table.

Table 10.1.3 Temperatures at which thermal moderator data are available in ENDF/B-VIII.0.

ID

Name

Temperatures

Notes

1001

h-1

283.6, 293.6, 300.0, 323.6, 350.0, 373.6, 400.0, 423.6, 450.0, 473.6, 500.0, 523.6, 550.0, 573.6, 600.0, 623.6, 650.0, 800.0

1002

h-2

283.6, 293.6, 300.0, 323.6, 350.0, 373.6, 400.0, 423.6, 450.0, 473.6, 500.0, 523.6, 550.0, 573.6, 600.0, 623.6, 650.0

1001001

h-liquid_ch4

100.0

1007014

n14-un

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

Should not be used(1)

1007015

n15-un

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

Should not be used(1)

1008016

o16-uo2

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

Should not be used(1)

1013027 1014028

albound si28-sio2

20.0, 80.0, 293.6, 400.0, 600.0, 800.0 293.6, 350.0, 400.0, 500.0, 800.0

1014029

si29-sio2

293.6, 350.0, 400.0, 500.0, 800.0

1014030

si30-sio2

293.6, 350.0, 400.0, 500.0, 800.0

1018016

o16-sio2

293.6, 350.0, 400.0, 500.0, 800.0

1026056

fe56-bound

20.0, 80.0, 293.6, 400.0, 600.0, 800.0

1039089

y89-yh2

293.6, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1400.0, 1600.0

1039090

y90-yh2

293.6, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1400.0, 1600.0

1039091

y91-yh2

293.6, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1400.0, 1600.0

1040090

zr90-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040091

zr91-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040092

zr92-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040093

zr93-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040094

zr94-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040095

zr95-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040096

zr96-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1101001

h-ice_ih

115.0, 188.2, 208.2, 228.2, 233.2, 248.2, 253.2, 268.1, 273.1

1108016

o16-ice_ih

115.0, 188.2, 208.2, 228.2, 233.2, 248.2, 253.2, 268.1, 273.1

1114028

si28-sio2_b

1000.0, 1100.0

1114029

si29-sio2_b

1000.0, 1100.0

1114030

si30-sio2_b

1000.0, 1100.0

1118016

o16-sio2_b

1000.0, 1100.0

1201001

h-yh2

293.6, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1400.0, 1600.0

2001001

h-solid_ch4

22.0

2008016

o16-d2o

283.6, 293.6, 300.0, 323.6, 350.0, 373.6, 400.0, 423.6, 450.0, 473.6, 500.0, 523.6, 550.0, 573.6, 600.0, 623.6, 650.0

2014028

si28-3c_sic

300.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

2014029

si29-3c_sic

300.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

2014030

si30-3c_sic

300.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

3004009

bebound

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

3006012

c12-graphite

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1600.0, 2000.0

3006013

c13-graphite

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1600.0, 2000.0

3106012

c12-10_graph

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1600.0, 2000.0

Should not be used(2)

3106013

c13-10_graph

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1600.0, 2000.0

Should not be used(2)

3206012

c12-30_graph

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1600.0, 2000.0

Should not be used(2)

3206013

c13-30_graph

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1600.0, 2000.0

Should not be used(2)

4001001

h-cryo_ortho

20.0

4001002

d-cryo_ortho

19.0

5001001

h-cryo_para

20.0

5001002

d-cryo_para

19.0

5004009

be-beo

293.6, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

5006012

c12-benzene

296.0, 350.0, 400.0, 450.0, 500.0, 600.0, 800.0, 1000.0

5006013

c13-benzene

296.0, 350.0, 400.0, 450.0, 500.0, 600.0, 800.0, 1000.0

5008016

o16-beo

293.6, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

5106012

c12_3c_sic

300.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

5106013

c13_3c_sic

300.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

6001001

h-benzene

296.0, 350.0, 400.0, 450.0, 500.0, 600.0, 800.0, 1000.0

7001001

h-zrh2

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

9001001

h-poly

77.0, 196.0, 233.0, 293.6, 300.0, 303.0, 313.0, 323.0, 333.0, 343.0, 350.0

9101001

h-lucite

300.0

  1. The decision was made to remove the uranium-based TSL files (U-UO2 and U-UN), as there are outstanding questions regarding their accuracy. The other elements in these materials (O-UO2 and N-UN, respectively) have been kept, in case a user would like to process the uranium contributions on their own.

  2. Internal and external testing has shown that these files are not representative of real-world graphite [XSLibAQCL+21]. Therefore, they are included only for comparison purposes; the recommendation in all cases where graphite is present is to use the c12-graphite and c13-graphite files.

Table 10.1.4 Temperatures at which thermal moderator data are available in ENDF/B-VII.1

ID

Name

Temperatures

Notes

1001

h-1

293.6, 350.0, 400.0, 450.0, 500.0, 550.0, 600.0, 650.0, 800.0

1002

h-2

293.6, 350.0, 400.0, 450.0, 500.0, 550.0, 600.0, 650.0

1001001

h-liquid_ch4

100.0

1008016

o16-uo2

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1013027

albound

20.0, 80.0, 293.6, 400.0, 600.0, 800.0

Additional naming convention(1)

1014028

si28-sio2

293.6, 350.0, 400.0, 500.0, 800.0, 1000.0, 1200.0

1014029

si29-sio2

293.6, 350.0, 400.0, 500.0, 800.0, 1000.0, 1200.0

1014030

si30-sio2

293.6, 350.0, 400.0, 500.0, 800.0, 1000.0, 1200.0

1026000

fe56-bound

20.0, 80.0, 293.6, 400.0, 600.0, 800.0

1040090

zr90-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040091

zr91-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040092

zr92-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040093

zr93-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040094

zr94-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040095

zr95-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

1040096

zr96-zr5h8

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

2001001

h-solid_ch4

22.0

3004009

bebound

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

Additional naming convention(2)

3006000

c-graphite

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0, 1600.0, 2000.0

4001001

h-cryo_ortho

20.0

4001002

d-cryo_ortho

19.0

5001001

h-cryo_para

20.0

5001002

d-cryo_para

19.0

5004009

be-beo

293.6, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

Additional naming convention(2)

5006000

c-benzene

296.0, 350.0, 400.0, 450.0, 500.0, 600.0, 800.0, 1000.0

5008016

o16-beo

293.6, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

6001001

h-benzene

296.0, 350.0, 400.0, 450.0, 500.0, 600.0, 800.0, 1000.0

7001001

h-zrh2

296.0, 400.0, 500.0, 600.0, 700.0, 800.0, 1000.0, 1200.0

9001001

h-poly

296.0, 350.0

  1. This is an exception to the rule in the above paragraph, as there is only one stable isotope of aluminum.

  2. This is an exception to the rule in the above paragraph, as there is only one stable isotope of beryllium.

Table 10.1.5 Standard SCALE cross section libraries.

