6.3.3.1. Data File Formats
Several data file formats that are used by the sensitivity and uncertainty analysis codes are presented in this appendix.
6.3.3.1.1. Format of TSUNAMI-A sensitivity data file
The format of the TSUNAMI-A sensitivity data file produced by SAMS for cases with deterministic transport solutions is given in Table 6.3.6. The occurrence of each entry in the data file is followed by an identification of the data contained on each line of the file and the FORTRAN edit descriptor denoting the format of each line. A brief description of each line is also presented.
A sample of the TSUNAMI-A data file for the Flattop-25 sample problem is provided in Example 6.3.13. Here, only two profiles out of the 130 computed are shown.
Occurrence |
Data |
Format |
Description |
|---|---|---|---|
Once at beginning of file. |
title |
a80 |
Title extracted from transport calculation |
number of neutron groups |
i10 |
Number of neutron groups in calculation |
|
total number of profiles, text descriptor, number of total profiles that are region integrated |
i10, a35, i10 |
Total number of sensitivity profiles in data file, separated by a text descriptor, then the number of profiles that contain region-integrated data |
|
keff |
f10.6 |
Value of keff from the forward transport calculation |
|
‘energy boundaries:’ |
a |
Text |
|
energy boundary data |
5es14.6 (repeats until all data is printed) |
Values of boundaries of energy groups. Begins with upper value for highest energy group and ends with lower value of lowest energy group. |
|
Repeats for each profile. |
isotope name, sensitivity reaction name, nuclide ID, MT number, Zone number or negative of material number, zone volume |
a12, 1x, a15, 3i12, es14.6 |
Provides data identifying the sensitivity data that follows. Note, if sensitivity data is region-integrated, zone number and zone volume are both 0. If data is integrated over all zones containing the same material, the material number is given in place of the zone number as a negative number. |
Energy integrated sensitivity coefficient, sum of absolute value of group-wise sensitivities, sum of the group-wise sensitivities with opposite sign as energy integrated value (osc) |
3es14.6 |
Energy-integrated sensitivity coefficients for this profile. |
|
group-wise sensitivity coefficients |
5es14.6 (repeats until all data is printed) |
Energy-dependent sensitivity coefficients. Begins with highest energy group. |
|
Once at end of file. |
Block of file verification information. |
flattop-25
238 number of neutron groups
130 number of sensitivity profiles 30 are region integrated
1.002969 k-eff from the forward case
energy boundaries:
2.000000E+07 1.733300E+07 1.568300E+07 1.455000E+07 1.384000E+07
1.284000E+07 1.000000E+07 8.187300E+06 6.434000E+06 4.800000E+06
4.304000E+06 3.000000E+06 2.479000E+06 2.354000E+06 1.850000E+06
1.500000E+06 1.400000E+06 1.356000E+06 1.317000E+06 1.250000E+06
1.200000E+06 1.100000E+06 1.010000E+06 9.200000E+05 9.000000E+05
8.750000E+05 8.611000E+05 8.200000E+05 7.500000E+05 6.790000E+05
6.700000E+05 6.000000E+05 5.730000E+05 5.500000E+05 4.995200E+05
4.700000E+05 4.400000E+05 4.200000E+05 4.000000E+05 3.300000E+05
2.700000E+05 2.000000E+05 1.500000E+05 1.283000E+05 1.000000E+05
8.500000E+04 8.200000E+04 7.500000E+04 7.300000E+04 6.000000E+04
5.200000E+04 5.000000E+04 4.500000E+04 3.000000E+04 2.500000E+04
1.700000E+04 1.300000E+04 9.500000E+03 8.030000E+03 6.000000E+03
3.900000E+03 3.740000E+03 3.000000E+03 2.580000E+03 2.290000E+03
2.200000E+03 1.800000E+03 1.550000E+03 1.500000E+03 1.150000E+03
9.500000E+02 6.830000E+02 6.700000E+02 5.500000E+02 3.050000E+02
2.850000E+02 2.400000E+02 2.100000E+02 2.075000E+02 1.925000E+02
1.860000E+02 1.220000E+02 1.190000E+02 1.150000E+02 1.080000E+02
1.000000E+02 9.000000E+01 8.200000E+01 8.000000E+01 7.600000E+01
7.200000E+01 6.750000E+01 6.500000E+01 6.100000E+01 5.900000E+01
5.340000E+01 5.200000E+01 5.060000E+01 4.920000E+01 4.830000E+01
4.700000E+01 4.520000E+01 4.400000E+01 4.240000E+01 4.100000E+01
