• 에너지공학
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• 제23권2호
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• pp.183-190
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• 2014

국내 가동중원전은 2012년 이후 일반규격품 품질검증 이행 체계 구축을 위해 정책 수립 및 기술 개발, 일반규격품 품질검증 전문기관 양성, 국내 원전 공급사들의 일반규격품 품질검증프로그램 보유 추진 및 원자력 산업계의 전문인력 양성 등을 적극 추진 중에 있다. 아울러 미국 전력연구소(EPRI)의 관련 기술기준을 기반으로 일반규격품 품질검증프로그램 도입 초기에 개발된 안전성(Q) 등급 품목 품질검증 프로세스를 개선하였고, 국내 원전 고유의 원자력 품질등급 체계인 안전성영향(A) 등급 품목을 위해 안전성등급 품목과 차별화시킨 별도의 검증 프로세스를 개발하였다. 결과적으로, 위와 같은 노력을 통해 국내 가동중원전의 일반규격품 품질검증 이행 체계가 구축될 경우, 원전에서 사용하는 기자재의 신뢰성 및 안전성이 향상될 것으로 기대된다.

• 전기학회논문지
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• 제63권12호
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• pp.1637-1639
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• 2014

In the past, the analog protection relays have been widely used for the safety-related systems in the nuclear power plants due to their stability and reliability. Meanwhile, as the high performance digital system has been developed, the digital systems have been adopted in the non-safety systems. However, since the digital systems currently used in the non-safety systems were not developed according to Q-class standard, Commercial Grade Item Dedication (CGID) procedure should be performed in order to apply them to the safety-related system. The purpose of this paper is to describe the CGID procedure including the analysis of the hardware architecture as well as the software embedded in protective relay to apply to the emergency diesel generator in the nuclear power plant. The entire CGID procedure was performed strictly according to the international standard and regulations.

• 한국신뢰성학회지:신뢰성응용연구
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• 제14권4호
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• pp.248-255
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• 2014

Nuclear power plants may use commercial grade items if they can pass special tests or inspections, which is called Commercial Grade Item Dedication (CGID). Digital items, however, should follow EPRI TR-106439 to be applied to nuclear power plants. This paper explains the scheme and requirements of the EPRI TR-106439 and introduces some guidelines. Firstly, in order to clarify requirements of the EPRI TR-106439, code interpretation is performed. And through case study of digital indicator, limitations of EPRI TR-106439 are mentioned, and improvement direction is proposed.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.115-125
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• 2016

The prototype SFR has currently been under design by KAERI. The size of its major components is much larger than that of APR1400 and high temperature materials are applied for it. The increased size of components and those specific materials effect on material procurement, manufacturing process and fabrication facilities. The manufacturing methods are studied for Reactor Vessel/Guard Vessel, Control Rod Drive Mechanism, Heat Exchanger, Primary Pump, Reactor Vessel Internals, Steam Generator and In-Vessel Transfer Machine. The proper manufacturing methods are suggested for each component including side forging technology for ultra large forgings of Reactor Vessel to minimize the weld seams on which In-service Inspection should be conducted.