Multi-group SP3 approximation for simulation of a three-dimensional PWR rod ejection accident
- 1. Ulsan National Institute of Science and Technology, School of Mechanical and Nuclear Engineering, UNIST-gil 50, Eonyang-eup, Ulju-gun, Ulsan 689-798 (Korea, Republic of)
- 2. University of Illinois at Urbana-Champaign, Department of Nuclear, Plasma, and Radiological Engineering, 216 Talbot Laboratory, Urbana, IL 61801 (United States)
- 3. University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, MI 48105 (United States)
Description
Highlights: • The multi-group SP3 method developed and implemented in PARCS for the MOX analysis. • The verifications were performed in 2D and 3D, 2G and MG, diffusion and transport, with and without feedback. • All results show consistency with the reference results obtained from the ANL PN transport code VARIANT for steady-state and transport calculations. • It was found that the SP3 angular approximation captures sufficient transport effects for both steady-state and transient, and provides essentially the same results as the VARIANT P5 method. • From the transient results of the full-core problem, it was noted that MG is more conservative than 2G, and P1 is more conservative than SP3. - Abstract: Previous researchers have shown that the simplified P3 (SP3) approximation is capable of providing sufficiently high accuracy for both static and transient simulations for reactor core analysis with considerably less computational expense than higher order transport methods such as the discrete ordinate or the full spherical harmonics methods. The objective of this paper is to provide a consistent comparison of two-group (2G) and multi-group (MG) diffusion and SP3 transport for rod ejection accident (REA) in a practical light water reactor (LWR) problem. The analysis is performed on two numerical benchmarks, a 3 × 3 assembly mini-core and a full pressurized water reactor (PWR) core. The calculations were performed using pin homogenized and assembly homogenized cross sections for a series of benchmarks of increasing difficulty, in two-dimensional (2D) and three-dimensional (3D), 2G and MG, diffusion and transport, as well as with and without feedback. All results show consistency with the reference results obtained from higher-order methods. It is demonstrated that the analyzed problems show small group-homogenization effects, but relatively significant transport effects which are satisfactorily addressed by the SP3 transport method. The sensitivity tests also show that, for the REA simulation, the MG is more conservative than 2G, P1 is more conservative than SP3 for a 1/3 MOX loaded full-core problem
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2014.10.019Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2014.10.019;
- PII
- S0306-4549(14)00558-1;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 77
- Journal Page Range
- p. 94-100
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47014987
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CROSS SECTIONS; DISCRETE ORDINATE METHOD; FUEL ASSEMBLIES; MIXED OXIDE FUELS; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; P3-APPROXIMATION; PWR TYPE REACTORS; ROD EJECTION ACCIDENTS; STEADY-STATE CONDITIONS; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL SYSTEMS
- Descriptors DEC
- ACCIDENTS; APPROXIMATIONS; CALCULATION METHODS; CRYSTAL LATTICES; CRYSTAL STRUCTURE; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EQUATIONS; EVALUATION; FUELS; MATERIALS; NUCLEAR FUELS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; SIMULATION; SOLID FUELS; SPHERICAL HARMONICS METHOD; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.