3.960000E+01 3.910000E+01 3.800000E+01 3.700000E+01 3.550000E+01
3.460000E+01 3.375000E+01 3.325000E+01 3.175000E+01 3.125000E+01
3.000000E+01 2.750000E+01 2.500000E+01 2.250000E+01 2.100000E+01
2.000000E+01 1.900000E+01 1.850000E+01 1.700000E+01 1.600000E+01
1.509990E+01 1.440000E+01 1.375000E+01 1.290000E+01 1.190000E+01
1.150000E+01 1.000000E+01 9.099990E+00 8.099990E+00 7.150000E+00
7.000000E+00 6.750000E+00 6.500000E+00 6.250000E+00 6.000000E+00
5.400000E+00 5.000000E+00 4.750000E+00 4.000000E+00 3.730000E+00
3.500000E+00 3.150000E+00 3.049990E+00 3.000000E+00 2.969990E+00
2.870000E+00 2.770000E+00 2.669990E+00 2.570000E+00 2.469990E+00
2.379990E+00 2.299990E+00 2.209990E+00 2.120000E+00 2.000000E+00
1.940000E+00 1.860000E+00 1.770000E+00 1.679990E+00 1.589990E+00
1.500000E+00 1.450000E+00 1.400000E+00 1.349990E+00 1.299990E+00
1.250000E+00 1.224990E+00 1.200000E+00 1.174990E+00 1.150000E+00
1.139990E+00 1.129990E+00 1.120000E+00 1.110000E+00 1.099990E+00
1.089990E+00 1.080000E+00 1.070000E+00 1.059990E+00 1.049990E+00
1.040000E+00 1.030000E+00 1.020000E+00 1.009990E+00 1.000000E+00
9.750000E-01 9.500000E-01 9.250000E-01 9.000000E-01 8.500000E-01
8.000000E-01 7.500000E-01 7.000000E-01 6.500000E-01 6.250000E-01
6.000000E-01 5.500000E-01 5.000000E-01 4.500000E-01 4.000000E-01
3.750000E-01 3.500000E-01 3.250000E-01 3.000000E-01 2.750000E-01
2.500000E-01 2.250000E-01 2.000000E-01 1.750000E-01 1.500000E-01
1.250000E-01 1.000000E-01 9.000000E-02 8.000000E-02 7.000000E-02
6.000000E-02 5.000000E-02 4.000000E-02 3.000000E-02 2.530000E-02
1.000000E-02 7.500000E-03 5.000000E-03 4.000000E-03 3.000000E-03
2.500000E-03 2.000000E-03 1.500000E-03 1.200000E-03 1.000000E-03
7.500000E-04 5.000000E-04 1.000000E-04 1.000000E-05
u-234 total 92234 1 0 0.000000E+00
4.717915E-03 4.975886E-03 -1.289843E-04
2.506892E-08 1.674526E-07 3.009241E-07 3.212515E-07 8.004773E-07
9.602059E-06 2.767762E-05 8.282738E-05 2.095243E-04 1.240423E-04
6.019243E-04 4.044642E-04 1.135071E-04 5.606487E-04 4.757248E-04
1.462671E-04 6.761932E-05 6.289243E-05 1.095966E-04 8.561461E-05
1.773753E-04 1.640000E-04 1.761175E-04 4.353814E-05 5.616768E-05
3.283979E-05 1.005176E-04 1.825428E-04 1.823796E-04 2.225234E-05
1.648190E-04 5.830123E-05 4.848578E-05 1.014302E-04 5.276815E-05
4.675121E-05 2.661435E-05 2.271738E-05 5.878201E-05 3.053242E-05
1.441957E-05 -3.866848E-06 -8.105675E-06 -1.524720E-05 -1.112164E-05
-1.873898E-06 -5.969614E-06 -1.989077E-06 -1.326105E-05 -9.321207E-06
-2.404530E-06 -6.309741E-06 -1.968570E-05 -7.035957E-06 -9.446309E-06
-4.643517E-06 -3.590477E-06 -1.204560E-06 -1.496028E-06 -1.231667E-06
-9.897018E-08 -3.797082E-07 -1.884879E-07 -1.238474E-07 -2.742831E-08
-9.015365E-08 -4.731163E-08 -5.688008E-09 -9.784721E-08 -4.339968E-08
-3.857598E-08 -1.788772E-09 -9.179912E-09 -1.942945E-08 -7.808444E-10
-1.033952E-09 -2.787285E-10 -7.649368E-11 3.174200E-12 -2.032114E-09
-2.519205E-09 -8.466172E-12 -1.782872E-11 -4.164121E-10 -1.019102E-10
-8.554906E-11 -8.181892E-12 -1.271741E-11 -2.199571E-10 -1.012644E-12
-2.525998E-11 3.873520E-12 3.246969E-12 -1.846717E-12 2.073834E-12
-2.864914E-12 -2.834941E-13 -1.647038E-12 -7.822336E-11 -3.875318E-12
-2.367591E-11 -2.433239E-13 4.302250E-13 1.328992E-12 -2.683548E-14
-3.569867E-15 -1.056719E-12 2.327642E-13 2.141648E-12 -6.464708E-15
2.102727E-13 4.061489E-13 4.297794E-12 -1.140715E-11 -2.485342E-11
3.520045E-12 -1.312734E-12 -6.466205E-13 4.677226E-14 5.384058E-13
-7.029536E-14 -3.172012E-13 -1.050521E-12 -1.448066E-12 8.609614E-14
-9.503147E-14 1.224622E-13 -5.610401E-14 1.206730E-13 -1.808347E-13
5.110267E-13 -2.647888E-14 -5.274697E-13 -1.360891E-13 -9.483789E-15
1.745369E-13 -2.324100E-13 -1.631119E-14 8.369275E-14 -2.896774E-12
-4.645450E-14 -1.014518E-12 -1.253069E-12 -1.224193E-13 -3.247751E-13
-2.170010E-14 5.679165E-15 -5.495932E-15 -5.738207E-15 -2.640171E-14
-4.723927E-14 -2.692265E-14 -2.470002E-14 -2.212313E-14 -1.887611E-14
-1.473034E-14 -1.451047E-14 -1.414891E-14 2.318902E-14 4.465008E-15
