原子力発電運転協会｜福島第一―重大事故の間の沸騰形軽水炉(BWR)計装とコントロールシステムのパフォーマンスのケーススタディ

This document summarizes available information regarding instrumentation performance during the accident at Fukushima Daiichi power station in Japan. Specifically, the report identifies key parameters used for subsequent boiling water reactor (BWR)/3 with a Mark I containment (BWR/3-Mark I) and BWR/4-Mark I accident evaluations and what sensors are available to monitor these parameters, either directly or indirectly, within the reactor vessel, drywell, suppression pool, and reactor building. For each sensor, a description is provided regarding the measured data, conclusions related to the sensor survivability, and the basis for conclusions about its survivability. Analyses of assessments of the Fukushima Daiichi accident were performed to assess the performance of key instrumentation during this event. The analyses included observation by Japanese experts regarding instrumentation performance, alternative measurement capabilities, and comparisons of instrument readings. --4. FUKUSHIMA DAIICHI ACCIDENT-- 4.1 ACCIDENT SEQUENCE PROGRESSION-- 4.2 INSTRUMENTATION PERFORMANCE SUMMARY --4.2.1 Time Period: Earthquake to Tsunami --4.2.2 Time Period: Tsunami to Reactor Building Explosions --4.2.3 Time Period: Post-Reactor Building Explosions until the end of March 2011-- 4.3 INSTRUMENTATION AND CONTROL SYSTEM PERFORMANCE/FAILURE ASSESSMENT --5. CONCLUSIONS