101. Coupling of reactor transient simulations via the SALOME platform.
- Author
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Aydemir, N.U., Trottier, Alexandre, Xu, T., Echlin, M., and Chin, T.
- Subjects
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NUCLEAR reactors , *COUPLING constants , *SIMULATION methods & models , *COUPLED reactor cores , *THERMAL hydraulics - Abstract
Highlights • First results of Canadian Nuclear Laboratories' new PT-HWR transient simulation toolset. • SALOME-based coupling of ARIANT (formerly known as CATHENA4) and NESTLE-C. • Results for a stylized 20% LBLOCA are presented. Abstract Canadian Nuclear Laboratories has developed a toolset of coupled reactor transient simulation codes for pressure tube heavy water reactors. This paper presents the first demonstration of the toolset's capabilities, using a hypothetical 20% reactor inlet header break (critical break) scenario. This scenario induces strong feedback between thermalhydraulic and reactor physics phenomena, owing to a positive coolant voiding coefficient. The scenario was simulated using the advanced thermalhydraulics code ARIANT and the reactor physics code NESTLE-C, coupled together using the SALOME platform. This paper summarizes recent advances in ARIANT, the coupling methodology, and the results of the transient simulation. [ABSTRACT FROM AUTHOR]
- Published
- 2019
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