Search academic texts

Information × Registration Number 0218U001473, 0117U004863 , R & D reports Title Radiation safety in the transport of spent nuclear fuel with high burnup for storing dry method popup.stage_title Head Girka Igor Oleksandrovich, Registration Date 19-04-2018 Organization Kharkov National University named after V.N. Karazin popup.description2 The aim of this work is to develop methods for determining the dose loads induced by neutrons and gamma quanta outside transport containers at transportation of SNF with enhanced burn-up, as well as methods for calculating heat loads and estimating the dose loads on the personnel and inhabitants when eliminating possible consequences of accidents. The object of the research and development is radiation fields, which are produced by neutrons and gamma quanta induced by SNF outside the containers at SNF transportation and storage. The method of research and development includes the processes and mechanisms of emission and propagation of gamma and neutron radiations, with changes in their spectral compositions in time taken into account. The MCNP package (Monte Carlo method) was used to develop some geometric models designed for calculating emissions from spent fuel loaded into a multipurpose container when transported in the HI-STAR transport module and TK-13 transport container used for transportation of SNF from Ukrainian nuclear power plants to the Russian Federation. The isotope composition of SNF was calculated, with WWER-1000 reactor fuel of different burn-up levels and cooling time taken into account, on the basis of the solution of N system for inhomogeneous differential equations of the first-order by Bateman using FISPACT program code. The analysis showed that the increase in burnup depth from 45 to 65 MW·day/kg U, which makes 41%, leads to approximately the same increase in the long-lived nuclides activity, and for actinide 244Cm it makes 240%, i.e. 3.4 times, what is much higher. So, the neutron flux increases 3.4 times, and the gamma-ray flux - 1.41 times. To estimate the thermal state of SNF loaded into the transport container (cask) for stationary (normal) transportation conditions, a mathematical model of this stationary (normal) thermal-physic process was developed. To calculate the consequences of radiation accidents that can occur while transporting the spent nuclear fuel to the centralized storage site, two programs, HotSpot and COSYMA, were applied. Product Description popup.authors C. Альохіна І. Гірка В. Вітько В. Пишкін В. Рудичев Г. Ветрова Г. Махненко Е. Рудичев popup.nrat_date 2020-04-02 Close