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Phisics/relap5-3D results for exercises II-1 and II-2 of the OECD/NEA mhtgr-350 benchmark

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The Idaho National Laboratory (INL) Advanced Reactor Technologies (ART) High-Temperature Gas-Cooled Reactor (HTGR) Methods group currently leads the Modular High-Temperature Gas-Cooled Reactor (MHTGR) 350 benchmark. The benchmark consists of a set of lattice-depletion, steady-state, and transient problems that can be used by HTGR simulation groups to assess the performance of their code suites. The paper summarizes the results obtained for the first two transient exercises defined for Phase II of the benchmark. The Parallel and Highly Innovative Simulation for INL Code System (PHISICS), coupled with the INL system code RELAP5-3D, was used to generate the results for the Depressurized Conduction Cooldown (DCC) (exercise II-1a) and Pressurized Conduction Cooldown (PCC) (exercise II-2) transients. These exercises require the time-dependent simulation of coupled neutronics and thermal-hydraulics phenomena, and utilize the steady-state solution previously obtained for exercise I-3 of Phase I. This paper also includes a comparison of the benchmark results obtained with a traditional system code "ring" model against a more detailed "block" model that include kinetics feedback on an individual block level and thermal feedbacks on a triangular sub-mesh. The higher spatial fidelity that can be obtained by the block model is illustrated with comparisons of the maximum fuel temperatures, especially in the case of natural convection conditions that dominate the DCC and PCC events. Differences up to 125 K (or 10%) were observed between the ring and block model predictions of the DCC transient, mostly due to the block model's capability of tracking individual block decay powers and more detailed helium flow distributions. In general, the block model only required DCC and PCC calculation times twice as long as the ring models, and it therefore seems that the additional development and calculation time required for the block model could be worth the gain that can be obtained in the spatial resolution and detailed data available for these transients.

Original languageEnglish
Title of host publicationInternational Congress on Advances in Nuclear Power Plants, ICAPP 2016
PublisherAmerican Nuclear Society
Pages381-390
Number of pages10
ISBN (Electronic)9781510825949
StatePublished - 2016
Event2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016 - San Francisco, United States
Duration: Apr 17 2016Apr 20 2016

Publication series

NameInternational Congress on Advances in Nuclear Power Plants, ICAPP 2016
Volume1

Conference

Conference2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016
Country/TerritoryUnited States
CitySan Francisco
Period04/17/1604/20/16

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