Decommissioning industrial uranium-graphite reactors

Soviet Atomic Energy - Tập 87 - Trang 569-576 - 1999
I. D. Kulikov1, V. D. Safutin1, V. M. Simanovskii1, M. I. Abramov, B. K. Bylkin2, Yu. A. Zverkov2, N. E. Kukharkin2, V. V. Vainshtein, B. A. Pyatunin, Yu. I. Kabanov3, V. M. Kondakov3, A. G. Nikolaev3
1All-Russian Scientific-Research and Design Institute of Power Technology, Russian
2Kurchatov Institute, Russian Scientific Center, Russian
3Siberian Chemical Combine, Russian

Tóm tắt

The basic problems in decommissioning industrial uranium-graphite reactors are analyzed, taking account of experience in decommissioning the I-1 and ÉI-2 reactors at the Siberian Chemical Combine. On the basis of the analysis, decommissioning with delayed dismantling of the reactor structures is recommended.

Tài liệu tham khảo

B. K. Bylkin and B. A. Pyatunin, “Development of radiation-safe technologies and equipment for dismantling Russian nuclear reactors,”Byull. Tsentra Obshch. Inform. po Ispol'zovaniyu Atomnoi Energii, No. 6, 7–13, 1996. Radiation Safety Standards (NRB-96) [in Russian] (1996). Basic Nuclear-Safety Rules for the Use, Processing, Storage, and Transportation of Hazardous Fissile Materials (PBYa-06-00-96) [in Russian] (1996). “Safety rules in decommissioning industrial reactors (draft),”Vestn. Gosatomnadzor Rossii, No. 1, 83–111 (1998). Environmental and Safety Rules for Power-Station Design and Operation (SP AS 88/93) [in Russian] (1993). Decommissioning Handbook, DOE/EM-0142P U.S. Department of Energy, Office of Environmental Restoration, 1994. Regulatory Process for the Decommissioning of Nuclear Facilities. IAEA Safety Series No. 105, IAEA, Vienna (1990).