Mnemonic names

Primary data source/format

Last field of cross section library filename

v7.1-252

v7.1-252n

ENDF/B-VII.1

252-group neutron

xn252v7.1

v8.0-252

ENDF/B-VIII.0 252-group neutron library

xn252v8.0

v7-56

v7-56n

v7.1-56n

ENDF/B-VII.1 56-group

neutron library

xn56v7.1

test-8grp

TEST LIBRARY 8-group ENDF/B-VII.1 neutron library

test8g_v7.1

v7.1-200n47g

ENDF/B-VII.1 200 neutron/47 gamma library

xn200g47v7.1

v8.0-200n47g

ENDF/B-VIII.0 200 neutron/47 gamma library

xn200g47v8.0

v7.1-28n19g

ENDF/B-VII.1 28 neutron/19 gamma library

xn28g19v7.1

v8.0-28n19g

ENDF/B-VIII.0 28 neutron/19 gamma library

xn28g19v8.0

ce_v7.1_endf

ENDF/B-VII.1 Continuous-energy neutron and gamma library

ce_v8.0_endf

ce_v8.0

ENDF/B-VIII.0 Continuous-energy neutron and gamma library

xn302

fine_fast_e7.1

ENDF/B-VII.1 302-group neutron library

fine_fast_e8.0

ENDF/B-VIII.0 302-group neutron library

v7.1-1597

vfine_e7.1

ENDF/B-VII.1 1597-group neutron library

v8.0-1597

vfine_e8.0

ENDF/B-VIII.0 1597-group neutron library

Additional convenience mnemonics are also available to always alias to the most recent nuclear data libraries for the intended purpose. The mnemonics shown in Table 10.1.2 will allow the use of the same input files with this and future versions of SCALE, but will always access the most recent nuclear data libraries and group structures.

Table 10.1.6 SCALE convenience mnemonics.

Mnemonic name

Aliased library

broad_lwr

xn56v7.1

fine_therm

xn252v7.1

ce

ce_v7.1_endf

ce.xml

ce_v7.1_endf.xml

test_n

test8g_v7.1

10.1.2. Description of the SCALE Cross Section Libraries

10.1.2.1. The 252-group ENDF/B libraries

SCALE includes a fine group structure for criticality safety and reactor physics applications: a 252-group library structure based on either ENDF/B-VII.1 or ENDF/B-VIII.0 is available for either criticality safety or reactor physics. Table 10.1.9, shows the group structure for the 252 fine-group libraries. The 252-group structure was developed to adequately capture spectral and temperature effects important for reactor systems and was processed with newer, improved procedures.

The SCALE control sequences for criticality safety and reactor physics applications normally perform self-shielding of the fine-group libraries using the BONAMI module for the unresolved resonance range; and the CENTRM/PMC modules for the resolved resonance/thermal range. However the 252-group libraries include Bondarenko self-shielding factors for the entire energy range, which provides the option of using the Bondarenko method to self-shield both the resolved and unresolved resonance ranges, as an alternative to the more rigorous (and computationally intensive) CENTRM/PMC approach. As discussed in the following section, one objective of the ENDF/B-VII.1 and ENDF/B-VIII.0 252-group and 56-group libraries was to provide a more accurate Bondarenko treatment for the resolved resonance range.

10.1.2.1.1. Differences in the 238-group and 252-group libraries

The standard weighting function described in Table 10.1.7 is typically used to create MG data for all materials in a library, and Bondarenko shielding factors can be computed using the narrow resonance (NR) approximation for the flux spectrum: \(\sigma\)t+ \(\sigma\)0)*C(E) where \(\sigma\)0 is the background cross section, and C(E) is the standard weight function. Bondarenko factors are tabulated at temperatures of at 293 K, 565 K, 600 K, 900 K, 1200 K, 2000 K, and 2400 K in the 252-group library.

Table 10.1.7 Standard weighting function for processing MG data.

Energy Range

Standard Weight Function

10-5 eV - 0.1 eV

Maxwellian, with peak at 0.025 eV

0.1 eV - 80 keV

1/E

80 keV - 10 MeV

Watt Fission spectrum at temperature of 1.273 MeV

10 MeV -20 MeV

1/E

Several enhancements were made in the MG processing procedures used to produce the 252-group library so that it would be more applicable to reactor physics as well as criticality safety applications. Some of the improvements in the 252-group library compared to the SCALE-6.2 238-group library are given below

(a) The base weighting function for processing MG data of actinide materials (Z>89) was computed by the PW transport code CENTRM for a PWR lattice at 300 K. This approach provides more representative weighted 2D scattering matrices for most cases of interest. The standard weighting function is still used for materials with Z<90.

(b) The thermal energy range which includes up-scattering reactions was extended to 5 eV, compared to 3 eV in the SCALE 6.2 238-group library

(c) Temperature-dependent thermal-scattering matrices for water-bound H, O-16, and actinide materials were processed with temperature-dependent thermal flux spectra obtained from CENTRM calculations for a PWR pincell. Actinide and O-16 MG thermal scattering kernels were weighted with the fuel zone flux at temperatures of 293 K, 600 K, 900 K, 1200 K, and 2400 K, and the water scatter kernels were weighted with the moderator flux at 293 K, 500 K, 600 K, 650 K, 900 K, and 1200 K. In the SCALE 6.2 238-group library, thermal scattering matrices at all temperatures were weighted with a temperature-independent Maxwellian spectrum.

(d) Group-dependent IR parameters (“lambdas”) were calculated for all materials and are included in the 252-group libraries. This allows the Bondarenko self-shielding method in SCALE to use the IR approximation for the 252-group libraries, while the SCALE 6.2 238-group library was limited to the NR approximation.

(e) A number of improvements were made in processing of Bondarenko self-shielding data.

  • The number of temperatures for the Bondarenko factors was increased. Shielding factors are tabulated at temperatures 292 K, 600 K, 900 K, 1200 K, and 2400 K for the 252-group libraries.

  • In addition to the Bondarenko factors normally included for capture, fission, elastic, and total cross sections, self-shielding factors are also included for the multigroup elastic within-group cross section to address the impact of resonance reactions on the scattering distribution.

  • In the unresolved resonance range, self-shielding factors were calculated using probability tables.

  • Bondarenko factors for nuclides with atomic numbers Z>39 were calculated with CENTRM PW flux spectra rather than the analytical NR approximation. Two types of CENTRM models were used. Heterogeneous models of water-moderated lattices spanning the range of expected self-shielding were used to calculate shielding factors for 235U, 238U, 239Pu, 240Pu, 241Pu, 90Zr, and 96Zr. The CENTRM transport calculations were performed using the method of characteristics method for 2D unit cell models. Homogeneous models were used to compute shielding factors for the remaining nuclides with Z>39. These CENTRM calculations were performed for homogeneous media containing the absorber material mixed with hydrogen, and the hydrogen concentration was varied to obtain the desired set of background cross sections. Table 10.1.8 summarizes the processing options for the 252-group library.

