Benchtop Zone Refinement of Simulated Future Spent Nuclear Fuel Pyroprocessing Waste

Research output: Contribution to journalArticlepeer-review

Standard Standard

Benchtop Zone Refinement of Simulated Future Spent Nuclear Fuel Pyroprocessing Waste. / Ogden, Mark; Bingham, Paul; Scrimshire, Alex et al.
In: Materials, Vol. 17, No. 8, 12.04.2024, p. 1781.

Research output: Contribution to journalArticlepeer-review

HarvardHarvard

Ogden, M, Bingham, P, Scrimshire, A, Backhouse, D, Wei, D, Sharrad, C, Mann, C, Harrison, M & McKendrick, D 2024, 'Benchtop Zone Refinement of Simulated Future Spent Nuclear Fuel Pyroprocessing Waste', Materials, vol. 17, no. 8, pp. 1781. https://doi.org/10.3390/ma17081781

APA

Ogden, M., Bingham, P., Scrimshire, A., Backhouse, D., Wei, D., Sharrad, C., Mann, C., Harrison, M., & McKendrick, D. (2024). Benchtop Zone Refinement of Simulated Future Spent Nuclear Fuel Pyroprocessing Waste. Materials, 17(8), 1781. https://doi.org/10.3390/ma17081781

CBE

Ogden M, Bingham P, Scrimshire A, Backhouse D, Wei D, Sharrad C, Mann C, Harrison M, McKendrick D. 2024. Benchtop Zone Refinement of Simulated Future Spent Nuclear Fuel Pyroprocessing Waste. Materials. 17(8):1781. https://doi.org/10.3390/ma17081781

MLA

VancouverVancouver

Ogden M, Bingham P, Scrimshire A, Backhouse D, Wei D, Sharrad C et al. Benchtop Zone Refinement of Simulated Future Spent Nuclear Fuel Pyroprocessing Waste. Materials. 2024 Apr 12;17(8):1781. doi: 10.3390/ma17081781

Author

Ogden, Mark ; Bingham, Paul ; Scrimshire, Alex et al. / Benchtop Zone Refinement of Simulated Future Spent Nuclear Fuel Pyroprocessing Waste. In: Materials. 2024 ; Vol. 17, No. 8. pp. 1781.

RIS

TY - JOUR

T1 - Benchtop Zone Refinement of Simulated Future Spent Nuclear Fuel Pyroprocessing Waste

AU - Ogden, Mark

AU - Bingham, Paul

AU - Scrimshire, Alex

AU - Backhouse, Daniel

AU - Wei, Deng

AU - Sharrad, Clint

AU - Mann, Colleen

AU - Harrison, Mike

AU - McKendrick, Donna

PY - 2024/4/12

Y1 - 2024/4/12

N2 - The UK’s adoption of pyroprocessing of spent nuclear fuel as an alternative to the current aqueous processing routes requires a robust scientific underpinning of all relevant processes. One key process is the clean-up of the contaminated salt from the electroreducing and electrorefining processes. A proposed method for this clean-up is zone refining, whereby the tendency of the contaminants to remain in the liquid phase during melting and freezing is exploited to ‘sweep’ the contaminants to one end of the sample. Experiments were performed, utilising off-the-shelf laboratory equipment, to demonstrate the feasibility of zone refining for clean-up of electroreducing and electrorefining wastes. This was successful for the electrorefining simulant samples, with effective segregation coefficient, keff, values, which provide a measure of the degree of separation in the sample, between 0 and 1. Lower values indicate greater separation, with values of as low as 0.542 achieved here, corresponding to a reduction in RECl3 content from 10.0 wt.% to 8.4 wt.% (for 80% salt reuse). Due to difficulties in obtaining a fully homogeneous electroreducing simulant waste, it was not possible to demonstrate the feasibility of zone refining using the current experimental setup. Further research is required to elucidate the correct preparation conditions for production of homogeneous electroreducing waste simulants.

AB - The UK’s adoption of pyroprocessing of spent nuclear fuel as an alternative to the current aqueous processing routes requires a robust scientific underpinning of all relevant processes. One key process is the clean-up of the contaminated salt from the electroreducing and electrorefining processes. A proposed method for this clean-up is zone refining, whereby the tendency of the contaminants to remain in the liquid phase during melting and freezing is exploited to ‘sweep’ the contaminants to one end of the sample. Experiments were performed, utilising off-the-shelf laboratory equipment, to demonstrate the feasibility of zone refining for clean-up of electroreducing and electrorefining wastes. This was successful for the electrorefining simulant samples, with effective segregation coefficient, keff, values, which provide a measure of the degree of separation in the sample, between 0 and 1. Lower values indicate greater separation, with values of as low as 0.542 achieved here, corresponding to a reduction in RECl3 content from 10.0 wt.% to 8.4 wt.% (for 80% salt reuse). Due to difficulties in obtaining a fully homogeneous electroreducing simulant waste, it was not possible to demonstrate the feasibility of zone refining using the current experimental setup. Further research is required to elucidate the correct preparation conditions for production of homogeneous electroreducing waste simulants.

KW - pyroprocessing

KW - zone refinement

KW - chloride salts

KW - LKE

KW - nuclear fuel cycle

KW - molten salt

U2 - 10.3390/ma17081781

DO - 10.3390/ma17081781

M3 - Article

VL - 17

SP - 1781

JO - Materials

JF - Materials

SN - 1996-1944

IS - 8

ER -