TY - GEN
T1 - Coupled Simulation of Reactor Pressure Vessel (RPV) subjected to Pressurized Thermal Shock (PTS) Using Cardinal
AU - Yu, Yiqi
AU - Novak, April
AU - Shaver, Dillon
AU - Merzari, Elia
N1 - This work was supported by the U.S. Department of Energy (US DOE), Office of Nuclear Energy, Nuclear Energy Advanced Modeling and Simulation (NEAMS), under contract DE-AC02-06CH11357. The U.S. Government retains for itself, and others acting on its behalf, a paid-up nonexclusive, irrevocable worldwide license in said article to reproduce, prepare derivative works, distribute copies to the public, and perform publicly and display publicly, by or on behalf of the Government. Argonne National Laboratory's work was supported by the US DOE Office of Nuclear Energy under contract number DE-AC02-06CH11357.
PY - 2022
Y1 - 2022
N2 - As one of the most significant components of a Reactor, the Reactor Pressure Vessel (RPV) is exposed to an aggressive environment during the operation time (e.g. more than 40 years). Ageing degradation mechanisms (e.g. thermo-fatigue) could grow initial defects up to a critical size, increasing the susceptibility to failure in the RPV. Very limited studies consider the real conditions of the RPV subjected to a thermal shock due to a Loss of Coolant Accident (LOCA). During a LOCA event, the most severe conditions take place when the emergency core cooling (ECC) water is injected inside the cold legs filled initially with hotter water and/or steam. The rapid cooling of the down-comer and the internal RPV surface followed probably by re-pressurization of the RPV causes large temperature gradients and variation of pressure which induces thermal-mechanical stresses. In order to develop the model for integrity assessment of a RPV subjected to pressurized thermal shock (PTS), a multi-physics simulation, which includes the thermo-hydraulic, thermo-mechanical and fracture mechanics analysis is necessary. In this paper, a demonstrational coupled simulation is performed to support multi-physics analysis for RPV subjected to PTS. The study use a simplified computational domain to represents a real RPV. The purpose of the study is to demonstrate the capability of predicting the transient temperature and stress response of RPV to ECC injection with coupled simulation. The prediction of the temperature and stress field is achieved by using Cardinal, a wrapping of the GPU-oriented spectral element Computational Fluid Dynamics (CFD) code NekRS and other multi-physics sub-module within the MOOSE framework.
AB - As one of the most significant components of a Reactor, the Reactor Pressure Vessel (RPV) is exposed to an aggressive environment during the operation time (e.g. more than 40 years). Ageing degradation mechanisms (e.g. thermo-fatigue) could grow initial defects up to a critical size, increasing the susceptibility to failure in the RPV. Very limited studies consider the real conditions of the RPV subjected to a thermal shock due to a Loss of Coolant Accident (LOCA). During a LOCA event, the most severe conditions take place when the emergency core cooling (ECC) water is injected inside the cold legs filled initially with hotter water and/or steam. The rapid cooling of the down-comer and the internal RPV surface followed probably by re-pressurization of the RPV causes large temperature gradients and variation of pressure which induces thermal-mechanical stresses. In order to develop the model for integrity assessment of a RPV subjected to pressurized thermal shock (PTS), a multi-physics simulation, which includes the thermo-hydraulic, thermo-mechanical and fracture mechanics analysis is necessary. In this paper, a demonstrational coupled simulation is performed to support multi-physics analysis for RPV subjected to PTS. The study use a simplified computational domain to represents a real RPV. The purpose of the study is to demonstrate the capability of predicting the transient temperature and stress response of RPV to ECC injection with coupled simulation. The prediction of the temperature and stress field is achieved by using Cardinal, a wrapping of the GPU-oriented spectral element Computational Fluid Dynamics (CFD) code NekRS and other multi-physics sub-module within the MOOSE framework.
KW - Cardinal
KW - MOOSE
KW - multi-physics
KW - Pressurized Thermal Shock (PTS)
KW - Reactor Pressure Vessel (RPV)
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U2 - 10.13182/T126-38792
DO - 10.13182/T126-38792
M3 - Conference contribution
AN - SCOPUS:85202850336
T3 - Proceedings of Advances in Thermal Hydraulics, ATH 2022 - Embedded with the 2022 ANS Annual Meeting
SP - 758
EP - 770
BT - Proceedings of Advances in Thermal Hydraulics, ATH 2022 - Embedded with the 2022 ANS Annual Meeting
PB - American Nuclear Society
T2 - 5th International Topical Meeting on Advances in Thermal Hydraulics 2022, ATH 2022, held in conjunction with the 2022 American Nuclear Society ,ANS Annual Meeting
Y2 - 12 June 2022 through 16 June 2022
ER -