ANALYSIS OF A BWR MARK Ⅰ REACTOR BUILDING RESPONSE TO VARIOUS POSTULATED SPENT FUEL POOL ACCIDENT SCENARIOS

摘要

Noteworthy accomplishments found within this document include the development and successful execution of a spent fuel pool (SFP) model with the MAAP 5.01 severe accident analysis code. Results obtained throughout the course of this endeavor lend insight into a Mark I containment building's response to a variety of SFP accident scenarios. Furthermore, this study provides insight into the ability of the MAAP 5.01 code to identify the impact of an SFP accident on reactor building conditions. SFP loading patterns have a significant impact on reactor building response based on the results of this study. Reactor building conditions observed include temperature changes, as well as flow rates through openings that lead to the environment. Currently, there is limited data available for Severe Accident Management Guideline (SAMG) development for SFP accident scenarios. This study serves to develop insights into reactor building response for postulated SFP accident scenarios of relevant SAMG response. Furthermore, with the ability to observe the evolution of reactor building compartment conditions during an SFP accident, habitability conditions can be assessed in order to determine the feasibility of allowing plant personnel to perform mitigative actions over extended time periods in each reactor building compartment. Of particular importance in this study is the fact that all scenarios are executed under the assumption that no cooling systems are available throughout the entire event. This is a more extreme situation than encountered during the Fukushima Dai-ichi event in March 2011.