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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
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Background: Interfacing-system loss-of-coolant-accident (ISLOCA) has been identified as the most hazardous accident scenario in the typical PWR plants. The present study as an effort to improve the knowledge of the source term to the environment during ISLOCA focuses on an improvement of the estimation method. Materials and Methods: The improvement was performed to take into account an effect of broken pipeline and auxiliary building structures relevant to ISLOCA. An estimation of the source term to the environment was for the OPR-1000 plants by MELOCR code version 1.8.6. Results and Discussion: The key features of the source term showed that the massive amount of fission products departed from the beginning of core degradation to the vessel breach. Conclusion: The release amount of fission products may be affected by the broken pipeline and the auxiliary building structure associated with release pathway.
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참고문헌 (7)
참고문헌 신청
Galyean WJ / 1994 / Intersystem LOCA risk assessment:methodology and results / Nucl. Eng. Des 152(1-3):159~174
U.S. Nuclear Regulatory Commission / 1989 / Interfacing systems LOCA: Pressurized water reactors :1
Lee M / 2008 / Quantification of severe accident source terms of a Westinghouse 3-loop plant / Nucl. Eng. Des 238(4):1080~1092
Korea Power Engineering Corporation / 2004 / AOT/STI relaxation study for Korean standard nuclear power plants :15~156
U.S. Nuclear Regulatory Commission / 2012 / State-of-the-art reactor consequence analyses (SOARCA) report :73
U.S. Nuclear Regulatory Commission / 1989 / Interfacing systems LOCA: Pressurized water reactors :1
Lee M / 2008 / Quantification of severe accident source terms of a Westinghouse 3-loop plant / Nucl. Eng. Des 238(4):1080~1092
Korea Power Engineering Corporation / 2004 / AOT/STI relaxation study for Korean standard nuclear power plants :15~156
U.S. Nuclear Regulatory Commission / 2012 / State-of-the-art reactor consequence analyses (SOARCA) report :73
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