Development and testing of the VITAMIN-B7/BUGLE-B7 coupled neutron-gamma multigroup cross-section libraries
Creators
- Risner, J.M.1
- Wiarda, D.1
- Miller, T.M.1
- Peplow, D.E.1
- Patton, B.W.1
- Dunn, M.E.1
- Parks, B.T.2
- American Society for Testing and Materials - ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA, 19428-2959 (United States)
- European Working Group on Reactor Dosimetry - EWGRD, SCK.CEN, Mol (Belgium)
- 1. Oak Ridge National Laboratory, MS 6170, P.O. Box 2008, Oak Ridge, TN 37831-6170 (United States)
- 2. U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Mail Stop O10-B3, 11555 Rockville Pike, Rockville, MD 20852 (United States)
Description
The U.S. Nuclear Regulatory Commission's Regulatory Guide 1.190 states that calculational methods used to estimate reactor pressure vessel (RPV) fluence should use the latest version of the evaluated nuclear data file (ENDF). The VITAMIN-B6 fine-group library and BUGLE-96 broad-group library, which are widely used for RPV fluence calculations, were generated using ENDF/B-VI.3 data, which was the most current data when Regulatory Guide 1.190 was issued. We have developed new fine-group (VITAMIN-B7) and broad-group (BUGLE-B7) libraries based on ENDF/B-VII.0. These new libraries, which were processed using the AMPX code system, maintain the same group structures as the VITAMIN-B6 and BUGLE-96 libraries. Verification and validation of the new libraries were accomplished using diagnostic checks in AMPX, 'unit tests' for each element in VITAMIN-B7, and a diverse set of benchmark experiments including critical evaluations for fast and thermal systems, a set of experimental benchmarks that are used for SCALE regression tests, and three RPV fluence benchmarks. The benchmark evaluation results demonstrate that VITAMIN-B7 and BUGLE-B7 are appropriate for use in RPV fluence calculations and meet the calculational uncertainty criterion in Regulatory Guide 1.190. (authors)
Availability note (English)
Available from the INIS Liaison Officer for France, see the INIS contacts section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- INIS-US--13-ISRD-14-os6p-4
Conference
- Title
- 14. International Symposium on Reactor Dosimetry
- Acronym
- ISRD-14
- Dates
- 22-27 May 2011
- Place
- Bretton Woods, NH (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 44045411
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENCHMARKS; EVALUATION; NEUTRONS; NUCLEAR DATA COLLECTIONS; PRESSURE VESSELS; REGULATORY GUIDES; VALIDATION; VERIFICATION; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- BARYONS; CONTAINERS; DOCUMENT TYPES; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NUCLEONS; REACTORS; TESTING
Optional Information
- Notes
- 24 refs.