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구대서,김은가,박윤규 韓國非破壞檢査學會 1996 한국비파괴검사학회지 Vol.16 No.1
핵연료봉의 결함 탐상을 위하여 차동환상형 와전류시험 탐촉자를 설계 및 제작하여, 핵연료봉 시험을 위한 최적 시험 조건을 구하였다. 관통결함, 내부결함, 외부결함을 낸 표준시편에 대하여 와전류시험을 수행함으로써 시험 주파수와 출력 신호의 위상 및 크기에 대한 상관 관계를 구하였다. 이를 토대로 하여 고리원자력 1호기에서 연소한 핵연봉 G33-N2에 대하여 와전류시험을 수행하여 관통결함 신호를 얻었다. 와전류시험에서 관통결함으로 예측된 위치에서 금속조직시험을 수행하여 얻은 결과는 와전류시험결과와 잘 일치하였다. 따라서 와전류시험법은 조사핵연료봉의 피복관에 대한 건전성을 평가하는 도구로써 그 신뢰성이 양호함을 실증하였다. The eddy current test(ECT) probe of differential encircling coil type was designed and fabricated, and the optimum condition of ECT was derived for the examination of the irradiated fuel rod.. The correlation between ECT test frequency and phase & amplitude was derived by performing the test of the standard rig that includes inner notches, outer notches and through-holes. The defect of through-hole was predicted by ECT at the G33-N2 fuel rod irradiated in the Kori-1 nuclear power reactor. The metallographic examination on the G33-N2 fuel rod was performed at the defect location predicted by ECT. The result of metallographic examination for the G33-N2 fuel rod was in good agreement with that of ECT. This proves that the evaluation for integrity of irradiated fuel rod by ECT is reliable.
수증기압과 전처리 산화막이 지르칼로이-4의 Nodule 형 부식거동에 미치는 영향
김인섭,김은가,이강문 대한금속재료학회(대한금속학회) 1990 대한금속·재료학회지 Vol.28 No.11
The effects of steam pressure and preoxidation on the nodular oxidation of Zircaloy -4 were investigated. The accelerated oxidation of nodular type occured at 500℃ above the threshold steam pressure and the oxidation rate increased with increasing the steam pressure. When the uniform preoxide layer, which had been formed at 500℃ near 1 bar, exceeded the size of intermetallic precipitate, the nodular oxidation was drastically reduced at 500℃ under 100 bar pressure. The preoxide thickness protecting the nodular oxidation increased as the steam pressure of preoxidation increased. It revealed that the nodular oxidation may be related to the hydrogen build-up at the sites of the intermetallic precipitates within the uniform oxide surface. The build-up of hydrogen at these sites may lead to stress generation, resulting the cracking of the protective oxide. The localized rapid oxidation with the surface cracking may have caused the nodular corrosion
유재형,김정국,이한수,서인석,김은가,Yoo, Jae-Hyung,Kim, Jung-Kuk,Lee, Han-Soo,Seo, In-Seok,Kim, Eun-Ka 한국방사성폐기물학회 2011 방사성폐기물학회지 Vol.9 No.4
사용후핵연료의 파이로처리기술에 대한 국내외 특허동향을 분석하였다. 1975-2009년에 걸쳐 한국, 미국, 일본 및 유럽연합에서 출원된 특허에 대하여 출원국별, 출원인별, 연도별 및 세부기술분야별로 구분하여 그 내용을 비교함으로써 파이로처리기술 개발 현황을 분석하였다. 그리고 주요 출원인의 세부기술별 특허활동지수로부터 특정분야의 기술개발 편중도, 분석대상 특허의 피인용횟수와 패밀리수로부터 각국의 기술 경쟁력을 조사하였다. 또 장차 파이로처리기술의 실용화에 대비하여 필수 요소기술들을 도출하고 그에 대한 현기술 수준과 기술개발동향 등을 파악하였다. Analysis of foreign and domestic patents for pyroprocessing technology of spent nuclear fuels was carried out in this study. The current status of pyroprocessing technology development in such countries as Korea, USA, Japan and EU was analyzed by classifying the patents for 1975 through 2009 according to registration country, assignee, calendar year and technology area. The major assignees' activity indices were compared in order to find out whether there is any concentrated area of technical details. Technology competitiveness of the countries was also investigated from the information of patent citation number and family size. Furthermore, some essential unit technologies required for the commercialization of pyroprocessing were derived and examined in the aspect of the state of art as well as the trend of technology development.