Subjects: Nuclear Science and Technology >> Nuclear Science and Technology submitted time 2024-05-24
Abstract： [Objective] In order to solve the problem that the existing R&D level of mobile reactors cannot meet the relevant requirements of the GB11806-2019 Regulations for the Safe Transport of Radioactive Materials, and cannot obtain transportation permits under the domestic regulatory system, [Method] In this study, according to the relevant requirements of 10 CFR 71 and §12 of the United States, the types of accidents that may be encountered in the transportation of mobile reactors were sorted out, and the most serious accident impact with the tanker truck was used as the design benchmark accident. The accident risk of a mobile reactor with an assumed power of 20 MWt under the design baseline accident is calculated. [Result] It was calculated that the probability of the design benchmark accident of the mobile reactor was 9.7×10-6/year under the condition of annual transportation, and the irradiation dose to the staff under the design benchmark accident after the reactor was cooled for one year was 810mSv. After 5 years of cooling, the radiation dose to workers under the design baseline accident was 590 mSv. [Conclusion] The accident consequences of mobile reactors under the design benchmark accident far exceed the irradiation dose limits for workers in SSG-26 Advisory Material for the IAEA Regulations For the Safe Transport of Radioactive Material and the GB18871 Safety Standards for Protection against Ionizing Radiation and Radiation Sources. Moreover, the probability of occurrence of design benchmark accidents does not meet the screening requirements of 10-7 years of over-design benchmark accidents in China. Therefore, it is necessary to take management measures, including armed escort and route planning, during the transportation of mobile reactors, to reduce the probability of design baseline accidents, and take corresponding protective measures to mitigate the consequences of design baseline accidents to meet the regulatory requirements of the nuclear safety department.
Subjects: Nuclear Science and Technology >> Nuclear Science and Technology submitted time 2024-05-08
Abstract： The high level radioactive liquid waste (HLLW) storage building is an essential facility in the spent fuel reprocessing plant. and its stable operation is related to the production safety of the entire plant area. This article elaborates on the process system design of HLLW storage building based on design standards and engineering practice. including the HLLW storage and transportation system. circulating cooling water system. HLLW mixing system. dilution air and exhaust treatment system of the liquid waste storage tank. and so on. The overall layout form. process equipment and pipeline layout characteristics of HLLW storage building are introduced with the example of the actual project. Reference can be provided for designing of HLLW storage building and other nuclear chemical projects in the future.
Subjects: Nuclear Science and Technology >> Radiation Protection Technology Subjects: Nuclear Science and Technology >> Nuclear Safety Subjects: Nuclear Science and Technology >> Engineering Technology of Nuclear Fusion submitted time 2024-04-02
Abstract： he amount of gaseous tritium stored and released in fusion reactor is higher than which in current fission reactors, so that tritium is an important source of potential radioactivity in fusion reactor. Therefore, in order to achieve the safety and environmental friendliness of fusion reactor in the future, it is necessary to study the environmental impact of gas tritium emission from fusion reactor. Based on the Gauss model to predict the atmospheric dispersion of gaseous tritium release and the dry deposition of tritium gas (HT), soil oxidation and reevaporation of HTO, the radiation dose of 1g HT released from fusion reactor to the public in the surrounding environment was calculated. The calculation results show that: The effective dose of inhalation internal irradiation of HT released at 10m height for adults at 500-3000m W of the release point ranges from 0.38mSv to 0.1mSv The dose caused by the reevaporation effect of HTO at different distances is the main source of the dose of gaseous tritium. The proportion of the HT deposited to soil being oxidized to HTO and the atmosphere condition are the key parameter determining the effective dose of the tritium gas. The study shows that the effective dose of HT released from fusion reactor to public is higher than which released from fission reactor,so that further attention to the environmental impact of the tritium is needed in the research on the fusion reactor subsequently.
Peer Review Status:
Awaiting Review
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