• Analytical Science and Technology
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• v.19 no.5
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• pp.389-393
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• 2006

The detector consisted of ZnS(Ag) scintillator and photomultiplier tube (PMT) is widely used as contamination monitor in the nuclear facilities. Such detectors are mainly manufactured by adhering the ZnS(Ag) powder onto the transparent plastic. In this study the preparation condition for ZnS(Ag) scintillator sheet using a simple method was established. The scintillator sheet was composed with a support polymer sheet and ZnS(Ag) scintillator layer. The base sheet was prepared by casting the polymer solution after solving the polymer with solvent and the scintillator layer was manufactured by printing the mixture solution with ZnS(Ag) and paste. It was found that the polysulfone(PSf) as a polymer for the base sheet and a cyano resin as a paste for adhering the ZnS(Ag) scintillator was suitable. Also, the prepared thin scintillator sheet had a sufficient mechanical strength, a optical transparency and an alpha-ray detection performance.

• Nuclear industry
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• v.8 no.8 s.66
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• pp.79-97
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• 1988

일본원자력연구소에서는 현재 원자력발전소의 확율논적 안전성평가방법을 개발$\cdot$작성하고 있다. 이 평가에서는 원자력발전소의 지진에 의한 리스크도 대상으로 하고 있으며, ${\ulcorner}$지진위험도평가${\lrcorner}$도 지진리스크 평가의 일환으로 수행되는 것이다. ${\ulcorner}$지진위험도${\lrcorner}$란 용어의 정의가 확정되어 있지는 않지만, 본고에서는 원자력발전소의 사이트에 어느 정도 레벨의 지진이 어느정도 빈도로 발생하는지로 정의한다.

• Nuclear industry
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• v.35 no.4
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• pp.63-64
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• 2015

국제원자력안전연구소(WINS : World Institute for Nuclear Security)가 내놓은 최신 보고서는 원전 분야에서도 빅 데이터 기반의 통합적 데이터 관리와 분석의 도입을 진지하게 고려할 것을 권고하고 있다.

• Nuclear Engineering and Technology
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• v.27 no.2
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• pp.216-225
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• 1995

Simulation for a dynamic analysis of the electrolytic preparation of U(IV) in two-phases system, which consisted of mass transfer of U(VI) from TBP phase into HNO$_3$ solution and electrolytic re-duction of U(VI) to U(IV) at a cathode in aqueous phase, was carried out in order to establish the most suitable operating condition and best electrode area as basic design data for the system. It was found that maintaining an appropriate mass transfer rate was more significant rather than enlarging the surface area of the cathode for more effective production yield of U(IV). The electrode area and the operation time affected deeply the production composition of U(IV) in the resulting aqueous phase. And optimal electrode areas ore evaluated to meet production criteria of U(IV) of resulting solution in several system conditions. Though about 0.37M HNO$_3$ was preferable to prepare the solution of U(IV), nitric acid concentration should be higher than 0.5M to prevent a hydrolysis of U(IV) in the aqueous phase.

• Nuclear Engineering and Technology
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• v.27 no.5
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• pp.784-791
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• 1995

This paper describes the counting-loss problem for radiation measurement Multi-channel analyzers and spectrometers adopt various techniques for compensation for counting-losses in process-ing the radiation pulses from a detector. Researchers hate tried to seek the best solution for the problem. However, any absolute solution has not been reached and vendors of radiation instruments use their own algorithms individually. This survey explains the various compensation algorithms with electronic implementation approach. Shortcomings and merits of each algorithm are also reviewed and a direction is suggested of the recommendable development strategy for counting-loss compensation.

• Nuclear industry
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• v.3 no.5 s.15
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• pp.34-37
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• 1983

• Radioisotope journal
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• v.18 no.2
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• pp.72-76
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• 2003

• Proceedings of the Korean System Dynamics Society
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• 2004.02a
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• pp.1-17
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• 2004

현재 국내 원자력 발전산업은 외국으로의 기술 수출을 시도하고 있을 정도로 국가 경쟁력을 갖고 있다는 것이 지배적이다. 실제 한국전력, 원자력연구소 등에서는 원자력 기술을 해외에 수출하고자 노력하고 있다. 원자력 발전기술의 해외 수출이나 연구개발 사업에서 가정 중요한 지표 중의 하나가 원자력 발전산업의 기술경쟁력이다.(중략)

• Korean Journal of Metals and Materials
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• v.47 no.7
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• pp.391-396
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• 2009

Tensile, low cycle fatigue, and fatigue crack growth rate tests were conducted at RT and $300^{\circ}C$ for type 304 stainless steel. Tensile was tested under displacement control and low cycle fatigue was tested under strain control. Fatigue crack growth rate test was conducted under load control and crack was measured by DCPD method. Yield strength and elongation decreased at $300^{\circ}C$. Dynamic strain aging was not detected at $300^{\circ}C$. Low cycle fatigue life increased but fatigue strength decreased at $300^{\circ}C$. Fatigue crack growth rate increased at $300^{\circ}C$. Dislocation structures were mixed with cell and planar and did not change with temperature. Grain size did not change but plastic strain increased at $300^{\circ}C$. Strain induced martensite after low cycle fatigue test increased at RT but decreased at $300^{\circ}C$. It was concluded that the increase of low cycle fatigue life at $300^{\circ}C$ was due to the decrease of strain induced martensite at which crack was initiated.

• Nuclear industry
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• v.7 no.7 s.53
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• pp.39-55
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• 1987

다음 내용은 지난 3월 16일에서 4월 24일까지 6주간 미국 알곤원자력 연구소와 카나다 원자력공사에서 공동 주최한 ${\ulcorner}$IAEA원전 안전운전과정${\lrcorner}$에서 특별연사로 초청된 Wisconsin Public Serice사의 S. Burstein부회장이 강의한 것이다. 이 과정에 참가했던 과학기술처 허남 과장이 제공한 자료를 원자력안전센터 은영수 박사가 완역했다.