# ENDF file definitions and supplied nuclear data

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FISPACT-II employs the standard ENDF reaction mt and other numbers to identify incident particle reactions, residual nuclide production, dpa, kerma, decay processes, fission yields, etc, depending on the library used and the completeness of the data. Below are descriptive lists which serve as a dictionary between the ENDF-6 values, corresponding FISPACT-II internal values, physical description and the details of the code use of these data. For more information on the the ENDF-6 format, see the ENDF-6 Manual.

## Neutron-induced reaction mt numbers

The table below lists all of the possible incident-particle reaction mt numbers that are read by FISPACT-II, as well as their products, N-Z modification of the parent, number of and species of the secondary particles. Note that two values mt=5,18 result in the removal of the parent nuclide and residuals are handled by a separate set of rules that employ mf=10 residual yields or mf=8 fission yields. For mf=10, the residual product data must be available in the incident-particle files and for mf=8 the user must employ the USEFISSION keyword and specify the requested fission yields. For more information see the fission example simulation.

Neutron induced reactions recognised by FISPACT-II
Projectile Products MT dZ dZ NSEC Secondaries
n total 1 0 0 0
n E 2 0 0 0
n nonel 3 0 0 0
n n 4 0 0 0
n O 5 0
n 2nd 11 -1 -3 1 $$^{2}$$H
n 2n 16 0 -1 0
n 3n 17 0 -2 0
n F 18 0
n 22 -2 -4 1 $$^{4}$$He
n n3α 23 -6 -12 3 $$^{4}$$He $$^{4}$$He $$^{4}$$He
n 2nα 24 -2 -5 1 $$^{4}$$He
n 3nα 25 -2 -6 1 $$^{4}$$He
n np 28 -1 -1 1 $$^{1}$$H
n n2α 29 -4 -8 2 $$^{4}$$He $$^{4}$$He
n 2n2α 30 -4 -9 2 $$^{4}$$He $$^{4}$$He
n nd 32 -1 -2 1 $$^{2}$$H
n nt 33 -1 -3 1 $$^{3}$$H
n nh 34 -2 -3 1 $$^{3}$$He
n nd2α 35 -5 -10 3 $$^{2}$$H $$^{4}$$He $$^{4}$$He
n nt2α 36 -5 -11 3 $$^{3}$$H $$^{4}$$He $$^{4}$$He
n 4n 37 0 -3 0
n 2np 41 -1 -2 1 $$^{1}$$H
n 3np 42 -1 -3 1 $$^{1}$$H
n n2p 44 -2 -2 2 $$^{1}$$H $$^{1}$$H
n npα 45 -3 -5 2 $$^{1}$$H $$^{4}$$He
n γ 102 0 1 0
n p 103 -1 0 1 $$^{1}$$H
n d 104 -1 -1 1 $$^{2}$$H
n t 105 -1 -2 1 $$^{3}$$H
n h 106 -2 -2 1 $$^{3}$$He
n α 107 -2 -3 1 $$^{4}$$He
n 108 -4 -7 2 $$^{4}$$He $$^{4}$$He
n 109 -6 -11 3 $$^{4}$$He $$^{4}$$He $$^{4}$$He
n 2p 111 -2 -1 2 $$^{1}$$H $$^{1}$$H
n 112 -3 -4 2 $$^{1}$$H $$^{4}$$He
n t2α 113 -5 -10 3 $$^{3}$$H $$^{4}$$He $$^{4}$$He
n d2α 114 -5 -9 3 $$^{2}$$H $$^{4}$$He $$^{4}$$He
n pd 115 -2 -2 2 $$^{1}$$H $$^{2}$$H
n pt 116 -2 -3 2 $$^{1}$$H $$^{3}$$H
n 117 -3 -5 2 $$^{2}$$H $$^{4}$$He
n 5n 152 0 -4 0
n 6n 153 0 -5 0
n 2nt 154 -1 -4 1 $$^{3}$$H
n 155 -3 -6 2 $$^{3}$$H $$^{4}$$He
n 4np 156 -1 -4 1 $$^{1}$$H
n 3nd 157 -1 -4 1 $$^{2}$$H
n ndα 158 -3 -6 2 $$^{2}$$H $$^{4}$$He
n 2npα 159 -3 -6 2 $$^{1}$$H $$^{4}$$He
n 7n 160 0 -6 0
n 8n 161 0 -7 0
n 5np 162 -1 -5 1 $$^{1}$$H
n 6np 163 -1 -6 1 $$^{1}$$H
n 7np 164 -1 -7 1 $$^{1}$$H
n 4nα 165 -2 -7 1 $$^{4}$$He
n 5nα 166 -2 -8 1 $$^{4}$$He
n 6nα 167 -2 -9 1 $$^{4}$$He
n 7nα 168 -2 -10 1 $$^{4}$$He
n 4nd 169 -1 -5 1 $$^{2}$$H
n 5nd 170 -1 -6 1 $$^{2}$$H
n 6nd 171 -1 -7 1 $$^{2}$$H
n 3nt 172 -1 -5 1 $$^{3}$$H
n 4nt 173 -1 -6 1 $$^{3}$$H
n 5nt 174 -1 -7 1 $$^{3}$$H
n 6nt 175 -1 -8 1 $$^{3}$$H
n 2nh 176 -2 -4 1 $$^{3}$$He
n 3nh 177 -2 -5 1 $$^{3}$$He
n 4nh 178 -2 -6 1 $$^{3}$$He
n 3n2p 179 -2 -4 2 $$^{1}$$H $$^{1}$$H
n 3n2α 180 -4 -10 2 $$^{4}$$He $$^{4}$$He
n 3npα 181 -3 -7 2 $$^{1}$$H $$^{4}$$He
n dt 182 -2 -4 2 $$^{2}$$H $$^{3}$$H
n npd 183 -2 -3 2 $$^{1}$$H $$^{2}$$H
n npt 184 -2 -4 2 $$^{1}$$H $$^{3}$$H
n ndt 185 -2 -5 2 $$^{2}$$H $$^{3}$$H
n nph 186 -3 -4 2 $$^{1}$$H $$^{3}$$He
n ndh 187 -3 -5 2 $$^{2}$$H $$^{3}$$He
n nth 188 -3 -6 2 $$^{3}$$H $$^{3}$$He
n ntα 189 -3 -7 2 $$^{3}$$H $$^{4}$$He
n 2n2p 190 -2 -3 2 $$^{1}$$H $$^{1}$$H
n ph 191 -3 -3 2 $$^{1}$$H $$^{3}$$He
n dh 192 -3 -4 2 $$^{2}$$H $$^{3}$$He
n 193 -4 -6 2 $$^{3}$$He $$^{4}$$He
n 4n2p 194 -2 -5 2 $$^{1}$$H $$^{1}$$H
n 4n2α 195 -4 -11 2 $$^{4}$$He $$^{4}$$He
n 4npα 196 -3 -8 2 $$^{1}$$H $$^{4}$$He
n 3p 197 -3 -2 3 $$^{1}$$H $$^{1}$$H $$^{1}$$H
n n3p 198 -3 -3 3 $$^{1}$$H $$^{1}$$H $$^{1}$$H
n 3n2pα 199 -4 -8 3 $$^{1}$$H $$^{1}$$H $$^{4}$$He
n 5n2p 200 -2 -6 2 $$^{1}$$H $$^{1}$$H

