Published December 1999 | Version v1
Report Open

Development of tritium fuel processing system using electrolytic reactor for ITER

  • 1. Tritium Engineering Laboratory, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan)

Description

The system composed of a palladium diffuser and an electrolytic reactor was proposed, and was developed for a Fuel Cleanup system of ITER. The performance of the system was studied in a stand-alone test in detail. A fuel simulation loop of ITER was constructed by connecting the developed Fuel Cleanup and Hydrogen Isotope Separation systems; and the function of each system in the loop was demonstrated. For the tritium recovery from the exhaust gas at He glow discharge cleaning of vacuum chamber of ITER, a cryogenic molecular sieve bed system was proposed and demonstrated. (author)

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Part of:
Fusion energy 1998. Proceedings. V. 1-4

Additional details

Publishing Information

Imprint Title
Fusion energy 1998. Proceedings. V. 1-4
Imprint Pagination
1721 p.
Journal Issue
no. 1/P
Series
C and S papers series
Journal Page Range
v. 3 p. 1065-1068
ISSN
1563-0153
Report number
IAEA-CSP--1/P

Conference

Title
17. IAEA fusion energy conference
Dates
18-24 Oct 1998
Place
Yokohama (Japan)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
31011429
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ELECTROLYTIC CELLS; FUEL CYCLE; ITER TOKAMAK; MEETINGS; TRITIUM
Descriptors DEC
BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
6 refs, 4 figs, 1 tab
Secondary number(s)
ITER-P2--05