Plutonium and other actinides behaviour in NEXT process

Sano, Yuichi; Miura, Susumu; Nakahara, Masaumi; Kamiya, M.; Nomura, Kazunori; Komaki, J.

doi:10.1016/j.jallcom.2007.03.092

Cited by 10 publications

(3 citation statements)

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“…JAEA researchers have observed the double nitrate of Pu 4+ to form with Cs + in a similar system, which they reported being removed quantitatively from solution. [16][17][18][19][20]35 Only 10 ± 1% of the Ce was observed to be removed. The difference between Pu 4+ and Ce 4+ is attributed to differences in the formation constants of the two nitrate species.…”

Section: ■ Results and Discussionmentioning

confidence: 99%

“…The new extraction system for transuranic (TRU) recovery (NEXT) − has been developed by the Japanese Atomic Energy Agency (JAEA) over the past decade, in which the bulk of the U is removed from solution by crystallization prior to PUREX processing. This helps reduce the effects of the organic phase being overloaded with U during subsequent extraction.…”

Section: Introductionmentioning

confidence: 99%

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Group Hexavalent Actinide Separations: A New Approach to Used Nuclear Fuel Recycling

Burns

Moyer

2016

Inorg. Chem.

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Hexavalent Np, Pu, and Am individually, and as a group, have all been cocrystallized with UO2(NO3)2·6H2O, constituting the first demonstration of an An(VI) group cocrystallization. The hexavalent dioxo cations of Np, Pu, and Am cocrystallize with UO2(NO3)2·6H2O in near proportion with a simple reduction in temperature, while the lower valence states, An(III) and An(IV), are only slightly removed from solution. A separation of An(VI) species from An(III) ions by crystallization has been demonstrated, with an observed separation factor of 14. Separation of An(VI) species from key fission products, (95)Zr, (95)Nb, (137)Cs, and (144)Ce, has also been demonstrated by crystallization, with separation factors ranging from 6.5 to 71 in the absence of Am(VI), while in the presence of Am(VI), the separation factors were reduced to 0.99-7.7. One interesting observation is that Am(VI) shows increased stability in the cocrystallized form, with no reduction observed after 13 days, as opposed to in solution, in which >50% is reduced after only 10 days. The ability to cocrystallize and stabilize hexavalent actinides from solution, especially Am(VI), introduces a new separations approach that can be applied to closing the nuclear fuel cycle.

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Section: ■ Results and Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Group Hexavalent Actinide Separations: A New Approach to Used Nuclear Fuel Recycling

Burns

Moyer

2016

Inorg. Chem.

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“…The loading of metal was 79.6 g/dm 3 , as calculated by MIXSET-X in RUN2. In the stripping section, to prevent U leakage to the spent solvent, U, Pu and Np were co-stripped by 0.02 mol/dm 3 HNO 3 pre-heated to about 45 • C [5]. For preventing the generation of Pu polymer at the high Pu concentration stages, a small amount of 3 mol/dm 3 HNO 3 was fed to the U, Pu and Np co-stripping section.…”

Section: Counter Current Experimentsmentioning

confidence: 99%

Uranium, plutonium and neptunium co-recovery with high nitric acid concentration in extraction section by simplified solvent extraction process

Nakahara¹,

Sano²

2009

Radiochimica Acta

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Simplified solvent extraction process / NEXT / Neptunium / Centrifugal contactor / Co-recovery / TBP Summary. As a part of NEXT, the behavior of Np in a simplified solvent extraction process using TBP as an extractant for U, Pu and Np co-recovery was investigated. Two approaches to Np co-recovery with U and Pu in the irradiated fast reactor core fuel using a dissolver solution in a counter current were examined. One used a feed solution with a high HNO 3 concentration, and the other used a scrubbing solution with a high HNO 3 concentration. The leakages of Np to the raffinate were 1.1 and 4.7% using high HNO 3 concentration feed and scrubbing solutions, respectively. Simulation results based on these experiments showed that high HNO 3 concentration in the feed solution is advantageous for the Np extraction because Np oxidation progresses in the feed solution before being supplied into the centrifugal contactor, and there is less effect of HNO 2 at the extraction section.

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Results of experimental testing of a hydrometallurgical technology for reprocessing spent nuclear fuel of fast neutron reactors

Shlyazhko,

Terentev,

Dvoeglazov

et al. 2024

At Energy

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Plutonium and other actinides behaviour in NEXT process

Cited by 10 publications

References 3 publications

Group Hexavalent Actinide Separations: A New Approach to Used Nuclear Fuel Recycling

Group Hexavalent Actinide Separations: A New Approach to Used Nuclear Fuel Recycling

Uranium, plutonium and neptunium co-recovery with high nitric acid concentration in extraction section by simplified solvent extraction process

Results of experimental testing of a hydrometallurgical technology for reprocessing spent nuclear fuel of fast neutron reactors

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