Fission product release characteristics of the experimental VHTR core
Creators
- 1. Japan Atomic Energy Research Institute, Toka-mura, Naka-gun, Ibaraki-ken (Japan)
Description
Fission product release characteristics of the experimental VHTR core is analyzed. The reactor is equipped with a loop type plant for process heat application test, and is designed to generate high temperature coolant of 950 deg C. Plateout activities and circulating activities in the primary cooling system are calculated for various core conditions, and operator dose in maintenance work and offsite public dose during normal operation of the reactor are evaluated. The result shows that fission product retention in the graphite matrix and the fuel sleeve is degraded at high temperature condition in the VHTR core, and that high radiation dose in the maintenance work is caused by cesium isotopes, and it is also indicated that development of coated fuel particle with higher performance or any means for plateout fission product will be required for a HTR plant with higher outlet temperature
Files
31049632.pdf
Files
(219.1 kB)
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Additional details
Publishing Information
- Imprint Title
- Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment
- Imprint Pagination
- 412 p.
- Journal Page Range
- p. 255-263
- Report number
- IWGGCR--8
Conference
- Title
- Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment
- Dates
- 18-21 Oct 1983
- Place
- Moscow (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 31049632
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FISSION PRODUCT RELEASE; GRAPHITE; RADIATION DOSES; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR MAINTENANCE; TEMPERATURE RANGE 0400-1000 K; VHTR REACTOR
- Descriptors DEC
- CARBON; COOLING SYSTEMS; DOSES; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MAINTENANCE; MINERALS; NONMETALS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TEMPERATURE RANGE; THERMAL REACTORS
Optional Information
- Notes
- 6 refs, 6 figs, 3 tabs