Table 10.1.8 Standard weighting functions for processing 252-group library data library.

Nuclide

Base Weight Function

Bondarenko Factor

U-238, -235; Pu-239, -240, -241

PWR spectrum

CENTRM heterogeneous calculations

Other actinides Z>90

PWR spectrum

CENTRM homogeneous calculations

39<Z<90

standard

CENTRM homogeneous calculations

Z<40

standard

NR analytical spectrum
Table 10.1.9 252 Multigroup energy structure (5 eV thermal boundary).

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

1

2.000E+07

85

1.877E+02

169

2.470E+00

2

1.733E+07

86

1.800E+02

170

2.380E+00

3

1.568E+07

87

1.700E+02

171

2.300E+00

4

1.455E+07

88

1.430E+02

172

2.210E+00

5

1.384E+07

89

1.220E+02

173

2.120E+00

6

1.284E+07

90

1.190E+02

174

2.000E+00

7

1.000E+07

91

1.175E+02

175

1.940E+00

8

8.187E+06

92

1.160E+02

176

1.860E+00

9

6.434E+06

93

1.130E+02

177

1.770E+00

10

4.800E+06

94

1.080E+02

178

1.680E+00

11

4.304E+06

95

1.050E+02

179

1.590E+00

12

3.000E+06

96

1.012E+02

180

1.500E+00

13

2.479E+06

97

9.700E+01

181

1.450E+00

14

2.354E+06

98

9.000E+01

182

1.400E+00

15

1.850E+06

99

8.170E+01

183

1.350E+00

16

1.500E+06

100

8.000E+01

184

1.300E+00

17

1.400E+06

101

7.600E+01

185

1.250E+00

18

1.356E+06

102

7.200E+01

186

1.225E+00

19

1.317E+06

103

6.750E+01

187

1.200E+00

20

1.250E+06

104

6.500E+01

188

1.175E+00

21

1.200E+06

105

6.300E+01

189

1.150E+00

22

1.100E+06

106

6.100E+01

190

1.140E+00

23

1.010E+06

107

5.800E+01

191

1.130E+00

24

9.200E+05

108

5.340E+01

192

1.120E+00

25

9.000E+05

109

5.060E+01

193

1.110E+00

26

8.750E+05

110

4.830E+01

194

1.100E+00

27

8.611E+05

111

4.520E+01

195

1.090E+00

28

8.200E+05

112

4.400E+01

196

1.080E+00

29

7.500E+05

113

4.240E+01

197

1.070E+00

30

6.790E+05

114

4.100E+01

198

1.060E+00

31

6.700E+05

115

3.960E+01

199

1.050E+00

32

6.000E+05

116

3.910E+01

200

1.040E+00

33

5.730E+05

117

3.800E+01

201

1.030E+00

34

5.500E+05

118

3.763E+01

202

1.020E+00

35

4.920E+05

119

3.727E+01

203

1.010E+00

36

4.700E+05

120

3.713E+01

204

1.000E+00

37

4.400E+05

121

3.700E+01

205

9.750E-01

38

4.200E+05

122

3.600E+01

206

9.500E-01

39

4.000E+05

123

3.550E+01

207

9.250E-01

40

3.300E+05

124

3.500E+01

208

9.000E-01

41

2.700E+05

125

3.375E+01

209

8.500E-01

42

2.000E+05

126

3.325E+01

210

8.000E-01

43

1.490E+05

127

3.175E+01

211

7.500E-01

44

1.283E+05

128

3.125E+01

212

7.000E-01

45

1.000E+05

129

3.000E+01

213

6.500E-01

46

8.500E+04

130

2.750E+01

214

6.250E-01

47

8.200E+04

131

2.500E+01

215

6.000E-01

48

7.500E+04

132

2.250E+01

216

5.500E-01

49

7.300E+04

133

2.175E+01

217

5.000E-01

50

6.000E+04

134

2.120E+01

218

4.500E-01

51

5.200E+04

135

2.050E+01

219

4.000E-01

52

5.000E+04

136

2.000E+01

220

3.750E-01

53

4.500E+04

137

1.940E+01

221

3.500E-01

54

3.000E+04

138

1.850E+01

222

3.250E-01

55

2.000E+04

139

1.700E+01

223

3.000E-01

56

1.700E+04

140

1.600E+01

224

2.750E-01

57

1.300E+04

141

1.440E+01

225

2.500E-01

58

9.500E+03

142

1.290E+01

226

2.250E-01

59

8.030E+03

143

1.190E+01

227

2.000E-01

60

5.700E+03

144

1.150E+01

228

1.750E-01

61

3.900E+03

145

1.000E+01

229

1.500E-01

62

3.740E+03

146

9.100E+00

230

1.250E-01

63

3.000E+03

147

8.100E+00

231

1.000E-01

64

2.500E+03

148

7.150E+00

232

9.000E-02

65

2.250E+03

149

7.000E+00

233

8.000E-02

66

2.200E+03

150

6.875E+00

234

7.000E-02

67

1.800E+03

151

6.750E+00

235

6.000E-02

68

1.550E+03

152

6.500E+00

236

5.000E-02

69

1.500E+03

153

6.250E+00

237

4.000E-02

70

1.150E+03

154

6.000E+00

238

3.000E-02

71

9.500E+02

155

5.400E+00

239

2.530E-02

72

6.830E+02

156

5.000E+00

240

1.000E-02

73

6.700E+02

157

4.700E+00

241

7.500E-03

74

5.500E+02

158

4.100E+00

242

5.000E-03

75

3.050E+02

159

3.730E+00

243

4.000E-03

76

2.850E+02

160

3.500E+00

244

3.000E-03

77

2.400E+02

161

3.200E+00

245

2.500E-03

78

2.200E+02

162

3.100E+00

246

2.000E-03

79

2.095E+02

163

3.000E+00

247

1.500E-03

80

2.074E+02

164

2.970E+00

248

1.200E-03

81

2.020E+02

165

2.870E+00

249

1.000E-03

82

1.930E+02

166

2.770E+00

250

7.500E-04

83

1.915E+02

167

2.670E+00

251

5.000E-04

84

1.885E+02

168

2.570E+00

252

1.000E-04

1.000E-05

10.1.2.2. The 56-group library

An ENDF/B-VII.1 and an ENDF/B-VIII.0 broad group library with 56 energy groups are available mainly for light water reactor physics calculations. The group structure is shown in Table 10.1.10. This library was processed using the same PW flux spectra used to generate the 252-group libraries (i.e., for a PWR fuel lattice). This library includes the same materials and properties as the 252-group library, and the data were computed in the same manner, except for several specially weighted nuclides which have heterogeneous Bondarenko shielding factors (in addition to those given in Table 10.1.5) computed for specific LWR components. These are summarized in Table 10.1.11.

