Transactions of the Atomic Energy Society of Japan
Online ISSN : 2186-2931
Print ISSN : 1347-2879
ISSN-L : 1347-2879
Article
Countermeasure against Thermal Fatigue Crack of Primary Loop Recirculation Pump in BWR
Hiroshi NODATadashi NARABAYASHIYuuji TAKAHASHI
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2008 Volume 7 Issue 4 Pages 338-349

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Abstract
  The reactor water was fed to the purge water of the mechanical seal on the original design of the primary loop recirculation pump. Because the mechanical seal had a short life due to the cruds in the reactor water, the clean purge water was adopted instead of the reactor water. After this modification, the shallow cracks were found on the surface of the pump shaft and casing cover due to the temperature fluctuation between the cold purge water and the hot pump discharge water. The fundamental mechanism and countermeasure were investigated by scale test, mock-up test and so on. The flow barrier with a heater was contrived through these tests. It has been introduced gradually in operating and constructing PLR pumps after its completion in 1995. The PLR pumps are overhauled around every 10 years in Japan. The first overhaul of the PLR pumps showed no cracks around the pump shaft and casing cover after 10 years' operation. This paper presents both its development process and inspection results.
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© 2008 Atomic Energy Society of Japan
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