• Title/Summary/Keyword: Tokamak exhaust processing

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Tritium Fuel Cycle Technology of ITER Project (ITER 사업의 삼중수소 연료주기 기술)

  • Yun, Sei-Hun;Chang, Min-Ho;Kang, Hyun-Goo;Kim, Chang-Shuk;Cho, Seung-Yon;Jung, Ki-Jung;Chung, Hong-Suk;Song, Kyu-Min
    • Transactions of the Korean hydrogen and new energy society
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    • v.23 no.1
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    • pp.56-64
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    • 2012
  • The ITER fuel cycle is designed for DT operation in equimolar ratio. It involves not only a group of fuelling system and torus cryo-pumping system of the exhaust gases through the divertor from the torus in tokamak plant, but also from the exhaust gas processing of the fusion effluent gas mixture connected to the hydrogen isotope separation in cryogenic distillation to the final safe storage & delivery of the hydrogen isotopes in tritium plant. Tritium plant system supplies deuterium and tritium from external sources and treats all tritiated fluids in ITER operation. Every operation and affairs is focused on the tritium inventory accountancy and the confinement. This paper describes the major fuel cycle processes and interfaces in the tritium plant in aspects of upcoming technologies for future hydrogen and/or hydrogen isotope utilization.

Storage and Delivery of Hydrogen Isotopes (삼중수소 저장기술)

  • Chung, Hong-Suk;Chung, Dong-You;Koo, Dae-Seo;Lee, Ji-Sung;Shim, Myung-Hwa;Cho, Seung-Yon;Jung, Ki-Jung;Yun, Sei-Hun
    • Transactions of the Korean hydrogen and new energy society
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    • v.22 no.3
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    • pp.372-379
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    • 2011
  • A nuclear fusion fuel cycle plant is composed of various subsystems such as a hydrogen isotope storage and delivery system, a tokamak exhaust processing system, and a hydrogen isotope separation system. Korea shares in the construction of its ITER fuel cycle plant with the EU, Japan, and the US, and is responsible for the development and supply of the storage and delivery system. The authors thus present details on the development status of hydrogen isotope storage technologies for nuclear fusion fuel cycle plants. We have developed various hydride beds of different size. We have realized a hydrogen delivery rate of 12.5 $Pam^3/s$ with a typical 1242g-ZrCo bed.

Rapid Cooling Performance Evaluation of a ZrCo bed for a Hydrogen Isotope Storage (수소동위원소 저장용 ZrCo용기의 급속 냉각 성능 평가)

  • Lee, Jungmin;Park, Jongchul;Koo, Daeseo;Chung, Dongyou;Yun, Sei-Hun;paek, Seungwoo;Chung, Hongsuk
    • Transactions of the Korean hydrogen and new energy society
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    • v.24 no.2
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    • pp.128-135
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    • 2013
  • The nuclear fuel cycle plant is composed of various subsystems such as a fuel storage and delivery system (SDS), a tokamak exhaust processing system, a hydrogen isotope separation system, and a tritium plant analytical system. Korea is sharing in the construction of the International Thermonuclear Experimental Reactor (ITER) fuel cycle plant with the EU, Japan, and the US, and is responsible for the development and supply of the SDS. Hydrogen isotopes are the main fuel for nuclear fusion reactors. Metal hydrides offer a safe and convenient method for hydrogen isotope storage. The storage of hydrogen isotopes is carried out by absorption and desorption in a metal hydride bed. These reactions require heat removal and supply respectively. Accordingly, the rapid storage and delivery of hydrogen isotopes are enabled by a rapid cooling and heating of the metal hydride bed. In this study, we designed and manufactured a vertical-type hydrogen isotope storage bed, which is used to enhance the cooling performance. We present the experimental details of the cooling performances of the bed using various cooling parameters. We also present the modeling results to estimate the heat transport phenomena. We compared the cooling performance of the bed by testing different cooling modes, such as an isolation mode, a natural convection mode, and an outer jacket helium circulation mode. We found that helium circulation mode is the most effective which was confirmed in our model calculations. Thus we can expect a more efficient bed design by employing a forced helium circulation method for new beds.

Safety Analysis of a Hydrogen Isotopes Process (수소동위원소 공정 안전해석)

  • Chung, Hong-Suk;Kang, Hyun-Goo;Chang, Min-Ho;Cho, Seung-Yon;Kim, Won-Kuk;Nam, Jae-Yeon;Kim, Duk-Jin;Song, Kyu-Min;Paek, Seung-Woo;Koo, Dae-Seo;Chung, Dong-You;Lee, Jeong-Min;Kim, Chang-Shuk;Jung, Ki-Jung;Yun, Sei-Hun
    • Transactions of the Korean hydrogen and new energy society
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    • v.23 no.3
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    • pp.219-226
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    • 2012
  • A nuclear fusion fuel cycle plant is composed of various subsystems such as a hydrogen isotope storage and delivery system, a tokamak exhaust processing system, and a hydrogen isotope separation system. Korea shares in the construction of the International Thermonuclear Experimental Reactor fuel cycle plant with the EU, Japan and US, and is responsible for the development and supply of the storage and delivery system. We thus present details on the hydrogen isotope process safety. The main safety analysis procedure is to use a hazard and operability study. Nine segments were studied how the plant might deviate from its design purpose. We present a detailed description of the process, examine every part of it to determine how deviations from the design intent can occur and decide whether these deviations can give rise to hazards. We determine possible causes and note protective systems, evaluate the consequences of the deviation, and recommend actions to achieve our safety goal.

Tritium Fuel Cycle of the International Thermonuclear Experimental Reactor (국제핵융합실험로 삼중수소 연료주기)

  • Song, Kyu-Min;Sohn, Soon Hwan;Chung, Hongsuk;Yun, Sei-Hun;Jung, Ki Jung
    • Korean Chemical Engineering Research
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    • v.50 no.4
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    • pp.595-603
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    • 2012
  • International Thermonuclear Experimental Reactor (ITER) will be constructed in 2019 according to the JIA (Joint Implementation Agreement) of 7 countries. The ITER fusion fuel cycle consists of fusion vacuum vessel, tritium plant and fuelling system. The tritium plant provides the functions of storage, delivery, separation, removal and recovery of the deuterium and tritium used as fusion fuels for the ITER. The tritium plant systems supply deuterium and tritium from external sources and treat all tritiated fluids from ITER operation through Storage and Delivery System (SDS), Tokamak Exhaust Processing (TEP), Isotope Separation System (ISS), Water Detritiation System & Atmosphere Detritiation System (WDS & ADS) and Analysis System (ANS). In this paper, the functions and design requirements of the major systems in the tritium plant and the status of R&D are described. Korean party is developing the SDS for ITER tritium plant and partially attaining the WDS technology through the construction and operation experience of the Wolsong Tritium Removal Facility (WTRF). Now it is expected that researchers in other fields such as chemical engineering take part in the development of upcoming technologies for ISS and TEP.