한국원자력학회:학술대회논문집 (Proceedings of the Korean Nuclear Society Conference)
- 한국원자력학회 1996년도 춘계학술발표회논문집(1)
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- Pages.291-295
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- 1996
Flaw Assessment Method of Pressure Tube in CANDU Reactor
- Kim, Jung-Gyu (Korea Atomic Energy Research Institute) ;
- Na, Bok-Gyun (Korea Atomic Energy Research Institute) ;
- Hwang, Jong-Keun (Korea Atomic Energy Research Institute) ;
- Park, Keon-Woo (Korea Atomic Energy Research Institute)
- 발행 : 1996.05.01
초록
In CANDU reactor, each pressure tubes contain twelve fuel bundles and provide the inlet and outlet for the primary coolant. If a leak develops in the pressure tube, it is detected by Annulus Gas System which contains circulating dry
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