Published April 2017 | Version v1
Book Metadata-only

Development of the CASL-VERA V4.2m5 MPACT 51-group Libraries with ENDF/B-VII.0 and VII.1

Creators

  • 1. Oak Ridge National Laboratory, 1 Bethel Valley Rd., Oak Ridge, TN 37831 (United States)
  • 2. Department of Nuclear Science and Engineering, University of Michigan: 2355 Bonisteel Blvd. Ann Arbor, MI, 48105 (United States)

Description

The MPACT neutronics module of the Consortium for Advanced Simulation of Light Water Reactors (CASL) core simulator is a 3-D whole core transport code being developed for the CASL toolset, Virtual Environment for Reactor Analysis (VERA). The v4.1m3 MPACT 47-group library with ENDF/B-VII.0, which was developed previously by using Oak Ridge National Laboratory AMPX/SCALE code packages, includes deficiencies, especially for burnt fuel cases. New v4.2m5 MPACT 51-group libraries with ENDF/B-VII.0 and VII.1 have been developed to have better accuracy by improving the library generation methodology. This study discusses a detailed procedure to generate the MPACT 51-group libraries and results for various benchmark problems. (authors)

Additional details

Publishing Information

Publisher
Korean Nuclear Society - KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Pagination
7 p.

Conference

Title
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017
Acronym
M and C 2017
Dates
16-20 Apr 2017
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
France
INIS RN
53074484
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; BENCHMARKS; COMPUTERIZED SIMULATION; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; SIMULATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Descriptors DEC
ANALOG SYSTEMS; ENERGY SOURCES; FUELS; FUNCTIONAL MODELS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTOR MATERIALS; REACTORS; SIMULATION

Optional Information

Notes
9 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses