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Phenomena identification and ranking table for thermal-hydraulic phenomena during a small-break LOCA with loss of high pressure injection

  • Published:2014-05 Issue: Volume:73 Page:51-63
  • ISSN:0149-1970
  • Container-title:Progress in Nuclear Energy
  • language:en
  • Short-container-title:Progress in Nuclear Energy

Author:

Griffiths M.J.,Schlegel J.P.,Hibiki T.,Ishii M.,Kinoshita I.,Yoshida Y.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference18 articles.

1. Core liquid responses due to secondary-side depressurization during PWR small-break LOCA;Asaka;J. Nucl. Sci. Technol.,1998

2. Secondary-side depressurization during PWR cold-leg small break LOCAs based on ROSA-V/LSTF experiments and analyses;Asaka;J. Nucl. Sci. Technol.,1998

3. Small break loss of coolant accident Phenomena Identification and Ranking Table (PIRT) for Westinghouse pressurized water reactors;Bajorek,1999

4. Quantifying reactor safety margins part 6: a physically based method of estimating PWR large break loss of coolant accident PCT;Catton;Nucl. Eng. Des.,1990

5. Heat transfer in a partially blocked sodium-cooled rod bundle;Han,1979

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