Application of the pyrochemical process to recycle of actinides from LWR spent fuel

McPheeters, C.C.; Pierce, R.D.; Mulcahey, T.P.

doi:10.1016/0149-1970(96)00010-8

Cited by 57 publications

(32 citation statements)

References 2 publications

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“…Later, the applicability of the pyroprocess was extended to spent oxide fuels discharged from light water reactors (LWRs) by the institute for the purpose of recycling the oxide spent fuels (SFs) as well as recovering the transuranics (TRUs) [2]. The oxide SFs are stable in a molten salt which is used as an electrolyte in an electrometallurgy process known as an electrorefining, and, thus, they cannot be directly introduced into the developed process for metal fuels.…”

Section: Introductionmentioning

confidence: 99%

Behavior of diffusing elements from an integrated cathode of an electrochemical reduction process

Park

Hur

2010

Korean J. Chem. Eng.

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The electrochemical reduction process for spent oxide fuel is operated in a molten salt bath and adopts an integrated cathode in which the oxides to be reduced act as a reactive cathode in the molten salt electrolyte cell. Heat-generating radioisotopes in the spent oxide fuel such as cesium and strontium are dissolved in the molten salt and diffuse from the integrated cathode. However, the behavior of the dissolved cations has not been clarified under an electrochemical reduction condition. In this work, the reduction potentials of cesium, strontium, and barium were measured in a molten LiCl-3 wt% Li 2 O salt and their mass transfer behavior was compared with two current conditions on the cell. The concentration changes of the cations in the molten salt phase were measured and no significant differences on the dissolution behavior were found with respect to the current. However, under a continued current condition, the removal of the high heat-generating elements requires more time than the complete reduction of metal oxide due to the slow rate of diffusion.

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Section: Introductionmentioning

confidence: 99%

Behavior of diffusing elements from an integrated cathode of an electrochemical reduction process

Park

Hur

2010

Korean J. Chem. Eng.

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“…The emitted fuel is converted into the uranium metal by the electroreduction process, and the uranium is recovered by the electrorefining process [12]; the remaining uranium and TRU are recovered in an ingot state by the electrowinning process [13]. The recovered surplus uranium is either recycled or disposed of as the low-level waste, and the U-TRU ingots are used in the SFR nuclear fuel [14]. This process has many benefits over the conventional aqueous process; e.g., it produces a smaller amount of secondary radioactive wastes and it needs compact equipment.…”

Section: Introductionmentioning

confidence: 99%

Fabrication and evaluation of rare-earth-bearing fuel slugs for sodium-cooled fast reactors

Kim

Song

Kim

et al. 2014

J Radioanal Nucl Chem

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Separation of rare-earth (RE) elements from minor actinides is difficult in pyroprocessing, especially for light REs (e.g., Nd, Ce, Pr, and La). Herein, U-10 wt%Zr fuel slugs containing 0, 3, and 7 wt%RE (RE: a rare-earth alloy comprising 53 % Nd, 25 % Ce, 16 % Pr, and 6 % La by weight) were prepared by gravity casting. Their casting soundness was characterized by gamma-ray radiography and immersion density measurement, while their microstructures and compositions were analyzed using scanning electron microscopy and energy-dispersive X-ray spectroscopy. Their actual compositions and impurities were confirmed using inductively coupled plasma atomic emission spectrometry. The compatibility of casting components and recovery of radioactive materials were evaluated based on the RE content.

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“…The uranium in SNF comprises about 96-97% of the mass of the fuel. UREX+ process has the goal, and laboratory scale demonstrations have shown, [9,10] that uranium recovery is >90%, and its purity requirement will allow its waste disposal as low-level waste according to 10CFR61.55. This is the criterion that the uranium contain less than 100 nCi/g of TRU.…”

Section: A) Urex+ Processmentioning

confidence: 99%

“…For non-aqueous processing the focus of this work will be on pyroprocessing [9,10] as developed by ANL in the IFR program. Pyroprocessing is not a continuous process but operates on batches of fuel in an electrochemical cell that is a LiCl bath operated at 650°C.…”

Section: Fuel Processing Systemsmentioning

confidence: 99%

Safeguards and Non-proliferation Issues as Related to Advanced Fuel Cycle and Advanced Fast Reactor Development with Processing of Reactor Fuel

Aryaeinejad¹,

Cole²,

Drigert³

et al. 2006

2006 IEEE Nuclear Science Symposium Conference Record

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Abstract--The goal of this work is to establish basic data and techniques to enable safeguards appropriate to a new generation of nuclear power systems that will be based on fast spectrum reactors and mixed actinide fuels containing significant quantities of "minor" actinides, possibly due to reprocessing, and determination of what new radiation signatures and parameters need to be considered. The research effort focuses on several problems associated with the use of fuel having significantly different actinide inventories that current practice and on the development of innovative techniques using new radiation signatures and other parameters useful for safeguards and monitoring. In addition, the development of new distinctive radiation signatures as an aid in controlling proliferation of nuclear materials has parallel applications to support Gen-IV and current advanced fuel cycle initiative (AFCI) goals as well as the anticipated Global Nuclear Energy Partnership (GNEP).

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Application of the pyrochemical process to recycle of actinides from LWR spent fuel

Cited by 57 publications

References 2 publications

Behavior of diffusing elements from an integrated cathode of an electrochemical reduction process

Behavior of diffusing elements from an integrated cathode of an electrochemical reduction process

Fabrication and evaluation of rare-earth-bearing fuel slugs for sodium-cooled fast reactors

Safeguards and Non-proliferation Issues as Related to Advanced Fuel Cycle and Advanced Fast Reactor Development with Processing of Reactor Fuel

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