핵연료 조사시험용 압력용기의 제작
(주)코리아스칼라
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- 2016.04.01
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- 2007.09
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서지정보
ㆍ발행기관 : 한국기계기술학회
ㆍ수록지정보 : 한국기계기술학회지 / 9권 / 3호
ㆍ저자명 : 박국남, 이종민, 심봉식, 안성호, 유성연
목차
Abstract
1. 서론
2. IVA 설계 및 모형 제작
2.1 IVA 설계
2. 2 IVA 모형 제작
3. 제작 및 조립
3. 1 모의 핵연료봉 제작
3. 2 브레이징(Brazing)
3. 3 조립
4. 성능검증을 위한 시험
4. 1 헬륨 누설시험
4. 2 수압시험
4. 3 고온고압시험
5. 결론
참고문헌
영어 초록
The Fuel Test Loop(FTL) which is capable of an irradiation testing under a similar operating condition to those of PWR(Pressurized Water Reactor) and CANDU(CANadian Deuterium Uranium reactor) nuclear power plants has been developed and installed in HANARO, KAERI(Korea Atomic Energy Research Institute). It is consisted of In-Pile Section(IPS) and Out-of Pile System(OPS). The IPS which is localed inside the pool is divided into 3-parts; they are in-pool pipes, IVA(IPS Vessel Assembly) and the support structures. The test fuel is loaded inside a double wall, inner pressure vessel and outer pressure vessel, to keep the functionality of the reactor collant pressure boundary. The localization of the IVA is achieved by manufacturing through local company and the functional test and verification were done through pressure drop, vibration, hydraulic and leakage tests. The brazing technique of the instrument lines has been checked for its functionality and yield. A IVA has been manufactured by local technique and will be finally tested under out of the high temperature and high pressure test.
참고 자료
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