Modeling and analysis of a molten-salt electrolytic process for nuclear waste treatment

Kim, K. R.; Bae, Jong Myon; Park, B. G.; Ahn, Do-Hee; Paek, Seungwoo; Kwon, Sung Youn; Shim, Joon-Bo; Kim, S. H.; Lee, H. S.; Kim, E. H.; Hwang, Il Soon

doi:10.1007/s10967-009-0534-4

Cited by 12 publications

(9 citation statements)

References 2 publications

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“…Thus, it is critical to find materials that are resistant to neutron radiation at elevated temperatures. There have been a large number of other experiments on irradiated ODS [7,8,9,10,11,13,14,15,16] balance of experimental evidence suggests that ODS steels exhibit a lower level of swelling and creep than equivalent steels without ODS dispersoids. For example, a strong candidate material for the inner wall of a fusion reactor is the EUROFER97 ferritic/martensitic steel, a chromium-rich iron alloy.…”

Section: Introductionmentioning

confidence: 99%

Mechanism for radiation damage resistance in yttrium oxide dispersion strengthened steels

Brodrick

Hepburn

Ackland

2014

Journal of Nuclear Materials

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ODS steels based on yttrium oxide have been suggested as potential fusion reactor wall materials due to their observed radiation resistance properties. Presumably this radiation resistance can be related to the interaction of the particle with vacancies, self-interstitial atoms (SIAs) and other radiation damage debris. Density functional theory has been used to investigate this at the atomic scale. Four distinct interfaces, some based on HRTEM observations, between iron and yttrium oxide were investigated. It is been shown that the Y 2 O 3 -Fe interface acts as a strong trap with long-range attraction for both interstitial and vacancy defects, allowing recombination without altering the interface structure. The catalytic elimination of defects without change to the microstructure explains the improved behaviour of ODS steels with respect to radiation creep and swelling.

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Section: Introductionmentioning

confidence: 99%

Mechanism for radiation damage resistance in yttrium oxide dispersion strengthened steels

Brodrick

Hepburn

Ackland

2014

Journal of Nuclear Materials

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“…This paper also describes waste forms containing a molten salt. These studies and modifications of the results have been included in other papers [101-104, 106-108, 115]; some of these papers also describe related studies on modeling and pyroprocessing of MSO waste [102,104,106,107].…”

Section: Spent Salt Processing and Encapsulationmentioning

confidence: 99%

Scientific and Engineering Literature Mini Review of Molten Salt Oxidation for Radioactive Waste Treatment and Organic Compound Gasification as well as Spent Salt Treatment

Kovařík

Navratil

John

2015

Science and Technology of Nuclear Installations

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Literature review was performed for the molten salt oxidation technology in order to collect all available scientific and engineering information for further use of this technology in nuclear applications. This report provides a summary of a review of scientific and engineering literature on MSO treatment of a wide variety of radioactive wastes, organic compound gasification, and related studies such as radioactive spent salt processing that was found important for further development of the MSO technology in the nuclear field for radioactive waste treatment. Miscellaneous nonnuclear uses of molten salts, such as converting carbon monoxide to carbon dioxide, are not discussed.

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“…In pyroprocessing, electrorefining is a cardinal step to recover depleted uranium from SNF [12]. Electrorefining is composed of three steps from material dissolution at the anode to material deposition at the cathode.…”

Section: Purpose Of Electrorefiner Modelingmentioning

confidence: 99%

“…1. Analysis tool consists of onedimensional electrochemical reaction simulation code, REFIN, and three-dimensional CFD code [12]. REFIN has been developed to solve the time-dependent simulation of molten-salt electrolysis within diffusion boundary layer for nuclear waste treatment.…”

Section: Analysis Tool and Proceduresmentioning

confidence: 99%

“…10 respectively represents neptunium current density at both the cathode side and bottom for various electrode rotational speeds. As uranium in molten salt is exhausted or cannot satisfy applied current, overpotential rises to find second reduction reaction and other species begin to deposit at the cathode surface [12]. At the low rotational speed, local neptunium deposition occurs at the edge of cathode side and bottom where materials are separated from the electrode surface.…”

Section: Multispecies Current Density Analysismentioning

confidence: 99%

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Three-dimensional multispecies current density simulation of molten-salt electrorefining

Choi

Park

Kim

et al. 2010

Journal of Alloys and Compounds

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Modeling and analysis of a molten-salt electrolytic process for nuclear waste treatment

Cited by 12 publications

References 2 publications

Mechanism for radiation damage resistance in yttrium oxide dispersion strengthened steels

Mechanism for radiation damage resistance in yttrium oxide dispersion strengthened steels

Scientific and Engineering Literature Mini Review of Molten Salt Oxidation for Radioactive Waste Treatment and Organic Compound Gasification as well as Spent Salt Treatment

Three-dimensional multispecies current density simulation of molten-salt electrorefining

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