• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.516-517
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• 2005

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.173-174
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• 2018

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.509.2-509
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• 2001

• 한국정보처리학회:학술대회논문집
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• 한국정보처리학회 2001년도 춘계학술발표논문집 (하)
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• pp.1097-1100
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• 2001

소프트웨어 개발자로부터 독립된 소프트웨어 시험자가 수행하는 소프트웨어 시험은 소프트웨어의 안전성 향상을 위해 필요하다. 컴퓨터기반의 디지틀시스템으로 설계되는 일체형원자로 MMIS에 적용하기 위한 소프트웨어 시험 계획을 개발할 필요가 있다. 본 논문은 소프트웨어 시험 계획을 소프트웨어시험 조직 구성, 시험 문서, 시험 절차, 시험 방법을 중심으로 제시한다. 소프트웨어 시험 방법은 원시코드 정적분석과 동적시험을 구분하여 기술한다. 본 논문에서 제시된 소프트웨어 시험 계획은 원자력 규제기관에서 요구하는 소프트웨어 시험 요구사항을 만족한다. 본 논문을 통해 제시된 소프트웨어 시험 계획을 일체형원자로 MMIS 소프트웨어 개발 시 적용하여 소프트웨어 고장율 데이터를 수집할 예정이다.

• Nuclear Engineering and Technology
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• 제51권3호
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• pp.922-929
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• 2019

This paper presents the drop performance test of the control rod assembly which is one of the main components strongly related to the safety of the prototype generation IV sodium-cooled fast reactor. To investigate the drop performance, a real-sized control rod assembly that was recently modified based on the drop analysis results was newly fabricated, and several free drop tests under different flow rate conditions were carried out. Then the results were compared with those obtained from the previous tests conducted on the conceptually designed control rod assembly to demonstrate the improvement in performance. Moreover, the drop performance tests under several types and magnitudes of seismic loadings were also conducted to investigate the effect of the seismic loading on the drop performance of the modified control rod assembly. The results showed that the effects of the type and magnitude of the seismic loading on the drop performance of the modified control rod assembly were not significant. Also, the drop time requirement was successfully satisfied, even under the seismic loading conditions.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.537-538
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• 2004

The performance of the ECWS was predicted for the anticipated operational occurrences. The inadvertent close of loop isolation valve is the most severe case for the five anticipated operational occurrences considered in this design and meets the design criteria of the ECWS. The correlation of critical heat flux for the geometry of three pins sub-channel analysis will be studied in the feature.

• Nuclear Engineering and Technology
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• 제41권6호
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• pp.859-866
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• 2009

KAERI has worked on the development of an advanced spent fuel conditioning process (ACP) since 1997. A hot cell facility, termed the ACPF, has also been developed. The ACPF consists of two air-sealed hot cells. The results of a safety analysis as part of the license procurement process stipulated by the Korean Government showed that the facility was designed safely. After its construction, an integrated performance test was performed. The results of this test confirmed that the facility satisfies the design requirements.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.1351-1352
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• 2004

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.285-286
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• 2004

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2003년도 추계학술발표대회 요약집
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• pp.71-71
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• 2003