• 한국재료학회지
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• 제13권7호
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• pp.473-477
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• 2003

The hydrogen redistribution induced by thermotransport at temperatures likely to be encountered in nuclear power reactors (300-$340^{\circ}C$) was investigated in modified Zircaloy-4 alloys. Modified Zircaloy-4 alloys were prepared by altering the chemical composition of Zircaloy-4; the oxygen content of Zircaloy-4 (0.1 wt%) was increased to 0.2, 0.5 and 1.0 wt%. The heat of transport ($Q^{*}$ ) for hydrogen was measured by changing the initial hydrogen and oxygen concentrations. It was found that the heat of transport was not affected by increases in the initial hydrogen concentration from 63.3 to 91.7 ppm. However, the value of $Q^{Q}$ decreased from 6.8 to 4.5 ㎉/mol as the initial oxygen concentration was increased from 0.2 to 1.0 wt%.

• 한국재료학회:학술대회논문집
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• 한국재료학회 2001년도 춘계학술발표강연 및 논문개요집
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• pp.47-47
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• 2001

• Nuclear Engineering and Technology
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• 제17권3호
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• pp.193-199
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• 1985

지르칼로이-4 피복재의 요드에 의한 응력부식 균열 현상을 개량된 내부가압방법으로 조사하였다. 요드 응력부식 균열 현상을 일으키는 임계요드농도와 임계 응력이 존재하였으며, 603$^{\circ}$K의 시험 온도에서 임계요드 농도는 약 0.2mg/$\textrm{cm}^2$였고 임계 응력은 시험온도와 시편의 기계적 성질에 다라 변하였다. 파괴면을 주사전자 현미경으로 관찰한 결과, 초기 단계는 입내 파손 형태로 W-형의 균열을 포함하고 있었으며, 균열이 진행됨에 따라 입내 파손과 편성 파손이 혼합된 형태로 나타남을 알 수 있었다. 그리고 균열은 한 결정립에서 다른 결정립으로 단계적으로 전파되어 나갔다.

• Nuclear Engineering and Technology
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• 제52권4호
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• pp.742-754
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• 2020

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.