WO2024238826 - METHODS AND SYSTEMS OF PARTITIONING, TRANSMUTING, AND RECYCLING USED NUCLEAR FUEL
National phase entry is expected:
Publication Number
WO/2024/238826
Publication Date
21.11.2024
International Application No.
PCT/US2024/029747
International Filing Date
16.05.2024
Title **
[English]
METHODS AND SYSTEMS OF PARTITIONING, TRANSMUTING, AND RECYCLING USED NUCLEAR FUEL
[French]
PROCÉDÉS ET SYSTÈMES DE PARTITIONNEMENT, DE TRANSMUTATION ET DE RECYCLAGE DE COMBUSTIBLE NUCLÉAIRE USAGÉ
Applicants **
SHINE TECHNOLOGIES, LLC
3400 Innovation Ct.
Janesville, WI 53546, US
RADEL, Ross
c/o Shine Technologies, LLC
3400 Innovation Ct.
Janesville, WI 53546, US
VAN ABEL, Eric
c/o Shine Technologies, LLC
3400 Innovation Ct.
Janesville, WI 53546, US
PIEFER, Greg
c/o Shine Technologies, LLC
3400 Innovation Ct.
Janesville, WI 53546, US
KARSLYAN, Yana
c/o Shine Technologies, LLC
3400 Innovation Ct.
Janesville, WI 53546, US
Inventors
RADEL, Ross
c/o Shine Technologies, LLC
3400 Innovation Ct.
Janesville, WI 53546, US
VAN ABEL, Eric
c/o Shine Technologies, LLC
3400 Innovation Ct.
Janesville, WI 53546, US
PIEFER, Greg
c/o Shine Technologies, LLC
3400 Innovation Ct.
Janesville, WI 53546, US
KARSLYAN, Yana
c/o Shine Technologies, LLC
3400 Innovation Ct.
Janesville, WI 53546, US
Priority Data
63/466,939
16.05.2023
US
Application details
| Total Number of Claims/PCT | * |
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International Searching Authority |
USPTO
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| Applicant's Legal Status |
Legal Entity
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| Entry into National Phase under |
Chapter I
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| Translation |
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Quotation for National Phase entry
| Country | Stages | Total | |
|---|---|---|---|
| China | Filing | 2454 | |
| EPO | Filing, Examination | 26526 | |
| Japan | Filing | 532 | |
| South Korea | Filing | 575 | |
| USA | Filing, Examination | 10205 |
Total: 40292 USD
Abstract[English]
A method of processing used nuclear fuel that includes voloxidizing used nuclear fuel pellets to form a used nuclear fuel powder dissolving the used nuclear fuel powder in a dissolution acid to form a main process stream extracting uranium (U), plutonium (Pu), neptunium (Np), and technetium (Tc) from the main process stream to form a first extraction stream, partitioning the first extraction stream into a U/Pu/Np stream and a U/Tc stream; partitioning the U/Pu/Np stream into Np and a U/Pu combination, partitioning one or more minor actinides and one or more lanthanides from the main process stream to form a second extraction stream, partitioning the one more minor actinides from the one or more lanthanides in the second extraction stream; and partitioning one or more noble metals from the main process stream.[French]
Procédé de traitement de combustible nucléaire usagé comprenant la voloxidation de pastilles de combustible nucléaire usagées pour former une poudre de combustible nucléaire usagée, la dissolution de la poudre de combustible nucléaire usagée dans un acide de dissolution pour former un flux de traitement principal, l'extraction de l'uranium (U), du plutonium (Pu), du neptunium (Np) et du technétium (Tc) à partir du flux de traitement principal pour former un premier flux d'extraction, le partitionnement du premier flux d'extraction en un flux U/Pu/Np et un flux U/Tc ; le partitionnement du flux U/Pu/Np en Np et une combinaison U/Pu, le partitionnement d'un ou plusieurs actinides mineurs et d'un ou plusieurs lanthanides à partir du flux de traitement principal pour former un second flux d'extraction, le partitionnement du ou des actinides mineurs à partir du ou des lanthanides dans le second flux d'extraction ; et le partitionnement d'un ou plusieurs métaux nobles du flux de traitement principal.