Hydrogen inventories in the vacuum pumping systems of ITER
Creators
- 1. Forschungszentrum Karlsruhe GmbH, P.O. Box 3640, 76021 Karlsruhe (Germany)
- 2. ITER IT, c/o Max-Planck-Institut fuer Plasmaphysik, Boltzmannstrasse 2, 85748 Garching (Germany)
- 3. EFDA CSU, c/o Max-Planck-Institut fuer Plasmaphysik, Boltzmannstrasse 2, 85748 Garching (Germany)
Description
The ITER in-vessel hydrogen inventory is highly dynamic and determined by a broad range of parameters. Moreover, it is of prime importance to allocate the inventory as accurately as possible. Two essential control issues have to be met. The basic safety approach is to limit the amount of hydrogen such that the resulting pressure in case of an explosion accident is compatible to the design criteria of the vacuum vessel. This requirement drives the operational philosophy and the design of the cryogenic pumps which are connected to the vessel. The administrative limitation of the tritium inventory is another essential requirement on reactor operation. This paper illustrates how hydrogen inventory control issues are reflected by the operational schemes of the vacuum pumping systems. Latest results include the release characteristics of hydrogens and tritium during normal regeneration of the cryopumps and under off-normal events. The different semi-permanent contributions to the overall tritium inventory are discussed. The forepumping systems reduce the in-vessel inventory and act as interface to the tritium plant. A typical example of an integral pump-out curve is discussed. It is shown that sufficient safety margin is included in the ITER vacuum pumping design
Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2005.07.020;
- PII
- S0920-3796(05)00585-5;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 81
- Journal Issue
- 1-7
- Journal Page Range
- p. 777-784
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 7. international symposium on fusion nuclear technology
- Acronym
- ISFNT-7
- Dates
- 22-27 May 2005
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37109394
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; CONTAINERS; CONTROL; CRYOPUMPS; DESIGN; HYDROGEN; INVENTORIES; ITER TOKAMAK; SAFETY; THERMONUCLEAR REACTOR MATERIALS; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; ELEMENTS; EQUIPMENT; HYDROGEN ISOTOPES; ISOTOPES; LABORATORY EQUIPMENT; LIGHT NUCLEI; MATERIALS; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; PUMPS; RADIOISOTOPES; REACTOR COMPONENTS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; VACUUM PUMPS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.