10.1.3.1. MT Reaction Types on SCALE CrossSection Libraries
ENDF reaction types (MT) are identified by an integer number from 1 through 999. Table 10.1.17 includes a copy of information taken from Ref. 8. Within SCALE, MT numbers are used to identify reactions on various input and output arrays.
MT numbers greater than 999 are additional SCALEspecific identifiers that may appear in SCALE crosssection libraries. These reaction types are not ENDF reaction types but may be added by various preprocessing codes in the SCALE and/or AMPX systems.
These reactions are listed in Table 10.1.18.
The dose conversion factors and their corresponding MT numbers in the SCALE shielding crosssection libraries can be found in Table 10.1.14.
MT 
Reaction 
Description 
1 
(n,total) 
Neutron total cross sections. Sum of MT=2, 4, 5, 11, 1618, 2226, 2837, 4142, 4445, 102117. 
2 
(z,z_{0}) 
Elastic scattering cross section for incident particles. 
3 
(z,nonelastic) 
Nonelastic neutron cross section. Sum of MT=4, 5, 11, 1618, 2226, 2837, 4142, 4445, 102117. 
4 
(z,n) 
Production of one neutron in the exit channel. Sum of the MT=5091. 
5 
(z,anything) 
Sum of all reactions not given explicitly in another MT number. This is a partial reaction to be added to obtain MT=1. 
69 
Not allowed in version 6. 

10 
(z,continuum) 
Total continuum reaction; includes all continuum reactions and excludes all discrete reactions. 
11 
(z,2nd) 
Production of two neutrons and a deuteron, plus a residual. 
1215 
(Unassigned) 

16 
(z,2n) 
Production of two neutrons and a residual [XS1]. Sum of MT=875891, if they are present. 
17 
(z,3n) 

18 
(z,fission) 

19 
(n,f) 

20 
(n,nf) 
Secondchance fission [XS2]. 
21 
(n,2nf) 
Thirdchance fission[XS2]. 
22 
(z,n\(\alpha\)) 
Production of a neutron and an alpha particle, plus a residual. 
23 
(n,n3\(\alpha\) 
Production of a neutron and three alpha particles, plus a residual. 
24 
(z,2n\(\alpha\)) 
Production of two neutrons and an alpha particle, plus a residual. 
25 
(z,3n\(\alpha\)) 
Production of three neutrons and an alpha particle, plus a residual. 
26 
Not allowed in version 6. 

27 
(n,abs) 
Absorption; sum of MT=18 and MT=102 through MT=117. 
28 
(z,np) 
Production of a neutron and a proton, plus a residual. 
29 
(z,n2\(\alpha\)) 
Production of a neutron and two alpha particles, plus a residual. 
30 
(z,2n2\(\alpha\)) 
Production of two neutrons and two alpha particles, plus a residual. 
31 
Not allowed for version 6. 

32 
(z,nd) 
Production of a neutron and a deuteron, plus a residual. 
33 
(z,nt) 
Production of a neutron and a triton, plus a residual. 
34 
(z,n^{3}He) 
Production of a neutron and a ^{3}He particle, plus a residual. 
35 
(z,nd2\(\alpha\)) 
Production of a neutron, a deuteron, and 2 alpha particles, plus a residual. 
36 
(z,nt2\(\alpha\)) 
Production of a neutron, a triton, and 2 alpha particles, plus a residual. 
37 
(z,4n) 
Production of 4 neutrons, plus a residual. 
38 
(n,3nf) 
Fourthchance fission cross section^{2}. 
39 
Not allowed for version 6. 

40 
Not allowed for version 6. 

41 
(z,2np) 
Production of 2 neutrons and a proton, plus a residual. 
42 
(z,3np) 
Production of 3 neutrons and a proton, plus a residual. 
43 
(Unassigned) 

44 
(z,n2p) 
Production of a neutron and 2 protons, plus a residual. 
45 
(z,np\(\alpha\)) 
Production of a neutron, a proton, and an alpha particle, plus a residual. 
4649 
Not allowed in Version 6. 