Table 10.1.10 56-Group energy structure (5 eV thermal boundary).

Grp

Energy(eV)

Grp

Energy(eV)

Grp

Energy(eV)

1

2.0000E+07

24

1.0500E+02

47

2.0000E-01

2

6.4340E+06

25

1.0120E+02

48

1.5000E-01

3

4.3040E+06

26

6.7500E+01

49

1.0000E-01

4

3.0000E+06

27

6.5000E+01

50

8.0000E-02

5

1.8500E+06

28

3.7130E+01

51

6.0000E-02

6

1.5000E+06

29

3.6000E+01

52

5.0000E-02

7

1.2000E+06

30

2.1750E+01

53

4.0000E-02

8

8.6110E+05

31

2.1200E+01

54

2.5300E-02

9

7.5000E+05

32

2.0500E+01

55

1.0000E-02

10

6.0000E+05

33

7.0000E+00

56

4.0000E-03

11

4.7000E+05

34

6.8750E+00

1.0000E-05

12

3.3000E+05

35

6.5000E+00

13

2.7000E+05

36

6.2500E+00

14

2.0000E+05

37

5.0000E+00

15

5.0000E+04

38

1.1300E+00

16

2.0000E+04

39

1.0800E+00

17

1.7000E+04

40

1.0100E+00

18

3.7400E+03

41

6.2500E-01

19

2.2500E+03

42

4.5000E-01

20

1.9150E+02

43

3.7500E-01

21

1.8770E+02

44

3.5000E-01

22

1.1750E+02

45

3.2500E-01

23

1.1600E+02

46

2.5000E-01
Table 10.1.11 LWR-sensitive nuclides with special shielding factors(*) in ENDF/B-VII.1 56-group library.

Nuclide

ID

Component configuration used to compute Bondarenko factors

Zr-91

10040091

standard library weighting

Zr-96

10040096

standard library weighting

Zr-91

40091

LWR lattice cladding, with U238 resonance interference

Zr-96

40096

LWR lattice cladding, with U238 resonance interference

Ag-107

47107

PWR Ag-In-Cd control rod

Ag-109

47109

PWR Ag-In-Cd control rod

In-113

49113

PWR Ag-In-Cd control rod

In-115

49115

PWR Ag-In-Cd control rod

Cd-113

48113

PWR Ag-In-Cd control rod

(*) in addition to nuclides shown with heterogeneous shielding factors in Table 10.1.5
Table 10.1.12 LWR-sensitive nuclides with special shielding factors(*) in ENDF/B-VIII.0 56-group library.

Nuclide

ID

Component configuration used to compute Bondarenko factors

Zr-91

10040091

standard library weighting

Zr-96

10040096

standard library weighting

Zr-91

40091

LWR lattice cladding, with U238 resonance interference

Zr-96

40096

LWR lattice cladding, with U238 resonance interference

Ag-107

47107

PWR Ag-In-Cd control rod

Ag-109

47109

PWR Ag-In-Cd control rod

In-113

49113

PWR Ag-In-Cd control rod

In-115

49115

PWR Ag-In-Cd control rod

Cd-113

48113

PWR Ag-In-Cd control rod

Note

The Zr-91 and Zr-96 cross sections and special shielding factors are using ENDF/B-VII.1 cross sections to preserve legacy self-shielding methods (new self-shielding methods and updated libraries are used in the 7.0.x beta versions of SCALE).

(*) in addition to nuclides shown with heterogeneous shielding factors in Table 10.1.5

10.1.2.3. The 302-group library

Libraries with 302 energy groups based on ENDF/B-VII.1 and ENDF/B-VIII.0 data, respectively, are available for the analysis of sodium-cooled fast reactor (SFR) systems. The base weighting function for processing the MG data of all materials is the neutron flux of a volume-homogenized SFR fuel assembly computed by the PW transport code CENTRM (Fig. 10.1.1). The fuel assembly model was generated corresponding to the specifications of the large oxide core (MOX3600) defined within the OECD/NEA Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs [XSLibB+2}]. The 302-group structure was developed based on group structures optimized for fast spectrum systems used in the DOE-NE Advanced Reactor Technologies (ART) program and, in particular, the MC2-3 code [XSLibLS12]. In particular, boundaries of the 425-group structure were added to the 230-group structure so as to include a finer resolution of resonances in the fast energy range. The group structure below 10-4 eV has been slightly modified from the original ANL structures to match group boundaries of the 1597-group library. Table 10.1.13 shows the group structure of the 302-group library. In contrast with the 252-group library, group-dependent IR parameters (“lambdas”) are not included, and Bondarenko factors were exclusively computed using the narrow resonance (NR) approximation for the flux spectrum for all nuclides. The 302-group library has been developed and tested with a focus on the models defined within the OECD/NEA UAM-SFR benchmark [XSLibBRZP20]. For the application of this library to other SFR or fast spectrum systems, verification with corresponding CE and 1597-group calculations is recommended.

_images/SFR-LWR-flux.png

Fig. 10.1.1 Neutron flux of a volume-homogenized SFR fuel assembly compared to an LWR pin cell spectrum. The SFR spectrum serves as a weighting spectrum for the 302-group SFR library.

Important

THIS LIBRARY SHOULD BE USED ONLY FOR FAST SPECTRUM APPLICATIONS.

Table 10.1.13 302-Group energy structure.