-7.884706E-15 -1.256517E-14 -1.036473E-14 -9.936883E-15 -9.776219E-15
-4.800508E-15 -4.391959E-15 -3.279705E-15 5.435813E-15 -6.187775E-15
-1.940775E-15 -5.997969E-16 -3.333506E-16 -4.412221E-17 -4.046016E-16
-3.825563E-17 -2.586768E-17 -1.933342E-17 -1.012773E-17 -5.796910E-18
-1.903947E-18 -1.731421E-18 -2.378372E-19 -2.074179E-18 -7.863836E-19
-1.446345E-18 1.001051E-18 5.654388E-18 7.607361E-18 -3.840432E-16
-6.762651E-16 -7.569632E-16 -7.992030E-16 -1.579348E-15 -1.638912E-15
-1.614449E-15 -1.524987E-15 -1.454677E-15 -2.958432E-16 -2.370000E-16
2.145063E-16 -1.680721E-15 -3.103977E-15 -2.352000E-15 1.009233E-16
1.583744E-17 4.777954E-18 5.125365E-19 -1.385105E-18 -7.333829E-19
9.783341E-19 1.885422E-20 1.280582E-22 -1.217866E-22 6.410866E-23
-2.958369E-24 -1.558733E-25 -5.544137E-26 -1.831995E-26 -5.448893E-27
-1.415088E-27 -3.110222E-28 -5.522761E-29 -5.429459E-30 -1.728100E-30
-2.514164E-32 0.000000E+00 0.000000E+00 0.000000E+00 0.000000E+00
0.000000E+00 0.000000E+00 0.000000E+00 0.000000E+00 0.000000E+00
0.000000E+00 0.000000E+00 0.000000E+00
u-234 scatter 92234 1 0 0.000000E+00
8.032846E-04 8.241044E-04 -1.041006E-05
-3.248099E-09 -2.849794E-09 3.761279E-09 4.894583E-09 8.374101E-09
-3.099800E-09 -7.458623E-07 -7.683340E-06 6.521506E-06 7.401795E-06
3.981803E-05 3.092353E-05 9.673315E-06 5.444300E-05 4.968639E-05
2.118375E-05 1.138184E-05 1.134012E-05 2.083885E-05 1.703296E-05
3.708780E-05 3.574228E-05 3.382708E-05 7.202870E-06 8.988859E-06
4.995195E-06 1.446466E-05 2.424787E-05 2.765288E-05 3.825457E-06
3.116989E-05 1.317151E-05 1.199450E-05 2.762489E-05 1.707364E-05
1.844534E-05 1.263098E-05 1.257121E-05 4.478947E-05 4.142602E-05
4.409844E-05 2.870006E-05 1.012683E-05 1.152729E-05 4.782801E-06
1.259705E-06 1.793371E-06 2.483675E-07 1.496686E-06 1.706688E-07
1.686857E-07 9.490054E-08 -7.954430E-07 -4.688914E-07 -2.309356E-07
-2.471537E-07 -1.786610E-07 -2.395761E-08 -3.666843E-09 1.724470E-08
-3.073805E-09 -2.746581E-09 1.909088E-09 -1.216879E-08 1.541106E-09
3.070286E-09 -1.714544E-09 2.222325E-09 4.704197E-09 -5.869767E-10
-2.023745E-09 -1.670404E-10 -3.456028E-10 4.846314E-10 1.168348E-10
9.827623E-12 -5.473694E-11 1.402322E-11 2.383711E-11 2.450650E-10
3.568164E-10 -7.159047E-12 -1.503380E-11 6.139393E-11 3.348865E-12
1.628715E-10 -4.819499E-12 -9.202975E-12 8.831698E-12 3.135675E-13
-1.961365E-11 3.846148E-12 2.808294E-12 -1.477353E-12 1.857857E-12
-2.155043E-12 -1.789186E-13 -4.133771E-13 3.033233E-12 4.904576E-14
3.694654E-14 -6.397666E-14 4.128331E-13 1.060395E-12 1.458698E-15
5.731954E-15 -7.811219E-13 2.242784E-13 1.751843E-12 -3.146954E-15
1.844389E-13 3.293311E-13 3.467402E-12 2.026690E-12 5.768864E-12
2.955440E-12 -8.597300E-13 5.334737E-14 1.100362E-13 4.331466E-13
-4.817834E-14 -2.394196E-13 -7.884115E-13 -1.120566E-12 8.127751E-14
-5.460604E-14 1.006648E-13 -3.436737E-14 9.646284E-14 -1.382066E-13
4.648416E-13 5.996957E-15 -3.646852E-13 6.023955E-14 -4.109659E-15
1.203473E-13 -1.351654E-13 -3.330587E-15 8.844682E-14 -1.428401E-13
6.663312E-13 -1.568665E-14 1.282612E-14 1.681431E-14 -8.390950E-14
1.250912E-14 5.585417E-15 3.200709E-16 -4.288993E-16 -4.661462E-15
-1.315587E-14 -2.131794E-15 -1.135026E-16 6.150330E-16 1.873476E-16
2.704163E-16 -8.424184E-17 -2.454189E-15 1.342258E-14 3.898874E-15
1.177619E-16 -8.072667E-16 3.713938E-16 3.286023E-16 -2.195845E-17
3.692910E-17 -8.551075E-18 2.126361E-16 4.077162E-15 -1.879803E-15
-5.420138E-16 5.678537E-18 6.148490E-17 1.547221E-16 -1.861868E-16
-1.463798E-17 -9.869435E-18 -7.532523E-18 -3.710468E-18 -2.008824E-18
-3.941254E-19 -4.338395E-19 1.982443E-19 -6.647317E-19 -6.961168E-21
-1.060476E-19 1.532491E-18 4.815554E-18 8.072217E-18 1.094195E-16
6.851480E-18 -8.567528E-18 -1.375315E-17 2.677723E-17 9.881978E-18
8.154495E-18 1.038738E-18 -1.150521E-17 -2.328087E-18 -1.094495E-18
5.286105E-16 -2.343353E-16 -7.924307E-16 -5.631898E-16 3.676678E-17
5.447929E-18 1.550351E-18 1.795543E-19 -3.911335E-19 -2.070213E-19
2.666570E-19 5.006574E-21 6.432183E-23 -1.883732E-23 1.634739E-23
