Coupling of reactor transient simulations via the SALOME platform. (April 2019)

• Record Type: Journal Article
• Authors: Aydemir, N.U.; Trottier, Alexandre; Xu, T.; Echlin, M.; Chin, T.
• Is Part Of: Annals of nuclear energy. Volume 126(2019)
• Page Start: 434
• Page End: 442
• Publication Date: 2019-04
• Subjects: PT-HWR -- Thermalhydraulics -- Reactor physics -- Code coupling -- Reactor transient -- SALOME; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2018.11.049
• Languages: English
• ISSNs: 0306-4549

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.