Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1996.05a
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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)
- Published : 1996.05.01
Abstract
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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