High Temperature Gas-Cooled Test Reactor Options Status Report
Preliminary scoping calculations are being performed for a 100 MWt gas-cooled test reactor. The initial design uses standard prismatic blocks and 15.5% enriched UCO fuel. Reactor physics and thermal-hydraulics simulations have been performed to identify some reactor design features to investigate further. Current status of the effort is described.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Idaho National Lab. (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; TEST REACTORS; THERMAL HYDRAULICS; REACTOR PHYSICS; DESIGN; COMPUTERIZED SIMULATION; URANIUM CARBIDES; URANIUM OXIDES; ENRICHED URANIUM REACTORS; Gas-cooled reactor; High temperature; Test reactor
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