Design and safety consideration in the High-Temperature Engineering Test Reactor (HTTR)
Creators
- 1. Department of HTTR Project, Japan Atomic Energy Research Institute (Japan)
Description
The budget for construction of the High-Temperature Engineering Test Reactor (HTTR) was recently committed by the Government in Japan. The HTTR is a test reactor with thermal output of 30 MW and reactor outlet coolant temperature of 950 deg. C at high temperature test operation. The HTTR plant uses a pin-in-block design core and will be used as an experience leading to high temperature applications. Several major important safety considerations are adopted in the design of the HTTR. These are as follows: 1) A coated particle fuel must not be failed during a normal reactor operation and an anticipated operational occurrence; 2) Two independent and diverse reactor shut-down systems are provided in order to shut down the reactor safely and reliably in any condition; 3) Back-up reactor cooling systems which are safety ones are provided in order to remove residual heat of reactor in any condition; 4) Multiple barriers and countermeasures are provided to contain fission products such as a containment, pressure gradient between the primary and secondary cooling circuit and so on, though coated particle fuels contain fission products with high reliability; 5) The functions of materials used in the primary cooling circuit are separated to be pressure-resisting and heat-resisting in order to resolve material problems and maintain high reliability. The detailed design of the HTTR was completed with extensive accumulation of material data and component tests. (author)
Files
32036111.pdf
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Additional details
Publishing Information
- Imprint Title
- Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material
- Imprint Pagination
- 724 p.
- Journal Page Range
- p. 368-388
- Report number
- IAEA-TC--389.26
Conference
- Title
- Technical committee meeting on gas-cooled reactor technology safety and siting
- Dates
- 21-23 Jun 1989
- Place
- Dimitrovgrad (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 32036111
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; COATED FUEL PARTICLES; CONTAINMENT SYSTEMS; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; HEAT RESISTANT MATERIALS; HTTR REACTOR; PRIMARY COOLANT CIRCUITS; REACTOR OPERATION; REACTOR SAFETY; RELIABILITY; SAFETY ANALYSIS
- Descriptors DEC
- CONTAINMENT; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATERIALS; OPERATION; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; RESEARCH AND TEST REACTORS; SAFETY
Optional Information
- Notes
- 8 figs, 1 tab