Verification of AEGIS/SCOPE2, a next-generation in-core fuel management system
Creators
- 1. Nuclear Fuel Industries, Ltd., 1-950, Asashiro-Nishi, Kumatori-cho, Sennan-gun, Osaka 590-0481 (Japan)
- 2. Nuclear Engineering, Ltd., 1-3-7 Tosabori, Nishi-ku, Osaka 550-0001 (Japan)
- 3. Nagoya Univ., Furo-cho, Chikusa-ku, Nagoya 464-8603 (Japan)
Description
AEGIS/SCOPE2 is a next-generation code system for in-core fuel management of PWRs; AEGIS is a 2-D lattice code which treats heterogeneous geometry based on the MOC, while SCOPE2 is a highly efficient parallel code which performs multi-group nodal-transport calculations in 3-D pin-by-pin geometry. Cross sections for SCOPE2 calculations are provided by AEGIS. In this paper, a preliminary result of numerical performance by the AEGIS/SCOPE2 system is presented. In assembly calculations, prediction results by AEGIS were compared with reference results by MVP, a continuous-energy Monte-Carlo code, for k∞ and fission rate distributions within an assembly. Good agreement between the codes was observed. A preliminary result of burnup calculation is also presented with comparisons of k∞ between AEGIS and MVP-burn, a burnup code coupled with MVP. AEGIS predicted k∞ within ±0.2 %Δk/k throughout burnup up to 60 GWd/t compared to the reference. An initial core of a commercial PWR at HZP was analyzed with AEGIS/SCOPE2 using nuclear data libraries including ENDF-B/VI rev. 8, B/VTI beta 0 and JENDL-3.3. In this preliminary study, the criticality was a little underestimated, however assembly-wise power distribution was predicted in good accuracy. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 8 p.
Conference
- Title
- American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
- Acronym
- PHYSOR-2006
- Dates
- 10-14 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43130101
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; ACCURACY; BURNUP; COMPARATIVE EVALUATIONS; CRITICALITY; CROSS SECTIONS; FUEL MANAGEMENT; MONTE CARLO METHOD; MULTIGROUP THEORY; MULTIPLICATION FACTORS; NODAL EXPANSION METHOD; NUCLEAR DATA COLLECTIONS; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR CORES; REACTOR LATTICE PARAMETERS; S CODES; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; VERIFICATION
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DIMENSIONLESS NUMBERS; ENRICHED URANIUM REACTORS; EVALUATION; MANAGEMENT; NEUTRON TRANSPORT THEORY; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 11 refs.