Title Impact of nuclide composition evolution to RBMK spent fuel nuclear safety and irradiated graphite radiation safety characteristics /
Translation of Title Nuklidinės sudėties evoliucijos įtaka RBMK reaktoriaus panaudoto kuro branduolinės saugos ir apšvitinto grafito radiacinės saugos charakteristikoms.
Authors Barkauskas, Vytenis
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Pages 148
Keywords [eng] RBMK ; actinides ; burn-up credit ; graphite
Abstract [eng] This dissertation is the study of the influence of actinides and other strongly neutron-absorbing nuclides on nuclear safety characteristics of spent nuclear fuel as well as radiation safety characteristics of the actinides in the RBMK reactor moderator graphite. The representative geometrical model of the RBMK reactor lattice was used to simulate the nuclear fuel burn in the reactor and to evaluate the spent nuclear fuel composition against the available experimental data. The effective neutron multiplication factor of the spent nuclear fuel cask was evaluated taking into account spent nuclear fuel composition changes during burn-up as well as introducing the axial burn-up profile of the nuclear fuel assembly. The build-up of long-lived actinides in the RBMK reactor graphite from very small fraction of uranium impurities in the virgin nuclear graphite during operation of the reactor was calculated precisely evaluating reactor neutron spectrum characteristics through the novel use of the average burn-up composition of the nuclear fuel.
Dissertation Institution Vilniaus universitetas.
Type Doctoral thesis
Language English
Publication date 2016