Loss-of-coolant accident experiment at the AVR gas-cooled reactor
Conference
·
OSTI ID:7027933
- Arbeitsgemeinschaft Versuchs-Reaktor GmbH, Juelich (Germany, F.R.)
- Oak Ridge National Lab., TN (USA)
A landmark safety test has been conducted at the AVR-reactor, a high-temperature gas-cooled reactor (HTGR) in the Federal Republic of Germany owned by the Arbeitsgemeinschaft Versuchsreaktor, AVR in Juelich. The 46-MW(t), 15-MW(e) AVR reactor was subjected to a simulated loss-of-coolant accident (LOCA), a very severe occurrence in which the coolant escapes from the reactor core and no emergency system provides coolant flow to the core. The test, which demonstrated the inherently safe response of this reactor to a LOCA, marked the first time ever that a reactor has been intentionally subjected to loss-of-coolant conditions without emergency cooling. Oak Ridge National Laboratory (ORNL) and General Atomics participated in the test by working with AVR staff by jointly performing the analyses needed to obtain the license to conduct the test and by performing post test analyses. This participation was carried out under the cooperative AVR Subprogram which is conducted within the US/FRG Agreement for Cooperation in Gas-Cooled Reactor Development. 7 figs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7027933
- Report Number(s):
- CONF-900917-3; ON: DE90012732
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
AVR REACTOR
COOPERATION
DEMONSTRATION PROGRAMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EUROPE
FEDERAL REPUBLIC OF GERMANY
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HOMOGENEOUS REACTORS
HTGR TYPE REACTORS
HYDRAULICS
INTERNATIONAL COOPERATION
LOSS OF COOLANT
MECHANICS
NORTH AMERICA
PEBBLE BED REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SOLID HOMOGENEOUS REACTORS
THERMAL REACTORS
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WESTERN EUROPE
210300 -- Power Reactors
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Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
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COOPERATION
DEMONSTRATION PROGRAMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EUROPE
FEDERAL REPUBLIC OF GERMANY
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HOMOGENEOUS REACTORS
HTGR TYPE REACTORS
HYDRAULICS
INTERNATIONAL COOPERATION
LOSS OF COOLANT
MECHANICS
NORTH AMERICA
PEBBLE BED REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SOLID HOMOGENEOUS REACTORS
THERMAL REACTORS
THORIUM REACTORS
USA
WESTERN EUROPE