ENDF reaction MT's and macroscopic reaction numbers

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Serpent uses standard ENDF reaction MT's to identify neutron and photon reactions. The numbers are used with detector response functions 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 MT's 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 definition of some response functions.


ENDF Reaction MT's

Neutron reactions

MT Description Notes
1 total
2 elastic scattering
3 nonelastic redundant
4 total inelastic scattering redundant (sum over MT's 51 to 91)
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 redundant
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 redundant
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 Note to developers: check if this needs to be multiplied by total xs
202 total photon production Note to developers: check if this needs to be multiplied by total xs
203 total proton production Note to developers: check if this needs to be multiplied by total xs
204 total deuteron production Note to developers: check if this needs to be multiplied by total xs
205 total triton production Note to developers: check if this needs to be multiplied by total xs
206 total 3He production Note to developers: check if this needs to be multiplied by total xs
207 total α production Note to developers: check if this needs to be multiplied by total xs
301 total heat production Total heating number multiplied by total cross section (note difference to MCNP)
443 kinematic KERMA Note to developers: check if this needs to be multiplied by total xs
444 damage-energy production Note to developers: check if this needs to be multiplied by total xs
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
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

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 equivalent with the F8 tally in MCNP
-5 macroscopic total photon production cross section
-6 macroscopic total fission cross section
-7 macroscopic total fission neutron production cross section \nu\Sigma_\mathrm{f}
-8 macroscopic total fission energy production cross section \kappa\Sigma_\mathrm{f}
-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
-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 equivalent with the *f8 tally in MCNP
-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

  1. ^ Herman, M. and Trkov, A. "ENDF-6 Formats Manual." CSEWG Document ENDF-102 / BNL-90365-2009.
  2. ^ 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/