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

1

2.00000E+07

77

1.57237E+06

153

1.53752E+05

229

2.29964E+04

2

1.38400E+07

78

1.53355E+06

154

1.49956E+05

230

2.24287E+04

3

1.34986E+07

79

1.49569E+06

155

1.46253E+05

231

2.18749E+04

4

1.31653E+07

80

1.42274E+06

156

1.42642E+05

232

2.13348E+04

5

1.28400E+07

81

1.35335E+06

157

1.39120E+05

233

2.08080E+04

6

1.25232E+07

82

1.28735E+06

158

1.35686E+05

234

2.02943E+04

7

1.22140E+07

83

1.22456E+06

159

1.32335E+05

235

1.93443E+04

8

1.19125E+07

84

1.19433E+06

160

1.29068E+05

236

1.70000E+04

9

1.16183E+07

85

1.16484E+06

161

1.25881E+05

237

1.50654E+04

10

1.13315E+07

86

1.10803E+06

162

1.22773E+05

238

1.32951E+04

11

1.10517E+07

87

1.05399E+06

163

1.19742E+05

239

1.17329E+04

12

1.07788E+07

88

1.00259E+06

164

1.16786E+05

240

1.03543E+04

13

1.05127E+07

89

9.77835E+05

165

1.13902E+05

241

9.13761E+03

14

1.02532E+07

90

9.61672E+05

166

1.11090E+05

242

8.03000E+03

15

1.00000E+07

91

9.53692E+05

167

1.08347E+05

243

7.11638E+03

16

9.75310E+06

92

9.07180E+05

168

1.05672E+05

244

6.28018E+03

17

9.51230E+06

93

8.62936E+05

169

1.03063E+05

245

5.54224E+03

18

9.27744E+06

94

8.20850E+05

170

1.00518E+05

246

5.01483E+03

19

9.04838E+06

95

7.80817E+05

171

9.80365E+04

247

4.53760E+03

20

8.82497E+06

96

7.42736E+05

172

9.56160E+04

248

4.31630E+03

21

8.60708E+06

97

7.06512E+05

173

9.32552E+04

249

4.07172E+03

22

8.39457E+06

98

6.72055E+05

174

9.09527E+04

250

3.71508E+03

23

8.18700E+06

99

6.39279E+05

175

8.87071E+04

251

3.36154E+03

24

7.98516E+06

100

6.08101E+05

176

8.65169E+04

252

3.01640E+03

25

7.78801E+06

101

5.78443E+05

177

8.43808E+04

253

2.86929E+03

26

7.59572E+06

102

5.50000E+05

178

8.22974E+04

254

2.75220E+03

27

7.40818E+06

103

5.36647E+05

179

8.02655E+04

255

2.61797E+03

28

7.22527E+06

104

5.23397E+05

180

7.82837E+04

256

2.46962E+03

29

7.04688E+06

105

5.10474E+05

181

7.63509E+04

257

2.25000E+03

30

6.87289E+06

106

4.97871E+05

182

7.44658E+04

258

2.03888E+03

31

6.70320E+06

107

4.85578E+05

183

7.26272E+04

259

1.82780E+03

32

6.64757E+06

108

4.73589E+05

184

7.08340E+04

260

1.66220E+03

33

6.59241E+06

109

4.61896E+05

185

6.90851E+04

261

1.58460E+03

34

6.53770E+06

110

4.50492E+05

186

6.73794E+04

262

1.50000E+03

35

6.37628E+06

111

4.39369E+05

187

6.57158E+04

263

1.36060E+03

36

6.21885E+06

112

4.28521E+05

188

6.40933E+04

264

1.23410E+03

37

6.06531E+06

113

4.17941E+05

189

6.25108E+04

265

1.17050E+03

38

5.91555E+06

114

4.07622E+05

190

6.09674E+04

266

1.11200E+03

39

5.76950E+06

115

3.97558E+05

191

5.94621E+04

267

1.06320E+03

40

5.48812E+06

116

3.87742E+05

192

5.79940E+04

268

1.01650E+03

41

5.22046E+06

117

3.78169E+05

193

5.65621E+04

269

9.61120E+02

42

4.96585E+06

118

3.68832E+05

194

5.51656E+04

270

7.48520E+02

43

4.84325E+06

119

3.59725E+05

195

5.38035E+04

271

5.82950E+02

44

4.72367E+06

120

3.50844E+05

196

5.24751E+04

272

4.54000E+02

45

4.60704E+06

121

3.42181E+05

197

5.11795E+04

273

3.53570E+02

46

4.49329E+06

122

3.33733E+05

198

4.99159E+04

274

2.75360E+02

47

4.27415E+06

123

3.25493E+05

199

4.86834E+04

275

2.14450E+02

48

4.06570E+06

124

3.17456E+05

200

4.74815E+04

276

1.67020E+02

49

3.86741E+06

125

3.09618E+05

201

4.63091E+04

277

1.30070E+02

50

3.67880E+06

126

3.01974E+05

202

4.51658E+04

278

1.00000E+02

51

3.49938E+06

127

2.94518E+05

203

4.40506E+04

279

7.88930E+01

52

3.32871E+06

128

2.87246E+05

204

4.29630E+04

280

6.14420E+01

53

3.24653E+06

129

2.80154E+05

205

4.19022E+04

281

4.78510E+01

54

3.16637E+06

130

2.73237E+05

206

4.08677E+04

282

3.72700E+01

55

3.08819E+06

131

2.66491E+05

207

3.98586E+04

283

2.90230E+01

56

3.01194E+06

132

2.59911E+05

208

3.88745E+04

284

2.25000E+01

57

2.86505E+06

133

2.53494E+05

209

3.79147E+04

285

1.76040E+01

58

2.72532E+06

134

2.47235E+05

210

3.69786E+04

286

1.37500E+01

59

2.59240E+06

135

2.41131E+05

211

3.60656E+04

287

1.06770E+01

60

2.46597E+06

136

2.35177E+05

212

3.51751E+04

288

8.31530E+00

61

2.42521E+06

137

2.29371E+05

213

3.43067E+04

289

6.50000E+00

62

2.38513E+06

138

2.23708E+05

214

3.34596E+04

290

5.04350E+00

63

2.36533E+06

139

2.18184E+05

215

3.26335E+04

291

3.92790E+00

64

2.34570E+06

140

2.12797E+05

216

3.18278E+04

292

3.05000E+00

65

2.30693E+06

141

2.07543E+05

217

3.10419E+04

293

2.38000E+00

66

2.26880E+06

142

2.02419E+05

218

3.02755E+04

294

1.86000E+00

67

2.23130E+06

143

1.97421E+05

219

2.95280E+04

295

1.45000E+00

68

2.12248E+06

144

1.92547E+05

220

2.87990E+04

296

1.13000E+00

69

2.01897E+06

145

1.87793E+05

221

2.80879E+04

297

8.76430E-01

70

1.96912E+06

146

1.83156E+05

222

2.73944E+04

298

8.50000E-01

71

1.92050E+06

147

1.78634E+05

223

2.67181E+04

299

6.82560E-01

72

1.87308E+06

148

1.74224E+05

224

2.60584E+04

300

6.25000E-01

73

1.82684E+06

149

1.69922E+05

225

2.54150E+04

301

5.31580E-01

74

1.73774E+06

150

1.65727E+05

226

2.47875E+04

302

4.13990E-01

75

1.65299E+06

151

1.61635E+05

227

2.41755E+04

1.00000E-05

76

1.61218E+06

152

1.57644E+05

228

2.35786E+04

10.1.2.4. The test-8grp library for code testing

The library named test-8grp is used for code testing and verification of reproducibility only. It was collapsed from the fine-group v7-252 library, using the standard weight functions in Table 10.1.7. This library has all the nuclides and same types of nuclear data as in the v7-252 library; but the eight energy-group structure provides capability to test codes and input in shorter times than with the standard production libraries. Table 10.1.14 gives the eight group structure, which has four thermal groups below 3 eV, and four fast groups.

