Use of MCDancoff factor correction for multi-group fuel depletion analyses of Liquid Salt Cooled Reactors
Creators
- 1. Department of Nuclear and Radiological Engineering, Georgia Institute of Technology, Atlanta, GA (United States)
Description
Liquid Salt Cooled Reactors (LSCRs) are high temperature reactors, cooled by liquid salt, with a TRISO-particle based fuel in a solid form (stationary fuel elements or circulating fuel pebbles); this paper is focusing on the former. In either case, due to the double heterogeneity, core physics analysis require different considerations with more complex approaches than LWRs core physics calculations. Additional challenges appear when using the multi-group approach. In this paper we examine the use of SCALE6.1.1. Double heterogeneity may be accounted for through the Dancoff factor, however, SCALE6.1.1 does not provide an automated method to calculate Dancoff Factors for fuel planks with TRISO fuel particles. Therefore, depletion with continuous energy Monte Carlo Transport (CE depletion) in SCALE6.2 beta was used to generate MC Dancoff factors for multi-group calculations. MCDancoff corrected multi-group depletion agrees with the results for CE depletion within ±100 pcm, and within ±2σ. Producing MCDancoff factors for multi-group (MG) depletion calculations is necessary to LSCR analysis because CE depletion runtime and memory requirements are prohibitive for routine use. MG depletion with MCDancoff provides significantly shorter runtime and lower memory requirements while providing results of acceptable accuracy. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the international conference on physics of reactors (PHYSOR2014)
- Imprint Pagination
- 5489 p.
- Journal Page Range
- 8 p.
- Report number
- JAEA-Conf--2014-003
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR2014
- Dates
- 28 Sep - 3 Oct 2014
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47042771
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CROSS SECTIONS; DANCOFF CORRECTION; DESIGN; FUEL ASSEMBLIES; FUEL PARTICLES; MOLTEN SALT COOLED REACTORS; MONTE CARLO METHOD; MULTIGROUP THEORY; OPTIMIZATION; REACTOR CORES
- Descriptors DEC
- CALCULATION METHODS; MOLTEN SALT REACTORS; NEUTRON TRANSPORT THEORY; REACTOR COMPONENTS; REACTORS; TRANSPORT THEORY
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: PAPERS, Paper ID: a11_1106115.pdf; 3 refs., 8 figs., 2 tabs.