title: ÐÑÐ³Ð°Ð½Ð¸Ð·Ð°ÑÐ¸Ñ Ð´Ð¾Ð¶Ð¸Ð³Ð°Ð½Ð¸Ñ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð° Ð¿ÑÐ¸ Ð²ÑÐ²Ð¾Ð´Ðµ Ð¸Ð· ÑÐºÑÐ¿Ð»ÑÐ°ÑÐ°ÑÐ¸Ð¸ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° ÐÐ­Ð¡
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° ÑÐ¿ÐµÑÐ¸Ð°Ð»Ð¸ÑÑÐ°
titleType: Subtitle
title: Organization of afterburning of fuel during decommissioning of the NPP power unit
Creators: name: ÐÐ¾Ð¿ÑÑÐ¾Ð², Ð Ð¾Ð¼Ð°Ð½
Publisher: name: Ð¡Ð°Ð½ÐºÑ-ÐÐµÑÐµÑÐ±ÑÑÐ³ÑÐºÐ¸Ð¹ Ð¿Ð¾Ð»Ð¸ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ½Ð¸Ð²ÐµÑÑÐ¸ÑÐµÑ ÐÐµÑÑÐ° ÐÐµÐ»Ð¸ÐºÐ¾Ð³Ð¾
Year: 2022
Subjects: ÐÑÐ¾Ð¼Ð½ÑÐµ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¸Ðµ ÑÑÐ°Ð½ÑÐ¸Ð¸
Ð¯Ð´ÐµÑÐ½Ð¾Ðµ Ð³Ð¾ÑÑÑÐµÐµ
Ð´Ð¾Ð¶Ð¸Ð³Ð°Ð½Ð¸Ðµ
ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾Ðº Ð ÐÐÐ
Ð²ÑÐ´ÐµÑÐ¶ÐºÐ°
Ð²Ð½ÑÑÑÐ¸ÑÑÐ°Ð½ÑÐ¸Ð¾Ð½Ð½Ð°Ñ Ð¿ÐµÑÐµÐ²Ð¾Ð·ÐºÐ°
afterburning
RBMKpower unit
holding
instation transportation

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description: The subject of the graduate qualification work is Â«Organization of afterburning of fuel during decommissioning of the NPP power unitÂ». This work is devoted to the study of technological issues of the organization of afterburning at a nuclear power plant with RBMK(LWGR). Tasks that were solved during the study: 1. To carry out a calculation justification of both radiation and nuclear safety of intra-station transportation of SFAS by means of VTUK-8M. 2. To analyze the calculation data in accordance with the main regulatory docu-ments regulating the activities of nuclear power plants. 3. Estimate the holding time of SFAS in spent fuel pool before transportation. 4. Formulate recommendations on the organization of transportation of SFAS at other nuclear power plants. The work was carried out on the basis of the Leningrad NPP, where a significant part of the factual material was collected: in-plant documents, design documentation, and the results of calculations of ionizing radiation. Calculations were made for the safety of intra-plant transportation of SFAs. The calculation of nuclear safety was car-ried out by a conservative method, which overestimated the neutron multiplication fac-tor. The method of homogenization of the elementary cell of a heterogeneous lattice was used in the calculation. The neutron-physical calculation was carried out in the one-group approximation. When calculating biological protection, the radiation power distribution was assumed to be uniform in volume and constant in time. Radiation from a real cylindrical source was replaced by radiation from a linear source. The exposure time was calculated using the data approximation method. As a result of the work, the neutron multiplication factors were calculated. The values of the dose rate on the surface of the VTUK were found. The holding time of leaky SFAs and sealed SFAs for afterburning has been found. Recommendations for the organization of fuel afterburning at other NPPs with RBMK are formulated.