The Verification of depletion capabilities in RMC and APOLLO2/COCAGNE based on KAIST 1A benchmark
Creators
- 1. Department of Engineering Physics, Tsinghua University, Beijing, 100084 (China)
- 2. Computational Reactor Physics Group, Massachusetts Institute of Technology (United States)
Description
EDF R and D and the Department of Engineering Physics of Tsinghua University have cooperated to make code to code comparisons for their newly improved codes, APOLLO2/COCAGNE and RMC. As an extension to the previous collaboration on a 3D neutron transport PWR benchmark, the goal of this paper is to validate burnup capabilities in APOLLO2/COCAGNE and RMC based on the KAIST 1A benchmark. Before launching the core depletion calculation, the assembly calculations and the core criticality calculation were performed to identify the discrepancies between these two code systems. The comparisons focus on multiplication factors (Kinf or Keff), flux, reaction rates, power and concentrations of several isotopes. The results of the final core depletion calculation are in good agreement and thus the burnup capability of both APOLLO2/COCAGNE and RMC is stable and reliable. (authors)
Additional details
Publishing Information
- Publisher
- Korean Nuclear Society - KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Pagination
- 8 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
- 53074499
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BURNUP; CRITICALITY; ELECTRICITE DE FRANCE; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; PWR TYPE REACTORS; REACTION KINETICS; VERIFICATION
- Descriptors DEC
- DIMENSIONLESS NUMBERS; ENRICHED URANIUM REACTORS; FRENCH ORGANIZATIONS; KINETICS; NATIONAL ORGANIZATIONS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses