[en] Transport of radioactive material as the flowing risk source, its security is relatively weaker than nuclear facilities or nuclear technology utilization, are more likely to happen radioactive material loss, theft, and destruction. An online monitoring platform for transport of radioactive material can effectively ensure the transport safety and the accident treatment in control. 'Satellite positioning system shall be used for online tracking of the vehicle when deliver Category I and II radioactive material' was provided in which has been implemented in 2010. At present a national monitoring platform for transport of Category I and II radioactive material has not been built yet. In this paper, the functions of online monitoring platform had been propounded after discussed the features of radioactive material transportation. The paper surveyed the device requesting and performance parameter for the platform that based on transport volume of Category I and II radioactive material in recent years. An online monitoring platform has been built eventually so as to meet the demands of real-time tracking, video monitoring, radiation monitoring, security technology, electronic fence, alarm and other technology. (authors)

[en] The developing background and importance of the rules on supervision of the radioactive material transport are discussed in the paper. Based on the existing problems found in the process of implementing the rule 'Regulations for the safe transport of Radioactive Material', some countermeasures are proposed. (authors)

[en] The concept of nuclear materials has been employed for nearly 30 years in China, and it will be used continuously. Comparing with the concept of nuclear material of IAEA in the domain of nuclear security, this paper analyses the legislation background and problems of the current controlled targets in China by researching the current situations and limitations of China. This is the first time that the concept of nuclear material controlled targets is being studied domestically. Based on this, some key factors of nuclear material control during the revision of nuclear material regulation have been promoted. (authors)

[en] There are two kinds of Spent fuel storage, wet storage and dry storage. Dry storage facility status of domestic and several main foreign countries was investigated in this paper. The technological characteristics of concrete silo and metal cask were studied and analysed. Some safety problems were pointed out about dry storage technologies. Finally, it is suggested to carry out some studies on dry storage facilities for spent fuel in the future combined with the needs for the away-from-reactor storage. (authors)

[en] In order to verify the criticality safety analysis results of CEFR-MOX fuel assembly transport container, this paper conducts independent check analysis and calculation for the criticality safety calculation model, scenario assumptions under normal and accident condition, and criticality safety analysis. The results of the check indicate that the change trend of the K_eff value is basically consistent with the original design under normal and accident conditions. The relative deviation between the maximum K_eff value and the original design K_eff value does not exceed 1%. (authors)

[en] Classification of fissile materials and regulatory requirements have taken place great changes in IAEA-SSR6-2012, GB11806-2004 is under revision, the technical route is equivalent to the adoption of IAEA-SSR6. This paper compares IAEA-SSR6 and GB11806-2004 classification methods and regulatory requirements for Transport of fissile materials, analyzes the fissile-excepted of IAEA-SSR6 variation and the new CSI-controlled fissile classification criteria, and study the applicability of IAEA-SSR6 Fissile content to revised GB11806-2004, citing actual examples, applicable conclusions and recommendations are given. (authors)

[en] GB 11806-2004 is technically equivalent to the IAEA Regulations for the Safe Transport of Radioactive Material (2003 Edition). Since then IAEA has revised the regulations several times, and the technical contents of the revised editions of 2012 and 2018 had changed a lot. Some of changes have major impact on the implementation of transport in related industries. This article briefly described the important changes of the latest version of the regulation (2018 version), and analyzed the changes and its applicability in order to revise and understand GB 11806 better. (authors)

[en] Objective: To study the radiation effects of spent fuel transportation from Guangdong to northwest region under different modes. Methods: Using the CRAMTRA 1.0 code, radiation doses of spent fuel transportation under different modes on the typical public and workers were calculated. Results: The public collective effective dose per ton of spent fuel delivered to the public had the greatest impact on long-distance road transport (1.65 × 10^-3 Sv/t), while the Road-Ocean-Rail transport mode had the least radiation impact (2.63 × 10^-4 man·Sv/t), and the radiation impact of Road-Rail transport mode was the middle (4.51 × 10^-4 man · Sv/t). The long-distance road transport mode had a significantly higher occupational exposure to workers (6.00 × 10^-1 man · Sv/t) than that of Road-Rail transport mode (7.93 × 10^-2 man · Sv/t) or Road-Ocean-Rail transport mode (1.05 × 10^-1 man · Sv/t). Conclusion: The radiation effects of Road-Ocean-Rail transport mode is relatively small. (authors)

[en] There are different requirements of the radiation monitoring before start shipment about transportation of three categories of radioactive material in China. Chinese programs of radiation monitoring for domestic transportation, radioactive material imported or by way of the territory of the People's Republic of China, are analyzed respectively in this research pursuant to Regulations for the Safe Transport of Radioactive Material of 2009, and the other regulations. The main contents, the submission procedures, and document requirements of the radiation monitoring report are concluded. (authors)

[en] Objective: This paper discusses the relevant issues of formulating the initial conditions of emergency response and the levels of emergency response (ICs/EALs) for nuclear power plants, such as the level of 'abnormal airborne effluents'. Methods: Some problems involved in the formulation of emergency response level for airborne outflow materials were discussed. Results: The analysis shows that the delayed release time, the share of nuclide release and the transformation of EAL units could affect the derivation of the emergency action level of 'abnormal airborne effluents'. Conclusion: The priority of emergency action level of abnormal airborne effluents is low, which is not the only criterion for decision-making, but it is an indicator of EAL diversity and can reflect the symptoms of some potential events. (authors)