Advanced reprocessing for fission product separation and extraction

Collins, E.D.; Cul, G. D. Del; Moyer, Bruce A.

doi:10.1533/9780857092274.2.201

Cited by 7 publications

(3 citation statements)

References 45 publications

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“…Fission product fraction is dependent on the fuel burn ups with greater amounts produced in higher burn up fuels. The US inventory of spent nuclear fuel consists of 2-5 wt% fission products depending on the fuel burn up [10] . The fission products are predominantly centred around two mass fractions of 90-100 in the light fraction and 135-145 in the heavy fraction [10] .…”

Section: Spent Nuclear Fuelmentioning

confidence: 99%

“…The US inventory of spent nuclear fuel consists of 2-5 wt% fission products depending on the fuel burn up [10] . The fission products are predominantly centred around two mass fractions of 90-100 in the light fraction and 135-145 in the heavy fraction [10] . For easier handling, the fission products are classified according to their chemical and radiological properties.…”

Section: Spent Nuclear Fuelmentioning

confidence: 99%

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Treatment of Spent Nuclear Fuel for Separation, Immobilization and Disposal of Heat Generating High Level Fission Products, Caesium and Strontium

Aziz¹,

Ahsan²,

Khan

et al. 2017

J Chem Engg

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Separation of heat generating, high level fission product caesium and strontium from spent nuclear fuel boosts the capacity of waste repositories by as much as fifty times. For efficient use of already scarce repositories, separation of such fission products is mandatory. Separations of caesium and strontium using Chlorinated Cobalt Dicarbollide (CCD), PEG (Polyethylene Glycol), UNEX process and by Calixarenes or Fission Product Extraction Process (FPEX) were discussed. The UNEX method was then proposed as the most feasible method option. Following separation, nuclear waste immobilization techniques for such high-level fission product were discussed. The techniques included usage of concrete, glass and synthetic rock. Among them synthetic rock was identified as the most suitable one for immobilization of high-level nuclear waste. Finally, a safe disposal system with necessary required geology was shown for safe disposal of the waste.

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Section: Spent Nuclear Fuelmentioning

confidence: 99%

Section: Spent Nuclear Fuelmentioning

confidence: 99%

Treatment of Spent Nuclear Fuel for Separation, Immobilization and Disposal of Heat Generating High Level Fission Products, Caesium and Strontium

Aziz¹,

Ahsan²,

Khan

et al. 2017

J Chem Engg

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“…As SNF burnups increase, so do their Pu contents, which can impact their dissolution in HNO 3 , as high-Pu ceramics are slow to dissolve, oftentimes resulting in Pu-containing UDS, particularly for MOX SNF. For UO 2 -based fuels, the primary effect observed is the conversion of the bulk ceramic from UO 2 to U 3 O 8 , which serves to increase the volume of the ceramic and converts it to a form more amenable to dissolution [61]. Several technologies to address this have been proposed:…”

mentioning

confidence: 99%

A Review of Opportunities and Methods for Recovery of Rhodium from Spent Nuclear Fuel during Reprocessing

Hodgson

Turner

Holdsworth

2023

JNE

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Rhodium is one of the scarcest, most valuable, and useful platinum group metals, a strategically important material relied on heavily by automotive and electronics industries. The limited finite natural sources of Rh and exponentially increasing demands on these supplies mean that new sources are being sought to stabilise supplies and prices. Spent nuclear fuel (SNF) contains a significant quantity of Rh, though methods to recover this are purely conceptual at this point, due to the differing chemistry between SNF reprocessing and the methods used to recycle natural Rh. During SNF reprocessing, Rh partitions between aqueous nitric acid streams, where its speciation is complex, and insoluble fission product waste streams. Various techniques have been investigated for Rh recovery during SNF reprocessing for over 50 years, including solvent extraction, ion exchange, precipitation, and electrochemical methods, with tuneable approaches such as impregnated composites and ionic liquids receiving the most attention recently, assisted by more the comprehensive understanding of Rh speciation in nitric acid developed recently. The quantitative recovery of Rh within the SNF reprocessing ecosystem has remained elusive thus far, and as such, this review discusses the recent developments within the field, and strategies that could be applied to maximise the recovery of Rh from SNF.

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Integration of a hyphenated HPIC-ICPMS protocol for the measurement of transplutonium isotopic mass distributions for 252Cf campaigns at Oak Ridge National Laboratory

Roach

Giaquinto

Keever

2018

J Radioanal Nucl Chem

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Advanced reprocessing for fission product separation and extraction

Cited by 7 publications

References 45 publications

Treatment of Spent Nuclear Fuel for Separation, Immobilization and Disposal of Heat Generating High Level Fission Products, Caesium and Strontium

Treatment of Spent Nuclear Fuel for Separation, Immobilization and Disposal of Heat Generating High Level Fission Products, Caesium and Strontium

A Review of Opportunities and Methods for Recovery of Rhodium from Spent Nuclear Fuel during Reprocessing

Integration of a hyphenated HPIC-ICPMS protocol for the measurement of transplutonium isotopic mass distributions for 252Cf campaigns at Oak Ridge National Laboratory

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