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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.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2011.1
- 수록면
- 25 - 44 (20page)
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초록· 키워드
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KAERI has been operating an integral effect test facility, ATLAS (Advanced Thermal-Hydraulic Test Loop for AccidentSimulation), for accident simulations of advanced PWRs. Regarding integral effect tests, a database for major design basisaccidents has been accumulated and a Domestic Standard Problem (DSP) exercise using the ATLAS has been proposed andsuccessfully performed. The ATLAS DSP aims at the effective utilization of an integral effect database obtained from theATLAS, the establishment of a cooperative framework in the domestic nuclear industry, better understanding of thermalhydraulic phenomena, and an investigation of the potential limitations of the existing best-estimate safety analysis codes. Forthe first ATLAS DSP exercise (DSP-01), integral effect test data for a 100% DVI line break accident of the APR1400 wasselected by considering its technical importance and by incorporating comments from participants. Twelve domesticorganizations joined in this DSP-01 exercise. Finally, ten of these organizations submitted their calculation results. ThisATLAS DSP-01 exercise progressed as an open calculation; the integral effect test data was delivered to the participantsprior to the code calculations. The MARS-KS was favored by most participants but the RELAP5/MOD3.3 code was alsoused by a few participants. This paper presents all the information of the DSP-01 exercise as well as the comparison resultsbetween the calculations and the test data. Lessons learned from the first DSP-01 are presented and recommendations forcode users as well as for developers are suggested.
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참고문헌 (23)
참고문헌 신청
A. Prosek / 2002 / Review of Quantitative Accuracy Assessments with Fast Fourier Transform Based Method (FFTBM) / Nuclear Engineering and Design 217 : 179 ~ 206
Ambrosini W. / 1990 / Evaluation of Accuracy of Thermal Hydraulic Code Calculations / J. Energia Nucleare 2
Andrej Prosek / 2006 / Quantitative Assessment of Thermal-Hydraulic Codes Used for Heavy Water Reactor Calculations / Nuclear Engineering and Design 236 (3) : 295 ~ 308
B. J. Yun / 2005 / Development of an Average Bidirectional Flow Tube for a Measurement of the Single and Two Phase Flow / The 11th International Topical Meeting on Nuclear Reactor
B.D. Chung / 2003 / Phenomena Identification and Ranking Tabulation for APR1400 Direct Vessel Injection Line Break
Ambrosini W. / 1990 / Evaluation of Accuracy of Thermal Hydraulic Code Calculations / J. Energia Nucleare 2
Andrej Prosek / 2006 / Quantitative Assessment of Thermal-Hydraulic Codes Used for Heavy Water Reactor Calculations / Nuclear Engineering and Design 236 (3) : 295 ~ 308
B. J. Yun / 2005 / Development of an Average Bidirectional Flow Tube for a Measurement of the Single and Two Phase Flow / The 11th International Topical Meeting on Nuclear Reactor
B.D. Chung / 2003 / Phenomena Identification and Ranking Tabulation for APR1400 Direct Vessel Injection Line Break
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