A review on UREX processes for nuclear spent fuel reprocessing

Kumari, Indu; Kumar, B. V. Rathish; Khanna, Ashok

doi:10.1016/j.nucengdes.2019.110410

Cited by 60 publications

(25 citation statements)

References 10 publications

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“…4%). 4 As of 2020, approximately 450 000 tons of SNF have been cumulatively generated worldwide, of which only $25% have been reprocessed using the decades-old Plutonium Uranium Redox EXtraction (PUREX) process. 5 While this commercial, liquid-liquid process is extremely efficient at extracting and recycling UO 2 2+ using stoichiometric extractants, in turn reducing SNF loads, PUREX involves the selective extraction of a pure Pu stream which raises signicant proliferation concerns from major stakeholders, such as the U.S. 6 While other reprocessing schemes addressing these concerns have been developed (e.g., UREX), none are commercial.…”

Section: Introductionmentioning

confidence: 99%

“…To this day, proliferation concerns have superseded reprocessing efforts in places like the U.S., forcing countries to instead increase their SNF storage capacity, thus deferring action on the nuclear waste issue. 4,6,7 New strategies for the selective separation and recovery of UO 2 2+ from SNF, without the parallel extraction of a Pu stream, could therefore significantly aid in reducing net SNF generated from reactors, minimizing demands on long-term geological repositories, and in turn closing the fuel cycle.…”

Section: Introductionmentioning

confidence: 99%

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Selective electrochemical capture and release of uranyl from aqueous alkali, lanthanide, and actinide mixtures using redox-switchable carboranes

et al. 2022

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Selective electrochemical capture and release of uranyl from aqueous alkali, lanthanide, and actinide mixtures using redox-switchable carboranes

et al. 2022

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“…However, nuclear spent fuel management is one of the major problems in the use of nuclear energy (Waris and Sekimoto, 2001;Warin, 2007;IAEA, 2009). In order to solve this problem, this spent fuels has high radiotoxicity should be converted into stable or short-lived isotopes by nuclear reactions (Fridstrom, 2010;Loberg, 2010;Loberg et al, 2010;Zakova and Wallenius, 2013;Kumari et al, 2020). This situation can be created naturally or artificially, such as through human intervention (Günay, 2016).…”

Section: Introductionmentioning

confidence: 99%

Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactor

Düz

2021

Front. Energy Res.

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In this study, a Boiling Water Reactor (BWR) design was made using the Monte Carlo (MCNPX) method. The reactor core in the designed BWR system was divided into an 8 × 8 square lattice with a constant pitch of 30.48 cm. In this study, americium (Am), which is found in the minor actinidine (MA) of spent nuclear fuel known as nuclear waste from existing reactors, was used as fuel with the addition of oxygen and fluorine. In this study, AmO2 and AmF3 fuels at the rate of 0.02–0.1% were used as Americium Mixed Fuels, and Zircaloy-2 (Zr-2), SiC, and VC were used as clad. Neutronic calculations for certain Americium Mixed Fuels and clads were compared in the designed BWR system. In the BWR system designed in the study; keff, neutron flux, fission energy, heating, and depleted Am were calculated. The three-dimensional (3-D) modeling of the designed BWR system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B-VII.0 nuclear data library.

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“…These reactors use an enriched uranium-based fuel, composed of uranium oxide (UOX). Containing 3–5% of fissile 235 U, this fuel generates fission products and plutonium [ 3 ]. France has long made the choice of reprocessing used fuel, in order to valorize both unburnt uranium and generated plutonium, through the preparation of fuel composed of mixed uranium and plutonium oxides—MOX, Mixed OXide fuel.…”

Section: Introductionmentioning

confidence: 99%

Short Alternative Route for Nuclear Fuel Reprocessing Based on Organic Phase Self-Splitting

et al. 2021

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A more sustainable management of natural resources and the establishment of processes allowing a joint management of nuclear materials to avoid their diversion from their civilian use are two issues for the nuclear industry. Short alternatives to existing processes have therefore been proposed based on known systems available, tributylphosphate (TBP), for the separation of actinides by liquid/liquid extraction. Proof of concept of such alternative has been established on the uranium(VI)/thorium(IV) system. From an organic phase consisting of a mixture of TBP/n-dodecane loaded with uranium and thorium, two fluxes have been obtained: the first contains almost all of the thorium in the presence of uranium in a controlled ratio, the second contains surplus uranium. Two levers were selected to control the spontaneous separation of the organic phase: the addition of concentrated nitric acid, or the temperature variation. Best results have been obtained using a temperature drop in the liquid/liquid extraction process, and variations in process conditions have been studied. Final metal recovery and solvent recycling have also been demonstrated, opening the door for further process development.

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A review on UREX processes for nuclear spent fuel reprocessing

Cited by 60 publications

References 10 publications

Selective electrochemical capture and release of uranyl from aqueous alkali, lanthanide, and actinide mixtures using redox-switchable carboranes

Selective electrochemical capture and release of uranyl from aqueous alkali, lanthanide, and actinide mixtures using redox-switchable carboranes

Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactor

Short Alternative Route for Nuclear Fuel Reprocessing Based on Organic Phase Self-Splitting

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