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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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