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Kim, Tae-Man; Ku, Ji-Young; Dho, Ho-Seog; Cho, Chun-Hyung; Ko, Jae-Hun
Proceedings of the 18th international symposium on the packaging and transportation of radioactive materials (PATRAM 2016)2016
Proceedings of the 18th international symposium on the packaging and transportation of radioactive materials (PATRAM 2016)2016
AbstractAbstract
[en] The Korea Radioactive Waste Agency (KORAD) has developed a dual-purpose metal cask for the dry storage of spent nuclear fuel that has been generated by domestic light-water reactors. The metal cask has been designed in compliance with international and domestic technology standards, and safety was the most important consideration in developing its design. It has been designed to maintain its integrity for 50 years in terms of major safety factors. The metal cask ensures the minimization of waste generated by maintenance activities during the storage period as well as the safe management of waste. An activation evaluation of the main body including internal and external components of metal casks whose design lifetime has expired provides quantitative data on their radioactive inventory. The radioactive inventory of the main body and the components of the metal cask was calculated by applying the MCNP5·ORIGEN-2 evaluation system and by considering each component’s chemical composition, neutron flux distribution, and reaction rate, as well as the duration of neutron irradiation during the storage period. From the evaluation results, it was found that 10 years after the end of the cask’s design life, 60Co had greater radioactivity than other nuclides among the metal materials. In the case of the neutron shield, nuclides that emit high-energy gamma rays such as 28Al and 24Na immediately after the design lifetime had greater radioactivity. However, their radioactivity level became ignorable after 6 months due to their short half-life. Based on the evaluations of this study it is believed that the nuclide inventory of a spent nuclear fuel metal cask can be utilized as basic data when the decommissioning of a metal cask is planned, for example, for the development of a decommissioning plan, the determination of a decommissioning method, the estimation of radiation exposure of workers engaged in decommissioning operations, the management of radioactive wastes, etc. (author)
Primary Subject
Source
Japan Society of Mechanical Engineers, Tokyo (Japan); [6947 p.]; 2016; 13 p; PATRAM 2016: 18. international symposium on the packaging and transportation of radioactive materials; Kobe, Hyogo (Japan); 18-23 Sep 2016; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, Japan; Available as DVD-ROM Data in PDF format, Folder Name: FinalPaper; Paper No. F5003.pdf; 8 refs., 3 figs., 12 tabs.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
ALLOYS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CALCULATION METHODS, CARBON ADDITIONS, CASKS, COBALT ISOTOPES, CONTAINERS, DOSES, HIGH ALLOY STEELS, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, IRON ALLOYS, IRON BASE ALLOYS, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIFETIME, MINUTES LIVING RADIOISOTOPES, NEUTRAL-PARTICLE TRANSPORT, NUCLEI, ODD-ODD NUCLEI, RADIATION TRANSPORT, RADIOISOTOPES, REACTORS, STEELS, STORAGE, TRANSITION ELEMENT ALLOYS, YEARS LIVING RADIOISOTOPES
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