Journal ArticleDOI
Cross-Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX
Mark B. Chadwick,Phillip G. Young,Satoshi Chiba,S.C. Frankle,Gerald M. Hale,H. G. Hughes,Arjan J. Koning,R. C. Little,R. E. MacFarlane,Richard E. Prael,Laurie S. Waters +10 more
TLDR
In this article, the GNASH nuclear model code is used to calculate cross sections using Hauser-Feshbach, exciton, and Feshbach-Kerman-Koonin preequilibrium models.Abstract:
New accelerator-driven technologies that utilize spallation neutrons, such as the production of tritium and the transmutation of radioactive waste, require accurate nuclear data to model the performance of the target/blanket assembly and to predict neutron production, activation, heating, shielding requirements, and material damage. To meet these needs, nuclear-data evaluations and libraries up to 150 MeV have been developed for use in transport calculations to guide engineering design. By using advanced nuclear models that account for details of nuclear structure and the quantum nature of the nuclear scattering, significant gains in accuracy can be achieved below 150 MeV, where intranuclear cascade calculations become less accurate. Evaluations are in ENDF-6 format for important target/blanket and shielding materials (isotopes of H, C, N, O, Al, Si, P, Ca, Cr, Fe, Ni, Cu, Nb, W, Hg, and Pb) for both incident neutrons and incident protons. The evaluations are based on measured data as well as predictions from the GNASH nuclear model code, which calculates cross sections using Hauser-Feshbach, exciton, and Feshbach-Kerman-Koonin preequilibrium models. Elastic scattering distributions and direct reactions are calculated from the optical model. All evaluations specify production cross sections and energy-angle correlated spectra of secondary light particles as well as production crossmore » sections and energy distributions of heavy recoils and gamma rays. A formalism developed to calculate recoil energy distributions is presented. The use of these nuclear data in the MCNPX radiation transport code is also briefly described. This code merges essential elements of the LAHET and MCNP codes and uses these new data below 150 MeV and intranuclear cascade collision physics at higher energies. Extensive comparisons are shown between the evaluated results and experimental cross-section data to benchmark and validate the evaluated library. In addition, integral benchmarks of calculated and measured kerma coefficients for neutron energy deposition and neutron transmission through an iron slab compared with MCNPX calculations are provided. These evaluations have been accepted into the ENDF/B-VI library as Release 6.« lessread more
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Journal ArticleDOI
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
Mark B. Chadwick,M.W. Herman,P. Obložinský,Michael E Dunn,Yaron Danon,A.C. Kahler,David Livingstone Smith,Boris Pritychenko,Goran Arbanas,R. Arcilla,R. Brewer,David Brown,David Brown,Roberto Capote,Allan D. Carlson,Y.S. Cho,Herve Derrien,Klaus H Guber,Gerald M. Hale,S. Hoblit,S. Holloway,Timothy Johnson,Toshihiko Kawano,Brian C. Kiedrowski,H. Kim,S. Kunieda,S. Kunieda,Nancy M. Larson,Luiz C Leal,John Lestone,R. C. Little,E. A. McCutchan,R. E. MacFarlane,Michael MacInnes,Caleb Mattoon,R.D. McKnight,Said F. Mughabghab,Gustavo Nobre,Giuseppe Palmiotti,A. Palumbo,Marco T. Pigni,V.G. Pronyaev,R. O. Sayer,A. A. Sonzogni,N.C. Summers,Patrick Talou,Ian J. Thompson,Andrej Trkov,Ramona Vogt,S. C. van der Marck,Anton Wallner,Morgan C. White,Dorothea Wiarda,Phillip G. Young +53 more
TL;DR: The ENDF/B-VII.1 library as mentioned in this paper is the most widely used data set for nuclear data analysis and has been updated several times over the last five years. But the most recent version of the ENDF-B-VI.0 library is based on the JENDL-4.0 standard.