The library can also be used with the CENTRM/PMC resonance shielding methodology.

Important

THIS LIBRARY SHOULD NOT BE USED FOR REAL APPLICATIONS.

Table 10.1.14 Energy boundaries for the 8 group energy structure.

Group

Upper Energy (eV)

1

2.0000E+07

2

8.2000E+05

3

2.0000E+04

4

1.0500E+02

5

5.0000E+00

6

6.5000E-01

7

1.5000E-01

8

4.0000E-02

1.0000E-05

10.1.2.5. The 200N-47G library for shielding

A coupled fine-group neutron-gamma library based on ENDF/B libraries is available for radiation transport calculations with SCALE shielding modules. The 200 neutron and 47 gamma energy group structures are provided in Table 10.1.15 and Table 10.1.16, respectively. The neutron group structure is identical to the 199-group VITAMIN-B6 [XSLibWDP+09] structure except that an additional group has been added to extend the top energy boundary to 20 MeV. The MG neutron data were generated using the standard weighting function described in Table 10.1.7, and the MG photon data were weighted with a flat spectrum with roll-offs. Full-range Bondarenko factors are provided for all nuclides, and the default self-shielding method for this library is to use BONAMI for all energy groups, enabling faster neutron resonance self-shielding calculations. The Bondarenko shielding factors for all nuclides are computed with the NR approximation. If the Bondarenko approach is not appropriate, self-shielding calculations can be done with the CENTRM module. The 200n-47g libraries have dose factor and response function data shown in Table 10.1.17 which are consistent with previous SCALE shielding libraries.

The fine-group coupled libraries were validated by performing radiation transport calculations with the SCALE shielding sequence MAVRIC for several shielding benchmark calculations [XSLibWDP+09]. The calculated results for transmission/attenuation values and spectral results matched experimental measurements well. Overall, the results obtained with using the 200n-47g coupled library demonstrate the effectiveness of the SCALE methods and data for shielding applications.

Table 10.1.15 Energy boundaries for the 200 neutron group structure.

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

1

2.0000E+07

42

2.7253E+06

83

3.3373E+05

124

2.3579E+04

165

5.0435E+00

2

1.9640E+07

43

2.5924E+06

84

3.0197E+05

125

2.1875E+04

166

3.9279E+00

3

1.7332E+07

44

2.4660E+06

85

2.9849E+05

126

1.9305E+04

167

3.0590E+00

4

1.6905E+07

45

2.3852E+06

86

2.9721E+05

127

1.5034E+04

168

2.3824E+00

5

1.6487E+07

46

2.3653E+06

87

2.9452E+05

128

1.1709E+04

169

1.8554E+00

6

1.5683E+07

47

2.3457E+06

88

2.8725E+05

129

1.0595E+04

170

1.4450E+00

7

1.4918E+07

48

2.3069E+06

89

2.7324E+05

130

9.1188E+03

171

1.3000E+00

8

1.4550E+07

49

2.2313E+06

90

2.4724E+05

131

7.1017E+03

172

1.1253E+00

9

1.4191E+07

50

2.1225E+06

91

2.3518E+05

132

5.5308E+03

173

1.0800E+00

10

1.3840E+07

51

2.0190E+06

92

2.2371E+05

133

4.3074E+03

174

1.0400E+00

11

1.3499E+07

52

1.9205E+06

93

2.1280E+05

134

3.7074E+03

175

1.0000E+00

12

1.2840E+07

53

1.8268E+06

94

2.0242E+05

135

3.3546E+03

176

8.7643E-01

13

1.2523E+07

54

1.7377E+06

95

1.9255E+05

136

3.0354E+03

177

8.0000E-01

14

1.2214E+07

55

1.6530E+06

96

1.8316E+05

137

2.7465E+03

178

6.8256E-01

15

1.1618E+07

56

1.5724E+06

97

1.7422E+05

138

2.6126E+03

179

6.2506E-01

16

1.1052E+07

57

1.4957E+06

98

1.6573E+05

139

2.4852E+03

180

5.3158E-01

17

1.0513E+07

58

1.4227E+06

99

1.5764E+05

140

2.2487E+03

181

5.0000E-01

18

1.0000E+07

59

1.3534E+06

100

1.4996E+05

141

2.0347E+03

182

4.1399E-01

19

9.5123E+06

60

1.2874E+06

101

1.4264E+05

142

1.5846E+03

183

3.6680E-01

20

9.0484E+06

61

1.2246E+06

102

1.3569E+05

143

1.2341E+03

184

3.2500E-01

21

8.6071E+06

62

1.1648E+06

103

1.2907E+05

144

9.6112E+02

185

2.7500E-01

22

8.1873E+06

63

1.1080E+06

104

1.2277E+05

145

7.4852E+02

186

2.2500E-01

23

7.7880E+06

64

1.0026E+06

105

1.1679E+05

146

5.8295E+02

187

1.8400E-01

24

7.4082E+06

65

9.6164E+05

106

1.1109E+05

147

4.5400E+02

188

1.5000E-01

25

7.0469E+06

66

9.0718E+05

107

9.8037E+04

148

3.5357E+02

189

1.2500E-01

26

6.7032E+06

67

8.6294E+05

108

8.6517E+04

149

2.7536E+02

190

1.0000E-01

27

6.5924E+06

68

8.2085E+05

109

8.2503E+04

150

2.1445E+02

191

7.0000E-02

28

6.3763E+06

69

7.8082E+05

110

7.9499E+04

151

1.6702E+02

192

5.0000E-02

29

6.0653E+06

70

7.4274E+05

111

7.1998E+04

152

1.3007E+02

193

4.0000E-02

30

5.7695E+06

71

7.0651E+05

112

6.7379E+04

153

1.0130E+02

194

3.0000E-02

31

5.4881E+06

72

6.7206E+05

113

5.6562E+04

154

7.8893E+01

195

2.1000E-02

32

5.2205E+06

73

6.3928E+05

114

5.2475E+04

155

6.1442E+01

196

1.4500E-02

33

4.9659E+06

74

6.0810E+05

115

4.6309E+04

156

4.7851E+01

197

1.0000E-02

34

4.7237E+06

75

5.7844E+05

116

4.0868E+04

157

3.7266E+01

198

5.0000E-03

35

4.4933E+06

76

5.5023E+05

117

3.4307E+04

158

2.9023E+01

199

2.0000E-03

36

4.0657E+06

77

5.2340E+05

118

3.1828E+04

159

2.2603E+01

200

5.0000E-04

37

3.6788E+06

78

4.9787E+05

119

2.8501E+04

160

1.7604E+01

1.0000E-05

38

3.3287E+06

79

4.5049E+05

120

2.7000E+04

161

1.3710E+01

39

3.1664E+06

80

4.0762E+05

121

2.6058E+04

162

1.0677E+01

40

3.0119E+06

81

3.8774E+05

122

2.4788E+04

163

8.3153E+00

41

2.8651E+06

82

3.6883E+05

123

2.4176E+04

164

6.4760E+00
Table 10.1.16 Energy boundaries for the 47 gamma group structure.

