Journal Article FZJ-2019-02800

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Homogenous Recycling of Transuranium Elements from Irradiated Fast Reactor Fuel by the EURO-GANEX Solvent Extraction Process

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2019
˜Deœ Gruyter Berlin

Radiochimica acta 107(9-11), 917-929 () [10.1515/ract-2018-3089]

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Abstract: The EURO-GANEX process was developed forco-separating transuranium elements from irradiatednuclear fuels. A hot flow-sheet trial was performed in acounter-current centrifugal contactor setup, using a genuinehigh active feed solution. Irradiated mixed (carbide,nitride) U80Pu20 fast reactor fuel containing 20 % Pu wasthermally treated to oxidise it to the oxide form which wasthen dissolved in HNO3. From this solution uranium wasseparated to >99.9 % in a primary solvent extraction cycleusing 1.0 mol/L DEHiBA (N,N-di(2-ethylhexyl)isobutyramidein TPH (hydrogenated tetrapropene) as the organicphase. The raffinate solution from this process, containing10 g/L Pu, was further processed in a second cycle of solventextraction. In this EURO-GANEX flow-sheet, TRU andfission product lanthanides were firstly co-extracted intoa solvent composed of 0.2 mol/L TODGA (N,N,N′,N′-tetran-octyl diglycolamide) and 0.5 mol/L DMDOHEMA (N,N′-dimethyl-N,N′-dioctyl-2-(2-hexyloxy-ethyl) malonamide)dissolved in Exxsol D80, separating them from most otherfission and corrosion products. Subsequently, the TRUwere selectively stripped from the collected loaded solventusing a solution containing 0.055 mol/L SO3-Ph-BTP(2,6-bis(5,6-di(3-sulphophenyl)-1,2,4-triazin-3-yl)pyridinetetrasodium salt) and 1 mol/L AHA (acetohydroxamicacid) in 0.5 mol/L HNO3; lanthanides were finally strippedusing 0.01 mol/L HNO3. Approximately 99.9 % of the TRUand less than 0.1 % of the lanthanides were found in theproduct solution, which also contained the major fractionsof Zr and Mo.

Classification:

Contributing Institute(s):
  1. Nukleare Entsorgung und Reaktorsicherheit (IEK-6)
Research Program(s):
  1. 161 - Nuclear Waste Management (POF3-161) (POF3-161)
  2. ACSEPT - Actinide reCycling by SEParation and Transmutation (211267) (211267)
  3. SACSESS - Safety of ACtinide Separation proceSSes (323282) (323282)
  4. GENIORS - GEN IV Integrated Oxide fuels recycling strategies (755171) (755171)

Appears in the scientific report 2019
Database coverage:
Medline ; Embargoed OpenAccess ; Clarivate Analytics Master Journal List ; Current Contents - Physical, Chemical and Earth Sciences ; IF < 5 ; JCR ; SCOPUS ; Science Citation Index ; Science Citation Index Expanded ; Web of Science Core Collection
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Institute Collections > IFN > IFN-2
Workflow collections > Public records
IEK > IEK-6
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Open Access

 Record created 2019-04-25, last modified 2024-07-12


Published on 2019-05-27. Available in OpenAccess from 2020-05-27.:
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