Preparation, conduct, and experimental results of the AVR loss-of-coolant accident simulation test
Journal Article
·
· Nuclear Science and Engineering; (United States)
OSTI ID:6017421
- Arbeitsgemeinschaft Versuchsreaktor AVR GmbH, Duesseldorf (DE)
- Oak Ridge National Lab., TN (United States)
A loss-of-coolant accident (LOCA) is one of the most severe accidents for a nuclear power plant. To demonstrate inherent safety characteristics incorporated into small high-temperature gas-cooled reactor (HTGR) design, LOCA simulation tests have been conducted at the Arbeitsgemeinschaft Versuchsreaktor (AVR), the German pebble-bed-high-temperature reactor plant. The AVR is the only nuclear power plant ever to have been intentionally subjected to LOCA conditions without emergency cooling. This paper presents the planning and licensing activities including pretest predictions performed for the LOCA test are described, and the conduct of the test and experimental results. The LOCA test was planned to create conditions that would exist if a rapid LOCA occurred with the reactor operating at full power. The test demonstrated this reactor's safe response to an accident in which the coolant escapes from the reactor core and no emergency system is available to provide coolant flow to the core. The test is of special interest because it demonstrates the inherent safety features incorporated into optimized modular HTGR designs. The main LOCA test lasted for 5 days. After the test began, core temperatures increased for {approx}13 h and then gradually and continually decreased as the rate of heat dissipation from the core exceeded the simulated decay power. Throughout the test, temperatures remained below limiting values for the core and other reactor components.
- OSTI ID:
- 6017421
- Journal Information:
- Nuclear Science and Engineering; (United States), Journal Name: Nuclear Science and Engineering; (United States) Vol. 107:2; ISSN 0029-5639; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Loss-of-coolant accident experiment at the AVR gas-cooled reactor
Loss-of-coolant accident experiment at the AVR (Arbeitsgemeinschaft Versuchsreaktor) gas-cooled reactor
Loss-of-coolant accident experiment at the AVR gas-cooled reactor
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:5655096
Loss-of-coolant accident experiment at the AVR (Arbeitsgemeinschaft Versuchsreaktor) gas-cooled reactor
Conference
·
Tue Oct 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5478399
Loss-of-coolant accident experiment at the AVR gas-cooled reactor
Conference
·
Sun Dec 31 23:00:00 EST 1989
·
OSTI ID:7027933
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANALOG SYSTEMS
AVR REACTOR
DATA
DESIGN
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
FUNCTIONAL MODELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HOMOGENEOUS REACTORS
HTGR TYPE REACTORS
INFORMATION
LOSS OF COOLANT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
OPTIMIZATION
PEBBLE BED REACTORS
POWER PLANTS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTOR SIMULATORS
REACTORS
SAFETY
SIMULATORS
SOLID HOMOGENEOUS REACTORS
THERMAL POWER PLANTS
THERMAL REACTORS
THORIUM REACTORS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANALOG SYSTEMS
AVR REACTOR
DATA
DESIGN
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
FUNCTIONAL MODELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HOMOGENEOUS REACTORS
HTGR TYPE REACTORS
INFORMATION
LOSS OF COOLANT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
OPTIMIZATION
PEBBLE BED REACTORS
POWER PLANTS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTOR SIMULATORS
REACTORS
SAFETY
SIMULATORS
SOLID HOMOGENEOUS REACTORS
THERMAL POWER PLANTS
THERMAL REACTORS
THORIUM REACTORS