Safety of Super LWR, (II)

Yuki Ishiwatari*, Yoshiaki Oka, Seiichi Koshizuka, Akifumi Yamaji, Jie Liu

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

51 Citations (Scopus)


This paper describes safety analysis of the high-temperature supercritical water-cooled thermal reactor with downward-flow water rods (called Super LWR) at supercritical pressure. Eleven transients and four accidents are chosen for the safety analysis considering types of abnormalities. The cladding temperature is taken as the important transient criterion instead of the heat flux ratio. The once-through cooling system and the downward-flow water rod system characterize safety of the Super LWR. “Loss of feedwater” is important because it is the same as “loss of reactor coolant flow” unlike BWR and PWR. However, the downward-flow water rods mitigate core heat-up before startup of the auxiliary feedwater system because they remove heat from the fuel channels by heat conduction and supply their water inventory to the fuel channels by volume expansion. During pressurization transients, the reactor power does not increase significantly unlike BWR due to no void collapse in single-phase flow and decrease in coolant density by flow stagnation in the once-through cooling system. All the transients and the accidents satisfy the criteria. Increases in the hottest cladding temperatures are about 50°C at transients and 250°C at accidents at maximum. The period of the high cladding temperature is very short at transients.

Original languageEnglish
Pages (from-to)935-948
Number of pages14
JournalJournal of Nuclear Science and Technology
Issue number11
Publication statusPublished - 2005 Nov
Externally publishedYes


  • Downward-flow water rod
  • Once-through cooling
  • Safety analysis
  • Supercritical-pressure

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering


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