Modeling of the ORNL PCA Benchmark Using SCALE6.0 Hybrid Deterministic-Stochastic Methodology
Joint Authors
Trontl, Krešimir
Pevec, Dubravko
Matijević, Mario
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2013, Issue 2013 (31 Dec. 2013), pp.1-9, 9 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2013-10-22
Country of Publication
Egypt
No. of Pages
9
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
Revised guidelines with the support of computational benchmarks are needed for the regulation of the allowed neutron irradiation to reactor structures during power plant lifetime.
Currently, US NRC Regulatory Guide 1.190 is the effective guideline for reactor dosimetry calculations.
A well known international shielding database SINBAD contains large selection of models for benchmarking neutron transport methods.
In this paper a PCA benchmark has been chosen from SINBAD for qualification of our methodology for pressure vessel neutron fluence calculations, as required by the Regulatory Guide 1.190.
The SCALE6.0 code package, developed at Oak Ridge National Laboratory, was used for modeling of the PCA benchmark.
The CSAS6 criticality sequence of the SCALE6.0 code package, which includes KENO-VI Monte Carlo code, as well as MAVRIC/Monaco hybrid shielding sequence, was utilized for calculation of equivalent fission fluxes.
The shielding analysis was performed using multigroup shielding library v7_200n47g derived from general purpose ENDF/B-VII.0 library.
As a source of response functions for reaction rate calculations with MAVRIC we used international reactor dosimetry libraries (IRDF-2002 and IRDF-90.v2) and appropriate cross-sections from transport library v7_200n47g.
The comparison of calculational results and benchmark data showed a good agreement of the calculated and measured equivalent fission fluxes.
American Psychological Association (APA)
Matijević, Mario& Pevec, Dubravko& Trontl, Krešimir. 2013. Modeling of the ORNL PCA Benchmark Using SCALE6.0 Hybrid Deterministic-Stochastic Methodology. Science and Technology of Nuclear Installations،Vol. 2013, no. 2013, pp.1-9.
https://search.emarefa.net/detail/BIM-457563
Modern Language Association (MLA)
Matijević, Mario…[et al.]. Modeling of the ORNL PCA Benchmark Using SCALE6.0 Hybrid Deterministic-Stochastic Methodology. Science and Technology of Nuclear Installations No. 2013 (2013), pp.1-9.
https://search.emarefa.net/detail/BIM-457563
American Medical Association (AMA)
Matijević, Mario& Pevec, Dubravko& Trontl, Krešimir. Modeling of the ORNL PCA Benchmark Using SCALE6.0 Hybrid Deterministic-Stochastic Methodology. Science and Technology of Nuclear Installations. 2013. Vol. 2013, no. 2013, pp.1-9.
https://search.emarefa.net/detail/BIM-457563
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-457563