skip to main content

Title: Preliminary design studies on the Broad Application Test Reactor

This report describes progress made at the Idaho National Engineering Laboratory during the first three quarters of Fiscal Year (FY) 1992 on the Laboratory-Directed Research and Development (LDRD) project to perform preliminary design studies on the Broad Application Test Reactor (BATR). This work builds on the FY-92 BATR studies, which identified anticipated mission and safety requirements for BATR and assessed a variety of reactor concepts for their potential capability to meet those requirements. The main accomplishment of the FY-92 BATR program is the development of baseline reactor configurations for the two conventional conceptual test reactors recommended in the FY-91 report. Much of the present report consists of descriptions and neutronics and thermohydraulics analyses of these baseline configurations. In addition, we considered reactor safety issues, compared the consequences of steam explosions for alternative conventional fuel types, explored a Molten Chloride Fast Reactor concept as an alternate BATR design, and examined strategies for the reduction of operating costs. Work planned for the last quarter of FY-92 is discussed, and recommendations for future work are also presented.
Authors:
 [1] ; ; ; ; ; ; ; ; ;
  1. (ed.)
Publication Date:
OSTI Identifier:
6935086
Report Number(s):
EGG-NRRT-10350
ON: DE93002038
DOE Contract Number:
AC07-76ID01570
Resource Type:
Technical Report
Research Org:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Org:
DOE; USDOE, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; TEST REACTORS; DESIGN; ATR REACTOR; COMPUTER CODES; COST; EXPLOSIONS; HEAT TRANSFER; HYDRAULICS; LIQUID METAL COOLED REACTORS; REACTOR COOLING SYSTEMS; REACTOR PHYSICS; REACTOR SAFETY; REACTOR SHUTDOWN; STEAM; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; MECHANICS; PHYSICS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SHUTDOWN; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS 220600* -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors; 220100 -- Nuclear Reactor Technology-- Theory & Calculation; 220900 -- Nuclear Reactor Technology-- Reactor Safety; 210500 -- Power Reactors, Breeding