Engineering design of the ITER invessel neutron monitor using micro-fission chambers
- 1. Japan Atomic Energy Agency, Naka-shi, Ibaraki 311-0193 (Japan)
- 2. Toshiba Corp., Isogo-ku, Yokohama 235-8523 (Japan)
- 3. AITEL Corp., Kawasaki 210-0862 (Japan)
Description
An invessel neutron monitor using micro-fission chambers is one of the most important diagnostics to measure the fusion power in ITER. A single micro-fission chamber with 10 mg of 235U to be installed in a gap between a shielding blanket module and a vacuum vessel can cover the range of the fusion power from 100 kW to 1 GW. For the low fusion power operation including D-D operation, a micro-fission chamber bundle consisting of 13 micro-fission chamber units has been designed. Nuclear heating of the micro-fission chamber for high power operations and the micro-fission chamber bundle for low power operation were analyzed by neutron transport calculations using the MCNPX code. Heat transport analyzes for the micro-fission chambers were carried out with a general purpose Finite Element Method code ANSYS 8.1, which indicated that the detector temperature might be kept less than the operational temperature limit by the thermal conduction to the vacuum vessel with the heat transfer coefficient of 100 W/m2 K or larger
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2007.05.060Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2007.05.060;
- PII
- S0920-3796(07)00280-3;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 82
- Journal Issue
- 5-14
- Journal Page Range
- p. 1192-1197
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 24. symposium on fusion technology
- Acronym
- SOFT-24
- Dates
- 11-15 Sep 2006
- Place
- Warsaw (Poland)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39109798
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINERS; DESIGN; ENGINEERING; FINITE ELEMENT METHOD; FISSION CHAMBERS; HEATING; ITER TOKAMAK; NEUTRON MONITORS; NEUTRON TRANSPORT; OPERATION; SHIELDING; THERMAL ANALYSIS; THERMAL CONDUCTION; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; CLOSED PLASMA DEVICES; ENERGY TRANSFER; EVEN-ODD NUCLEI; HEAT TRANSFER; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IONIZATION CHAMBERS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATHEMATICAL SOLUTIONS; MEASURING INSTRUMENTS; MINUTES LIVING RADIOISOTOPES; MONITORS; NEUTRAL-PARTICLE TRANSPORT; NEUTRON DETECTORS; NUCLEI; NUMERICAL SOLUTION; RADIATION DETECTORS; RADIATION MONITORS; RADIATION TRANSPORT; RADIOISOTOPES; SPONTANEOUS FISSION RADIOISOTOPES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.