Difference between revisions of "ENDF reaction MT's and macroscopic reaction numbers"
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Revision as of 21:00, 13 December 2021
Serpent uses standard ENDF reaction MTs to identify neutron and photon reactions. The numbers are used with detector response functions, microscopic cross section calculations and printed in various output files. Detector responses also include macroscopic cross sections (and similar), identified by negative reaction numbers.
Below are descriptive lists of ENDF reaction MTs and macroscopic reaction numbers. For more information on the MT numbers, see the ENDF Format Manual.^{[1]} It should be noted that even though the notation is very similar to that used by MCNP, there are some differences in the definitions of some response functions.
Contents
ENDF Reaction MTs
Neutron reactions
MT | Description | Notes |
---|---|---|
1 | (n,total) | incident neutrons only (sum over MTs 2, 4, 5, 11, 16-18, 22-26, 28-37, 41-43, 44-45, 102-117) |
2 | (z,z_{0}) | elastic scattering |
3 | (z,nonelastic) | nonelastic (sum over MTs 4, 5, 11, 16-18, 22-26, 28-37, 41-42, 44-45, 102-117) - redundant |
4 | (z,n) | total inelastic scattering (incident neutrons); production of one neutron in the exit channel (sum over MTs 51 to 91) - redundant |
5 | (n,anything) | sum of all reactions not given explicitly in another MT number, used for lumping together multiple reaction modes |
11 | (z,2nd) | production of two neutrons and a deuteron, plus a residual if any |
16 | (z,2n) | production of two neutrons, plus a residual (if any) - some nuclides miss MT 16 and have only MTs 875-891 instead |
17 | (z,3n) | production of three neutrons, plus a residual (if any) |
18 | (z,fission) | total fission (sum over MTs 19-21 and 38) |
19 | (n,f) | 1st-chance neutron-induced fission |
20 | (n,nf) | 2nd-chance neutron-induced fission |
21 | (n,2nf) | 3rd-chance neutron-induced fission |
22 | (z,nα) | production of a neutron and an alpha particle, plus a residual (if any) |
23 | (z,n3α) | production of a neutron and three alpha particles, plus a residual (if any) |
24 | (z,2nα) | production of two neutron and an alpha particle, plus a residual (if any) |
25 | (z,3nα) | production of three neutrons and an alpha particle, plus a residual (if any) |
27 | (n,abs) | absorption (sum over MTs 18 and 102-117)- redundant |
28 | (z,np) | production of a neutron and a proton, plus a residual (if any) |
29 | (z,n2α) | production of a neutrons and two alpha particles, plus a residual (if any) |
30 | (z,2n2α) | production of two neutrons and two alpha particles, plus a residual (if any) |
32 | (z,nd) | production of a neutron and a deuteron, plus a residual (if any) |
33 | (z,nt) | production of a neutron and a triton, plus a residual (if any) |
34 | (z,n^{3}He) | production of a neutron and a ^{3}He particle, plus a residual (if any) |
35 | (z,nd2α) | production of a neutron, a deuteron and two alpha particles, plus a residual (if any) |
36 | (z,nt2α) | production of a neutron, a triton, and two alpha particles, plus a residual (if any) |
37 | (z,4n) | production of four neutrons, plus a residual (if any) |
38 | (n,3nf) | 4th-chance neutron-induced fission |
41 | (z,2np) | production of two neutrons and a proton, plus a residual (if any) |
42 | (z,3np) | production of three neutrons and a proton, plus a residual (if any) |
44 | (z,n2p) | production of a neutron and two protons, plus a residual (if any) |
45 | (z,npα) | production of a neutron, a proton and an alpha particle, plus a residual (if any) |
51-90 | (z,n_{i}) | inelastic scattering to excited states; production of a neutron leaving the residual nucleus in the ith excited state (i = 1, 2,...,40) |
91 | (z,n_{c}) | inelastic scattering to continuum; production of a neutron in the continuum not included in the above discrete representation |
101 | (n,disap) | total absorption or dissaparance (sum over MTs 102-117) - redundant |
102 | (z,γ) | radiative capture (102g/102m for transmutation to ground/isomeric state) |
103 | (z,p) | production of a proton (sum over MTs 600-647, if present), plus a residual (if any) |
104 | (z,d) | production of a deuteron (sum over MTs 650-699, if present), plus a residual (if any) |
105 | (z,t) | production of a triton (sum over MTs 700-749, if present), plus a residual (if any) |
106 | (z,^{3}He) | production of a ^{3}He particle (sum over MTs 750-799, if present), plus a residual (if any) |
107 | (z,α) | production of an alpha particle (sum over MTs 800-849, if present), plus a residual (if any) |
108 | (z,2α) | production of two alpha particles, plus a residual (if any) |
