Run - Beyond - Cladding - Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:7176746

Batte, G L ^[1]; Hoffman, G L ^[2]

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1. Argonne National Lab., Idaho Falls, ID (USA)
2. Argonne National Lab., IL (USA)

In 1984 Argonne National Laboratory (ANL) began an aggressive program of research and development based on the concept of a closed system for fast-reactor power generation and on-site fuel reprocessing, exclusively designed around the use of metallic fuel. This is the Integral Fast Reactor (IFR). Although the Experimental Breeder Reactor-II (EBR-II) has used metallic fuel since its creation 25 yeas ago, in 1985 ANL began a study of the characteristics and behavior of an advanced-design metallic fuel based on uranium-zirconium (U-Zr) and uranium-plutonium-zirconium (U-Pu-Zr) alloys. During the past five years several areas were addressed concerning the performance of this fuel system. In all instances of testing the metallic fuel has demonstrated its ability to perform reliably to high burnups under varying design conditions. This paper will present one area of testing which concerns the fuel system's performance under breach conditions. It is the purpose of this paper to document the observed post-breach behavior of this advanced-design metallic fuel. 2 figs., 1 tab.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7176746
• Report Number(s): CONF-900804-2; ON: DE90005662; TRN: 90-020015
• Resource Relation: Conference: International topical meeting on fast reactor safety, Snowbird, UT (USA), 12-16 Aug 1990
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
IFR REACTOR
FUEL ELEMENTS
BURNUP
DEMONSTRATION PROGRAMS
DESIGN
EBR-2 REACTOR
EXPERIMENTAL DATA
FUEL CANS
FUEL-CLADDING INTERACTIONS
IRRADIATION
MATERIALS TESTING
PERFORMANCE TESTING
REACTOR CORES
REACTOR OPERATION
REACTOR SAFETY
RELIABILITY
RESEARCH PROGRAMS
RUPTURES
STRESS ANALYSIS
TECHNOLOGY ASSESSMENT
BREEDER REACTORS
DATA
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
INFORMATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUMERICAL DATA
OPERATION
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
TESTING
ZERO POWER REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
210500 - Power Reactors
Breeding
050700 - Nuclear Fuels- Fuels Production & Properties
220900 - Nuclear Reactor Technology- Reactor Safety