## Derived induced-particle reaction mt numbers

Several nuclear data values are not provided in the raw ENDF data, requiring summation where desired (such as gas production by species) or semi-empirical formulae to generate derived quantities such as kerma or dpa. These are done through the nuclear data processing scripts that are used to generate the nuclear data supplied with FISPACT-II. The following data are listed with their mt numbers and a physical description.

Note that these are for user information and do not affect the nuclide inventories, hence the lack of columns from the previous table.

Derived MT numbers read by FISPACT-II, including gas production, dpa and kerma
MT Description
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,Xh) Total helion (3He) production
207 (z,Xα) Total alpha particle production
301 Kerma total (eV-barns)
302 Kerma elastic
303 Kerma non-elastic (all but mt=2)
304 Kerma inelastic (mt={51-91})
318 Kerma fission (mt=18 or mt= {19, 20, 21, 38})
401 Kerma disappearance (mt={102-120})
402 Kerma radiative capture (mt=102)
403 Kerma proton production (mt=103)
407 Kerma α production (mt=107)
442 Total photon (eV-barns)
443 Total kinematic kerma (high limit)
444 Dpa total (eV-barns)
445 Dpa elastic (mt=2)
446 Dpa inelastic (mt={51-91})
447 Dpa disappearance (mt={102-120})

## Radioactive decay processes

FISPACT-II allows 27 decay processes and 9 decay radiation types that are used to follow the nuclide inventory and generate decay radiation source terms, respectively. These are summarised below.