109 | (z,3α) | production of three alpha particles, plus a residual (if any) |
111 | (z,2p) | production of two protons, plus a residual (if any) |
112 | (z,pα) | production of a proton and an alpha particle, plus a residual (if any) |
113 | (z,t2α) | production of a triton and two alpha particles, plus a residual (if any) |
114 | (z,d2α) | production of a deuteron and two alpha particles, plus a residual (if any) |
115 | (z,pd) | production of proton and a deuteron, plus a residual (if any) |
116 | (z,pt) | production of a proton and a triton, plus a residual (if any) |
117 | (z,dα) | production of a deuteron and an alpha particle, plus a residual (if any) |
201 | (z,Xn) | total neutron production (use -6 instead) - redundant |
202 | (z,Xγ) | total photon production - redundant |
203 | (z,Xp) | total proton production - redundant |
204 | (z,Xd) | total deuteron production redundant |
205 | (z,Xt) | total triton production - redundant |
206 | (z,X^{3}He) | total ^{3}He production - redundant |
207 | (z,Xα) | total alpha production - redundant |
301 | (z,totheat) | total heat production; total heating number multiplied by total cross section (note difference to MCNP) |
443 | (z,kinkerma) | kinematic KERMA - Note to developers: check if this needs to be multiplied by total xs |
444 | (z,damenergy) | damage-energy production - Note to developers: check if this needs to be multiplied by total xs |
600 | (z,p_{0}) | production of a proton, leaving the residual nucleus in the ground state - MTs 600-649 can be used to replace MT 103 |
601-648 | (z,p_{i}) | production of a proton, leaving the residual nucleus in the ith excited state (i = 1,2,...,48) |
649 | (z,p_{c}) | production of a proton 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 - MTs 650-699 can be used to replace MT 104 |
651-698 | (z,d_{i}) | production of a deuteron, leaving the residual nucleus in the ith excited state (i = 1,2,...,48) |
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 - MTs 700-749 can be used to replace MT 105 |
701-748 | (z,t_{i}) | production of a triton, leaving the residual nucleus in the ith excited state (i = 1,2,...,48) |
749 | (z,t_{c}) | production of a triton in the continuum not included in the above discrete representation |
750 | (z,^{3}He_{0}) | production of a^{3}He particle, leaving the residual nucleus in the ground state - MTs 750-799 can be used to replace MT 106 |
751-798 | (z,^{3}He_{i}) | production of a ^{3}He particle, leaving the residual nucleus in the ith excited state (i = 1,2,...,48) |
799 | (z,^{3}He_{c}) | production of a^{3}He particle in the continuum not included in the above discrete representation |
800 | (z,α_{0}) | production of an alpha particle, leaving the residual nucleus in the ground state - MTs 800-849 can be used to replace MT 107 |
801 - 848 | (z,α_{i}) | production of an alpha particle, leaving the residual nucleus in the ith excited state (i = 1,2,...,48) |
849 | (z,α_{c}) | production of an alpha particle in the continuum not included in the above discrete representation |
875 | (z,2n_{0}) | production of a neutron, leaving the residual nucleus in the ground state - MTs 875-891 can be used to replace MT 16 |
876-890 | (z,2n_{i}) | production of a neutron, leaving the residual nucleus in the ith excited state (i = 1,2,...,48) |
891 | (z,2n_{c}) | production of a neutron in the continuum not included in the above discrete representation |
1002 | S(α,β) | elastic scattering - not an official ENDF MT number |
1004 | S(α,β) | inelastic scattering - not an official ENDF MT number |
Photon reactions
MT | Description | Notes |
---|---|---|
301 | average heating number | energy release |
502 | Rayleigh scattering | coherent scattering |
504 | Compton scattering | incoherent scattering |
516 | pair production | (sum over MTs 515 and 517, electron and nuclear field) |
522 | photoelectric effect | absorption |
Macroscopic reaction numbers
Neutron reactions
Reaction # | Description | Notes |
---|---|---|
-1 | macroscopic total cross section | |
-2 | macroscopic total capture cross section | sum of all reactions that do not produce secondary neutrons |
-3 | macroscopic total elastic scattering cross section | |
-4 | macroscopic total heating cross section | |
-5 | macroscopic total photon production cross section | |
-6 | macroscopic total fission cross section | |
-7 | macroscopic total fission neutron production cross section | |
-8 | macroscopic total fission energy production cross section | |
-9 | majorant cross section | |
-10 | macroscopic scattering recoil energy production cross section | calculated from neutron energy loss in elastic and inelastic scattering |
-11 | source rate | |
-15 | neutron density | flux multiplied by inverse neutron speed |