-7.540091E-26 -3.531102E-27 -1.165437E-27 -3.541294E-28 -9.582782E-29
-2.220252E-29 -4.245368E-30 -6.290953E-31 -5.169058E-32 -1.116416E-32
-2.558539E-36 0.000000E+00 0.000000E+00 0.000000E+00 0.000000E+00
0.000000E+00 0.000000E+00 0.000000E+00 0.000000E+00 0.000000E+00
0.000000E+00 0.000000E+00 0.000000E+00
...
file verification information
code system: scale
version: 6.2
program: sams
creation date: 01_apr_2016
library: /home/c53/scale_freeze/Linux_x86_64-release/bin/scale
migration code: sams
version: 6.2.0
jobname: c53
machine name: node23
date of file creation: 01_apr_2016
time of file creation: 17:22:50.45
filename: tsunami-1d4.sdf
chi sensitivities are constrained
6.3.3.1.2. Format of TSUNAMI-B sensitivity data file
The format of the TSUNAMI-B sensitivity data file produced by SAMS for cases with Monte Carlo transport solutions is given in Table 6.3.7. The occurrence of each entry in the data file is followed by an identification of the data contained on each line of the file and the FORTRAN edit descriptor denoting the format of each line. A brief description of each line is also presented.
A sample of the TSUNAMI-B data file for the LEU-COMP-THERM-009 case 10 sample problem is provided in Example 6.3.14. Here, only two profiles out of the 3389 computed are shown.
Occurrence |
Data |
Format |
Description |
|---|---|---|---|
Once at beginning of file. |
title |
a80 |
Title extracted from transport calculation |
number of neutron groups |
i10 |
Number of neutron groups in calculation |
|
total number of profiles, text descriptor, number of total profiles that are region integrated |
i10, a35, i10 |
Total number of sensitivity profiles in data file, separated by a text descriptor, then the number of profiles that contain region-integrated data |
|
keff ‘+/-’ |
f10.6 |
Value of keff from the forward transport calculation and its standard deviation |
|
‘energy boundaries:’ |
a |
Text |
|
energy boundary data |
5es14.6 (repeats until all data is printed) |
Values of boundaries of energy groups. Begins with upper value for highest energy group and ends with lower value of lowest energy group. |
|
Repeats for each profile. |
isotope name, sensitivity reaction name, nuclide ID, MT number |
a12, 1x, a15, 2i12 |
Provides data identifying the sensitivity data that follows. Note, if sensitivity data is region-integrated, zone number and zone volume are both 0. If data is integrated over all zones containing the same material, the material number is given in place of the zone number as a negative number. |
Unit number, number of the region within the unit, unit comments |
2i7, a50 |
||
Zone number or negative of material number, zone volume, number of times unit is referenced in the problem MatId |
2es14.6, 2i7 |
Note, if sensitivity data is region-integrated, zone number and zone volume are both 0. If data is integrated over all zones containing the same material, the material number is given in place of the zone number as a negative number. |
|
energy integrated sensitivity coefficient, standard deviation for energy integrated sensitivity coefficient, sum of absolute value of group-wise sensitivities, sum of the group-wise sensitivities with opposite sign as energy integrated value (osc), standard deviation for osc. |
5es14.6 |
Energy-integrated sensitivity coefficients and their standard deviations for this profile. |
|
group-wise sensitivity coefficients |
5es14.6 (repeats until all data is printed) |
Energy-dependent sensitivity coefficients. Begins with highest energy group. |
|
standard deviation in group-wise sensitivity coefficients |
5es14.6 (repeats until all data is printed) |
Standard deviation for energy-dependent sensitivity coefficients. Begins with highest energy group. |
|
Once at end of file. |
Block of file verification information. |
sample 3 - tsunami-3d
238 number of neutron groups
3389 number of sensitivity profiles 291 are region integrated
1.004674 +/- 0.000543 k-eff from the forward case
