Top of page. Skip to main contents. Skip to sub menu. Skip to main menu. Skip to footer.

HOME > Technology > Technical ReviewVolume 49  Number 1  > A New Concept for Critical Heat Flux Correlations for Safety Analysis of Pressurized-water Reactors
Mitsubishi Heavy Industries Technical Review
 Volume 50 (2013)
 Volume 49 (2012)
 Volume 48 (2011)
 Volume 47 (2010)
 Volume 46 (2009)
 Volume 45 (2008)
 Volume 44 (2007)
 Volume 43 (2006)
 Volume 42 (2005)
 Volume 41 (2004)
 Volume 40 (2003)
 Volume 39 (2002)
 Volume 38 (2001)
 Volume 37 (2000)
 Volume 36 (1999)
 Volume 35 (1998)
 Volume 34 (1997)
 Volume 33 (1996)
 Volume 32 (1995)
 Volume 31 (1994)
Mitsubishi Heavy Industries Technical Review
 Volume 49 Number 1  New Products & Technologies
 English: Pdf
 Japanese: Pdf
A New Concept for Critical Heat Flux Correlations
for Safety Analysis of Pressurized-water Reactors





The most important priority of nuclear power plant design is "safety." The accident at Fukushima Dai-ichi Nuclear Power Plant following the Great East Japan Earthquake has re-emphasized the importance of nuclear safety, requiring us to make a strong effort to improve safety. Mitsubishi Heavy Industries, Ltd. (MHI) has been working on improving the accuracy and reliability of safety design evaluations to ensure safer and more flexible operations of pressurized-water reactors (PWRs). In this context, MHI has developed and utilized a new concept for critical heat flux correlations.