Published August 1, 2015
| Version v1
Report
High Temperature Gas-Cooled Test Reactor Options Status Report
Creators
- 1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Description
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.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 36 p.
- Report number
- INL/EXT--15-36340
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 47046051
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; DESIGN; ENRICHED URANIUM REACTORS; HTGR TYPE REACTORS; REACTOR PHYSICS; TEST REACTORS; THERMAL HYDRAULICS; URANIUM CARBIDES; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HYDRAULICS; MECHANICS; OXIDES; OXYGEN COMPOUNDS; PHYSICS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; TEST FACILITIES; URANIUM COMPOUNDS
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy (United States)
- Secondary number(s)
- OSTIID--1236794