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IDENTIFICATION OF SAFETY CONTROLS FOR ENGINEERING-SCALE PYROPROCESS FACILITY
문성인,서석준,종원명,유길성 한국원자력학회 2015 Nuclear Engineering and Technology Vol.47 No.7
Pyroprocess technology has been considered as a fuel cycle option to solve the spent fuelaccumulation problems in Korea. The Korea Atomic Energy Research Institute, Daejeon,Korea has been studying pyroprocess technology, and the conceptual design of anengineering-scale pyroprocess facility, called the Reference Engineering-scale PyroprocessFacility, has been performed on the basis of a 10 ton heavy metal throughput per year. Inthis paper the concept of Reference Engineering-scale Pyroprocess Facility is introducedalong with its safety requirements for the protection of facility workers, collocatedworkers, the off-site public, and the environment. For the identification of safety structures,systems, and components and/or administrative controls, the following activitieswere conducted: (1) identifying hazards associated with operations; (2) identifying potentialevents associated with these hazards; and (3) identifying the potential preventive and/or mitigative controls that reduce the risk associated with these accident events. Thisstudy will be used to perform a safety evaluation for accidents involving any of the hazardsidentified, and to establish safety design policies and propose a more definite safety design.
Preliminary Safety Study of Engineering-scale Pyroprocess Facility
문성인,종원명,유길성,구정호,김호동 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.1
Pyroprocess technology has been considered as a fuel cycle option to solve the spent fuel accumulation problems inKorea. The Korea Atomic Energy Research Institute has been studying pyroprocess technology, and the conceptual design ofan engineering-scale pyroprocess facility, called the Advanced Fuel Cycle (AFC) facility, has been performed on the basis ofa 10tHM throughput per year. In this paper, the concept of the AFC facility was introduced, and its safety evaluations wereperformed. For the safety evaluations, anticipated accident events were selected, and environmental safety analyses wereconducted for the safety of the public and workers. In addition, basic radiation shielding safety analyses and criticality safetyanalyses were conducted. These preliminary safety studies will be used to specify the concept of safety systems forpyroprocess facilities, and to establish safety design policies and advance more definite safety designs.
문성인,김영진,최영환,송명호,이진호 한국원자력학회 2004 Nuclear Engineering and Technology Vol.36 No.4
The 40% of wall criterion, which is generally used for the plugging of steam generator tubes,is applied only to a single crack. In a previous study, a total number of 9 failure models wereproposed to estimate the local failure of the ligament between cracks, and the optimumcoalescence model of multiple collinear cracks was determined among these models. It is,however known that parallel axial cracks are more frequently detected than collinear axialcracks during an in-service inspection. The objective of this study is to determine the plasticcollapse model that can be applied to steam generator tubes containing two parallel axialthrough-wall cracks. Three previously proposed local failure models were selected as thecandidates. Subsequently, the interaction effects between two adjacent cracks were evaluated toscreen them. Plastic collapse tests for the plate with two parallel through-wall cracks and finiteelement analyses were performed to determine the optimum plastic collapse model. Bycomparing the test results with the prediction results obtained from the candidate models, aCOD base model was selected as an optimum model.