skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

Abstract

The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0. These advances focus on neutron cross sections, covariances, fission product yields and decay data, and represent work by the US Cross Section Evaluation Working Group (CSEWG) in nuclear data evaluation that utilizes developments in nuclear theory, modeling, simulation, and experiment. The principal advances in the new library are: (1) An increase in the breadth of neutron reaction cross section coverage, extending from 393 nuclides to 423 nuclides; (2) Covariance uncertainty data for 190 of the most important nuclides, as documented in companion papers in this edition; (3) R-matrix analyses of neutron reactions on light nuclei, including isotopes of He, Li, and Be; (4) Resonance parameter analyses at lower energies and statistical high energy reactions for isotopes of Cl, K, Ti, V, Mn, Cr, Ni, Zr and W; (5) Modifications to thermal neutron reactions on fission products (isotopes of Mo, Tc, Rh, Ag, Cs, Nd, Sm, Eu) and neutron absorber materials (Cd, Gd); (6) Improved minor actinide evaluations for isotopes of U, Np, Pu, and Am (we are notmore » making changes to the major actinides {sup 235,238}U and {sup 239}Pu at this point, except for delayed neutron data and covariances, and instead we intend to update them after a further period of research in experiment and theory), and our adoption of JENDL-4.0 evaluations for isotopes of Cm, Bk, Cf, Es, Fm, and some other minor actinides; (7) Fission energy release evaluations; (8) Fission product yield advances for fission-spectrum neutrons and 14 MeV neutrons incident on {sup 239}Pu; and (9) A new decay data sublibrary. Integral validation testing of the ENDF/B-VII.1 library is provided for a variety of quantities: For nuclear criticality, the VII.1 library maintains the generally-good performance seen for VII.0 for a wide range of MCNP simulations of criticality benchmarks, with improved performance coming from new structural material evaluations, especially for Ti, Mn, Cr, Zr and W. For Be we see some improvements although the fast assembly data appear to be mutually inconsistent. Actinide cross section updates are also assessed through comparisons of fission and capture reaction rate measurements in critical assemblies and fast reactors, and improvements are evident. Maxwellian-averaged capture cross sections at 30 keV are also provided for astrophysics applications. We describe the cross section evaluations that have been updated for ENDF/B-VII.1 and the measured data and calculations that motivated the changes, and therefore this paper augments the ENDF/B-VII.0 publication 'ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology,' Nuclear Data Sheets 107, 2931 (2006).« less

Authors:
; ;  [1]; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; more »; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; « less
  1. s
Publication Date:
Research Org.:
Brookhaven National Lab. (BNL), Upton, NY (United States). National Nuclear Data Center (NNDC)
Sponsoring Org.:
USDOE SC OFFICE OF SCIENCE (SC)
OSTI Identifier:
1034733
Report Number(s):
BNL-96636-2011-JA
Journal ID: ISSN 0090-3752; NDTSBA; R&D Project: EST-003-NEFA; KB0301041; TRN: US1200914
DOE Contract Number:  
DE-AC02-98CH10886
Resource Type:
Journal Article
Journal Name:
Nuclear Data Sheets
Additional Journal Information:
Journal Volume: 112; Journal Issue: 12; Journal ID: ISSN 0090-3752
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; ACTINIDES; ASTROPHYSICS; CRITICALITY; CROSS SECTIONS; DATA COVARIANCES; DECAY; DELAYED NEUTRONS; FAST REACTORS; FISSION; FISSION PRODUCTS; ISOTOPES; LIGHT NUCLEI; NEUTRON ABSORBERS; NEUTRON REACTIONS; NEUTRONS; NUCLEAR DATA COLLECTIONS; NUCLEAR THEORY; R MATRIX; REACTION KINETICS; THERMAL NEUTRONS; ZERO POWER REACTORS; national nuclear data center

