Comparisons between passive RCCSS on degree of passive safety features against accidental conditions and methodology to determine structural thickness of scaled-down heat removal test facilities

Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita

Research output: Contribution to journalArticlepeer-review

Abstract

Reactor Cavity Cooling Systems (RCCSs) with passive safety features use the atmosphere as a coolant, which cannot be lost; however, the drawback is that they are easily affected by atmospheric disturbances. To realize the commercial application of two types of passive RCCSs, their safety must be evaluated, i.e., they must be able to remove heat from the reactor at all times and under any conditions, including both expected and unexpected natural phenomena and accidents. The objectives of this study are to understand the characteristics and the degree of passive safety features for heat removal by comparing RCCSs based on atmospheric radiation and on atmospheric natural circulation under the same conditions. Simulations of accidental conditions, such as increasing average heat transfer coefficient via natural convection due to natural disasters, were performed using STAR-CCM+, and a methodology to control the amount of heat removal was discussed. A new RCCS based on atmospheric radiation is recommended because of the excellent degree of passive safety features/conditions, and the ability to control amount of heat removal by heat transfer surfaces. Finally, a methodology to determine the structural thickness of RCCS of scaled-down heat removal test facilities for reproducing natural convection and radiation was developed, and experimental methods using pressurized and decompressed chambers were proposed. The authors are convinced that the proposed RCCS based on atmospheric radiation has advantage that the temperature of the RPV can be maintained stably against the disturbance of outside air.

Original languageEnglish
Article number108512
JournalAnnals of Nuclear Energy
Volume162
DOIs
Publication statusPublished - Nov 2021

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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