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

1

2.0000E+07

11

5.0000E+06

21

1.8000E+06

31

7.0000E+05

41

1.0000E+05

2

1.4000E+07

12

4.5000E+06

22

1.6600E+06

32

6.0000E+05

42

7.5000E+04

3

1.2000E+07

13

4.0000E+06

23

1.5700E+06

33

5.1200E+05

43

7.0000E+04

4

1.0000E+07

14

3.5000E+06

24

1.5000E+06

34

5.1000E+05

44

6.0000E+04

5

8.0000E+06

15

3.0000E+06

25

1.4400E+06

35

4.5000E+05

45

4.5000E+04

6

7.5000E+06

16

2.7500E+06

26

1.3300E+06

36

4.0000E+05

46

3.0000E+04

7

7.0000E+06

17

2.5000E+06

27

1.2000E+06

37

3.0000E+05

47

2.0000E+04

8

6.5000E+06

18

2.3500E+06

28

1.0000E+06

38

2.6000E+05

1.0000E+04

9

6.0000E+06

19

2.1500E+06

29

9.0000E+05

39

2.0000E+05

10

5.5000E+06

20

2.0000E+06

30

8.0000E+05

40

1.5000E+05
Table 10.1.17 Available dose functions on the coupled neutron-gamma libraries.

MAT

MT

Description

999

1
1/v total cross section normalized to 1.0 at 0.0253 eV
1/v absorption cross section normalized to 1.0 at 0.0253 eV
capture, same as MT 1 and 27

Radiative capture, same as MT 1 and 27

27

101

102

900

9032

International Commission on Radiation Units and Measurements, Report 44 (ICRU-44), Table B.3 (air) Kerma (Gy/h)/(neutron/cm2/s)

9027

Henderson conversion from neutron flux to absorbed dose rate in tissue (rad/h)/(neutrons/cm2/s)

9033

ICRU-44, Table B.3 (air) Kerma (rad/h)/(neutron/cm2/s)

9034

Ambient dose equivalent (ICRU-57, Table A.42) (Sv/h)/(neutron/cm2/s)

9035

Ambient dose equivalent (ICRU-57, Table A.42) (rem/h)/(neutron/cm2/s)

9036

Effective dose (ICRU-57, Table A.41) (Sv/h)/(neutron/cm2/s)

9037

Effective dose (ICRU-57, Table A.41) (rem/h)/(neutron/cm2/s)

9029

American National Standards Institute (ANSI) standard (1977) neutron flux-to-dose rate factors (rem/h)/(neutron/cm2/s)

9031

ANSI standard (1991) neutron flux-to-dose rate factors (rem/h)/(neutron/cm2/s)

9502

Henderson conversion factors (rad/h)/(photons/cm2/s)

9503

Claiborne-Trubey conversion factors (rad/h)/(photons/cm2/s)

9504

ANSI standard (1977) gamma flux-to-dose rate factors (rem/h)/(photons/cm2/s)

9505

ANSI standard (1991) gamma flux-to-dose rate factors (rem/h)/(photons/cm2/s)

9506

ICRU-57 Table A.21 (air) Kerma (Gy/h)/(photons/cm2/s)

9507

ICRU-57 Table A.21 (air) Kerma (rad/h)/(photons/cm2/s)

9508

Ambient dose equivalent (ICRU-57 Table A.21) (Sv/h)/(photons/cm2/s)

9509

Ambient dose equivalent (ICRU-57 Table A.21) (rem/h)/(photons/cm2/s)

9510

Effective dose (ICRU-57 Table A.17) (Sv/h)/(photons/cm2/s)

9511

Effective dose (ICRU-57 Table A.17) (rem/h)/(photons/cm2/s)

10.1.2.6. The 28N-19G shielding libraries

In addition to the fine-group shielding library, SCALE has a broad-group ENDF/B-VII.1 and -VIII.0 library. The library has 28 neutron and 19 gamma groups. The change in the neutron group structure (as compared with the SCALE 6.2 27 group structure) was necessary to allow for thermal up-scatter up to 5 eV; the gamma groups are identical in both libraries. The broad-group library was primarily developed to perform adjoint discrete ordinates calculations needed to prepare importance maps and biased source distributions for biasing forward Monte Carlo shielding calculations with the fine-group libraries in the MAVRIC shielding analysis sequence. The constituents of the 28n-19g library and the processing methods are the same as the 200n-47g library. The 28 neutron and 19 gamma group structures are provided in Table 10.1.18 and Table 10.1.19, respectively. The broad-group library has the same dose factor information described in Table 10.1.17 for the fine group library.

Table 10.1.18 Energy boundaries for the 28 neutron group structure.

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

1

2.0000E+07

7

4.0762E+05

13

2.9023E+01

19

1.1253E+00

25

1.0000E-01

2

6.3763E+06

8

1.1109E+05

14

1.0677E+01

20

1.0000E+00

26

5.0000E-02

3

3.0119E+06

9

1.5034E+04

15

5.0000E+00

21

8.0000E-01

27

3.0000E-02

4

1.8268E+06

10

3.0354E+03

16

3.0590E+00

22

4.1399E-01

28

1.0000E-02

5

1.4227E+06

11

5.8295E+02

17

1.8554E+00

23

3.2500E-01

1.0000E-05

6

9.0718E+05

12

1.0130E+02

18

1.3000E+00

24

2.2500E-01
Table 10.1.19 Energy boundaries for the 19 gamma group structure.

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

Group

Upper Energy (eV)

