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Application of the Statistical Safety Evaluation Method to the Small Break Loca With High Pressure Injection Failure: Quantification of the Uncertainty of Uncovered Core Heat Transfer Model

[+] Author Affiliations
Toshihide Torige, Ikuo Kinoshita

Institute of Nuclear Safety System, Inc., Mihama, Fukui, Japan

Paper No. IMECE2013-64305, pp. V06BT07A052; 9 pages
  • ASME 2013 International Mechanical Engineering Congress and Exposition
  • Volume 6B: Energy
  • San Diego, California, USA, November 15–21, 2013
  • Conference Sponsors: ASME
  • ISBN: 978-0-7918-5629-1
  • Copyright © 2013 by ASME


In order to improve the reliability of the accident management technique “low-pressure injection by intentional depressurization of steam generator secondary side” in small-break loss-of-coolant accidents (SBLOCAs) with high-pressure injection failure, a statistical safety evaluation method is applied to the thermal-hydraulic analysis of this event. In a past study, the Phenomena Identification and Ranking Table (PIRT) was made and important phenomena were extracted. Then, sensitivity analyses with the important phenomena were carried out, and the influence on peak cladding temperature (PCT) was checked. As a result, one of the parameters whose influence on PCT was especially great was identified as “uncovered core heat transfer”. In this study, the uncertainty of the uncovered core heat transfer model was quantified using separate effect test data. As the separate effect test, uncovered-bundle heat transfer tests done with the Thermal Hydraulic Test Facility (THTF) of Oak Ridge National Laboratory (ORNL) were used. The THTF is a high-pressure bundle thermal-hydraulics loop, and was designed to produce a thermal-hydraulic environment similar to that expected in a SBLOCA.

Copyright © 2013 by ASME



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