The AVR nuclear power plant - a milestone in high-temperature reactor development

Journal Article · Thu Aug 01 00:00:00 EDT 1985 · Nucl. Sci. Eng.; (United States)

OSTI ID:6147194

Schulten, R

For some time small high-temperature reactors, because of their special safety properties, have been of interest to various countries. The prototype of these facilities is the Arbeitsgemeinschaft Versuchsreaktor in Julich. During the past 17 years of operation, the components of the reactor, especially the fuel elements, have proved suitable for achieving permanent temperatures of the heat transfer medium of up to 950/sup 0/ C with low contamination of the loop. The convincing safety behavior of th reactor has been demonstrated. It is apparent that for this design an afterheat removal system is not required, since the afterheat can be adequately removed by heat conduction. In addition to the thorium/uranium fuel cycle originally planned, utilization of low-enrichment uranium in the fuel elements has also been fully developed.

• Research Organization: Institut fur Reaktorentwicklung, Kernforschungsanlage Julich GmbH, Julich
• OSTI ID: 6147194
• Journal Information: Nucl. Sci. Eng.; (United States), Vol. 90:4
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AVR REACTOR
FUEL CYCLE
PERFORMANCE
AFTER-HEAT REMOVAL
FUEL ELEMENTS
HTGR TYPE REACTORS
SLIGHTLY ENRICHED URANIUM
THORIUM
URANIUM
ACTINIDES
ELEMENTS
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HOMOGENEOUS REACTORS
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
PEBBLE BED REACTORS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
REMOVAL
SOLID HOMOGENEOUS REACTORS
THERMAL REACTORS
THORIUM REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated