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Title: 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.
Authors:
 [1] ;  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
1236794
Report Number(s):
INL/EXT--15-36340
TRN: US1600263
DOE Contract Number:
AC07-05ID14517
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
Language:
English
Subject:
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