energy boundaries:
2.000000E+07 1.733300E+07 1.568300E+07 1.455000E+07 1.384000E+07
1.284000E+07 1.000000E+07 8.187300E+06 6.434000E+06 4.800000E+06
4.304000E+06 3.000000E+06 2.479000E+06 2.354000E+06 1.850000E+06
1.500000E+06 1.400000E+06 1.356000E+06 1.317000E+06 1.250000E+06
1.200000E+06 1.100000E+06 1.010000E+06 9.200000E+05 9.000000E+05
8.750000E+05 8.611000E+05 8.200000E+05 7.500000E+05 6.790000E+05
6.700000E+05 6.000000E+05 5.730000E+05 5.500000E+05 4.995200E+05
4.700000E+05 4.400000E+05 4.200000E+05 4.000000E+05 3.300000E+05
2.700000E+05 2.000000E+05 1.500000E+05 1.283000E+05 1.000000E+05
8.500000E+04 8.200000E+04 7.500000E+04 7.300000E+04 6.000000E+04
5.200000E+04 5.000000E+04 4.500000E+04 3.000000E+04 2.500000E+04
1.700000E+04 1.300000E+04 9.500000E+03 8.030000E+03 6.000000E+03
3.900000E+03 3.740000E+03 3.000000E+03 2.580000E+03 2.290000E+03
2.200000E+03 1.800000E+03 1.550000E+03 1.500000E+03 1.150000E+03
9.500000E+02 6.830000E+02 6.700000E+02 5.500000E+02 3.050000E+02
2.850000E+02 2.400000E+02 2.100000E+02 2.075000E+02 1.925000E+02
1.860000E+02 1.220000E+02 1.190000E+02 1.150000E+02 1.080000E+02
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2.590273E-04 2.741619E-04 3.632040E-04 4.282485E-04 2.063481E-04
6.650581E-04 4.944312E-04 5.869004E-04 5.798635E-04 1.535210E-04
2.230120E-04 2.313091E-04 2.422020E-04 2.482344E-04 5.418594E-04
4.144033E-04 2.981307E-04 8.099135E-04 3.777744E-04 3.503435E-04
5.259281E-04 1.995055E-04 1.282225E-04 9.399701E-05 2.180021E-04
2.204282E-04 2.289391E-04 2.353957E-04 2.476291E-04 2.310753E-04
2.197705E-04 2.479305E-04 2.547174E-04 3.352607E-04 2.009506E-04
2.600849E-04 2.930110E-04 3.068041E-04 3.205445E-04 3.365811E-04
2.213007E-04 2.267429E-04 2.309969E-04 2.360546E-04 2.429477E-04
1.488554E-04 1.501431E-04 1.523043E-04 1.490992E-04 7.836059E-05
7.676734E-05 7.504028E-05 7.123577E-05 6.306674E-05 5.374799E-05
4.217917E-05 3.237631E-05 2.594829E-05 2.435751E-05 2.680074E-05
3.477155E-05 4.508479E-05 5.790404E-05 6.986748E-05 1.487892E-04
1.707188E-04 1.793168E-04 1.919402E-04 3.358301E-04 3.615817E-04
3.865266E-04 4.114530E-04 4.392739E-04 2.714958E-04 2.801094E-04
5.011157E-04 5.390380E-04 5.729596E-04 5.910309E-04 3.334616E-04
3.061873E-04 2.661426E-04 2.248651E-04 2.308670E-04 2.803224E-04
3.708528E-04 4.862559E-04 6.188882E-04 8.189344E-04 1.110189E-03
1.577516E-03 1.075698E-03 1.270736E-03 1.520277E-03 1.828479E-03
2.146210E-03 2.457027E-03 2.729725E-03 1.737714E-03 2.854629E-03
7.541633E-04 5.796042E-04 2.197686E-04 1.895209E-04 9.598149E-05
8.502876E-05 7.599381E-05 4.814730E-05 3.389918E-05 3.443490E-05
3.153711E-05 3.212018E-05 8.655023E-06
…
file verification information
code system: scale
version: 6.2
program: sams
creation date: 01_apr_2016
library: /home/c53/scale_freeze/Linux_x86_64-release/bin/scale
migration code: sams
version: 6.2.0
jobname: c53
machine name: node23
date of file creation: 01_apr_2016
time of file creation: 17:34:23.02
filename: tsunami-3d3.sdf
chi sensitivities are constrained
6.3.3.1.3. Format of HDF5-based sensitivity data file
An HDF5-based format for the sensitivity data files has been introduced. The format used here has been found to improve I/O speed for TSUNAMI-IP cases that read many SDF files. The HDF5-based SDF can be loaded in Fulcrum to produce the same plots that the text-based SDF can. The HDF5-based SDF may also be read with standard HDF5 tools such as h5dump, h5py, and HDFview.
The tao utility includes a feature that facilitates conversion between the HDF5-based SDF and the text-based SDF.
For example, the tao utility may be used to convert a batch of text-based SDF files in a directory into HDF5-based SDF files by:
tao convert *.sdf
Each HDF5-based SDF file has a file extension “.sdf.h5”. The tao convert tool may also be used to convert from HDF5 to the text-based format via
tao convert -fromFormat=sdf.h5 -toFormat=sdf <filename>.sdf.h5
For tao convert, the -fromFormat and -toFormat options
take the intended file extension as the arguments.
