• 제목/요약/키워드: Wolsong Unit-1

검색결과 60건 처리시간 0.025초

중수로 칼란드리아 내장품 원격 육안검사 기술 개발 (Development of Remote Visual Inspection Technology for Calandria & Internal of CANDU NPP)

  • 이상훈;진석홍;문균영
    • 한국압력기기공학회 논문집
    • /
    • 제6권1호
    • /
    • pp.72-77
    • /
    • 2010
  • During the period of reinforcement work for the licensing renewal of CANDU NPP, the fuel channels, Calandria tubes and feeders of CANDU Reactor are replaced. The remote visual inspection of Calandria internal is also performed during the period of reinforcement work. This period is a unique opportunity to inspect the inside of the Calandria. The visual inspection for the Calandria vessel and its internals of Wolsong NPP Unit 1 was performed by Nuclear Engineering & Technology Institute(NETEC) of KHNP. To perform this inspection, NETEC developed equipment applied new technology such as the synchronization of 3D CAD, automatic alignment and control system. The inspection confirmed that the Calandria integrity of Wolsong NPP Unit 1 is perfect.

  • PDF

Hydrogen Absorption Behavior of Zr-2.5Nb Pressure Tubes in Wolsong Unit 1

  • Choo, Kee-Nam;Kwon, Sang-Chul;Kim, Young-Suk
    • Nuclear Engineering and Technology
    • /
    • 제30권4호
    • /
    • pp.318-327
    • /
    • 1998
  • The deuterium uptake behavior of Zr-2.5Nb pressure tubes in Wolsong Unit 1 was analyzed in terms of longitudinal location, operation time, and coolant temperature. The results were compared with those obtained from Canadian CANDU reactors. The amount of deuterium uptake was higher at the outlet part than at the inlet part and was also higher when subjected to a longer operation time and a higher coolant temperature. The hydrogen uptake of Zr-2.5Nb in a hydrogen gas atmosphere was dependent on the microstructure of the alloy. The aged Zr-2.5Nb consisting of $\alpha$-Zr and $\beta$-Nb phases showed higher hydrogen uptake than that consisting of $\alpha$-Zr and $\beta$-Zr phases. The hydrogen in the alloy decreased the rate of oxidation. This could be explained in terms of the cathodic controlled reaction of Zr-2.5Nb oxidation.

  • PDF

Microstructure and Mechanical Property of Irradiated Zr-2.5Nb Pressure Tube in Wolsong Unit-1

  • 김영숙;안상복;오동준;김성수;정용무
    • 소성∙가공
    • /
    • 제8권3호
    • /
    • pp.241-241
    • /
    • 1999
  • With the aim of assessing the degradation of Zr-2.5Nb pressure tubes operating in the Wolsong unit-1 nuclear power plant, characterization tests are being conducted on irradiated Zr-2.5Nb tubes removed after 10-year operation. The examined tube had been exposed to temperatures ranging from 264 to 306℃ and a neutron fluence of 8.9×$10^{21}$ n/cm²(E>1 MeV) at the maximum. Tensile tests were carried out at temperatures ranging from RT to 300℃. The density of a-type and c-type dislocations was examined on the irradiated Zr-2.5Nb tube using a transmission electron microscope. Neutron irradiation up to 8.9×$10^{21}$ n/cm²(E>1 MeV) yielded an increase in a-type dislocation density of the Zr-2.5Nb pressure tube to 7.5×$10^{14} m^{-2}$, which was highest at the inlet of the tube exposed to the low temperature of 275℃. In contrast, the c-component dislocation density did not change with irradiation, keeping an initial dislocation density of 0.8×$10^{14} m^{-2}$ over the whole length of the tube. As expected, the neutron irradiation increased mechanical strength by about 17-26% in the transverse direction and by 34-39% in the longitudinal direction compared to that of the unirradiated tube at 300℃. The change in the mechanical properties with irradiation is discussed in association with the microstructural change as a function of temperature and neutron fluence.

Design of Improved Detection Instrumentation for the Annulus Gas System for Wolsong 2

  • Kim, Seog-Nam;Koo, Jun-Mo;Chang, Ik-Ho;Jung, Ho-Chang;Han, Sang-Joon
    • Nuclear Engineering and Technology
    • /
    • 제28권4호
    • /
    • pp.423-430
    • /
    • 1996
  • The improved and advanced Annulus Gas System(AGS) has been developed for Wolsong 2 to satisfy the requirements of the regulatory body. The Atomic Energy Control Board(AECB) required a shorter detection time following a small leak from a pressure tube and/or calandria tube. This paper describes licensing requirements, functional requirements and detail design description for the AGS. The Wolsong unit No. 1 AGS was designed to operate as a stagnant system normally requiring only pressure regulation and having provisions for purging. no improved AGS involves the adoption of gas recirculation in AGS, duplication of dew point indicators with additional instrumentation and sampling provisions to prompt operator action. The improved system operates in the recirculation mode with continuous dew point measurement for leak detection. An AGS with improved detection instrumentation is provided.

  • PDF

Design on SDS2 On-line Poison Concentration Monitoring in CANDU

  • Kim, Seog-Nam;Jung, Ho-Chang;Kim, Sung;Kim, Ji-Hyeon;Han, Sang-Joon
    • Nuclear Engineering and Technology
    • /
    • 제28권5호
    • /
    • pp.500-505
    • /
    • 1996
  • At the reference plant(Wolsong unit No. 1) a manual poison sampling system is provided to periodically sample gadolinium from each tank and analyze it in the laboratory to provide assurance that adequate poison concentration in each tank is maintained. The AECB required a continuous, on-line monitoring system. On Wolsong unit No. 2, process piping adapter and new instrument loops added to the Liquid Injection Shutdown System(LISS) which is part of SDS2. The new instrument loops continuously monitor SDS2 poison conductivity and initiate an alarm when the poison concentration is too low.

  • PDF