Citation Formats

Chadwick, M B, Herman, M, Author: Chadwick, M B, Herman, M, Oblozinsky, P, Dunn, M E, Danon, Y, Kahler, A C, Smith, D L, Pritychenko, B, Arbanas, G, Arcilla, R, Brewer, R, Brown, D A, Capote, R, Carlson, A D, Cho, Y S, Derrien, H, Guber, K, Hale, G M, Hoblit, S, Holloway,S.: Johnson,T.D., Kawano, T, Kiedrowski, B C, Kim, H, Kunieda, S, Larson, N M, Leal, L, Lestone, J P, Little, R C, McCutchan, E A, MacFarlane, R E, MacInnes, M, Mattoon, C M, McKnight, R D, Mughabghab, S F, Nobre, G P.A., Palmiotti, G, Palumbo, A, Pigni, M T, Pronyaev, V G, Sayer, R O, Sonzogni, A A, Summers, N C, Talou, P, Thompson, I J, Trkov, A, Vogt, R L, van der Marck, S C, Wallner, A, White, M C, Wiarda, D, and Young, P G. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data. United States: N. p., 2011. Web. doi:10.1016/j.nds.2011.11.002.
Chadwick, M B, Herman, M, Author: Chadwick, M B, Herman, M, Oblozinsky, P, Dunn, M E, Danon, Y, Kahler, A C, Smith, D L, Pritychenko, B, Arbanas, G, Arcilla, R, Brewer, R, Brown, D A, Capote, R, Carlson, A D, Cho, Y S, Derrien, H, Guber, K, Hale, G M, Hoblit, S, Holloway,S.: Johnson,T.D., Kawano, T, Kiedrowski, B C, Kim, H, Kunieda, S, Larson, N M, Leal, L, Lestone, J P, Little, R C, McCutchan, E A, MacFarlane, R E, MacInnes, M, Mattoon, C M, McKnight, R D, Mughabghab, S F, Nobre, G P.A., Palmiotti, G, Palumbo, A, Pigni, M T, Pronyaev, V G, Sayer, R O, Sonzogni, A A, Summers, N C, Talou, P, Thompson, I J, Trkov, A, Vogt, R L, van der Marck, S C, Wallner, A, White, M C, Wiarda, D, & Young, P G. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data. United States. https://doi.org/10.1016/j.nds.2011.11.002
Chadwick, M B, Herman, M, Author: Chadwick, M B, Herman, M, Oblozinsky, P, Dunn, M E, Danon, Y, Kahler, A C, Smith, D L, Pritychenko, B, Arbanas, G, Arcilla, R, Brewer, R, Brown, D A, Capote, R, Carlson, A D, Cho, Y S, Derrien, H, Guber, K, Hale, G M, Hoblit, S, Holloway,S.: Johnson,T.D., Kawano, T, Kiedrowski, B C, Kim, H, Kunieda, S, Larson, N M, Leal, L, Lestone, J P, Little, R C, McCutchan, E A, MacFarlane, R E, MacInnes, M, Mattoon, C M, McKnight, R D, Mughabghab, S F, Nobre, G P.A., Palmiotti, G, Palumbo, A, Pigni, M T, Pronyaev, V G, Sayer, R O, Sonzogni, A A, Summers, N C, Talou, P, Thompson, I J, Trkov, A, Vogt, R L, van der Marck, S C, Wallner, A, White, M C, Wiarda, D, and Young, P G. 2011. "ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data". United States. https://doi.org/10.1016/j.nds.2011.11.002.
@article{osti_1034733,
title = {ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data},
author = {Chadwick, M B and Herman, M and Author: Chadwick, M B and Herman, M and Oblozinsky, P and Dunn, M E and Danon, Y and Kahler, A C and Smith, D L and Pritychenko, B and Arbanas, G and Arcilla, R and Brewer, R and Brown, D A and Capote, R and Carlson, A D and Cho, Y S and Derrien, H and Guber, K and Hale, G M and Hoblit, S and Holloway,S.: Johnson,T.D. and Kawano, T and Kiedrowski, B C and Kim, H and Kunieda, S and Larson, N M and Leal, L and Lestone, J P and Little, R C and McCutchan, E A and MacFarlane, R E and MacInnes, M and Mattoon, C M and McKnight, R D and Mughabghab, S F and Nobre, G P.A. and Palmiotti, G and Palumbo, A and Pigni, M T and Pronyaev, V G and Sayer, R O and Sonzogni, A A and Summers, N C and Talou, P and Thompson, I J and Trkov, A and Vogt, R L and van der Marck, S C and Wallner, A and White, M C and Wiarda, D and Young, P G},
abstractNote = {The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0. These advances focus on neutron cross sections, covariances, fission product yields and decay data, and represent work by the US Cross Section Evaluation Working Group (CSEWG) in nuclear data evaluation that utilizes developments in nuclear theory, modeling, simulation, and experiment. The principal advances in the new library are: (1) An increase in the breadth of neutron reaction cross section coverage, extending from 393 nuclides to 423 nuclides; (2) Covariance uncertainty data for 190 of the most important nuclides, as documented in companion papers in this edition; (3) R-matrix analyses of neutron reactions on light nuclei, including isotopes of He, Li, and Be; (4) Resonance parameter analyses at lower energies and statistical high energy reactions for isotopes of Cl, K, Ti, V, Mn, Cr, Ni, Zr and W; (5) Modifications to thermal neutron reactions on fission products (isotopes of Mo, Tc, Rh, Ag, Cs, Nd, Sm, Eu) and neutron absorber materials (Cd, Gd); (6) Improved minor actinide evaluations for isotopes of U, Np, Pu, and Am (we are not making changes to the major actinides {sup 235,238}U and {sup 239}Pu at this point, except for delayed neutron data and covariances, and instead we intend to update them after a further period of research in experiment and theory), and our adoption of JENDL-4.0 evaluations for isotopes of Cm, Bk, Cf, Es, Fm, and some other minor actinides; (7) Fission energy release evaluations; (8) Fission product yield advances for fission-spectrum neutrons and 14 MeV neutrons incident on {sup 239}Pu; and (9) A new decay data sublibrary. Integral validation testing of the ENDF/B-VII.1 library is provided for a variety of quantities: For nuclear criticality, the VII.1 library maintains the generally-good performance seen for VII.0 for a wide range of MCNP simulations of criticality benchmarks, with improved performance coming from new structural material evaluations, especially for Ti, Mn, Cr, Zr and W. For Be we see some improvements although the fast assembly data appear to be mutually inconsistent. Actinide cross section updates are also assessed through comparisons of fission and capture reaction rate measurements in critical assemblies and fast reactors, and improvements are evident. Maxwellian-averaged capture cross sections at 30 keV are also provided for astrophysics applications. We describe the cross section evaluations that have been updated for ENDF/B-VII.1 and the measured data and calculations that motivated the changes, and therefore this paper augments the ENDF/B-VII.0 publication 'ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology,' Nuclear Data Sheets 107, 2931 (2006).},
doi = {10.1016/j.nds.2011.11.002},
url = {https://www.osti.gov/biblio/1034733}, journal = {Nuclear Data Sheets},
issn = {0090-3752},
number = 12,
volume = 112,
place = {United States},
year = {Thu Dec 01 00:00:00 EST 2011},
month = {Thu Dec 01 00:00:00 EST 2011}
}