2014
DOI: 10.1134/s1066362214050099
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Ways of technetium and neptunium localization in extraction reprocessing of spent nuclear fuel from nuclear power plants

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Cited by 15 publications
(2 citation statements)
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“…Within the framework of this flowsheet, it is possible to obtain U and Pu strips, as well as their master mixtures (with Np or without it). The flowsheet was tested on a rig of mixer-settlers at the Scientific and Experimental Complex of the Radium Institute for UREA DERIVATIVES reprocessing of WWER-1000 fuel with the burn-up of up to 70 GW day (t U) -1 [81][82][83].…”
Section: Hydroxamic Acidsmentioning
confidence: 99%
“…Within the framework of this flowsheet, it is possible to obtain U and Pu strips, as well as their master mixtures (with Np or without it). The flowsheet was tested on a rig of mixer-settlers at the Scientific and Experimental Complex of the Radium Institute for UREA DERIVATIVES reprocessing of WWER-1000 fuel with the burn-up of up to 70 GW day (t U) -1 [81][82][83].…”
Section: Hydroxamic Acidsmentioning
confidence: 99%
“…Several modifications of the PUREX process have been proposed in which parameters such as HNO 3 concentration, metal ion (U, Pu, Np, and Tc) concentrations, and nature of the reducing agent can vary. For example, the solution composition of the single-cycle flowsheet for the UNF reprocessing from the WWER-440 reactor using N 2 H 4 as the reducing agent is presented in Table …”
Section: Introductionmentioning
confidence: 99%