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자료유형
학술대회자료
저자정보
김진혁 (한국원자력안전기술원)
저널정보
대한기계학회 대한기계학회 춘추학술대회 대한기계학회 2014년도 추계학술대회
발행연도
2014.11
수록면
2,844 - 2,848 (5page)

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이 논문의 연구 히스토리 (2)

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Korea has 23 units of NPP in operation, and 4 units in Wolsong site are PHWR(Pressurized Heavy Water Reactor). In case of Wolsong unit1, plant design life was assumed in 30 years, and then it is expired at Nov. 2012. Therefore, the review is ongoing for continued operation. The purpose of this study is to analysis the temperature behavior of the fuel sheath during the flow stagnation accident in PHWR using computer code. MARS-KS-CANDU (Multi-dimensional Analysis of Reactor Safety-KINS Standard-CANDU version) code has been developed as a regulatory tool (system code) for calculating the thermal hydraulic behavior of PHWR. Since the flow stagnation accident is most limiting case for the temperature rise of the fuel due to the insufficient cooling, the fuel sheath can be damaged by uncontrolled increase in temperature. The flow stagnation caused by the balance between pump power and flow through the break of the pipe. The calculation was done using MARS-KS-CANDU for the case that the inlet header was broken as it is a kind of the accident that describes in safety analysis report for Wolsong unit 1. And the sensitivity study was done to see which break size was the most limiting case on the fuel sheath temperature.

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Abstract
1. 서론
2. 유량정체사고 개요
3. 해석 모델링
4. 사고해석 결과
4. 결론
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