50 
(y,n_{0}) 
Production of a neutron, leaving the residual nucleus in the ground state. 
51 
(z,n_{1}) 
Production of a neutron, with residual in the 1st excited state. 
52 
(z,n_{2}) 
Production of a neutron, with residual in the 2nd excited state. 
… 

… 

90 
(z,n_{40}) 
Production of a neutron, with residual in the 40th excited state. 
91 
(z,n_{c}) 
Production of a neutron in the continuum not included in the above discrete representation. 
92100 
(Unassigned) 

101 
(n,disap) 
Neutron disappearance; equal to sum of MT=102117. 
102 
(z,:math:gamma) 
Radiative capture. 
103 
(z,p) 
Production of a proton, plus a residual. Sum of MT=600649, if they are present. 
104 
(z,d) 
Production of a deuteron, plus a residual. Sum of MT=650699, if they are present. 
105 
(z,t) 
Production of a triton, plus a residual. Sum of MT=700749, if they are present. 
106 
(z,^{3}He) 
Production of a ^{3}He particle plus a residual. Sum of MT=750799, if they are present. 
107 
(z,\(\alpha\)) 
Production of an alpha particle, plus a residual. Sum of MT=800849, if they are present. 
108 
(z,2\(\alpha\)) 
Production of 2 alpha particles, plus a residual. 
109 
(z,3\(\alpha\)) 
Production of 3 alpha particles, plus a residual. 
110 
(Unassigned) 

111 
(z,2p) 
Production of 2 protons, plus a residual. 
112 
(z,p\(\alpha\)) 
Production a proton and an alpha particle, plus a residual. 
113 
(z,t2\(\alpha\)) 
Production of a triton and 2 alpha particles, plus a residual. 
114 
(z,d2\(\alpha\)) 
Production of a deuteron and 2 alpha particles, plus a residual. 
115 
(z,pd) 
Production of proton and a deuteron, plus a residual. 
116 
(z,pt) 
Production of proton and a triton, plus a residual. 
117 
(z,d\(\alpha\)) 
Production of deuteron and an alpha particle, plus a residual. 
118119 
(Unassigned) 

120 
Not allowed for version 6. 

121150 
(Unassigned) 

151 
(n,RES) 
Resonance parameters that can be used to calculate cross sections at different temperatures in the resolved and unresolved energy regions. 
152200 
(Unassigned) 

201 
(z,Xn) 
Total neutron production. 
202 
(z,X \(\gamma\)) 
Total gamma production. 
203 
(z,Xp) 
Total proton production. 
204 
(z,Xd) 
Total deuteron production. 
205 
(z,Xt) 
Total triton production. 
206 
(z,X ^{3}He) 
Total ^{3}He production. 
207 
(z,X\(\alpha\)) 
Total alpha particle production. 
208 
(z,X \(\pi^+\)) 
Total \(\pi^+\) production. 
209 
(z,X \(\pi^0\)) 
Total \(pi^0\) production. 
210 
(z,X \(\pi^\)) 
Total \(\pi^\) production. 
211 
(z,X :math:mu^+`) 
Total \(\mu^+\) production. 
212 
(z,X \(\mu^\)) 
Total \(\mu^\) production. 
213 
(z,X\(\kappa^+\)) 
Total \(\kappa^+\) production. 
214 
(z,X\(\kappa^0_{long}\)) 
Total \(\kappa^0_{long}\) production. 
215 
(z,X\(\kappa^0_{short}\)) 
Total \(\kappa^0_{short}\) production. 
216 
(z,X\(\kappa^\)) 
Total \(\kappa^\) production. 
217 
(z,Xp) 
Total antiproton production. 
218 
(z,Xn) 
Total antineutron production. 
219250 
(Unassigned) 

251 
(n,…) 
\(\bar{\mu}_{L}\), average cosine of the scattering angle (laboratory system) for elastic scattering of neutrons. 
252 
(n,…) 
\(\xi\), average logarithmic energy decrement for elastic scattering of neutrons. 
253 
(n,…) 
\(\gamma\), average of the square of the logarithmic energy decrement divided by twice the average logarithmic energy decrement, for elastic scattering of neutrons. 
254300 
(Unassigned) 

301450 
(z,…) 
Energy release parameters,\(E * \sigma\), for total and partial cross sections; MT= 300 plus the reaction MT number, e.g., MT=302 is the elastic scattering kerma. 
451 
(z,…) 
Heading or title information; given in File 1 only. 
452 
(z,…) 
\(\bar{V}_{T}\), average total (prompt plus delayed) number of neutrons released per fission event. 
453 
(Unassigned) 

454 
(z,…) 
Independent fission product yield data. 
455 
(z,…) 
\(\bar{V} d\), average number of delayed neutrons released per fission event. 
456 
(z,…) 
\(\bar{V} p\), average number of prompt neutrons released per fission event. 
457 
(z,…) 
Radioactive decay data. 
458 
(n,…) 
Energy release in fission for incident neutrons. 
459 
(z,…) 
Cumulative fission product yield data. 
460464 
(Unassigned) 

