Published January 1, 2016
| Version v1
Report
High Temperature Gas-Cooled Test Reactor Point Design: Summary Report
Creators
- 1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Description
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.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 50 p.
- Report number
- INL/EXT--16-37661
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 47061246
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; COST; DESIGN; ENRICHED URANIUM REACTORS; HTGR TYPE REACTORS; OXYCARBIDES; POWER RANGE 100-1000 MW; REACTOR LICENSING; REACTOR PHYSICS; TEST REACTORS; THERMAL HYDRAULICS
- Descriptors DEC
- CARBON COMPOUNDS; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HYDRAULICS; LICENSING; MECHANICS; MEGAWATT POWER RANGE; OXYGEN COMPOUNDS; PHYSICS; POWER RANGE; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; TEST FACILITIES
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy - NE (United States)
- Secondary number(s)
- OSTIID--1238543