PuF3, AmF3, CeF3, and NdF3 Solubility in LiF–NaF–KF Melt

Lizin, A. A.; Tomilin, S. V.; Gnevashov, O. E.; Газизов, Р. К.; Осипенко, А. Г.; Kormilitsyn, M. V.; Баранов, А. А.; Zaharova, L. V.; Naumov, V. S.; Ponomarev, L. I.

doi:10.1007/s10512-013-9740-9

Cited by 36 publications

(9 citation statements)

References 4 publications

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“…However, it has very high solubility of actinides. For the composition 46.5% LiF, 11.5% NaF, and 42% KF, the solubility limits for ThF 4 , UF 4 , PuF 3 , and AmF 3 are as high as 37.5%, 45%, 30%, and 43%, respectively 42,43 …”

Section: Tmsr Transmutation Core Designmentioning

confidence: 99%

Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors

Zou

et al. 2021

Int J Energy Res

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Summary Transmutation of minor actinides (MAs) is an effective solution to reduce the long‐term radiotoxicity of nuclear waste. Online refueling and no fuel rod fabrication in thorium‐based molten salt reactors (TMSR) are two remarkable advantages of MA transmutation. However, MA solubility limit of the fuel salt and the neutron spectrum in the core are two key parameters that have a strong impact on MA transmutation capability. In this paper, three types of carrier salt with different MA solubility limits and various salt volume fractions (SVFs) are introduced in a TMSR core to evaluate the MA transmutation characteristics. The results indicate that the Flibe salt with the best neutron economy can obtain the highest MA transmutation rate (TR), while the Flinak salt with the largest MA inventory can achieve the highest specific MA transmutation consumption (STC). STC and TR for the case with the Flibe salt and 5% SVF are about 200 kg/GWth.yr and 82%, respectively, which indicates that it can consume the annual MA yields from about 3.37 typical pressurized water reactors (PWRs). Meanwhile, the STC and TR for the case with the Flinak salt and 40% SVF are about 366 kg/GWth.yr and 75%, respectively, which indicates that it can consume the annual MA yields from about 50 typical PWRs. In addition, the total radiotoxicity of MAs after 50‐year operation in TMSR can be lowered by as high as about 50%. The significant production of Pu isotopes can be reused as nuclear fuel in fast reactors. In particular, Pu‐238, with the mass fraction of more than 60% in Pu isotopes, is a useful material for many nuclear applications. In conclusion, it is feasible to transmute MAs in TMSR and thus achieve the goals of reduction of MA's long‐term radioactive hazards.

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Section: Tmsr Transmutation Core Designmentioning

confidence: 99%

Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors

Zou

et al. 2021

Int J Energy Res

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“…The measurements were performed in the range of high concentrations of REM fluoride; nevertheless, the interval between measurement points was large enough. As a result, the data obtained by different researchers often do not coincide [14,18].…”

Section: Introductionmentioning

confidence: 98%

“…However, the solubility values of most actinide fluorides in molten FLiNaK are not known. It should be noted that an experiment related to the actinide fluorides' solubility in molten salt requires quite complex equipment, duration time and material costs [14]. Studies of actinide analogues-lanthanides, which are similar in physicochemical, thermodynamic, and crystallographic properties-are much more efficient to carry out.…”

Section: Introductionmentioning

confidence: 99%

“…Studies of actinide analogues-lanthanides, which are similar in physicochemical, thermodynamic, and crystallographic properties-are much more efficient to carry out. It is known [14,15] that CeF 3 and NdF 3 are analogues of PuF 3 and AmF 3 , and UF 4 can serve as a simulator of NpF 4 .…”

Section: Introductionmentioning

confidence: 99%

“…The solubility of rare earth fluorides in the molten eutectic FLiNaK was investigated by several researchers [14,[16][17][18]. Usually, studies were carried out by isothermal saturation using complex design cells and various ways of data acquisition (including visual).…”

Section: Introductionmentioning

confidence: 99%

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Investigation of the Quasi-Binary Phase Diagram FLiNaK-NdF3

et al. 2021

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The NdF3 solubility in molten eutectic FLiNaK, which is a conceivable medium for a molten salt reactor (MSR), was determined by the quasi-binary phase diagram FLiNaK-NdF3. The eutectic mixture FLiNaK was prepared by direct melting of components LiF, NaF and KF·HF. The acidic anhydrous salt (KF·HF) was used instead of the hygroscopic KF. The NdF3 was sintered by hydrofluorination of Nd2O3. The oxygen impurity in the prepared eutectic FLiNaK, determined by an oxygen analyzer LECO OH836, was 0.036 wt.%, whereas the NdF3 contained 0.04 wt.% of oxygen. A part of the FLiNaK-NdF3 quasi-binary phase diagram was obtained using two thermal analysis techniques: differential thermal analysis (DTA) and differential scanning calorimetry (DSC). The FLiNaK-NdF3 phase diagram in the region of 0–30 mol.% NdF3 contains one eutectic at 2 mol.% NdF3 and 450 °C and two peritectic points: 8 mol.% NdF3 at 500 °C and 22 mol.% NdF3 at 575 °C. The region of the FLiNaK-NdF3 phase diagram below the liquidus line is rather complicated due to the complex structure of the multicomponent system in its molten state, as in its solid state. The NdF3 solubility in FLiNaK is about 5 mol.% at 490 °C and 29 mol.% at 700 °C; this means that the process of the MA transmutation in the MSR can be carried out in molten FLiNaK with a content of actinides as high as 15–20 mol.% in the temperature range of 550–650 °C.

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Minor Actinides Transmutation in Thermal, Epithermal and Fast Molten Salt Reactors with Very Deep Burnup

Zou

Zhou

et al. 2023

Springer Proceedings in Physics

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Deep burnup and high minor actinides (MA) loading are two alluring features for molten salt reactors (MSR) to incinerate the nuclear wastes. The transmutation capability of minor actinides in MSR is tightly related with the neutron spectrum, the loading of MA and the carrier salt compositions. In this work, three MSR core designs (thermal, epithermal and fast) and two types of salt compositions (Flibe and Flinak) with different solubility limits of transuranic elements are chosen for analyzing the transmutation capability of MA. With a significant mole fraction of MA loading (4% in the Flibe salt and 10% in the Flinak salt) and the continuous MA refueling, MSR acquires an excellent transmutation rate. The specific incineration rates of MA in the thermal, epithermal and fast MSR cores with the Flibe salt are about 167, 185 and 206 kg/GWth/y, respectively. With a larger loading of MA in the Flinak salt, a higher annual incineration rate of MA can be obtained, which are about 170, 206 and 247 kg/GWth/y in thermal, epithermal and fast MSRs, respectively. On the other hand, since there is a preferred neutron economy for the Flibe salt, a higher MA incineration ratio is achieved than that for the Flinak salt. When the neutron spectrum varies from the thermal to fast region, the MA incineration ratio ranges from 0.79 to 0.82 for the Flibe salt and it ranges from 0.75 to 0.81 for the Flinak salt. The transmutation capability of MA in MSR is much higher than that in solid-fueled reactors (~20 kg/GW.y in a PWR), which can provide a feasible way for reducing the current nuclear wastes.

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PuF3, AmF3, CeF3, and NdF3 Solubility in LiF–NaF–KF Melt

Cited by 36 publications

References 4 publications

Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors

Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors

Investigation of the Quasi-Binary Phase Diagram FLiNaK-NdF3

Minor Actinides Transmutation in Thermal, Epithermal and Fast Molten Salt Reactors with Very Deep Burnup

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