2013
DOI: 10.1007/978-1-4471-5589-8_6
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Fabrication Technologies for ThO2-based Fuel

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Cited by 5 publications
(4 citation statements)
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“…This work presents the first single-crystal structure of Pu-(C 2 O 4 ) 2 • 6 H 2 O, which is widely used for the precipitation of Pu in the PUREX process, as well as in other fundamental Pu chemistry. The first Th(C 2 O 4 ) 2 • 6 H 2 O crystal structure, another vital compound in the Th fuel cycle, [38] is also reported. The previously reported Np(C 2 O 4 ) 2 • 6 H 2 O and U(C 2 O 4 ) 2 • 6 H 2 O compounds were synthesized and characterized to better compare the An(C 2 O 4 ) 2 • 6 H 2 O series and attempt to resolve discrepancies with the previous work.…”
Section: Discussionmentioning
confidence: 95%
“…This work presents the first single-crystal structure of Pu-(C 2 O 4 ) 2 • 6 H 2 O, which is widely used for the precipitation of Pu in the PUREX process, as well as in other fundamental Pu chemistry. The first Th(C 2 O 4 ) 2 • 6 H 2 O crystal structure, another vital compound in the Th fuel cycle, [38] is also reported. The previously reported Np(C 2 O 4 ) 2 • 6 H 2 O and U(C 2 O 4 ) 2 • 6 H 2 O compounds were synthesized and characterized to better compare the An(C 2 O 4 ) 2 • 6 H 2 O series and attempt to resolve discrepancies with the previous work.…”
Section: Discussionmentioning
confidence: 95%
“…This work presents the first single crystal structure of Pu(C2O4)2•6H2O, which is widely used for the precipitation of Pu in the PUREX process, as well as in other fundamental Pu chemistry. The first Th(C2O4)2•6H2O crystal structure, another vital compound in the Th fuel cycle, 38 is also reported. The previously reported Np(C2O4)2•6H2O and U(C2O4)2•6H2O compounds were synthesized and characterized to better compare the An(C2O4)2•6H2O series and attempt to resolve discrepancies with the previous work.…”
Section: Discussionmentioning
confidence: 95%
“…UO 2 (Et-Tol-BPymDA)(NO 3 )•UO 2 (NO 3 ) 3 (4). A solution of Et-Tol-BPymDA (12 mg, 0.025 mmol) in 2 mL of dichloromethane was mixed with a solution of UO 2 (NO 3 ) 2 •6H 2 O (13 mg, 0.025 mmol) in 2 mL of ethanol.…”
Section: ■ Experimental Sectionmentioning
confidence: 99%
“…Facing the ever-growing low-carbon energy demand and ensuring energy security, thorium-based molten salt reactors (TMSRs) for the Gen-IV nuclear reactor system have attracted escalating attention in recent years. , Compared to the well-known uranium-plutonium fuel cycle, the thorium-uranium fuel cycle offers several potential merits, such as high actinide burnup, less long-lived minor actinide production, intrinsic nuclear proliferation resistance, and so forth. , Thorium in the earth’s crust is 3–4 times more abundant than uranium (the worldwide thorium resources amount to 6.35–6.37 million tonnes) and naturally exists in a monoisotopic form of 232 Th, and thus the use of thorium could greatly reduce energy-intensive enrichment activities and mining operations. As the counterpart of 239 Pu in the uranium-plutonium fuel cycle, the fissile nucleus 233 U could be produced via neutron capture on the fertile material 232 Th in breeder reactors , and then separated and recovered during the reprocessing of irradiated thorium for ultimate use as a fuel.…”
Section: Introductionmentioning
confidence: 99%