ORNL Experience and Perspectives Related to Processing of Thorium and <sup>233</sup>U for Nuclear Fuel

Croff, A.G.; Collins, E.D.; Cul, G. D. Del; Wymer, R.G.; Krichinsky, Alan M; Spencer, Barry B.; Patton, Bradley D

doi:10.13182/nt15-59

Cited by 7 publications

(7 citation statements)

References 18 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Table 3 Mass distributions of actinides and fission products through RUN-1 to RUN-3. Data in % represent the amount of the element divided by its initial amount in the fuel segments before RUN-1 to RUN-3 calculated by the ORIGEN code [22]. Before the irradiation, the gap between the fuel rod and the cladding was filled with a Na bond, in the present case a gap volume was 0.278 cm 3 .…”

Section: Actinidesmentioning

confidence: 96%

See 1 more Smart Citation

Anodic dissolution of irradiated metallic fuels in LiCl–KCl melt

Murakami

Kato

Rodrigues³

et al. 2014

Journal of Nuclear Materials

View full text Add to dashboard Cite

Section: Actinidesmentioning

confidence: 96%

“…The length and weight of each segment are summarized in Table 1. ORIGEN code [22] was used to calculate the initial amounts of elements in the fuel segments before electrorefining in the present study.…”

Section: Irradiated Metallic Fuel (Metaphix-1)mentioning

confidence: 99%

Anodic dissolution of irradiated metallic fuels in LiCl–KCl melt

Murakami

Kato

Rodrigues³

et al. 2014

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…Once the fuel kernels are exposed, methods of extracting the fissile materials include traditional aqueous digestion, supercritical CO 2 solvent extraction (as the carrier for an appropriate extractant), and molten salt dissolution. [628][629][630][631][632][633][634][635][636][637][638]…”

Section: Processes Applied To Triso-type Fuelsmentioning

confidence: 99%

Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective

Fredrickson

Yoo

2021

View full text Add to dashboard Cite

Reprocessing and/or waste management issues are of concern to the "back end" of the nuclear fuel cycle. Of course, there are a great many "nuclear fuel cycle" scenarios to consider; if not in practice, then at least in theory. The simplest conceptually is the "once through" fuel cycle in which the spent fuel is discarded. The more complex fuel cycle scenarios involve reprocessing spent nuclear fuels and a family of nuclear reactor technologies to accommodate burning and breeding for various military and commercial needs. Therefore, the selection of a specific "fuel cycle" is what ultimately imposes the engineering requirements of the reprocessing and waste management technologies. No one part is independent of the other parts in a fuel cycle flowsheet; all parts should be fully integrated. This paper presents a summary of nuclear chemistry processes, nuclear reactor technologies, associated nuclear fuel types, and the reprocessing technologies that serve the different nuclear fuel types. Comprehending how this series of topics are related to each other is a prerequisite to understanding the requirements of any reprocessing strategy. The summary materials presented here are selective, as opposed to comprehensive. More detailed information on any one subject can be found in the reference materials.

show abstract

“…Unlike uranium, natural thorium lacks a fissile isotope and its consideration as nuclear fuel relates to the potential to breed fissile 233 U in thermal and epithermal spectra. In theory, closed Th-233 U fuel cycles are possible, but contamination with 232 U and its fission products (primarily 208 Tl) requires shielding and remote handling [3]. The technological challenges and the costs related to such a closed fuel cycle are huge.…”

Section: Introductionmentioning

confidence: 99%