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정재후(Jae Hoo Jung),김영환(Young Hwan Kim),홍동희(Dong Hee Hong),박병석(Byung Suk Park),송태길(Tai Gil Song) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.11
Performance test of decladding device was carried out by using simulated nuclear spent fuel rods after installing the device in ACPF(Advanced Spent Fuel Conditioning Process Facility). As a result of the test, it was confirmed that this device has a capability of treating 135 rodcuts(20 ㎏HM/batch) within 10 hours. And a procedure was prepared for the operation of the decladding unit process and the transportation to the subsequent unit process which produces powder from the fuel pellets separated from the 250 ㎜ length fuel rodcuts by decladding process. Data obtained from this procedure could be applied to a new decladding device design as a basic data for a scale-up facility in the future.
김성영,송태길,윤지섭,정운관,여화연 조선대학교 에너지.자원신기술연구소 2003 에너지·자원신기술연구소 논문지 Vol.25 No.1
For hot operation of advanced spent fuel conditioning process(ACP), the analysis of radiation-resistant Requirements effect and the system design process are required to design equipment to operate to operate reliably in a gamma radiation environment such as hot cell. To analysis the effects of radiation for ACP, we used the SCALE codes which were certified by Nuclear Regulatory Commission(NRC). The source term was calculated which reflects the features of target nuclear fuels using ORIGEN-S, a module of the SCALE code, and the gamma dose rates were calculated by using the QADS modules, considering the geometry of process equipment respectively. the results are shows that the value was maximum 3.03 ㏉/h from the rod storage box in hot cell, maximum 0.6 ㏉/h from the metallizer, and maximum 72.0 ㏉/h from the vol-oxidizer. Considering those values, the design methods for shielding and repositioning the major equipments and components should be induced, and, the preventive maintenance for components before failure actually occurs should be minimized the effects of radiation.