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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 742 - 754 (13page)
이용수
초록· 키워드
오류제보하기
Zircaloy cladding oxidation is an important phenomenon for both design basis accident and severe accidents, because it results in cladding embrittlement and rapid fuel temperature escalation. For this reason during the last decade, many experts have been conducting experiments to identify the oxidation phenomena that occur under design basis accidents and to develop mathematical analysis models. However, since the study of design extension conditions (DEC) is relatively insufficient, it is essential to develop and validate a physical and mathematical model simulating the oxidation of the cladding material at high temperatures. In this study, the QUENCH-05 and -06 experiments were utilized to develop the best-fitted oxidation model and to validate the SPACE code modified with it under the design extension condition. It is found out that the cladding temperature and oxidation thickness predicted by the Cathcart-Pawel oxidation model at low temperature (T < 1853 K) and Urbanic-Heidrick at high temperature (T > 1853 K) were in excellent agreement with the data of the QUENCH experiments. For ‘LOCA without SI’ (Safety Injection) accidents, which should be considered in design extension conditions, it has been performed the evaluation of the operator action time to prevent core melting for the APR1400 plant using the modified SPACE. For the ‘LBLOCA without SI’ and ‘SBLOCA without SI’ accidents, it has been performed that sensitivity analysis for the operator action time in terms of the number of SIT (Safety Injection Tank), the recovery number of the SIP (Safety Injection Pump), and the break sizes for the SBLOCA. Also, with the extended acceptance criteria, it has been evaluated the available operator action time margin and the power margin. It is confirmed that the power can be enabled to uprate about 12% through best-estimate calculations.
목차
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참고문헌 (19)
참고문헌 신청
Keyou Mao / 2015 / Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000 / Prog. Nucl. Energy 85:352~365
IRSN / A state-of-the-art review of past programmes devoted to fuel behavior under Loss-of-Coolant conditions. Part 3”, DPAM/SEMCA 2008-093
J.V. Cathcart / Zirconium metal-water oxidation kinetics IV, React. Rate Stud. ORNL/NUREG 17
S. Leistikow / 1987 / Oxidation kinetics and related phenomena of Zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions / Nucl. Eng. Des. 103:65~84
V.F. Urbanic / 1978 / High-temperature oxidation of zircaloy-2 and zircaloy-4 in steam / J. Nucl. Mater 74
IRSN / A state-of-the-art review of past programmes devoted to fuel behavior under Loss-of-Coolant conditions. Part 3”, DPAM/SEMCA 2008-093
J.V. Cathcart / Zirconium metal-water oxidation kinetics IV, React. Rate Stud. ORNL/NUREG 17
S. Leistikow / 1987 / Oxidation kinetics and related phenomena of Zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions / Nucl. Eng. Des. 103:65~84
V.F. Urbanic / 1978 / High-temperature oxidation of zircaloy-2 and zircaloy-4 in steam / J. Nucl. Mater 74
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