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Nuclear Criticality Safety Calculating For Dissolution And Pulsed Extraction Column

Posted on:2020-07-01Degree:MasterType:Thesis
Country:ChinaCandidate:K ZhaoFull Text:PDF
GTID:2392330620451580Subject:Nuclear power and nuclear technology engineering
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This thesis describes the necessity of spent fuel reprocessing,and introduces the main reprocessing plants in the world as well as the dissolver and pulse extraction column of reprocessing plants,and analyzes the problems existing in the dissolver and pulse extraction column of reprocessing plants at present.The critical safety calculation and analysis of the critical equipment in the post-treatment plant can effectively avoid the nuclear critical reaction during the operation of the equipment.The critical safety design principle and the critical control method of the post-treatment plant are also introduced.At present,the domestic reprocessing plant can only deal with the uranium dioxide core of fuel rod with an initial 235U concentration of 3.30%.To meet the need of reprocessing plants'design when the initial 235U concentration in UO2 core of fuel rod is 4.45%or 5.00%,the MCNP program is used to calculate and investigate Keff limited by nuclear criticality safety of dissolver and pulsed extraction column and to determine whether the dissolver and pulsed extraction column with set parameters can deal with the spent fuel with an initial 235U concentration of 4.45%or 5.00%in the uranium dioxide core of fuel rod.Kinf limited by three different 235U enrichments?3.30%,4.45%and 5.00%? are respectively calculated and analyzed according to the short rod model in the case of specular reflection of dissolver,and the best radius and slowing down model are found out.According to the best radius and the best slowing down model,the best grid model was established to calculate the nucleus critical safety of keff when the three 235U enrichment degrees?3.30%,4.45%and 5.00%?are treated by the dissolver.Through the analysis,it can be concluded that the dissolver with set parameters cannot deal with the spent fuel when 235U enrichment degrees is 4.45%or 5.00%.In order to solve this problem,some schemes are proposed,such as adding neutron poison,reducing the size of the basket of the dissolver and annular arrangement of multiple dissolvers,and the relevant critical control parameters are given.There are two systems in the pulse extraction column:organic phase continuous system and water phase continuous system.When the concentration of 235U is 3.30%,4.45%,5.00%and the concentration of 239Pu is 100%,the keff of total water reflection and vacuum reflection are calculated,respectively.The keff of the central column of the extraction column in case of accident was also calculated.The results show that when the concentration of 235U is 5.00%,keff in the whole water reflection,vacuum reflection and accidental feeding of materials into the central column of extraction column in the water phase continuous system are all beyond the critical safety acceptance criteria.Therefore,it is concluded that the large-scale annular baffled pulse extraction column cannot deal with the material with the 235U concentration of 5.00%.In order to solve this problem,the scheme of adding neutron poison,adding polyethylene in the central column,changing the size of equipment and so on are put forward,and the critical safety calculation of the scheme is carried out,and the relevant critical control parameters are given.
Keywords/Search Tags:MCNP program, dissolution tank, pulsed extraction column, nuclear criticality, safety analyzing, grid model
PDF Full Text Request
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