The HDF5-based SDF may be requested as output from TSUNAMI calculations
by including the sensitivity_format keyword in the SAMS block
of the calculation input. For example:
read sams
sensitivity_format=hdf5
end sams
will produce the result senstivity file in HDF5 format, with extension “.sdf.h5”.
The default sensitivity output for TSUNAMI calculations is the text-based format
described previously. This may be requested by removing the sensitivity_format
keyword from the input file, or by
read sams
sensitivity_format=txt
end sams
Brief Description of Data Layout
The HDF5 attributes are defined as
Name |
Datatype |
Comments: MC denotes “only in Monte Carlo-derived files” |
|---|---|---|
|
string |
The type of file - should be |
|
string |
The version of the SDF HDF5 format used for this file |
|
string |
A simple checksum |
|
string |
A link to the specification |
|
string |
The SDF title |
|
enumeration |
“MonteCarlo” or “Deterministic” |
|
string |
The quantity of interest, e.g. keff |
|
string |
Any comment about the reference quantity |
|
double |
The value of the reference quantity in the transport calculation |
|
double |
MC Uncertainty in the reference value |
|
int |
The number of sensitivity profiles |
|
int |
The number of region-integrated sensitivity profiles |
|
int |
The number of neutron groups for the sensitivity calculation |
|
bool |
Whether the \(\chi\) (fission neutron spectrum, MT=1018) sensitivities are constrained |
|
vector<double> |
Energy group boundaries, with size = |
The datasets are stored as vectors, each of size number_profiles.
The exceptions are profile_values and profile_sigmas –
in order to optimize I/O time (especially in TSUNAMI-IP and TSURFER
calculations that read many SDFs),
both of these datasets are hyperslabs of dimension
number_profiles \(\times\) number_neutron_groups.
Name |
Datatype |
Comments: MC denotes “only present in Monte Carlo-derived files” |
|---|---|---|
|
double |
The sensitivity coefficients |
|
double |
MC The uncertainties in the sensitivity coefficients |
|
int |
The numerical IDs of the nuclides, in ZZAAA form |
|
int |
The reaction ID (MT) values |
|
string |
Any comment |
|
int |
Same conventions as text-based region values |
|
int |
Number of times region has been used |
|
int |
Same conventions as text-based material values |
|
int |
Same conventions as text-based unit values |
|
double |
Volume of region |
|
double |
Energy-integrated value of the sensitivity coefficients for corresponding profile |
|
double |
MC Uncertainty in energy-integrated value of the sensitivity coefficients for corresponding profile |
|
double |
Sum of absolute values of the sensitivity coefficients for corresponding profile |
|
double |
Sum of the sensitivity coefficients with sign opposite |
|
double |
MC Uncertainty in |
An example of the output of h5dump --header CE-TSUNAMI_test_k6_IFP_godiva.sdf.h5:
HDF5 "CE-TSUNAMI_test_k6_IFP_godiva.sdf.h5" {
GROUP "/" {
ATTRIBUTE "constrained_chi" {
DATATYPE H5T_ENUM {
H5T_STD_I8LE;
"FALSE" 0;
"TRUE" 1;
}
DATASPACE SCALAR
}
ATTRIBUTE "file_type" {
DATATYPE H5T_STRING {
STRSIZE 12;
STRPAD H5T_STR_NULLTERM;
CSET H5T_CSET_ASCII;
CTYPE H5T_C_S1;
}
DATASPACE SCALAR
}
ATTRIBUTE "file_version" {
DATATYPE H5T_STRING {
STRSIZE 6;
STRPAD H5T_STR_NULLTERM;
CSET H5T_CSET_ASCII;
CTYPE H5T_C_S1;
}
DATASPACE SCALAR
}
ATTRIBUTE "id_chk_sum" {
DATATYPE H5T_STRING {
STRSIZE 12;
STRPAD H5T_STR_NULLTERM;
CSET H5T_CSET_ASCII;
CTYPE H5T_C_S1;
}
DATASPACE SCALAR
}
ATTRIBUTE "id_spec" {
DATATYPE H5T_STRING {
STRSIZE 12;
STRPAD H5T_STR_NULLTERM;
CSET H5T_CSET_ASCII;
CTYPE H5T_C_S1;
}
DATASPACE SCALAR
}
ATTRIBUTE "list_energies" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SIMPLE { ( 253 ) / ( 253 ) }
}
ATTRIBUTE "number_neutron_groups" {
DATATYPE H5T_STD_U64LE
DATASPACE SCALAR
}
ATTRIBUTE "number_profiles" {
DATATYPE H5T_STD_U64LE
DATASPACE SCALAR
}
ATTRIBUTE "number_region_integrated" {
DATATYPE H5T_STD_U64LE
DATASPACE SCALAR
}
ATTRIBUTE "reference_comment" {
DATATYPE H5T_STRING {
STRSIZE 28;
STRPAD H5T_STR_NULLTERM;
CSET H5T_CSET_ASCII;
CTYPE H5T_C_S1;
}
DATASPACE SCALAR
}
ATTRIBUTE "reference_quantity" {
DATATYPE H5T_STRING {
STRSIZE 5;
STRPAD H5T_STR_NULLTERM;
CSET H5T_CSET_ASCII;
CTYPE H5T_C_S1;
}
DATASPACE SCALAR
}
ATTRIBUTE "reference_sigma" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SCALAR
}
ATTRIBUTE "reference_value" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SCALAR
}
ATTRIBUTE "sdf_type" {
DATATYPE H5T_STRING {
STRSIZE 11;
STRPAD H5T_STR_NULLTERM;
CSET H5T_CSET_ASCII;
CTYPE H5T_C_S1;
}
DATASPACE SCALAR
}
ATTRIBUTE "title" {
DATATYPE H5T_STRING {
STRSIZE 37;
STRPAD H5T_STR_NULLTERM;
CSET H5T_CSET_ASCII;
CTYPE H5T_C_S1;
}
DATASPACE SCALAR
}
DATASET "comment" {
DATATYPE H5T_STRING {
STRSIZE H5T_VARIABLE;
STRPAD H5T_STR_NULLTERM;
CSET H5T_CSET_ASCII;
CTYPE H5T_C_S1;
}
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "material" {
DATATYPE H5T_STD_I32LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "mt" {
DATATYPE H5T_STD_I32LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "nuclide_id" {
DATATYPE H5T_STD_I32LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "profile_sigmas" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SIMPLE { ( 54, 252 ) / ( 54, 252 ) }
