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Title: New approaches in the USA for high-temperature gas-cooled reactors. Gas-Cooled Reactor Programs

Several concepts are being evaluated in the US HTR Program to explore designs which might improve the commercial viability of nuclear power. The general approach is to reduce the reactor power and increase the ability to use inherent features for removing heat following extreme accidents. The unit size and design of these concepts are constrained so that extreme accidents do not result in significant release of radioactivity from the reactor plant. Through the greater reliance on inherent safety features in small HTRs, it should be possible to minimize the amount of nuclear grade components required in the balance-of-plant, which could lead to an economic system. Four HTR concepts are presently being evaluated within the US Program, and these concepts are briefly summarized. A modular HTR using a steel pressure vessel, which is very similar to one of the four HTR concepts being evaluated within the US National program, is presented as an example of a specific concept to illustrate the features and performance of HTRs having a high degree of inherent safety.
Authors:
; ;
Publication Date:
OSTI Identifier:
6279709
Report Number(s):
ORNL/TM-9508; DOE/HTGR-85-082; CONF-841287-1
ON: DE86001464
DOE Contract Number:
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: Japan Atomic Energy Research Institute annual open seminar on research and development of the multipurpose VHTR, Tokyo, Japan, 12 Dec 1984
Research Org:
Oak Ridge National Lab., TN (USA); GA Technologies, Inc., San Diego, CA (USA); Gas-Cooled Reactor Associates, San Diego, CA (USA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HTGR TYPE REACTORS; DESIGN; AFTER-HEAT REMOVAL; EVALUATION; PRESSURE VESSELS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTOR SAFETY; RISK ASSESSMENT; SIZE; STEELS; ACCIDENTS; ALLOYS; CONTAINERS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; REACTORS; REMOVAL; SAFETY 210300* -- Power Reactors, Nonbreeding, Graphite Moderated