2013
DOI: 10.1007/s10512-013-9742-7
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UF4, ThF4 Solubility in LiF–NaF–KF Melt

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Cited by 22 publications
(17 citation statements)
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“…In addition to the predicted solubility data from thermodynamic calculations [2], recently actualized high solubility data of various fluorides of actinides and lanthanides specifically in the LiF-NaF-KF eutectic mixture (traditionally named as FLiNaK) [3][4][5][6] reportedly could allow utilizing the high enough energy neutrons for the U-Pu breeding cycle aided by a high heavy element inventory (2.8 t/m 3 ) and a small neutron moderating capability [7].…”
Section: Introductionmentioning
confidence: 99%
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“…In addition to the predicted solubility data from thermodynamic calculations [2], recently actualized high solubility data of various fluorides of actinides and lanthanides specifically in the LiF-NaF-KF eutectic mixture (traditionally named as FLiNaK) [3][4][5][6] reportedly could allow utilizing the high enough energy neutrons for the U-Pu breeding cycle aided by a high heavy element inventory (2.8 t/m 3 ) and a small neutron moderating capability [7].…”
Section: Introductionmentioning
confidence: 99%
“…The author and associates have successfully performed a follow-up calculation not only for FLiNaK but also NaF-KF-UF 4 system as a matrix of the fuel salt [8,9]. Their efforts have borne a fruit as a nuclear reactor plant using a mixture of NaF-KF-UF 4 fertile and NaF-KF-TRUF 3 fissile as the fuel salt incorporated with designated online chemical processes based upon the oxide selective precipitation process with extremely low heavy element released to the environment which was nominated as the fast-spectrum fluoride molten salt reactor (FFMSR) [10][11][12].…”
Section: Introductionmentioning
confidence: 99%
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