Joint solubility of PuF3 and UF4 in a melt of lithium, sodium, and potassium fluorides

Lizin, A. A.; Tomilin, S. V.; Naumov, V. S.; Ignat’ev, V. V.; Nezgovorov, N. Yu.; Баранов, А. А.

doi:10.1134/s1066362215050082

Cited by 9 publications

(2 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%

“…The elaborated solubility measurements in FLiNaK by Russian scientists [3][4][5][6] should have been more appropriately respected if they had made the chemical composition of alkali fluoride matrix of liquefied samples analytically quantified instead of their customary practice in which the matrix had been always assumed as FLiNaK, even if they have found no UF 4 or PuF 3 but 2KF-UF 4 , 7KF-6UF 4 , KPu 2 F 7 , KPuF 4 , and NaPuF 4 in the solidified residue by the X-ray diffractometric analysis.…”

Section: Introductionmentioning

confidence: 99%

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Fast-Spectrum Fluoride Molten Salt Reactor (FFMSR) with Ultimately Reduced Radiotoxicity of Nuclear Wastes

Hirose¹

2021

Nuclear Power Plants - The Processes From the Cradle to the Grave

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A mixture of NaF-KF-UF 4 eutectic and NaF-KF-TRUF 3 eutectic containing heavy elements as much as 2.8 g/cc makes a fast-spectrum molten salt reactor based upon the U-Pu cycle available without a blanket. It does not object breeding but a stable operation without fissile makeup under practical contingencies. It is highly integrated with online dry chemical processes based on "selective oxide precipitation" to create a U-Pu cycle to provide as low as 0.01% leakage of TRU and nominated as the FFMSR. This certifies that the radiotoxicity of HLW for 1500 effective full power days (EFPD) operation can be equivalent to 405 tons of depleted uranium after 500 years cooling without Partition and Transmutation (P&T). A certain amount of U-TRU mixture recovered from LWR spent fuel is loaded after the initial criticality until U-Pu equilibrium but the fixed amount of 238 U only thereafter. The TRU inventory in an FFMSR stays at an equilibrium perpetually. Accumulation of spent fuel of an LWR for 55 years should afford to start up the identical thermal capacity of FFMSR and to keep operation hypothetically until running out of 238 U. Full deployment of the FFMSR should make the entire fuel cycle infrastructures needless except the HLW disposal site.Keywords: fast-spectrum fluoride molten salt reactor, high-level radioactive waste, structure of fuel salt, density of fuel salt, redox potential control, freezing behavior of fuel salt, selective oxide precipitation process, front-end processing dedicated to the MOX spent fuel, nuclear fuel cycle and associated wastes

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