Assessment of fuel integrity of the High Temperature Engineering Test Reactor (HTTR) and its permissible design limit
Creators
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Description
This report describes the results of integrity assessment of the HTTR fuel as a part of safety design of the reactor. Functions of individual coating layer of the coated fuel particles were investigated to clarify the characteristic properties of the HTTR fuel. Integrity of the fuel under normal operating conditions of HTTR was shown to be maintained through analyses on fuel failure and due to kernel migration (amoeba effect) and corrosion of the silicon carbide layer by palladium. The fuel integrity has been demonstrated by successful results of the irradiation performance tests. By considering the failure behavior of coated fuel particles, the permissible design limit of the fuel was determined such that the fuel temperature should not exceed 1600degC under abnormal transient conditions. The validity of the determination of the limit has been confirmed by results of heating experiments of coated fuel particles at extremely high temperature. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
21036910.pdf
Files
(3.2 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 88 p.
- Report number
- JAERI-M--89-162
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 21036910
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COATED FUEL PARTICLES; CORROSION; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; FUEL INTEGRITY; HTTR REACTOR; PALLADIUM; POST-IRRADIATION EXAMINATION; REACTOR OPERATION; REACTOR SAFETY; SILICON CARBIDES; SPECIFICATIONS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CARBIDES; CARBON COMPOUNDS; CHEMICAL REACTIONS; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; METALS; OPERATION; PLATINUM METALS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SILICON COMPOUNDS; TRANSITION ELEMENTS