title: Ð Ð°ÑÑÐµÑÐ½Ð°Ñ Ð¾ÑÐµÐ½ÐºÐ° Ð·Ð°ÑÐ¸ÑÐ½ÑÑ Ñ Ð°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸Ðº ÑÑÐ°Ð½ÑÐ¿Ð¾ÑÑÐ½Ð¾Ð³Ð¾ ÑÐ¿Ð°ÐºÐ¾Ð²Ð¾ÑÐ½Ð¾Ð³Ð¾ ÐºÐ¾Ð¼Ð¿Ð»ÐµÐºÑÐ° Ð´Ð»Ñ Ð¿ÐµÑÐµÐ²Ð¾Ð·ÐºÐ¸ Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð²ÑÐµÐ³Ð¾ ÑÐ´ÐµÑÐ½Ð¾Ð³Ð¾ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð° ÐÐÐ­Ð
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¼Ð°Ð³Ð¸ÑÑÑÐ°
titleType: Subtitle
title: Calculation assessment of the protective characteristics of the transport packaging for the transportation of VVER SNF
Creators: name: ÐÐ°Ð»ÑÑÐµÐ²Ð°, ÐÐ»ÑÐ½Ð°
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: 2023
Subjects: ÑÐ°Ð´Ð¸Ð°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ Ð·Ð°ÑÐ¸ÑÐ°
Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð²ÑÐµÐµ ÑÐ´ÐµÑÐ½Ð¾Ðµ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð¾
Ð³Ð»ÑÐ±Ð¸Ð½Ð° Ð²ÑÐ³Ð¾ÑÐ°Ð½Ð¸Ñ
ÑÑÐ°Ð½ÑÐ¿Ð¾ÑÑÐ½ÑÐ¹ ÑÐ¿Ð°ÐºÐ¾Ð²Ð¾ÑÐ½ÑÐ¹ ÐºÐ¾Ð¼Ð¿Ð»ÐµÐºÑ
Ð°ÐºÑÐ¸Ð²Ð½Ð¾ÑÑÑ
Ð¼Ð¾ÑÐ½Ð¾ÑÑÑ Ð´Ð¾Ð·Ñ
radiation protection
spent nuclear fuel
burnout depth
transport package
activity
dose intensity

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description: Topic of the final qualification work: "Calculation assessment of the protective characteristics of the transport packaging for the transportation of VVER SNF". The work considers issues related to the transportation of SNF from NPPs with VVER-1200 from the point of view of radiation safety, a study of the effectiveness of radiation protection was carried out using the example of a specific transport packaging set of TUK intended for the transportation of VVER SNF. The calculation was carried out taking into account the change in the isotopic composition of the fuel during burnup. SFA transportation safety is considered in two aspects: nuclear and radiation safety. Nuclear safety is based on the principle of preventing accidental criticality in all possible states of the nuclear fuel handling system. The main task of radiation safety is to limit the harm received by a person from SNF radiation sources. The substantiation of nuclear safety was carried out by a conservative method of homogenization of the elementary cell of a heterogeneous lattice, which overstates the neutron multiplication factor. The calculation of radiation protection was carried out in the FLUKA program, which implements the Monte Carlo method. As a result, the neutron multiplication factor in the TUK+SFA system was obtained, the values of the dose rate on the TUK surface and the decay dynamics depending on the distance were found. Recommendations are formulated for organizing the transportation of spent fuel assemblies from VVER-1200 reactors.