Journal ArticleDOI
ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
Mark B. Chadwick,P. Obložinský,M.W. Herman,N.M. Greene,R.D. McKnight,David Livingstone Smith,Phillip G. Young,R. E. MacFarlane,Gerald M. Hale,S.C. Frankle,A.C. Kahler,Toshihiko Kawano,R. C. Little,D. G. Madland,Peter Möller,Russell D. Mosteller,Philip R. Page,Patrick Talou,Holly R. Trellue,Morgan C. White,William B. Wilson,R. Arcilla,C.L. Dunford,Said F. Mughabghab,Boris Pritychenko,D. Rochman,Alejandro Sonzogni,C.R. Lubitz,T.H. Trumbull,J.P. Weinman,David Brown,D.E. Cullen,David P. Heinrichs,D. P. McNabb,Herve Derrien,Michael E Dunn,Nancy M. Larson,Luiz C Leal,Allan D. Carlson,R.C. Block,J.B. Briggs,E.T. Cheng,H.C. Huria,M.L. Zerkle,K.S. Kozier,A. Courcelle,V.G. Pronyaev,S. C. van der Marck +47 more
TL;DR: The ENDF/B-VII.0 as discussed by the authors file contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes, based on experimental data and theory predictions.
Journal ArticleDOI
Modern Nuclear Data Evaluation with the TALYS Code System
Arjan J. Koning,D. Rochman +1 more
TL;DR: A general overview of nuclear data evaluation and its applications as developed at NRG, Petten is presented and a new way of approaching the analysis of nuclear applications is opened, with consequences in both applied nuclear physics and safety of nuclear installations.
Journal ArticleDOI
Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures
Nina Petoussi-Henss,Wesley E. Bolch,Keith F. Eckerman,A. Endo,Nolan E. Hertel,J Hunt,M. Pelliccioni,Helmut Schlattl,Maria Zankl +8 more
TL;DR: This presentation discusses the relationships between dose conversion coefficients for operational and protection quantities, and methods used for evaluation of reference data.
Journal ArticleDOI
Measurement of the energy spectrum of cosmic-ray induced neutrons aboard an ER-2 high-altitude airplane.
P. Goldhagen,Marcel Reginatto,T. Kniss,John W. Wilson,R. C. Singleterry,I. W. Jones,W. Van Steveninck +6 more
TL;DR: The atmospheric ionizing radiation (AIR) project made simultaneous radiation measurements with 14 instruments on five flights of a NASA ER-2 high-altitude aircraft, measuring the cosmic-ray neutron spectrum, total neutron fluence rate, and neutron effective dose and dose equivalent rates and their dependence on altitude and geomagnetic cutoff.
References
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MCNP-A General Monte Carlo N-Particle Transport Code
TL;DR: In this article, the authors present a practical guide for the use of general-purpose Monte Carlo code MCNP, including several examples and a discussion of the particular techniques and the Monte Carlo method itself.
Journal ArticleDOI
Compilation of phenomenological optical-model parameters 1954–1975
C.M. Perey,F.G. Perey +1 more
TL;DR: In this paper, a compilation of optical-model parameters determined by fitting elastic-scattering angular distributions for various incident particles including heavy ions is presented, including parameters from previous compilations back to 1954 and from an extensive literature search in the leading journals and publications up to June 1975.
ReportDOI
The NJOY nuclear data processing system Version 91
R.E. MacFarlane,D.W. Muir +1 more
TL;DR: The NJOY2012 packages all the capabilities of the recent versions of NJOY, plus a few new options, using modern modularized Fortran-90 style.
Journal ArticleDOI
Optical-model analysis of the scattering of 24.7 MeV alpha particles
Lynne McFadden,G.R. Satchler +1 more
TL;DR: In this article, the measured elastic scattering of 24.7 MeV alpha particles from the nuclei O, Mg, Al, Si, Ca, Ma, Ni, Co, Cu, Ge, Zr, Ag, In, Sn, Hf, W, Au, Bi and U has been analyzed using the optical model.
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ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
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