### Decay types

The table below gives the internal IRT numbers and their ENDF-6 correspondence, as well as the parent nuclide N-Z shift, number and species of secondaries and how the code reports the decay in output data. Note that thres values IRT=6,17,27 result in the removal of the parent nuclide and residuals are handled by a separate set of rules that employ spontaneous fission yields. The user must employ the READSF keyword and include a sf_endf directory in the files file.

Decay types from MT=457 utilised by FISPACT-II
STYP RTYP Description $$\Delta Z$$ $$\Delta A$$ Code NSEC Secs
1 1 $$\beta^-$$ decay 1 0 b- 0
2 2 $$\beta^+$$ decay or electron capture $$-$$1 0 b+ 0
3 3 isomeric transition (IT) 0 0 IT 0
4 4 $$\alpha$$ decay $$-$$2 $$-$$4 a 1 $$^4$$He
5 5 neutron emission 0 $$-$$1 n 0
6 6 spontaneous fission (SF) $$-$$999 $$-$$999 SF 0
7 7 proton emission $$-$$1 $$-$$1 p 1 $$^1$$H
8 8 not used 0 0 0
9 9 not used 0 0 0
10 10 unknown 0 0 0
11 1.5 $$\beta^-$$ decay + neutron emission 1 $$-$$1 b-n 0
12 1.4 $$\beta^-$$ decay + $$\alpha$$ emission $$-$$1 $$-$$4 b-a 1 $$^4$$He
13 2.4 $$\beta^+$$ decay + $$\alpha$$ emission $$-$$3 $$-$$4 b+a 1 $$^4$$He
14 2.7 $$\beta^+$$ decay + proton emission $$-$$2 $$-$$1 b+p 1 $$^1$$H
15 3.4 IT followed by $$\alpha$$ emission $$-$$2 $$-$$4 IT+a 1 $$^4$$He
16 1.1 double $$\beta^-$$ decay 2 0 b-b- 0
17 1.6 $$\beta^-$$ decay followed by SF $$-$$999 $$-$$999 b-SF 0
18 7.7 double proton emission $$-$$2 $$-$$2 pp 2 $$^1$$H $$^1$$H
19 2.2 double $$\beta^+$$ or electron capture $$-$$2 0 b+b+ 0
20 1.55 $$\beta^-$$ and double neutron emission 1 $$-$$2 b-2n 0
21 1.555 $$\beta^-$$ and triple neutron emission 1 $$-$$3 b-3n 0
22 1.5555 $$\beta^-$$ and quadruple neutron emission 1 $$-$$4 b-4n 0
23 5.5 double neutron emission 0 $$-$$2 2n 0
24 5.55 triple neutron emission 0 $$-$$3 3n 0
25 2.77 $$\beta^+$$ decay + double proton emission $$-$$3 $$-$$2 b+2p 2 $$^1$$H $$^1$$H
26 2.777 $$\beta^+$$ decay + triple proton emission $$-$$4 $$-$$3 b+3p 3 $$^1$$H $$^1$$H $$^1$$H
27 2.6 $$\beta^+$$ decay followed by SF $$-$$999 $$-$$999 b+SF 0

### Decay radiation types

For decay radiation, FISPACT-II allows 9 radiation types which are taken from the ENDF-6 manual. Their physical description and how the code reports the data are summarised in the table below.

Decay radiation types from MT=457 utilised by FISPACT-II
STYP Radiation type Code
0 $$\gamma$$ gamma rays gamma
1 $$\beta^-$$ beta rays beta
2 ec,$$\beta^+$$ electron capture and/or positron emission ec, beta+
3 not known not known
4 $$\alpha$$ alpha particles alpha
5 $$n$$ neutrons n
6 SF spontaneous fission fragments SF
7 $$p$$ protons p
8 $$e^-$$ "discrete electrons" e-
9 $$x$$ X-rays and annihilation radiation x