Unit Operation Analysis of the Tritium Plant Storage and Delivery System in ITER
Creators
- 1. National Fusion Research Institute, Gwahangno 113, Yusung-gu, Daejeon 305-806 (Korea, Republic of)
- 2. Korea Atomic Energy Research Institute, Daeduk-daero 1045, Yusung-gu, Daejeon 305-353 (Korea, Republic of)
- 3. Korea Electric Power Research Institute, Moonjiro 65, Yusung-gu, Daejeon 305-380 (Korea, Republic of)
- 4. KOCEN Consulting and Services, Inc, 5442-1 Sangdaewon-dong, Seongnam-si, Gyeonggi 462- 729 (Korea, Republic of)
- 5. ITER Organization, CS 90 046, 13067 St Paul Lez Durance Cedex (France)
Description
Full text: The storage and delivery system of the tritium plant in the ITER has major functions to handle the fuel gases, mainly tritium-contaminated gases, safely. The new strategy of fuelling gases and the regulation of construction site in the ITER have led the change of the process design of the storage and delivery system. There are three kinds of needs to change the process design of the storage and delivery system. Regarding the pressure of manifold from the storage and delivery system to the fuelling system, it was proposed that the pressure of fuel gases will be reduced from 1.2 bar to sub-atmospheric pressure to prevent the tritium release into gallery in case of the guillotine brake of the double contained fuelling manifold. Regarding the need of fuel gases in the fuelling system, DT is not needed any more and the new fuelling rate of each gas has been evaluated. Regarding the safety to use of tritium-contaminated gases, the strict inventory limitation will be applied to prevent the propagation of fire and to reduce of the release amount of the tritium-contaminated gases. This study focused on the process analysis to satisfy the change of the environments in the process design of the storage and delivery system: how to perform the required fuelling rates and conditions of fuels and how to satisfy the safety regulation and guidelines to treat tritium-contaminated gases. (author)
Additional details
Publishing Information
- Imprint Title
- 23. IAEA Fusion Energy Conference. Book of Abstracts
- Imprint Pagination
- 637 p.
- Journal Page Range
- p. 552
- Report number
- IAEA-CN--180
Conference
- Title
- 23. IAEA Fusion Energy Conference
- Acronym
- FEC 2010
- Dates
- 11-16 Oct 2010
- Place
- Daejeon (Korea, Republic of)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43046211
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FIRES; FUEL SYSTEMS; FUELS; GASES; ITER TOKAMAK; OPERATION; SAFETY; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; FLUIDS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- ITR--P1-39