IAEA NEUTRON DATA STANDARDS (2017)

A.D. Carlson, et al., Nuclear Data Sheets 148 (2018) 143-188

#	Reaction	Energy Range	ENDF-6 formatted data	Free text format
1	H(n,n)	1e-5 eV to 20 MeV (Standard range: 1 keV - 20 MeV)	std17-001_H_001.endf	std17-001_H_001.txt
2	3He(n,p)	1e-5 eV to 20 MeV (Standard range: Thermal - 50 keV)	std-002_He_003.endf	not available
3	6Li(n,t)	1e-5 eV to 4 MeV (Standard range: Thermal - 1 MeV)	std17-003_Li_006.endf	std17-003_Li_006.txt
4	10B(n,α);(n,α1γ)	1e-5 eV to 1 MeV (Standard range: Thermal - 1 MeV)	std17-005_B_010.endf	std17-005_B_010.txt
5	natC(n,n)	up to 6.45 MeV (Standard range: 1keV - 1.8 MeV, angular distribution standard)	std17-006_C_000.endf	std17-006_C_000.txt
6	197Au(n,γ)	2.5 keV to 2.8 MeV (Standard range: 200keV - 2.5MeV)	std17-079_Au_197.endf	std17-079_Au_197.txt
7	235U(n,f)	150 eV to 200 MeV (Standard range: 150keV - 200MeV)	std17-092_U_235.endf	std17-092_U_235.txt
8	238U(n,f)	0.5 to 200 MeV (Standard range: 2 - 200MeV)	std17-092_U_238.endf	std17-092_U_238.txt
9	Thermal Neutron Constants (17): Total nubar, (nth,f), (nth,el), (nth,γ) cross sections for fissile targets 233U, 235U, 239Pu, 241Pu. Total nubar 252Cf(sf).	0.0253 eV (2200 m/s)		Standards2017_TNC.txt
10	197Au(n,γ)	Thermal: 98.66(0.14) b MACS (30 keV)= 620(11) mb
11	235U(n,f)	Integral from 7.8 eV to 11 eV = 247.5(3.3) b*eV

#	Reaction	Energy Range	ENDF-6 formatted data	Free text format
1	238U(n,γ)	150 eV - 2.2 MeV (150 eV - 20keV, average cross sections RRR)	rec17-092_U_238g.endf	rec17-092_U_238g.txt
2	239Pu(n,f)	150 eV - 200 MeV (150 eV - 2.5keV, average cross sections RRR)	rec17-094_Pu_239.endf	rec17-094_Pu_239.txt

#	Reaction	Energy Range	ENDF-6 formatted data	Free text format
10	252Cf(sf) PFNS from the IRDFF-II library W. Mannhart 1987-1989	0.00001-30 MeV (outgoing)	PFNS-Cf252sf-ENDF.txt	PFNS-Cf252sf (tabulated)
10	235U(nth,f) from the IRDFF-II library A. Trkov, V.G. Pronyaev, R. Capote, 2017	Thermal energy (incident), 0.00001-30 MeV (outgoing)	PFNS-U235nth-ENDF.txt	PFNS-U235nth (tabulated)

The neutron induced fission cross sections at high energies are recognised as a convenient reference for other reaction cross sections measurement where already established standards are not available yet. The reference (n,f) cross sections were evaluated for the following 5 nuclei (detailed information is available in Report INDC(NDS)-0681 "²⁰⁹Bi and ^natPb neutron fission cross sections as new references and extensions of the ²³⁵U, ²³⁸U and ²³⁹Pu(n,f) standards up to 1 GeV", B. Marcinkevicius, S. Simakov and V. Pronyaev ).
The ENDF-6 file with cross sections, energy-energy correlations and cross-reaction correlations for ²⁰⁹Bi, ^natPb, ²³⁵U, ²³⁸U and ²³⁹Pu (n,f) is available here: High-En-Ref.endf

Reaction	Energy Range	ENDF-6 formatted data	NJOY plot	Free text format
235U(n,f)	0.0253 eV - 1 GeV (reference above 200 MeV)	235U-Ref-HighErg.endf	file.pdf	235U_nf_Reference_xs_data.txt
238U(n,f)	0.0253 eV - 1 GeV (reference above 200 MeV)	238U-Ref-HighErg.endf	file.pdf	238U_nf_Reference_xs_data.txt
239Pu(n,f)	0.0253 eV - 300 MeV (reference above 200 MeV)	239Pu-Ref-HighErg.endf	file.pdf	239Pu_nf_Reference_xs_data.txt
209Bi(n,f)	34 MeV - 1 GeV	209Bi-Ref-HighErg.endf	file.pdf	209Bi_nf_Reference_xs_data.txt
natPb(n,f)	34 MeV - 1 GeV	natPB-Ref-HighErg.endf	file.pdf	natPb_nf_Reference_xs_data.txt

The reference discrete γ-ray production cross sections (n,n'γ) were evaluated for target nuclei ⁷Li (detailed information is available in Report INDC(NDS)-0739 by S. Simakov, R. Capote, R. Nelson and V. Pronyaev) and ⁴⁸Ti (Report INDC(NDS)-0740 by S. Simakov, R. Capote, R. Nelson and V. Pronyaev). The numerical data in the various formats in energy ranges recommended for use are presented in the following Table.

Reaction	Energy Range	ENDF-6 formatted data	NJOY plot	Free text format
10B(n,αγ=478keV)	0.0253 eV - 1 MeV	std17-005_B_010.endf		std17-005_B_010.txt
7Li(n,n'γ=478keV)	0.8 - 8.0 MeV	Li7nng478.endf	Li7nng478.pdf	Li7nng478.txt
48Ti(n,n'γ=984keV)	3 - 16 MeV	Ti48nng984.endf	Ti48nng984.pdf	Ti48nng984.txt

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