RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES

• Main Authors: Ma Yugao, Liu Minyun, Chen Erhui, Xie Biheng, Chai Xiaoming, Huang Shanfang, Wang Kan, Yu Hongxing
• Format: Article
• Language: English
• Published: EDP Sciences 2021-01-01
• Series: EPJ Web of Conferences
• Subjects: monte carlo methods; finite element method; neutronic and thermomechanical (n-t/m) coupling; heat pipe reactor
• Online Access: https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06007.pdf

The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion.