EBR-II: summary of operating experience
Conference
·
OSTI ID:6542410
Experimental Breeder Reactor II (EBR-II) is an unmoderated, sodium-cooled reactor with a design power of 62.5 MWt. The primary cooling system is a submerged-pool type. The early operation of the reactor successfully demonstrated the feasibility of a sodium-cooled fast breeder reactor operating as an integrated reactor, power plant, and fuel-processing facility. In 1967, the role of EBR-II was reoriented from a demonstration plant to an irradiation facility. Many changes have been made and are continuing to be made to increase the usefulness of EBR-II for irradiation and safety tests. A review of EBR-II's operating history reveals a plant that has demonstrated high availability, stable and safe operating characteristics, and excellent performance of sodium components. Levels of radiation exposure to the operating and maintenance workers have been low; and fission-gas releases to the atmosphere have been minimal. Driver-fuel performance has been excellent. The repairability of radioactive sodium components has been successfully demonstrated a number of times. Recent highlights include installation and successful operation of (1) the hydrogen-meter leak detectors for the steam generators, (2) the cover-gas-cleanup system and (3) the cesium trap in the primary sodium. Irradiations now being conducted in EBR-II include the run-beyond-cladding breach fuel tests for mixed-oxide and carbide elements. Studies are in progress to determine EBR-II's capability for conducting important ''operational safety'' tests. These tests would extend the need and usefulness of EBR-II into the 1980's.
- Research Organization:
- Argonne National Lab., Idaho Falls, ID (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6542410
- Report Number(s):
- CONF-780963-1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BREEDER REACTORS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
MAINTENANCE
OPERATION
PERFORMANCE
POWER REACTORS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR MAINTENANCE
REACTOR OPERATION
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BREEDER REACTORS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
MAINTENANCE
OPERATION
PERFORMANCE
POWER REACTORS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR MAINTENANCE
REACTOR OPERATION
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS