nTRACER whole core transport solutions to C5G7-TD benchmark
Creators
- 1. Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul, 151-744 (Korea, Republic of)
Description
The C5G7-TD benchmark problems are solved by the nTRACER direct whole calculation code employing faithful models of the core configuration and transient control parameters. In the cases of TD1-1 through TD1-3, nTRACER results are compared with those of the SUHAM-TD code of the benchmark originator to confirm the soundness of the solutions. For selected 2-D cases, the nTRACER results are compared with the McCARD Monte Carlo transient simulation results. For the 3-D TD4 problems involving control rod insertions and withdrawals, a fine axial plane model is used first to generate the reference solutions without significant control rod cusping effect. Then coarser axial plane models are used in which the modified approximate flux weighting method is employed as a decusping approach. The results consisting of transient power behaviors and dynamic reactivity changes are presented. (authors)
Additional details
Publishing Information
- Publisher
- Korean Nuclear Society - KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Pagination
- 9 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
- 53074509
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; CONFIGURATION; CONTROL ELEMENTS; CUSPED GEOMETRIES; MONTE CARLO METHOD; NEUTRON TRANSPORT; REACTIVITY; SOUND WAVES; TRANSIENTS
- Descriptors DEC
- CALCULATION METHODS; MAGNETIC FIELD CONFIGURATIONS; NEUTRAL-PARTICLE TRANSPORT; OPEN CONFIGURATIONS; RADIATION TRANSPORT; REACTOR COMPONENTS; SIMULATION
Optional Information
- Notes
- 16 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses