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Analysis of benchmark critical experiments with ENDF/B-VI data sets

Description: Several clean critical experiments were analyzed with ENDF/B-VI data to assess the adequacy of the data for U{sup 235}, U{sup 238} and oxygen. These experiments were (1) a set of homogeneous U{sup 235}-H{sub 2}O assemblies spanning a wide range of hydrogen/uranium ratio, and (2) TRX-1, a simple, H{sub 2}O-moderated Bettis lattice of slightly-enriched uranium metal rods. The analyses used the Monte Carlo program RCP01, with explicit three-dimensional geometry and detailed representation of cross… more
Date: December 31, 1991
Creator: Hardy, J. Jr. & Kahler, A. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Processing Neutron Cross Section Covariances using NJOY-99 and PUFF-IV

Description: With the growing demand for multigroup covariances, the National Nuclear Data Center (NNDC) has been experiencing an upsurge in its covariance data processing activities using the two US codes NJOY-99 (LANL) and PUFF-IV (ORNL). The code NJOY-99 was upgraded by incorporating the new module ERRORJ-2.3, while the NNDC served as the active user and provided feedback. The NNDC has been primarily processing neutron cross section covariances on its 64-bit Linux cluster in support of two DOE programs, … more
Date: June 24, 2008
Creator: Arcilla, R.; Kahler, A. C.; Oblozinsky, P. & Herman, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Initial data testing of ENDF/B-VI for thermal reactor benchmark analysis

Description: This paper summarizes some early data testing of ENDF/B-VI by members of the Cross Section Evaluation Working Group (CSEWG) Thermal Reactor Data Testing Subcommittee. Projections of ENDF/B-VI performance in thermal benchmark calculations are beginning to be available; and in some cases the calculations were performed with only a portion of the cross sections taken from version VI, the remainder taken from earlier data files. A factor delaying the thermal reactor data testing is that the final {… more
Date: December 31, 1991
Creator: Williams, M. L.; Kahler, A. C.; MacFarlane, R. E.; Milgram, M. & Wright, R. Q.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Monte Carlo simulation of gamma ray scanning gauge

Description: A gamma ray scanning gauge was simulated with Monte Carlo to study the properties of gamma scanning gauges and to resolve the counts coming from a {sup 235}U source from those coming from a contaminant ({sup 232}U) whose daughters emit high energy gamma rays. The simulation has been used to infer the amount of the {sup 232}U contaminant in a {sup 235}U source to select the best size for the NaI(Tl) detector crystal to minimize the effect of the contaminant. The results demonstrate that Monte Ca… more
Date: December 31, 1990
Creator: Hartfield, G. L.; Freeman, L. B.; Dei, D. E.; Emert, C. J.; Glickstein, S. S.; Kahler, A. C. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

AFCI-2.0 Library of Neutron Cross Section Covariances

Description: Neutron cross section covariance library has been under development by BNL-LANL collaborative effort over the last three years. The primary purpose of the library is to provide covariances for the Advanced Fuel Cycle Initiative (AFCI) data adjustment project, which is focusing on the needs of fast advanced burner reactors. The covariances refer to central values given in the 2006 release of the U.S. neutron evaluated library ENDF/B-VII. The preliminary version (AFCI-2.0beta) has been completed … more
Date: June 26, 2011
Creator: Herman, M.; Herman, M.; Oblozinsky, P.; Mattoon, C.; Pigni, M.; Hoblit, S. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

AFCI-2.0 Neutron Cross Section Covariance Library

Description: The cross section covariance library has been under development by BNL-LANL collaborative effort over the last three years. The project builds on two covariance libraries developed earlier, with considerable input from BNL and LANL. In 2006, international effort under WPEC Subgroup 26 produced BOLNA covariance library by putting together data, often preliminary, from various sources for most important materials for nuclear reactor technology. This was followed in 2007 by collaborative effort of… more
Date: March 1, 2011
Creator: Herman, M.; Oblozinsky, P.; Mattoon, C. M.; Pigni, M.; Hoblit, S.; Mughabghab, S. F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

Description: We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advan… more
Date: October 2, 2006
Creator: Chadwick, M. B.; Oblozinsky, P.; Herman, M.; Greene, N. M.; McKnight, R. D.; Smith, D. L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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