465466 
Not allowed in version 6. 

467499 
(Unassigned) 

500 
Total chargedparticle stopping power. 

501 
Total photon interaction. 

502 
Photon coherent scattering. 

503 
(Unassigned) 

504 
Photon incoherent scattering. 

505 
Imaginary scattering factor. 

506 
Real scattering factor. 

507514 
(Unassigned) 

515 
Pair production, electron field. 

516 
Pair production; sum of MT=515, 517. 

517 
Pair production, nuclear field. 

518 
Not allowed in version 6. 

519521 
(Unassigned) 

522 
Photoelectric absorption. 

523 
Photoexcitation cross section. 

524525 
(Unassigned) 

526 
Electroatomic scattering. 

527 
Electroatomic bremsstrahlung. 

528 
Electroatomic excitation cross section. 

529531 
(Unassigned) 

532 
Not allowed in version 6. 

533 
Atomic relaxation data. 

534 
K 
(1s1/2) subshell photoelectric or electroatomic cross section. 
535 
L1 
(2s1/2) subshell photoelectric or electroatomic cross section. 
536 
L2 
(2p1/2) subshell photoelectric or electroatomic cross section. 
537 
L3 
(2p3/2) subshell photoelectric or electroatomic cross section. 
538 
M1 
(3s1/2) subshell photoelectric or electroatomic cross section. 
539 
M2 
(3p1/2) subshell photoelectric or electroatomic cross section. 
540 
M3 
(3p3/2) subshell photoelectric or electroatomic cross section. 
541 
M4 
(3d3/2) subshell photoelectric or electroatomic cross section. 
542 
M5 
(3d5/2) subshell photoelectric or electroatomic cross section. 
543 
N1 
(4s1/2) subshell photoelectric or electroatomic cross section. 
544 
N2 
(4p1/2) subshell photoelectric or electroatomic cross section. 
545 
N3 
(4p3/2) subshell photoelectric or electroatomic cross section. 
546 
N4 
(4dp3/2) subshell photoelectric or electroatomic cross section. 
547 
N5 
(4d5/2) subshell photoelectric or electroatomic cross section. 
548 
N6 
(4f5/2) subshell photoelectric or electroatomic cross section. 
549 
N7 
(4f7/2) subshell photoelectric or electroatomic cross section. 
550 
O1 
(5s1/2) subshell photoelectric or electroatomic cross section. 
551 
O2 
(5p1/2) subshell photoelectric or electroatomic cross section. 
552 
O3 
(5p3/2) subshell photoelectric or electroatomic cross section. 
553 
O4 
(5d3/2) subshell photoelectric or electroatomic cross section. 
554 
O5 
(5d5/2) subshell photoelectric or electroatomic cross section. 
555 
O6 
(5f5/2) subshell photoelectric or electroatomic cross section. 
556 
O7 
(5f7/2) subshell photoelectric or electroatomic cross section. 
557 
O8 
(5g7/2) subshell photoelectric or electroatomic cross section. 
558 
O9 
(5g9/2) subshell photoelectric or electroatomic cross section. 
559 
P1 
(6s1/2) subshell photoelectric or electroatomic cross section. 
560 
P2 
(6p1/2) subshell photoelectric or electroatomic cross section. 
561 
P3 
(6p3/2) subshell photoelectric or electroatomic cross section. 
562 
P4 
(6d3/2) subshell photoelectric or electroatomic cross section. 
563 
P5 
(6d5/2) subshell photoelectric or electroatomic cross section. 
564 
P6 
(6f5/2) subshell photoelectric or electroatomic cross section. 
565 
P7 
(6f7/2) subshell photoelectric or electroatomic cross section. 
566 
P8 
(6g7/2) subshell photoelectric or electroatomic cross section. 
567 
P9 
(6g9/2) subshell photoelectric or electroatomic cross section. 
568 
P10 
(6h9/2) subshell photoelectric or electroatomic cross section. 
569 
P11 
(6h11/2) subshell photoelectric or electroatomic cross section. 
570 
Q1 
(7s1/2) subshell photoelectric or electroatomic cross section. 
571 
Q2 
(7p1/2) subshell photoelectric or electroatomic cross section. 
572 
Q3 
(7p3/2) subshell photoelectric or electroatomic cross section. 
573599 
(Unassigned) 

