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Title: Generation and Testing of the ENDF/B-VI Continuous-Energy Cross-Section Library for Use with Continuous-Energy Versions of KENO

Abstract

KENO V.a and KENO-VI are Monte Carlo codes that solve the multigroup form of the Boltzmann transport equation. These codes are part of the SCALE system of codes and are used for performing criticality calculations of systems with fissionable material. In general, continuous-energy Monte Carlo methods are preferred because such an approach avoids many of the assumptions inherent in the multigroup treatment. On the other hand, continuous-energy treatment is much more demanding in terms of computer storage space for data, memory requirements, and calculation speed. Continuous-energy versions of KENO V.a and KENO-VI have been created and are being extensively tested. Generation of ENDF/B-VI continuous-energy cross sections is explained, and the results of the validation and verification of the codes and the data are presented.

Authors:
 [1];  [1];  [1];  [1];  [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
931781
DOE Contract Number:
DE-AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 8th International Conference of Nuclear Criticality Safety, St. Petersburg, Russian Fed., 20070528, 20070601
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; BOLTZMANN EQUATION; COMPUTERS; CRITICALITY; CROSS SECTIONS; FISSIONABLE MATERIALS; MONTE CARLO METHOD; SAFETY; STORAGE; TESTING; VALIDATION; VERIFICATION; NUCLEAR DATA COLLECTIONS; COMPUTER CODES

Citation Formats

Goluoglu, Sedat, Dunn, Michael E, Greene, Norman Maurice, Petrie Jr, Lester M, and Hollenbach, Daniel F. Generation and Testing of the ENDF/B-VI Continuous-Energy Cross-Section Library for Use with Continuous-Energy Versions of KENO. United States: N. p., 2007. Web.
Goluoglu, Sedat, Dunn, Michael E, Greene, Norman Maurice, Petrie Jr, Lester M, & Hollenbach, Daniel F. Generation and Testing of the ENDF/B-VI Continuous-Energy Cross-Section Library for Use with Continuous-Energy Versions of KENO. United States.
Goluoglu, Sedat, Dunn, Michael E, Greene, Norman Maurice, Petrie Jr, Lester M, and Hollenbach, Daniel F. Mon . "Generation and Testing of the ENDF/B-VI Continuous-Energy Cross-Section Library for Use with Continuous-Energy Versions of KENO". United States. doi:.
@article{osti_931781,
title = {Generation and Testing of the ENDF/B-VI Continuous-Energy Cross-Section Library for Use with Continuous-Energy Versions of KENO},
author = {Goluoglu, Sedat and Dunn, Michael E and Greene, Norman Maurice and Petrie Jr, Lester M and Hollenbach, Daniel F},
abstractNote = {KENO V.a and KENO-VI are Monte Carlo codes that solve the multigroup form of the Boltzmann transport equation. These codes are part of the SCALE system of codes and are used for performing criticality calculations of systems with fissionable material. In general, continuous-energy Monte Carlo methods are preferred because such an approach avoids many of the assumptions inherent in the multigroup treatment. On the other hand, continuous-energy treatment is much more demanding in terms of computer storage space for data, memory requirements, and calculation speed. Continuous-energy versions of KENO V.a and KENO-VI have been created and are being extensively tested. Generation of ENDF/B-VI continuous-energy cross sections is explained, and the results of the validation and verification of the codes and the data are presented.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 2007},
month = {Mon Jan 01 00:00:00 EST 2007}
}

Conference:
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  • Several integral shielding benchmarks were selected to perform data testing for new multigroup cross-section libraries compiled from the ENDF/B-VI data for light water reactor (LWR) shielding and dosimetry. The new multigroup libraries, BUGLE-93 and VITAMIN-B6, were studied to establish their reliability and response to the benchmark measurements by use of radiation transport codes, ANISN and DORT. Also, direct comparisons of BUGLE-93 and VITAMIN-B6 to BUGLE-80 (ENDF/B-IV) and VITAMIN-E (ENDF/B-V) were performed. Some benchmarks involved the nuclides used in LWR shielding and dosimetry applications, and some were sensitive specific nuclear data, i.e. iron due to its dominant use in nuclear reactormore » systems and complex set of cross-section resonances. Five shielding benchmarks (four experimental and one calculational) are described and results are presented.« less
  • The purpose of this study is to compare the results of using either the reference cross-section data set ENDF/B-V or ENDF/B-VI RACER vectorized Monte Carlo calculations on several fast critical experiments. Seven benchmark cores were chosen that span a range of [sup 235]U enrichments and neutron leakage fractions. These include Godiva, Flat-Top-25, Zero-Power Reactor (ZPR)-Ill 6F, Vera-1 B, ZPR-III 12, ZPR- III 12, and Zebra-2.
  • The purpose of this study is to investigate the eigenvalue sensitivity to changes in ENDF/B-V and ENDF/B-VI cross section data sets by comparing RACER vectorized Monte Carlo calculations for several thermal and intermediate spectrum critical experiments. Nineteen Oak Ridge and Rocky Flats thermal solution benchmark critical assemblies that span a range of hydrogen-to-{sup 235}U (H/U) concentrations (2052 to 27.1) and above-thermal neutron leakage fractions (0.555 to 0.011) were analyzed. In addition, three intermediate spectrum critical assemblies (UH3-UR, UH3-NI, and HISS-HUG) were studied.
  • A new multigroup cross-section library based on ENDF/B-VI data has been produced and tested for light water reactor shielding and reactor pressure vessel dosimetry applications. This fine-group library, which is designated VITAMIN-B6, contains 120 nuclides. Several dosimetry response functions and kerma factors for all 120 nuclides are also included with the library. Significant benchmark data testing of VITAMIN-B6 was an integral part of this development work to accelerate the qualification. Over 50 benchmarks were calculated using the VITAMIN-B6 library. In general, results using the new data show significant improvements relative to earlier ENDF data.