1

2.0000E+07

5

5.0000E+06

9

2.0000E+06

13

8.0000E+05

17

2.0000E+05

2

1.0000E+07

6

4.0000E+06

10

1.6600E+06

14

6.0000E+05

18

1.0000E+05

3

8.0000E+06

7

3.0000E+06

11

1.3300E+06

15

4.0000E+05

19

4.5000E+04

4

6.5000E+06

8

2.5000E+06

12

1.0000E+06

16

3.0000E+05

1.0000E+04

10.1.2.7. The continuous-energy libraries

The ENDF/B-VII.1 and ENDF/B-VIII.0 CE libraries are general-purpose libraries used for both criticality calculations and shielding calculations, although the former do not use the photon data in the libraries. These libraries have CE data for the same nuclides as the MG libraries. CE data for each nuclide are stored in individual files contained in the SCALE data directory. The CE libraries were generated using AMPX to an energy-mesh tolerance of 0.1%; i.e., the data value at any intermediate energy point can be interpolated linearly within an error of 0.1%. Cross section data and kinematic data are provided for all reactions given in the ENDF evaluations and are identical to the reactions available on the MG libraries. Kinematic data are given for a range of incident energies as marginal probability distributions over the exit angles and conditional probability distributions over the exit energies in the laboratory system. Usually, 32 equiprobable exit angle bins are used for the conditional probability distribution, except if the distribution is isotropic or can be described with fewer exit angles. For elastic and discrete inelastic reaction, a larger number of exit angles are used as needed to accurately describe the kinematic in the laboratory system. Gamma production kinematic data are provided if available for nuclides that provide gamma production kinematic data. If gamma production data are present, sections for each discrete photon and the continuum are given along with the yield for each of the section. The incident neutron CE libraries are generated at temperature 293 K, 565 K, 600 K, 900 K, 1200 K, 2000 K, and 2400 K. The kinematic data are not temperature dependent except for thermal moderators, which are included at the temperatures provided by the evaluator (see Table 10.1.4 for a list of thermal moderator nuclides and the list of available temperatures). Probability tables for the unresolved resonance range are provided, if the evaluations included unresolved resonance data [XSLibDL04]. Probability tables are available at 293 K, 565 K, 600 K, 900 K, 1200 K, and 2400 K. For neutron transport calculations, the CE cross sections and thermal kernels are automatically interpolated to the specified temperature using the methods described in [XSLibWDP+09].

For use in CE_MONACO, CE libraries for incident gammas are also available, based on ENDF/B-VII.1 ENDF/B-VIII.0 data, respectively. Only temperature independent cross section and kinematic data are available in the incident gamma libraries.

10.1.2.8. Gleaning Data from the Multigroup Libraries

As mentioned in Section 11.1, “AMPX LIBRARY UTILITY MODULES,” the AMPX module rade can be used to print useful information, such as the available neutron targets, neutron energy group structure, and gamma energy group structure (when present). Please see the AMPX manual [XSLibWWCD15a] for more detailed instructions explaining the input for the relevant AMPX modules.

References

[XSLibAQCL+21]

Iyad I. Al-Qasir, Yongqiang Cheng, Jiao Y.Y. Lin, Anne A. Campbell, G. Sala, Kemal Ramic, Fahima F. Islam, Abdallah Qteish, Barry Marsden, Douglas L. Abernathy, and Matthew B. Stone. Neutron thermalization in nuclear graphite: a modern story of a classic moderator. Annals of Nuclear Energy, 161:108437, 2021. URL: https://www.sciencedirect.com/science/article/pii/S0306454921003133, doi:https://doi.org/10.1016/j.anucene.2021.108437.

[XSLibB+2}]

Friederike Bostelmann and others. Objectives and Status of Neutronics Sub-exercises of the OECD/NEA Benchmark for Uncertainty Analysis in Modelling for Design, Operation and Safety Analysis of SFRs. In Proc. International Conference on Fast Reactors and Related Fuel Cycles (FR22). American Nuclear Society Saratoga Springs, New York, April 19-22, 2022.

[XSLibBRZP20]

Friederike Bostelmann, B. T. Rearden, W. Zwermann, and A. Pautz. SCALE/AMPX Multigroup Libraries for Sodium-Cooled Fast Reactor Systems. Annals of Nuclear Energy, 140:107102, 2020. URL: https://doi.org/10.1016/j.anucene.2019.107102, doi:10.1016/j.anucene.2019.107102.

[XSLibCHO+11]

M.B. Chadwick, M. Herman, P. Obložinský, M.E. Dunn, Y. Danon, A.C. Kahler, D.L. Smith, B. Pritychenko, G. Arbanas, R. Arcilla, R. Brewer, D.A. Brown, R. Capote, A.D. Carlson, Y.S. Cho, H. Derrien, K. Guber, G.M. Hale, S. Hoblit, S. Holloway, T.D. Johnson, T. Kawano, B.C. Kiedrowski, H. Kim, S. Kunieda, N.M. Larson, L. Leal, J.P. Lestone, R.C. Little, E.A. McCutchan, R.E. MacFarlane, M. MacInnes, C.M. Mattoon, R.D. McKnight, S.F. Mughabghab, G.P.A. Nobre, G. Palmiotti, A. Palumbo, M.T. Pigni, V.G. Pronyaev, R.O. Sayer, A.A. Sonzogni, N.C. Summers, P. Talou, I.J. Thompson, A. Trkov, R.L. Vogt, S.C. van der Marck, A. Wallner, M.C. White, D. Wiarda, and P.G. Young. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data. Nuclear Data Sheets, 112(12):2887–2996, 2011. URL: https://www.sciencedirect.com/science/article/pii/S009037521100113X, doi:https://doi.org/10.1016/j.nds.2011.11.002.

[XSLibDAB18]

et al. D.A. Brown. ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data. Nuclear Data Sheets, 148(12):1–142, 2018. URL: https://www.sciencedirect.com/science/article/pii/S0090375218300206, doi:https://doi.org/10.1016/j.nds.2018.02.001.

[XSLibDL04]

M. E. Dunn and L. C. Leal. Calculating probability tables for the unresolved-resonance region using Monte Carlo methods. Nuclear science and engineering, 148(1):30–42, 2004. Publisher: Taylor & Francis.

[XSLibHCML16]

Shane WD Hart, Cihangir Celik, G. Ivan Maldonado, and Luiz Leal. Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code. Annals of Nuclear Energy, 88:49–56, 2016.

[XSLibLS12]

D. L. Lessor and R. E. Schenter. Mc²-3: multigroup cross section generation code for fast reactor analysis. Technical Report ANL/NE-11-41, Argonne National Laboratory, Lemont, IL, 2012.

[XSLibWWCD15a]

D. Wiarda, M. L. Williams, C. Celik, and M. E. Dunn. AMPX-2000: A cross-section processing system for generating nuclear data for criticality safety applications. In Proc. Int. Conf. Nuclear Criticality Safety (ICNC 2015), Charlotte, North Carolina. 2015.

[XSLibWDP+09] (1,2,3)

Dorothea Wiarda, Michael E. Dunn, Douglas E. Peplow, Thomas M. Miller, and Hatice Akkurt. Development and Testing of Endf/b-vi. 8 and Endf/b-vii. 0 Coupled Neutron-gamma Libraries for Scale 6. Technical Report ORNL/TM-2008/047, Oak Ridge National Laboratory, Oak Ridge, TN (USA), 2009.

[XSLibWWCD15b]

Dorothea Wiarda, Mark L. Williams, Cihangir Celik, and Michael E. Dunn. AMPX: A Modern Cross Section Processing System for Generating Nuclear Data Libraries. Technical Report, Oak Ridge National Laboratory, Charlotte, NC (USA), 9 2015.

10.1.3. Appendices