• Nuclear Engineering and Technology
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• 제50권3호
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• pp.356-367
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• 2018

A series of tests dedicated to station blackout (SBO) accident scenarios have been recently performed at the $Prim{\ddot{a}}rkreislauf-Versuchsanlage$ (primary coolant loop test facility; PKL) facility in the framework of the OECD/NEA PKL-3 project. These investigations address current safety issues related to beyond design basis accident transients with significant core heat up. This work presents a detailed analysis using the best estimate thermal-hydraulic code TRACE (v5.0 Patch4) of different SBO scenarios conducted at the PKL facility; failures of high- and low-pressure safety injection systems together with steam generator (SG) feedwater supply are considered, thus calling for adequate accident management actions and timely implementation of alternative emergency cooling procedures to prevent core meltdown. The presented analysis evaluates the capability of the applied TRACE model of the PKL facility to correctly capture the sequences of events in the different SBO scenarios, namely the SBO tests H2.1, H2.2 run 1 and H2.2 run 2, including symmetric or asymmetric secondary side depressurization, primary side depressurization, accumulator (ACC) injection in the cold legs and secondary side feeding with mobile pump and/or primary side emergency core coolant injection from the fuel pool cooling pump. This study is focused specifically on the prediction of the core exit temperature, which drives the execution of the most relevant accident management actions. This work presents, in particular, the key improvements made to the TRACE model that helped to improve the code predictions, including the modeling of dynamical heat losses, the nodalization of SGs' heat exchanger tubes and the ACCs. Another relevant aspect of this work is to evaluate how well the model simulations of the three different scenarios qualitatively and quantitatively capture the trends and results exhibited by the actual experiments. For instance, how the number of SGs considered for secondary side depressurization affects the heat transfer from primary side; how the discharge capacity of the pressurizer relief valve affects the dynamics of the transient; how ACC initial pressure and nitrogen release affect the grace time between ACC injection and subsequent core heat up; and how well the alternative feeding modes of the secondary and/or primary side with mobile injection pumps affect core quenching and ensure stable long-term core cooling under controlled boiling conditions.

• 한국가스학회지
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• 제12권1호
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• pp.31-35
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• 2008

압축천연가스 자동차는 최근 대기환경 개선을 위해 대도시 시내버스에 적용되고 있으며 대기 오염물질을 저감시키는데 효과적인 것으로 입증되고 있다. 압축천연가스의 단점인 낮은 연료저장밀도를 높이기 위해 액화천연가스를 연료로 하는 차량기술이 시도되고 있다. 본 논문에서는 자동차에 액화 천연가스를 적용하기 위한 LNG 저장 용기의 단열특성을 실험적으로 측정하여 기준과의 적합성을 판단하였으며 측정방법에 대한 비교검토를 통해 측정결과의 신뢰성을 제고하였다. 시험용기의 단열성능계수는 $40J/h{\cdot}^{\circ}C{\cdot}m^2$으로 기준범위 이내의 성능을 확인하였으며 두 가지 측정방법들은 상호 일치하는 결과를 보여주었다. 또한 용기의 벤트밸브 동작특성을 조사하여 증발가스의 방출량 특성을 파악하였다.