Application of Probabilistic Safety Assessment to the Pipe Rupture Incident at Hamaoka Unit-1

• Published in: Journal of nuclear science and technology Vol. 41; no. 1; pp. 77 - 85
• Main Authors: KISHI, Toru, KIKUCHI, Hiromu, MIURA, Satoshi, FUKUDA, Mamoru, HIRANO, Mitsumasa, WATANABE, Norio
• Format: Journal Article
• Language: English
• Published: Tokyo Taylor & Francis Group 01.01.2004; Atomic Energy Society of Japan
• Subjects: Applied sciences; core damage frequencies (CDFs); corrective actions; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; high pressure injection system (HPCI); Installations for energy generation and conversion: thermal and electrical energy; pipe rupture; probabilistic safety assessment (PSA); reactor core isolation cooling (RCIC); residual heat removal system (RHR); risk significance; safe operation rules (SORs); steam condensation mode (STCM); Asia; Japan; probabilistic safety assessment (PSA); safe operation rules (SORs); residual heat removal system (RHR); risk significance; Rupture; high pressure injection system (HPCI); reactor core isolation cooling (RCIC); Steam lines; Risk analysis; steam condensation mode (STCM); Probabilistic assessment; Safety measure; Accident; Nuclear power plant; pipe rupture; Fission reactor safety; corrective actions; core damage frequencies (CDFs)

On November 7, 2001, a pipe rupture occurred in the steam condensation line of the residual heat removal system at the Hamaoka Unit-1 while operating at rated power, resulting in steam release with radioactivity into the reactor building and the high pressure coolant injection being unavailable. The...