Object-Oriented Three-Dimensional Fine-Mesh Transport Calculation on Parallel/Distributed Environments for Advanced Reactor Core Analyses

Journal Article · Mon Jul 15 04:00:00 EDT 2002 · Nuclear Science and Engineering

OSTI ID:20804789

Tatsumi, Masahiro; Yamamoto, Akio ^[1]

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1. Nuclear Fuel Industries, Ltd. (Japan)

This paper describes a comprehensive study on the feasibility of advanced reactor core analyses within the framework of pin-by-pin multigroup transport calculations using a prototype of the object-oriented parallel core calculation code SCOPE. The SCOPE code enables the coupling of the diffusion theory method and the SP{sub N} transport theory method. The formulation of the method coupling and its verifications with benchmarks are presented.Quantitative estimation of the pin-cell homogenization effects within the octant core geometry of a three-loop-type pressurized water reactor (PWR) was performed. Comparisons between results by heterogeneous and homogeneous calculations revealed the effects on pin-cell homogenization in large-scale geometry. In order to preserve the neutronic property in the heterogeneous calculation within the framework of pin-cell homogenized pin-by-pin calculations, the applicability of the homogenized cross section corrected by the superhomogeneisation SPH method was studied. It was found that the pin-by-pin nine-group calculation by the SP3 transport theory method with the SPH-corrected cross sections gave good accuracy for the pin power distribution approximately <1% of the root-mean-square error. The calculation accuracy of the transport calculation and the effectiveness of the method coupling were also demonstrated through analyses of the initial core of an identical three-loop-type PWR.With fine-grained parallelism, the identical convergence property was obtained regardless of the number of processors. Parallel performance was almost scalable up to eight processors, 93% with eight processors in three-dimensional nine-group fine-mesh transport calculations with meshes of 180 x 180 x 30.

• OSTI ID: 20804789
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 3 Vol. 141; ISSN NSENAO; ISSN 0029-5639
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACCURACY
BENCHMARKS
CROSS SECTIONS
ENVIRONMENT
POWER DISTRIBUTION
PWR TYPE REACTORS
REACTOR CORES
THREE-DIMENSIONAL CALCULATIONS
TRANSPORT THEORY
VERIFICATION