Bibliographic Citation
| Document | For copies of Journal Articles, please contact the Publisher or your local public or university library and refer to the information in the Resource Relation field. For copies of other documents, please see the Availability, Publisher, Research Organization, Resource Relation and/or Author (affiliation information) fields and/or Document Availability. |
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| Title | Loss-of-coolant accident experiment at the AVR gas-cooled reactor |
| Creator/Author | Krueger, K. (Arbeitsgemeinschaft Versuchs-Reaktor GmbH, Juelich (Germany, F.R.)) ; Cleveland, J. (Oak Ridge National Lab., TN (USA)) |
| Publication Date | 1990 Jan 01 |
| OSTI Identifier | OSTI ID: 7027933; Legacy ID: DE90012732 |
| Report Number(s) | CONF-900917-3 |
| DOE Contract Number | AC05-84OR21400 |
| Other Number(s) | Other: ON: DE90012732 |
| Resource Type | Conference |
| Specific Type | Technical Report |
| Resource Relation | Conference: American Nuclear Society topical meeting on safety of non-commercial nuclear reactor research and irradiation facilities, Boise, ID (USA), 30 Sep - 3 Oct 1990 |
| Research Org | Oak Ridge National Lab., TN (USA) |
| Sponsoring Org | DOE/NE |
| Subject | 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; AVR REACTOR; LOSS OF COOLANT; DEMONSTRATION PROGRAMS; FEDERAL REPUBLIC OF GERMANY; HEAT TRANSFER; HTGR TYPE REACTORS; HYDRAULICS; INTERNATIONAL COOPERATION; REACTOR SAFETY; USA; ACCIDENTS; COOPERATION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EUROPE; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HOMOGENEOUS REACTORS; MECHANICS; NORTH AMERICA; PEBBLE BED REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; THORIUM REACTORS; WESTERN EUROPE |
| Description/Abstract | 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. |
| Country of Publication | United States |
| Language | English |
| Format | Medium: X; Size: Pages: (18 p) |
| Availability | NTIS, PC A03/MF A01; OSTI; INIS; GPO Dep. |
| System Entry Date | 2008 Feb 12 |
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