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

Conference · Thu Aug 01 00:00:00 EDT 1985

OSTI ID:6279709

Kasten, P. R.; Neylan, A. J.; Penfield, Jr., S. R.

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.

• Research Organization: Oak Ridge National Lab., TN (USA); GA Technologies, Inc., San Diego, CA (USA); Gas-Cooled Reactor Associates, San Diego, CA (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6279709
• Report Number(s): ORNL/TM-9508; DOE/HTGR-85-082; CONF-841287-1; ON: DE86001464
• Resource Relation: Conference: Japan Atomic Energy Research Institute annual open seminar on research and development of the multipurpose VHTR, Tokyo, Japan, 12 Dec 1984
• Country of Publication: United States
• Language: English

Related Subjects

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