R&amp;D Activities on the Tritium Storage and Delivery System in Korea

Cho, S.; Chang, Min-Sun; Yun, Sei-Hun; Kang, Hee-Seok; Chung, Hongsuk; Song, Kyu‐Min; Koo, Daeseo; Chung, Dong-Yong; Jeong, Doyeon; Lee, M. K.; Lim, Jong Yeon; Kim, D. J.

doi:10.13182/fst11-a12602

Cited by 19 publications

(3 citation statements)

References 8 publications

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“…While the ITER SDS is in preliminary design phase, there have been some reports for the SDS R&D activities and progress, including tritium related research . On‐going R&D works are like the followings: 1:1 scaled SDS getter bed mock‐up test, SDS unit process feasibility verification test, tritium inventory calorimetry test, He‐3 recovery process verification, SDS modeling and so forth.…”

Section: Progress Of the Iter Projectmentioning

confidence: 99%

Fusion energy development status in Korea

et al. 2017

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SummaryThis overview discusses the status of fusion energy development in the Republic of Korea. Korea studies fusion energy through research and development in 2 ways: one by performing the Korea Superconducting Tokamak Advanced Research (KSTAR) for a domestic approach and the other by participating in the international collaboration project ITER. Korea had remarkable progresses not only in KSTAR but also in the ITER project in 2016. In KSTAR, a world record of more than 70 seconds in high-performance plasma (H-mode) operation in the superconducting tokamak has been achieved. For the ITER project, toroidal field conductors have been successfully accomplished and the other major equipment such as vacuum vessel sectors, ports, and assembly tooling seem to be reaching an end. This paper deals with current research and development results on both fields of KSTAR study and ITER project progress.

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Section: Progress Of the Iter Projectmentioning

confidence: 99%

Fusion energy development status in Korea

et al. 2017

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“…The famous fusion reactor, the International Thermonuclear Experimental Reactor (ITER), was built to research effectiveness, in the sense of technological possibility, using a deuterium–tritium plasma fusion reaction [ 1 , 2 , 3 , 4 , 5 , 6 , 7 , 8 , 9 , 10 , 11 , 12 , 13 ]. Due to the scarcity and radioactivity of tritium, and the actual operation of the fusion reactor, deuterium and tritium fuel gas must be quickly supplied to the fuel filling system in a limited time according to the operation scene of the plasma [ 14 , 15 ]. This requires an efficient and safe storage and delivery system (SDS) to ensure the smooth operation of the fusion reactor while avoiding radioactive hazards and waste of resources, and the SDS is a crucial important part of the ITER fuel cycle [ 16 , 17 , 18 ].…”

Section: Introductionmentioning

confidence: 99%

Research Progress on the Anti-Disproportionation of the ZrCo Alloy by Element Substitution

Wang

et al. 2020

Materials

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Hydrogen-induced disproportionation (HID) during the cycles of absorption and desorption leads to a serious decline in the storage capacity of the ZrCo alloy, which has been recognized as the biggest obstacle to its application. Therefore, the prerequisite of a ZrCo application is to solve its anti-disproportionation problem in the field of rapid hydrogen isotope storage. Beyond surface modification and nanoball milling, this work systematically reviews the method of element substitution, which can obviously improve the anti-disproportionation. From a micro angle, as hydrogen atoms that occupy the 8e site in the ZrCoH3 lattice are instable and are considered to be the driving force of disproportionation, researchers believe that element substitution by changing the occupation of hydrogen atoms at the 8e site can improve the anti-disproportionation of the alloy. At present, Ti/Nb substitutions for the Zr terminal among substitute elements have an excellent anti-disproportionation performance. In this work, up-to-date research studies on anti-disproportionation and its disproportionation mechanism of the ZrCo alloy are introduced by combining experiments and simulations. Moreover, the optimization of the alloy based on the occupation mechanism of 8e sites is expected to improve the anti-disproportionation of the ZrCo alloy.

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“…The development of tritium storage material, which replaces the existing radioactive uranium, is of great interest in Fast Breeder Reactors (FBR) and Thermonuclear Experimental Reactor-Supply and Delivery Systems (ITER-SDS) [8][9][10][11][12][13][14][15]. In FBRs, a cold trap mesh is used to trap hydrogen isotope H, D, and T present in the sodium loop.…”

Section: Introduction *mentioning

confidence: 99%

Synthesis of Hydrogen Getter Zr1-xCox (x=0-1) Alloy Films by Magnetron Co-Sputtering

Dhonge

Singh

Panda

et al. 2020

J. Coat. Sci. Technol.

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The Zr1-xCox(x=0, 0.25, 0.53, 0.63, 1) thin films were deposited on quartz substrate using magnetron co-sputtering of Zirconium and Cobalt targets in confocal geometry. A constant pulsed direct current (PDC) on Zirconium and radio frequency (RF) of various powers on Cobalt target were applied to vary the concentration of Co in the Zr1-xCox film. The film composition was quantified using EDX measurements. The hydrogen storage capacity of these films was studied using an in-house developed hydrogen adsorption setup, in which the electrical resistivity of the film was monitored as a function of hydrogen partial pressure and temperature. The films' surface morphology and crystal structure before and after hydrogenation were characterized using atomic force microscopy and grazing incidence X-ray diffraction techniques using synchrotron radiation, respectively. An increase in the particle size after hydrogenation was observed for all the films. An increase in resistivity was also observed due to the absorption of hydrogen in all the compositions. The near stoichiometric film Zr0.47Co0.53 showed the highest hydrogen absorption level at 200 o C at all partial pressures. However, a decrease in the response at temperatures higher than 200 o C was observed in the film containing a Co concentration. The mechanism for the increase in resistivity of the film on hydrogenation is explained.

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R&D Activities on the Tritium Storage and Delivery System in Korea

Cited by 19 publications

References 8 publications

Fusion energy development status in Korea

Fusion energy development status in Korea

Research Progress on the Anti-Disproportionation of the ZrCo Alloy by Element Substitution

Synthesis of Hydrogen Getter Zr1-xCox (x=0-1) Alloy Films by Magnetron Co-Sputtering

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