-16 | macroscopic total scattering neutron production cross section | |
-30 | temperature majorant cross section | majorant used for rejetion sampling in TMS |
-53 | macroscopic proton production cross section | |
-54 | macroscopic deuteron production cross section | |
-55 | macroscopic triton production cross section | |
-56 | macroscopic He-3 production cross section | |
-57 | macroscopic He-4 production cross section | |
-80 | total energy deposition | combines responses for fission heating, neutron heating based on KERMA coefficients and analog photon heating |
-100 | user-defined response function | followed by a function name corresponding to a function defined using the fun card, response material is omitted |
Photon reactions
Reaction # | Description | Notes |
---|---|---|
-9 | majorant cross section | Note to developers: check that this really works |
-11 | source rate | Note to developers: check that this really works |
-12 | analog photon heating | Energy deposition detector |
-15 | photon density | flux multiplied by 1/c (Note to developers: check that this really works) |
-25 | macroscopic total cross section | Note to developers: use -1 instead? |
-26 | macroscopic total heating cross section | Note to developers: use -4 instead? |
-27 | photon pulse-height detector | see detailed description |
-100 | user-defined response function | followed by a function name corresponding to a function defined using the fun card, response material is omitted |
-200 | photon dose rate in local material | in Gy/h, using mass attenuation coefficients from NIST data,^{[2]} see detailed description |
-201 | photon dose rate in A-150 Tissue-Equivalent Plastic | Reaction numbers -201 to -248 are reserved for photon dose rates in pre-defined material compositions using same data as -200 |
-202 | photon dose rate in adipose Tissue (ICRU-44) | |
-203 | photon dose rate in air, Dry (Near Sea Level) | |
-204 | photon dose rate in alanine | |
-205 | photon dose rate in B-100 Bone-Equivalent Plastic | |
-206 | photon dose rate in bakelite | |
-207 | photon dose rate in blood, Whole (ICRU-44) | |
-208 | photon dose rate in bone, Cortical (ICRU-44) | |
-209 | photon dose rate in brain, Grey/White Matter (ICRU-44) | |
-210 | photon dose rate in breast Tissue (ICRU-44) | |
-211 | photon dose rate in C-552 Air-equivalent Plastic | |
-212 | photon dose rate in calcium Sulfate | |
-213 | photon dose rate in 15 mmol/l Ceric Ammonium Sulfate Solution | |
-214 | photon dose rate in cesium Iodide | |
-215 | photon dose rate in concrete, Barite (Type BA) | |
-216 | photon dose rate in concrete, Ordinary | |
-217 | photon dose rate in eye Lens (ICRU-44) | |
-218 | photon dose rate in calcium Fluoride | |
-219 | photon dose rate in ferrous Sulfate (Standard Fricke) | |
-220 | photon dose rate in gadolinium Oxysulfide | |
-221 | photon dose rate in gafchromic Sensor | |
-222 | photon dose rate in gallium Arsenide | |
-223 | photon dose rate in glass, Lead | |
-224 | photon dose rate in photographic Emulsion (Kodak Type AA) | |
-225 | photon dose rate in lithium Fluride | |
-226 | photon dose rate in lithium Tetraborate | |
-227 | photon dose rate in lung Tissue (ICRU-44) | |
-228 | photon dose rate in magnesium Tetroborate | |
-229 | photon dose rate in mercuric Iodide | |
-230 | photon dose rate in muscle, Skeletal | |
-231 | photon dose rate in polyethylene Terephthalate (Mylar) | |
-232 | photon dose rate in radiochromic Dye Film (Nylon Base) | |
-233 | photon dose rate in ovary (ICRU-44) | |
-234 | photon dose rate in photographic Emulsion (Standard Nuclear) | |
-235 | photon dose rate in polymethyl Methacrylate | |
-236 | photon dose rate in polyethylene | |
-237 | photon dose rate in polystyrene | |
-238 | photon dose rate in polyvinyl Chloride | |
-239 | photon dose rate in glass, Borosilicate (Pyrex) | |
-240 | photon dose rate in polytetrafluoroethylene (Teflon) | |
-241 | photon dose rate in cadmium Telluride | |
-242 | photon dose rate in tissue-Equivalent Gas (Methane Based) | |
-243 | photon dose rate in tissue-Equivalent Gas (Propane Based) | |
-244 | photon dose rate in testis (ICRU-44) | |
-245 | photon dose rate in tissue, Soft (ICRU Four-Component) | |
-246 | photon dose rate in tissue, Soft (ICRU-44) | |
-247 | photon dose rate in plastic Scintillator (Vinyltoluene) | |
-248 | photon dose rate in water, Liquid |
References
- ^ Herman, M. and Trkov, A. "ENDF-6 Formats Manual." CSEWG Document ENDF-102 / BNL-90365-2009.
- ^ Hubbell, J. H. and Seltzer, S.M. "Tables of X-Ray Mass Attenuation Coefficients and Mass Energy-Absorption Coefficients." (version 1.4). http://www.nist.gov/pml/data/xraycoef/