Tritium Research and Development Status at KAERI

Kim, Ji-Soo; Park, S.; Kang, Hyun Suk; Jung, Ki Jung; Kim, K. Y.; Yim, Sung Paal; Kim, S. B.; Ahn, Hong Joo; Park, C. W.; Lee, S. N.; Chang, Min-Sun; Chung, Hongsuk

doi:10.1080/15361055.2019.1705750

Cited by 6 publications

(2 citation statements)

References 6 publications

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“…However, advanced technologies for tritium capture are being investigated for several applications other than UNF processing. These lower TRL capture technologies are being investigated for a variety of applications from fusion to the operation of heavy-water and molten-salt reactors (Forsberg et al 2017;Kim et al 2020). Some uncertainties remain, depending on the off-gas stream and other gas constituents.…”

Section: Tritium Capture and Waste Formsmentioning

confidence: 99%

Technology Development Roadmap for Volatile Radionuclide Capture and Immobilization

Soelberg,

Jubin,

Strachan

et al. 2023

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An "Off-Gas and Waste Forms Strategy Workshop" was held in Washington, D.C. on January 31, and February 1, 2023, to review the current state of the art (baseline) technologies for capturing and immobilizing these volatile radionuclides in waste forms (WFs). The discussions in that workshop were used to develop a roadmap for future research and development to mature technologies that are presently not ready for use in a commercial reprocessing facility and develop and demonstrate technologies that provide more safety, more simplicity, or lower costs compared to the current baseline. Technology Development Roadmap for Volatile Radionuclide Capture and Immobilization iv October 2023demonstration of viable WFs and advancing the TRL through large-scale demonstrations and testing under high-fidelity conditions.Long term R&D (out to 25-100 years) should continue on less mature or even currently unknown technologies to lower the costs and risks of UNF reprocessing. Some workshop participants suggested multiradionuclide sorbents and WFs. These are currently not technically possible considering the differences in the chemical, physical, and radiological properties of the four volatile radionuclides.

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Section: Tritium Capture and Waste Formsmentioning

confidence: 99%

Technology Development Roadmap for Volatile Radionuclide Capture and Immobilization

Soelberg,

Jubin,

Strachan

et al. 2023

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“…Gaseous tritium (T) is an important fusion raw material in fusion reactors, and is often saved in metallic uranium, which possesses good properties of charging and releasing T [1][2][3][4]. However, uranium has many defects as well, such as spontaneous combustion after the storage of T, being radioactive, and being easy to pulverize.…”

Section: Introductionmentioning

confidence: 99%

Influence of Alloy Atoms on Substitution Properties of Hydrogen by Helium in ZrCoH3

et al. 2021

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Intermetallic alloy ZrCo is a good material for storing tritium (T). However, ZrCo is prone to disproportionation reactions during the process of charging and discharging T. Alloying atoms are often added in ZrCo, occupying the Zr or Co site, in order to restrain disproportionation reactions. Meanwhile, T often decays into helium (He), and the purity of T seriously decreases once He escapes from ZrCo. Therefore, it is necessary to understand the influence of alloying atoms on the basic stability property of He. In this work, we perform systematical ab initio calculations to study the stability property of He in ZrCoH3 (ZrCo adsorbs the H isotope, forming ZrCoH3). The results suggest that the He atom will undergo displacements of 0.31 and 0.12 Å when it substitutes for Co and Zr, respectively. In contrast, the displacements are very large, at 0.67–1.09 Å, for He replacing H. Then, we introduce more than 20 alloying atoms in ZrCo to replace Co and Zr in order to examine the influence of alloying atoms on the stability of He at H sites. It is found that Ti, V, Cr, Mn, Fe, Zn, Nb, Mo, Tc, Ru, Ta, W, Re, and Os replacing Co can increase the substitution energy of H by the He closest to the alloying atom, whereas only Cr, Mn, Fe, Mo, Tc, Ru, Ta, W, Re, and Os replacing Co can increase the substitution energy of H by the He next closest to the alloying atom. The influence of the alloying atom substituting Zr site on the substitution energies is inconspicuous, and only Nb, Mo, Ru, Ta, and W increase the substitution energies of H by the He closest to the alloying atom. The increase in the substitution energy may suggest that these alloy atoms are conducive to fix the He atom in ZrCo and avoid the reduction in tritium purity.

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Superwetting metal-organic frameworks optimized interface for high-performance hydrogen-water isotopic exchange for tritiated water treatment

Ding

Hou

et al. 2023

International Journal of Hydrogen Energy

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Tritium Research and Development Status at KAERI

Cited by 6 publications

References 6 publications

Technology Development Roadmap for Volatile Radionuclide Capture and Immobilization

Technology Development Roadmap for Volatile Radionuclide Capture and Immobilization

Influence of Alloy Atoms on Substitution Properties of Hydrogen by Helium in ZrCoH3

Superwetting metal-organic frameworks optimized interface for high-performance hydrogen-water isotopic exchange for tritiated water treatment

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