Published 2011 | Version v1
Miscellaneous

Development and testing of the VITAMIN-B7/BUGLE-B7 coupled neutron-gamma multigroup cross-section libraries

  • 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

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.