2022
DOI: 10.1016/j.pnucene.2021.104082
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A comparison of actinide halides for use in molten salt reactor fuels

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Cited by 11 publications
(4 citation statements)
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“…Actinide halides ([AnX n ] q − , X = halide) have attracted the scientific community’s attention due to their use in the nuclear industry, primarily for isotope enrichment, and are among the most extensively exploited molecular units within the domain of actinide chemistry. Furthermore, actinide halides are widely used in actinide separation processes and also have significant applications in non-aqueous transuranic chemistry. , [AnO 2 Cl 2 ] and [AnCl 6 ] 2– are two dominating structural motifs identified for An­(VI) and An­(IV) chlorides, respectively. For example, [UO 2 Cl 2 ] and [PuO 2 Cl 2 ] have been characterized both in solution as well as in the solid state . Similarly, [UCl 6 ] 2– , [NpCl 6 ] 2– , and [PuCl 6 ] 2– have been isolated and explored in the literature. ,− Moreover, the octahedral ligand environment in [AnCl 6 ] 2– provides a suitable platform to examine the properties of actinides and compare them with transition metals in a similar coordination environment. ,, The presence of non-aquo inner sphere ligands limits the hydrolyzation of An­(IV) species; therefore, there is a fundamental need to understand and control their speciation, especially toward the formation of intermediates capable of undergoing olation or oxolation reactions.…”
Section: Introductionsupporting
confidence: 84%
“…Actinide halides ([AnX n ] q − , X = halide) have attracted the scientific community’s attention due to their use in the nuclear industry, primarily for isotope enrichment, and are among the most extensively exploited molecular units within the domain of actinide chemistry. Furthermore, actinide halides are widely used in actinide separation processes and also have significant applications in non-aqueous transuranic chemistry. , [AnO 2 Cl 2 ] and [AnCl 6 ] 2– are two dominating structural motifs identified for An­(VI) and An­(IV) chlorides, respectively. For example, [UO 2 Cl 2 ] and [PuO 2 Cl 2 ] have been characterized both in solution as well as in the solid state . Similarly, [UCl 6 ] 2– , [NpCl 6 ] 2– , and [PuCl 6 ] 2– have been isolated and explored in the literature. ,− Moreover, the octahedral ligand environment in [AnCl 6 ] 2– provides a suitable platform to examine the properties of actinides and compare them with transition metals in a similar coordination environment. ,, The presence of non-aquo inner sphere ligands limits the hydrolyzation of An­(IV) species; therefore, there is a fundamental need to understand and control their speciation, especially toward the formation of intermediates capable of undergoing olation or oxolation reactions.…”
Section: Introductionsupporting
confidence: 84%
“…Actinyl halide chemistry is of relevance for understanding actinide behavior in, for example, molten salt nuclear reactor systems and long-term stewardship of spent nuclear fuel. Uranyl fluoride phases are particularly important considering the roles of compounds such as uranium hexafluoride (UF 6 ), uranium tetrafluoride (UF 4 ), and uranyl fluoride (UO 2 F 2 ) as vital intermediates in the conversion, enrichment, and fuel fabrication steps within the nuclear fuel cycle. , However, in the solid state, the chemistry of uranyl halides has been dominated by chloride and bromide phases, owing largely to their ease of synthesis and the platform they provide for studying the molecular assembly and electronic structure. In brief, preparation from high-halide, low-pH aqueous media generates reproducible [UO 2 X 4 ] 2– anions (X = Cl or Br) for directed assembly with various organic cations, often assisted with noncovalent interactions (NCIs) such as halogen or hydrogen bonding. , …”
Section: Introductionmentioning
confidence: 99%
“…The first MSR by Oak Ridge National Laboratory (ORNL), named the Molten Salt Reactor Experiment (MSRE), received a positive response after operating for approximately four years [6,7]. The reactor used fluoride-fueled salt and graphite as moderators, which is considered a successful demonstration of the potential of MSR technology [8]. In 1971, ORNL developed the MSRE into a molten salt breeder reactor (MSBR).…”
Section: Introductionmentioning
confidence: 99%