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Title: Key technologies for tritium storage bed development

ITER Storage and Delivery System (SDS) is a complex system involving tens of storage beds. The most important SDS getter bed will be used for the absorption and desorption of hydrogen isotopes in accordance with the fusion fuel cycle scenario. In this paper the current status concerning research/development activities for the optimal approach to the final SDS design is introduced. A thermal analysis is performed and discussed on the aspect of heat losses considering whether the reflector and/or the feed-through is present or not. A thermal hydraulic simulation shows that the presence of 3 or 4 reflectors minimize the heat loss. Another important point is to introduce the real-time gas analysis in the He{sup 3} collection system. In this study 2 independent strength methods based on gas chromatography and quadruple mass spectrometer for one and on a modified self-assaying quadruple mass spectrometer for the second are applied to separate the hydrogen isotopes in helium gas. Another issue is the possibility of using depleted uranium getter material for the storage of hydrogen isotopes, especially of tritium.
Authors:
; ; ; ; ;  [1] ; ;  [2] ; ;  [3]
  1. National Fusion Research Institute, Yusung-gu, Daejeon (Korea, Republic of)
  2. Korea Atomic Energy Research Institute, Yusung-gu, Daejeon (Korea, Republic of)
  3. Korea Hydro and Nuclear Power Co, Yusung-daero, Yusung-gu, Daejeon (Korea, Republic of)
Publication Date:
OSTI Identifier:
22429794
Resource Type:
Journal Article
Resource Relation:
Journal Name: Fusion Science and Technology; Journal Volume: 67; Journal Issue: 3; Conference: TRITIUM 2013: 10. International Conference on Tritium Science and Technology, Nice Acropolis (France), 21-25 Oct 2013; Other Information: Country of input: France; 15 refs.
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ABSORPTION; DEPLETED URANIUM; DESORPTION; GAS ANALYSIS; GAS CHROMATOGRAPHY; HEAT LOSSES; HELIUM; HELIUM 3; ITER TOKAMAK; MASS SPECTROMETERS; SIMULATION; STORAGE; THERMAL ANALYSIS; THERMAL HYDRAULICS; THERMONUCLEAR FUELS; TRITIUM