High Temperature Gas-Cooled Test Reactor Point Design: Summary Report
A point design has been developed for a 200-MW high-temperature gas-cooled test reactor. The point design concept uses standard prismatic blocks and 15.5% enriched uranium oxycarbide fuel. Reactor physics and thermal-hydraulics simulations have been performed to characterize the capabilities of the design. In addition to the technical data, overviews are provided on the technology readiness level, licensing approach, and costs of the test reactor point design.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Org:
- USDOE Office of Nuclear Energy (NE)
- Country of Publication:
- United States
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; HTGR TYPE REACTORS; POWER RANGE 100-1000 MW; ENRICHED URANIUM REACTORS; TEST REACTORS; DESIGN; OXYCARBIDES; COMPUTERIZED SIMULATION; THERMAL HYDRAULICS; REACTOR PHYSICS; REACTOR LICENSING; COST ART; High Temperature Gas-Cooled; permanent side reflector; TDO; UCO
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