Conceptual design of small-sized HTGR system (3). Core thermal and hydraulic design
Creators
- 1. Japan Atomic Energy Agency, Nuclear Hydrogen and Heat Application Research Center, Oarai, Ibaraki (Japan)
Description
The Japan Atomic Energy Agency has started the conceptual designs of small-sized High Temperature Gas-cooled Reactor (HTGR) systems, aiming for the 2030s deployment into developing countries. The small-sized HTGR systems can provide power generation by steam turbine, high temperature steam for industry process and/or low temperature steam for district heating. As one of the conceptual designs in the first stage, the core thermal and hydraulic design of the power generation and steam supply small-sized HTGR system with a thermal power of 50 MW (HTR50S), which was a reference reactor system positioned as a first commercial or demonstration reactor system, was carried out. HTR50S in the first stage has the same coated particle fuel as HTTR. The purpose of the design is to make sure that the maximum fuel temperature in normal operation doesn't exceed the design target. Following the design, safety analysis assuming a depressurization accident was carried out. The fuel temperature in the normal operation and the fuel and reactor pressure vessel temperatures in the depressurization accident were evaluated. As a result, it was cleared that the thermal integrity of the fuel and the reactor coolant pressure boundary is not damaged. (author)
Availability note (English)
Available from JAEA; DOI: https://doi.org/10.11484/jaea-technology-2012-019
Files
System files
(300.4 kB)
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 150 p.
- Report number
- JAEA-Technology--2012-019
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 44035202
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENTS; DEPRESSURIZATION; DESIGN; DISTRICT HEATING; FUEL INTEGRITY; HTGR TYPE REACTORS; HTTR REACTOR; PRESSURE VESSELS; PROCESS HEAT; REACTOR CORES; SAFETY ANALYSIS; STEAM TURBINES; THERMAL HYDRAULICS
- Descriptors DEC
- CONTAINERS; ENERGY; ENRICHED URANIUM REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT; HEATING; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; HYDRAULICS; MACHINERY; MECHANICS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TURBINES; TURBOMACHINERY
Optional Information
- Notes
- 27 refs., 81 figs., 71 tabs.