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Conference Article: The PBMR Steady State And Coupled Kinetics Core Thermal-Hydraulics Benchmark Test Problems

Frederik Reitsma, Gerhard Strydom, Reactor Analysis Group, PBMR (Pty) Ltd, SOUTH AFRICA; Han de Haas, D.F. da Cruz, Fuel, Actinides & Isotopes Group, NRG, THE NETHERLANDS; Kostadin Ivanov, Bismark Tyobeka, Nuclear Engineering Program, Penn State University, USA; Ramatsemela Mphahlele, Nuclear Engineering Program, Penn State University, USA and National Nuclear Regulator, Centurion, SOUTH AFRICA; Tom Downar, Volkan Seker, Nuclear Engineering Department, Purdue University, USA; Hans D. Gougar, Fission & Fusion Systems, INEEL, USA

Abstract

In support of the Pebble Bed Modular Reactor (PBMR) Verification and Validation (V&V) effort, a set of benchmark test problems has been defined that focus on coupled core neutronics and thermal-hydraulic code-to-code comparisons. The motivation is not only to test the existing methods or codes available for High-temperature Gas-cooled Reactors (HTGRs), but also to serve as a basis for the development of more accurate and efficient tools to analyse the neutronics and thermal-hydraulic behaviour for design and safety evaluations in future. The reference design for the PBMR268 benchmark problem is derived from the 268 MW PBMR design with a dynamic central column containing only graphite spheres. Several simplifications were made to the design in order to limit the need for any further approximations when defining code models. During this process, care was taken to ensure that all the important characteristics of the reactor design were preserved. The definition and initial phases of the benchmark were performed under a cooperative research project between NRG, Penn State University (PSU) and PBMR (Pty) Ltd. However, participation has recently been extended to include Purdue University and INEEL, and will be opened as soon as the benchmark definition has reached maturity. The benchmark has also been formally proposed as an OECD benchmark problem and approval is expected this year. In this paper, the benchmark definition and the different test cases are described in some detail. Phase 1 focuses on steady-state conditions with the purpose of quantifying differences between code systems, models and basic data. It also serves as the basis to establish a common starting condition for the transient cases. In Phase 2, the focus is on performing coupled kinetics/core thermal-hydraulics test problems with a common cross-section and material property sets. The six events selected are described, and examples of some results are included to illustrate the behaviour of the transients.

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key words: PBMR, Test Problems, Benchmark, Kinetics, Verification & Validation, VSOP, TINTE, PANTHERMIX, NEM, PARCS, MICROX, THERMIX
Reference:
Proceedings of the Conference on High Temperature Reactors, Beijing, China, September, 22-24, 2004
International Atomic Energy Agency, Vienna (Austria)
HTR-2004, pp:1-19