Difference between revisions of "ENDF reaction MT's and macroscopic reaction numbers"
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Revision as of 13:56, 21 November 2015
Serpent uses standard ENDF reaction MT's to identify neutron and photon reactions. The number are used with detector response functions and printed in various output files. Detector responses also include macroscopic cross sections, identified by negative reaction numbers.
Below are descriptive lists of ENDF reaction MT's and macroscopic reaction numbers. For more information on the MT numbers, see the ENDF Format Manual.[1]
ENDF Reaction MT's
MT | Description | Notes |
---|---|---|
1 | total | |
2 | elastic scattering | |
3 | nonelastic | |
4 | total inelastic scattering | |
5 | anything | used for lumping together multiple reaction modes |
11 | (n,2nd) | |
16 | (n,2n) | |
17 | (n,3n) | |
18 | total fission | sum over all fission channels (MT's 19-21 and 38) |
19 | (n,f) | 1st-chance fission |
20 | (n,nf) | 2nd-chance fission |
21 | (n,2nf) | 3rd-chance fission |
22 | (n,nα) | |
23 | (n,n3α) | |
24 | (n,2nα) | |
25 | (n,3nα) | |
27 | absorption | |
28 | (n,np) | |
29 | (n,n2α) | |
30 | (n,2n2α) | |
32 | (n,nd) | |
33 | (n,nt) | |
34 | (n,n3He) | |
35 | (n,nd2α) | |
36 | (n,nt2α) | |
37 | (n,4n) | |
38 | (n,3nf) | 4th-chance fission |
41 | (n,2np) | |
42 | (n,3np) | |
44 | (n,n2p) | |
45 | (n,npα) | |
51-90 | inelastic scattering to excited states | |
91 | inelastic scattering to continuum | |
101 | total absorption | |
102 | (n,γ) | |
103 | (n,p) | |
104 | (n,d) | |
105 | (n,t) | |
106 | (n,3He) | |
107 | (n,α) | |
108 | (n,2α) | |
109 | (n,3α) | |
111 | (n,2p) | |
112 | (n,pα) | |
113 | (n,t2α) | |
114 | (n,d2α) | |
115 | (n,pd) | |
116 | (n,pt) | |
117 | (n,dα) | |
201 | total neutron production | |
202 | total photon production | |
203 | total proton production | |
204 | total deuteron production | |
205 | total triton production | |
206 | total 3He production | |
207 | total α production | |
301 | total heat production | Total heating number multiplied by total cross section (difference to MCNP) |
443 | kinematic KERMA | |
444 | damage-energy production | |
600 | (n,p) to ground state | MT's 600-649 can be used to replace MT 103 |
601-648 | (n,p) to excited states | |
649 | (n,p) to continuum | |
650 | (n,d) to ground state | MT's 650-699 can be used to replace MT 104 |
651-698 | (n,d) to excited states | |
699 | (n,d) to continuum | |
700 | (n,t) to ground state | MT's 700-749 can be used to replace MT 105 |
701-748 | (n,t) to excited states | |
749 | (n,t) to continuum | |
750 | (n,3He) to ground state | MT's 750-799 can be used to replace MT 106 |
751-798 | (n,3He) to excited states | |
799 | (n,3He) to continuum | |
800 | (n,α) to ground state | MT's 800-849 can be used to replace MT 107 |
801 - 848 | (n,α) to excited states | |
849 | (n,α) to continuum | |
875 | (n,2n) to ground state | MT's 875-891 can be used to replace MT 16 |
876-890 | (n,2n) to excited states | |
891 | (n,2n) to continuum |
Macroscopic reaction numbers
References
- ^ Herman, M. and Trkov, A. "ENDF-6 Formats Manual." CSEWG Document ENDF-102 / BNL-90365-2009.