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Hyun Dae Kim;Chang Hyun Chung;Chang Hyo Kim
- Nuclear Engineering and Technology
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- v.13 no.3
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- pp.153-161
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- 1981
The dynamic behavior of the Ko-ri Unit 1 nuclear reactor following some credible and postulated accidents has been analyzed to a certain extent by means of neutronics and temperature equations formulated in terms of point reactor model. In general, the result of numerical calculation is harnessed to be incorporated in more elaborate models so as to predict transient behavior in a reliable mode as a part of accident analysis. It is shown in the case of power response upon an uncontrolled withdrawal of rod cluster control assembly at hot full power that the point reactor kinetics model proves to be good enough to reproduce the generic features described in the final safety analysis report of the Ko-ri Unit 1.
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서두환
- Nuclear industry
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- v.16 no.2 s.156
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- pp.42-46
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- 1996
원자력발전소의 증기발생기 교체는, 대형원자력기기의 교체공사로서, 현재로서는 가압경수로형 원자력발전로(PWR)에 대한 보수대책의 하나로 정착되어 있는 조치이다. 증기발생기 교체는 현재 미국$\cdot$일본$\cdot$독일$\cdot$프랑스$\cdot$스웨덴$\cdot$스위스$\cdot$벨기에 등의 23기 플랜트가 공사한 실적이 있다. 우리나라도 고리 1호기(587 MWe)와 고리 2호기(650 MWe)의 증기발생기를 97년경에 교체할 계획으로 있다.
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