600 
(z,p_{0}) 
Production of a proton leaving the residual nucleus in the ground state. 
601 
(z,p_{1}) 
Production of a proton, with residual in the 1st excited state. 
602 
(z,p_{2}) 
Production of a proton, with residual in the 2nd excited state. 
603 
(z,p_{3}) 
Production of a proton, with residual in the 3rd excited state. 
604 
(z,p_{4}) 
Production of a proton, with residual in the 4th excited state. 
… 

… 

649 
(z,p_{c}) 
Production of a proton in the continuum not included in the above discrete representation. 
650 
(z,d_{0}) 
Production of a deuteron leaving the residual nucleus in the ground state. 
651 
(z,d_{1}) 
Production of a deuteron, with the residual in the 1st excited state. 
652 
(z,d_{2}) 
Production of a deuteron, with the residual in the 2nd excited state. 
… 

… 

699 
(z,d_{c}) 
Production of a deuteron in the continuum not included in the above discrete representation. 
700 
(z,t_{0}) 
Production of a triton leaving the residual nucleus in the ground state. 
701 
(z,t_{1}) 
Production of a triton, with residual in the 1st excited state. 
702 
(z,t_{2}) 
Production of a triton, with residual in the 2nd excited state. 
… 

… 

749 
(z,t_{c}) 
Production of a triton in the continuum not included in the above discrete representation. 
750 
(n,:sup`3`He_{1}) 
Production of a ^{3}He particle leaving the residual nucleus in the ground state. 
751 
(n,:sup`3`He_{2}) 
Production of a ^{3}He, with residual in the 1st excited state. 
… 

… 

799 
(n,:sup`3`He_{c}) 
Production of a ^{3}He in the continuum not included in the above discrete representation. 
800 
(z,:math:alpha_0) 
Production of an alpha particle leaving the residual nucleus in the ground state. 
801 
(z,:math:alpha_1) 
Production of an alpha particle, with residual in the 1st excited state. 
… 

… 

849 
(z,:math:alpha_c) 
Production of an alpha particle in the continuum not included in the above discrete representation. 
850 
(Unassigned) 

851870 
Lumped reaction covariances. 

871874 
(Unassigned) 

875 
(z,2n_{0}) 
Production of 2 neutrons with residual in the ground state. 
876 
(z,2n_{1}) 
Production of 2 neutrons with residual in the 1st excited state. 
… 

891 
(z,2n_{c}) 
Production of 2 neutrons in the continuum not included in the above discrete representation. 
892999 
(Unassigned) 
SCALE MT 
Description 
1000 
Transport cross section based on the outscatter approximation. See XSDRNPM chapter, section Outscatter approximation (inconsistent method). 
1001 
Transport cross section based on the inscatter approximation. See XSDRNPM chapter, section Inscatter approximation (consistent method) 
1007 
Thermal scattering matrix 
1008 
Elastic part of thermal scattering matrix 
1018 
Fission spectrum 
1019 
First chance fission spectrum 
1020 
Second chance fission spectrum 
1021 
Third chance fission spectrum 
1038 
Fourth chance fission spectrum 
1099 
Group integral of the weight function 
1111 
Flux moment (P_{1}) weighted total cross section 
1112 
Flux moment (P_{2}) weighted total cross section 
1113 
Flux moment (P_{3}) weighted total cross section 
1114 
Flux moment (P_{4}) weighted total cross section 
1115 
Flux moment (P_{5}) weighted total cross section 
1116 
Flux moment (P_{6}) weighted total cross section 
1117 
Flux moment (P_{7}) weighted total cross section 
1118 
Flux moment (P_{8}) weighted total cross section 
1119 
Flux moment (P_{9}) weighted total cross section 
1452 
Product of \(\bar{V} T\) times the fission cross section 
1456 
Product of \(\bar{V}_{p}\) times the fission cross section 
1455 
Product of \(\bar{v}_{d}\) times the fission cross section 
15001501 
Same as 1000, 1001 except for gammaray cross sections 
1527 
Gammaray energy absorption coefficient factors 
2006 
Nonabsorption collision probability (CE libraries only) 
2016 
Probability of emitting two neutrons (CE libraries only) 
2017 
Probability of emitting three neutrons (CE libraries only) 
2018 
Fission probability (CE libraries only) 
2022 
Withingroup scattering cross section 
2027 
Absorption probability (CE libraries only) 
4561 
\(\bar{V}_{p}\) for first chance fissions 
4562 
\(\bar{V}_{p}\) for second chance fissions 
4563 
\(\bar{V}_{p}\) for third chance fissions 
4564 
\(\bar{V}_{p}\) for fourth chance fissions 