Earticle

초록

영어

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.

목차

Abstract
 1. 서 론
 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 조 립
 4. 성능검증을 위한 시험
  4. 1 헬륨 누설시험
  4. 2 수압시험
  4. 3 고온고압시험
 5. 결 론
 참고문헌

키워드

저자

• 박국남 [ K. N. PARK | 한국원자력연구원, 하나로이용연구본부 ]
• 이종민 [ J. M. LEE | 한국원자력연구원, 하나로이용연구본부 ]
• 심봉식 [ B. S. SIM | 한국원자력연구원, 하나로이용연구본부 ]
• 안성호 [ S. H. AHN | 한국원자력연구원, 하나로이용연구본부 ]
• 유성연 [ S. Y. YOO | 충남대학교, 기계설계공학과 ]

참고문헌

발행기관

간행물

표지보기 관심저널 등록

• 간행물명

  한국기계항공기술학회지(구 한국기계기술학회지) [Journal of the Korean Society of Mechanical and Aviation Technology ]

• 간기

  격월간

• pISSN

  1229-604X

• eISSN

  2508-3805

• 수록기간

  1999~2026

• 등재여부

  KCI 등재

• 십진분류

  KDC 550 DDC 620