Author
S.C. Frankle
Bio: S.C. Frankle is an academic researcher from Los Alamos National Laboratory. The author has contributed to research in topics: Nuclear data & Neutron. The author has an hindex of 6, co-authored 8 publications receiving 2281 citations.
Papers
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Los Alamos National Laboratory1, National Nuclear Data Center2, Oak Ridge National Laboratory3, Argonne National Laboratory4, Lawrence Livermore National Laboratory5, National Institute of Standards and Technology6, Rensselaer Polytechnic Institute7, Idaho National Laboratory8, Westinghouse Electric9, Atomic Energy of Canada Limited10, Nuclear Research and Consultancy Group11
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.
1,913 citations
TL;DR: 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.« less
339 citations
Los Alamos National Laboratory1, Nuclear Energy Agency2, Brookhaven National Laboratory3, International Atomic Energy Agency4, National Institute of Standards and Technology5, Rensselaer Polytechnic Institute6, Oak Ridge National Laboratory7, Karlsruhe Institute of Technology8, Japan Atomic Energy Agency9, Ohio University10, Jožef Stefan Institute11, Nuclear Research and Consultancy Group12, Lawrence Livermore National Laboratory13, Argonne National Laboratory14, Idaho National Laboratory15, Institute for Reference Materials and Measurements16, Chalk River Laboratories17, Joint Institute for Nuclear Research18, Culham Centre for Fusion Energy19
TL;DR: The paper summarizes a program of nuclear science and computational work needed to create the new CIELO nuclear data evaluations and identifies discrepancies between various evaluations of the highest priority isotopes.
103 citations
TL;DR: The ENDF/B-VII.1 library is the latest revision to the United States Evaluated Nuclear Data File (ENDF) as discussed by the authors, which is currently in its seventh generation and was released in 2006, including the addition of new evaluated files (was 393 neutron files previously, now 423 including replacement of elemental vanadium and zinc evaluations with isotopic evaluations).
48 citations
TL;DR: In this article, an approach to uncertainty quantification for nuclear applications that combines the covariance evaluation of differential cross-section data and the error propagation from matching a matching process is presented.
Abstract: We present an approach to uncertainty quantification for nuclear applications that combines the covariance evaluation of differential cross-section data and the error propagation from matching a cr...
44 citations
Cited by
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Los Alamos National Laboratory1, Brookhaven National Laboratory2, Oak Ridge National Laboratory3, Rensselaer Polytechnic Institute4, Argonne National Laboratory5, Lawrence Livermore National Laboratory6, International Atomic Energy Agency7, National Institute of Standards and Technology8, Japan Atomic Energy Agency9, Idaho National Laboratory10, Jožef Stefan Institute11, Nuclear Research and Consultancy Group12, University of Vienna13
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.
2,171 citations
Los Alamos National Laboratory1, National Nuclear Data Center2, Oak Ridge National Laboratory3, Argonne National Laboratory4, Lawrence Livermore National Laboratory5, National Institute of Standards and Technology6, Rensselaer Polytechnic Institute7, Idaho National Laboratory8, Westinghouse Electric9, Atomic Energy of Canada Limited10, Nuclear Research and Consultancy Group11
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.
1,913 citations
TL;DR: The fourth version of the Japanese Evaluated Nuclear Data Library has been produced in cooperation with the Japanese Nuclear Data Committee as mentioned in this paper, and much emphasis is placed on the improvement of the original library.
Abstract: The fourth version of the Japanese Evaluated Nuclear Data Library has been produced in cooperation with the Japanese Nuclear Data Committee. In the new library, much emphasis is placed on the impro...
1,699 citations
Brookhaven National Laboratory1, Los Alamos National Laboratory2, International Atomic Energy Agency3, Rensselaer Polytechnic Institute4, National Institute of Standards and Technology5, Oak Ridge National Laboratory6, Argonne National Laboratory7, Lawrence Livermore National Laboratory8, Lawrence Berkeley National Laboratory9, North Carolina State University10, University of Michigan11, Institut de radioprotection et de sûreté nucléaire12, TRIUMF13, Rosatom14, Chalk River Laboratories15, Paul Scherrer Institute16, Karlsruhe Institute of Technology17, University of Bucharest18, Joint Institute for Nuclear Research19
TL;DR: The new ENDF/B-VIII.0 evaluated nuclear reaction data library as mentioned in this paper includes improved thermal neutron scattering data and uses new evaluated data from the CIELO project for neutron reactions on 1 H, 16 O, 56 Fe, 235 U, 238 U and 239 Pu described in companion papers.
1,249 citations
TL;DR: The Reference Input Parameter Library (RIPL-3) as mentioned in this paper is a library of validated nuclear-model input parameters, referred to as the RIPL-2 library, which has been used extensively in the development and use of nuclear reaction modelling.
1,013 citations