}
DATASET "profile_values" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SIMPLE { ( 54, 252 ) / ( 54, 252 ) }
}
DATASET "region" {
DATATYPE H5T_STD_I32LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "region_uses" {
DATATYPE H5T_STD_I32LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "unit" {
DATATYPE H5T_STD_I32LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "values_abs_sum" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "values_osc_sigma" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "values_osc_sum" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "values_sigma" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "values_sum" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
DATASET "volume" {
DATATYPE H5T_IEEE_F64LE
DATASPACE SIMPLE { ( 54 ) / ( 54 ) }
}
}
}
6.3.3.1.4. Format of SENLIB.SEN data file
The SENLIB.SEN data file is generated by the SENLIB routines used in the TSUNAMI modules to compute implicit sensitivity effects. The data file contains the sensitivity of data computed in SENLIB and input to the resonance processing code BONAMIST. This file also contains the sensitivities of the extra cross sections input to BONAMIST to the number densities of each nuclide for each region of the BONAMIST input. In BONAMIST, the extra cross section contains data for the Dancoff factor. Each of the parameters for which sensitivity coefficients are computed has a unique identification number. The parameter identification numbers, corresponding parameters, and their locations in the resonance processing code input are shown in Table 6.3.10. The format of the records of the SENLIB.SEN data file is given in Table 6.3.11. Each sensitivity coefficient is identified by three records. These records are repeated until all sensitivities are listed on the data file.
Identifier number |
Parameter |
Location of parameter in resonance processing code input |
-1004 |
Extra cross section (cm-1) by zone, account for Dancoff factor in BONAMIST |
9* array in data block 2 of BONAMIST input |
Record number |
Data |
Format |
Description |
1 |
Region for BONAMIST data and parameter |
2i12 |
BONAMIST region and parameter for which sensitivity coefficient is computed. |
2 |
Nuclide and reaction MT number to which sensitivity coefficient is computed |
2i12 |
Nuclide and reaction MT number to which the sensitivity of the parameter is computed. For data currently computed by SENLIB, only the sensitivities of the parameters to the number densities of the nuclides are computed. Thus, the reaction MT number is always 1. |
3 |
Sensitivity coefficient |
es14.6 |
Relative sensitivity of parameter identified in first record to nuclide and reaction identified in second record. |
6.3.3.1.5. Format of BONAMIST.SEN data file
The BONAMIST.SEN data file is generated by the BONAMIST code, which is executed as part of the TSUNAMI-1D sequence. This data file contains the sensitivities of the groupwise cross sections that are resonance shielded in BONAMIST to the certain data input to BONAMIST. The data to which the sensitivity coefficients are computed are the number densities of the nuclides and the extra cross section by region, which contains data for the Dancoff factor. These data are listed in the data file according to the identifiers listed in Table 6.3.10. Additionally, the sensitivity of group cross sections to the number density of a particular nuclide is identified with the nuclide number from the AMPX cross-section data library.
The format of the records in the data file is identified in Table 6.3.12. Blocks of these records are printed for the non-zero sensitivities for all nuclides and reactions for which resolved resonances are processed.
Record number |
Data |
Format |
Description |
1 |
Nuclide and MT number for cross sections for which sensitivity coefficients are computed |
2i12 |
Nuclide identifier and MT number of reaction for which sensitivity data are computed. |
2 |
Parameter or nuclide and the MT number to which the sensitivity data are computed |
2i12 |
Parameter identifier for scattering cross sections and Dancoff factor or nuclide identifier and MT number to which the sensitivity coefficients are computed. If a parameter identifier is used, the MT number is set to 1. Currently only the sensitivities to number densities are computed in BONAMIST, so the only MT number printed is 1. |
3 |
First and last group for which sensitivity coefficients are printed |
2i12 |
First and last group for the sensitivity coefficients that follow. |
4 |
Sensitivity coefficients, record repeats until all groups identified by record 3 are printed |
5es14.6 |
Relative sensitivities of cross sections for nuclide and process identified by record 1 to parameter or nuclide identified in record 2 for groups corresponding to those identified by record 3. |
6.3.3.1.6. COVERX format
The COVERX data file format for storing multigroup cross-section uncertainty information is presented in this section. The COVERX format was used with the FORSS code system at ORNL. The covariance data processing code PUFF-III outputs multigroup data in the COVERX format. This the only covariance format available for use with the sensitivity and uncertainty analysis codes in SCALE.
