Published October 2002 | Version v1
Conference paper Metadata-only

The ENHS core benchmark

Creators

  • 1. Dept. of Nuclear Engineering, University of California, Berkeley, CA 94720-1730 (United States)
  • 2. Reactor Analysis Division, Argonne National Laboratory, 9700 South Cass Av., Argonne, IL 60439-4842 (United States)
  • 3. Korea Atomic Energy Research Institute, Yusong, Taejon 305-600 (Korea, Republic of)

Description

Benchmarking of computational tools for neutronic design and analysis of the lead-cooled fast reactor ENHS was undertaken. The computational tools benchmarked include the MOCUP code and data libraries in use at UC Berkeley, the well-established fast reactor neutronic design tools in use at ANL, and similar tools in use at KAERI but with different cross-section data sets. Inter-compared are keff evolution with burnup, effective one group ν values and cross sections for fission and capture, burnup dependent inventory of fuel isotopes, reflector reactivity worth and space dependent burnup and peak neutron flux. (author)

Part of:
Proceedings of the PHYSOR 2002 International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
Imprint Pagination
14 p.

Conference

Title
International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing
Acronym
Physor 2002
Dates
7-10 Oct 2002
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
55004279
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; BURNUP; CROSS SECTIONS; FAST REACTORS; ISOTOPES; LEAD COOLED REACTORS; NEUTRON FLUX; NUCLEAR DATA COLLECTIONS; REACTOR DESIGN; SPACE DEPENDENCE; TOOLS
Descriptors DEC
DESIGN; EPITHERMAL REACTORS; EQUIPMENT; LIQUID METAL COOLED REACTORS; RADIATION FLUX; REACTOR LIFE CYCLE; REACTORS

Optional Information

Notes
16 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)