Passive Cooldown Performance of Integral Pressurized Water Reactor
Shoubao Dai, Jin Chun-nan, Jingfu Wang, Yuxiang Chen
Abstract
Open-access reader
Shoubao Dai, Jin Chun-nan, Jingfu Wang, Yuxiang Chen
Abstract
Open-access reader
The design of an integral pressurized water reactor (IPWR) focuses on enhancing the safety and reliability of the reactor by incorporating a number of inherent safety features and engineered safety features.However, the characteristics of passive safety systems for the marine reactors are quiet different from those for the land nuclear power plant because of the more formidable and dangerous operation environments of them.This paper presents results of marine black out accident analyses.In the case of a transient, the passive residual heat removal system (PRHRS) is designed to cool the reactor coolant system (RCS) from a normal operation condition to a hot shutdown condition by a natural circulation, and the shutdown cooling system (SCS) is designed to cool the primary system from a hot shutdown condition to a refueling condition by a forced circulation.A realistic calculation has been carried out by using the RELAP5/MOD3.4code and a sensitivity analysis has been performed to evaluate a passive cooldown capability.The results of the accident analyses show that the reactor coolant system and the passive residual heat removal system adequately remove the core decay heat by a natural circulation.
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The design of an integral pressurized water reactor (IPWR) focuses on enhancing the safety and reliability of the reactor by incorporating a number of inherent safety features and engineered safety features.However, the characteristics of passive safety systems for the marine reactors are quiet different from those for the land nuclear power plant because of the more formidable and dangerous operation environments of them.This paper presents results of marine black out accident analyses.In the case of a transient, the passive residual heat removal system (PRHRS) is designed to cool the reactor coolant system (RCS) from a normal operation condition to a hot shutdown condition by a natural circulation, and the shutdown cooling system (SCS) is designed to cool the primary system from a hot shutdown condition to a refueling condition by a forced circulation.A realistic calculation has been carried out by using the RELAP5/MOD3.4code and a sensitivity analysis has been performed to evaluate a passive cooldown capability.The results of the accident analyses show that the reactor coolant system and the passive residual heat removal system adequately remove the core decay heat by a natural circulation.
Key concepts: Pressurized water reactor, Nuclear engineering, Environmental science, Materials science, Waste management, Engineering