The overall structure of a COVERX file is given in Table 6.3.13. The occurrence of the particular record type, the name of the record type and when a given record type is present on the file are identified.
Occurrence |
Record type |
Present if |
Once at beginning of file |
File Identification |
Always |
File Control |
Always |
|
File Description |
NHOLL > 0 |
|
Neutron Group Boundaries |
NNGRUP > 0 |
|
Gamma Group Boundaries |
NGGRUP > 0 |
|
Material-Reaction Control |
Always |
|
Repeat for all material-reaction type pairs |
Material-Reaction Type Cross Sections and Error Files |
Always |
Repeat for all matrices |
Matrix Control |
Always |
Block Control |
Always |
|
Repeat for all blocks |
Matrix Data |
Always |
The details of each record type identified in Table 6.3.13 are presented in Table 6.3.14. Here, the name of the record type, the variables present on the record, the length of the record, the format of the record in FORTRAN context and a description of the content of the record are given.
Record type |
Variables |
Length |
Format |
Description |
|
|---|---|---|---|---|---|
File Identification |
HNAME, (HUSE(I), I=1,2), IVERS |
1+3*MULT |
(’ 0V COVERX ‘, A6, ‘*’, 2A6, ‘*’, I6) |
HNAME |
File name (A6) |
HUSE |
User identification (A6) |
||||
IVERS |
File version number |
||||
MULT |
1 – A6 is a single precision word |
||||
2 – A6 is double precision word |
|||||
File Control |
NGROUP, NNGRUP, NGGRUP, NTYPE, NMMP, NMTRIX, NHOLL |
7 |
(’ 1D’, 7I6) |
NGROUP |
Number of energy groups |
NNGRUP |
Number of neutron groups |
||||
NGGRUP |
Number of gamma groups |
||||
NTYPE |
Type of Data |
||||
1 – Covariance matrix, standard deviation |
|||||
2 – Relative covariance matrix, relative standard deviation |
|||||
3 – Correlation matrix, standard deviation |
|||||
NMMP |
Number of MAT-MT pairs |
||||
NMTRIX |
Number of matrices |
||||
NHOLL |
Number of Hollerith words in description |
||||
File Description |
(WORDS(J), J=1,NHOLL) |
MULT*NHOLL |
(’ 2D ‘,’*’,11A6/(11A6)) |
WORDS(J) |
Hollerith description of file |
Neutron Group Boundaries |
(GPBN(J), J=1,NNGRUP), ENMIN |
NNGRUP+1 |
(’ 3D ‘,5E12.4/(6E12.4)) |
GPBN(J) |
Maximum energy bound of neutron group (J) (eV) |
ENMIN |
Minimum energy of neutron in energy range |
||||
Gamma Group Boundaries |
(GPBG(J), J=1,NGGRUP), EGMIN |
NGGRUP+1 |
(’ 4D ‘,5E12.4/(6E12.4)) |
GPBG(J) |
Maximum energy bound of gamma group (J) (eV) |
EGMIN |
Minimum energy of neutron in energy range |
||||
Material–Reaction Control |
(MATID(I), MTID(I), MWGT(I), I=1,NMMP) |
3*NMMP |
(’ 5D ‘,11I6,(12I6)) |
MATID(I) |
Material identification number |
MTID(I) |
Reaction type identification number |
||||
MWGT(I) |
Cross section weighting option |
||||
1 – Constant |
|||||
2 – 1/E |
|||||
3 – Thermal + 1/E + Fission |
|||||
4 – Arbitrary |
|||||
5 – Combined CTR CRBR |
|||||
Material–Reaction Type Cross Sections and Error Files |
(CRS(J), J=1,NGROUP), (ERROR(J), J=1,NGROUP) |
2*NGROUP |
(’ 6D ‘,5E12.4/(6E12.4)) |
CRS |
Cross section |
ERROR |
Standard deviation |
||||
Matrix Control |
MAT1, MT1, MAT2, MT2, NBLOK |
5 |
(’ 7D ‘,5I6) |
MAT1 |
Material 1 identification number |
MT1 |
Reaction type 1 identification number |
||||
MAT2 |
Material 2 identification number |
||||
MT2 |
Reaction type 2 identification number |
||||
NBLOK |
Number of blocks into which matrix is divided |
||||
Block Control |
(JBAND(J), IJJ(J), J=1,NGROUP), (LGRP(N), N=1,NBLOK) |
2*NGROUP*NBLOK |
(’ 8D ‘,11I6/(12I6)) |
JBAND(J) |
Bandwidth for group J |
IJJ(J) |
Position of diagonal element for group J |
||||
LGRP(N) |
Number of groups in block(N) |
||||
Matrix Data |
(COV(K), K=1,KMAX) |
KMAX |
(’ 9D ‘,5E12.4/(6E12.4)) |
COV |
NTYPE matrix data |