The integral fast reactor
Description
On April 3rd, 1986, two dramatic demonstrations of the inherent capability of sodium-cooled fast reactors to survive unprotected loss of cooling accidents were carried out on the experimental sodium-cooled power reactor, EBR-II, on the Idaho site of Argonne National Laboratory. Transients potentially of the most serious kind, one an unprotected loss of flow, the other an unprotected loss of heat sink, both initiated from full power. In both cases the reactor quietly shut itself down, without damage of any kind. The contrast between the consequences of these events in EBR-II and the Chernobyl events just twenty-three days later thrust EBR-II, and the underlying Integral Fast Reactor development program at Argonne, into the national news. The paper describes the IFR concept, the inherent safety tests, and status of IRF development today
Additional details
Publishing Information
- Journal Title
- Nucl. Mater. Manage.
- Journal Volume
- 16
- Series
- Nucl. Mater. Manage.
- Journal Page Range
- 19-23
- ISSN
- 0362-0034
- CODEN
- NUMMB
Conference
- Title
- a mature technology.
- Acronym
- 28. INMM annual meeting on safeguards
- Dates
- 12-15 Jul 1987.
- Place
- Newport Beach, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19041874
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHERNOBYLSK-4 REACTOR; DEMONSTRATION PROGRAMS; EBR-2 REACTOR; ENERGY LOSSES; HEAT SINKS; HEAT TRANSFER; LOSS OF FLOW; REACTOR SAFETY; REACTOR SHUTDOWN; REVIEWS; SHUTDOWN; TESTING; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; DOCUMENT TYPES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GRAPHITE MODERATED REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; LWGR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SODIUM COOLED REACTORS; THERMAL REACTORS; WATER COOLED REACTORS
Optional Information
- Secondary number(s)
- CONF-870713--.