Irradiation and examination results of the AC-3 mixed-carbide test
                            Conference
                            ·
                            
                            · Transactions of the American Nuclear Society; (United States)
                            
                    
                                
                                OSTI ID:6982442
                                
                            
                        - Los Alamos National Lab., NM (United States)
- Paul Scherrer Institute, Villigen (Switzerland)
The AC-3 test was a cooperative Swiss/US irradiation test of mixed-carbide, (U,Pr)C, fuel pins in the Fast Flux Test Facility. The test included 25 Swiss-fabricated sphere-pac-type fuel pins and 66 U.S. fabricated pellet-type fuel pins. The test was designed to operate at prototypical fast reactor conditions to provide a direct comparison of the irradiation performance of the two fuel types. The test design and fuel fabrication processes used for the AC-3 test are presented.
- OSTI ID:
- 6982442
- Report Number(s):
- CONF-921102--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 66; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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                                        Design and fuel fabrication processes for the AC-3 mixed-carbide irradiation test
                                        
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                                            Conference
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                                            Tue Dec 31 23:00:00 EST 1991
                                            · Transactions of the American Nuclear Society; (United States)
                                            ·
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                                            Wed Dec 31 23:00:00 EST 1986
                                            · Trans. Am. Nucl. Soc.; (United States)
                                            ·
                                            OSTI ID:5580459
                                        
                                        
                                        
                                    
                                
                                    
                                        Comparison of sphere-pac and pellet (U,Pu)O$sub 2$ fuel pins in low burnup instrumented irradiation tests
                                            Journal Article
                                            ·
                                            Mon Dec 31 23:00:00 EST 1973
                                            · Nucl. Technol., v. 21, no. 1, pp. 26-38
                                            ·
                                            OSTI ID:4350708
                                        
                                        
                                        
                                    
                                
                            Related Subjects
                                
                                    
                                        
                                        
                                            
                                                21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BURNUP
COOPERATION
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENTS
FUEL PELLETS
FUEL PINS
FUELS
INTERNATIONAL COOPERATION
IRRADIATION
LIQUID METAL COOLED REACTORS
MATERIALS
MIXED CARBIDE FUELS
NUCLEAR FUELS
PELLETS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TESTING
THERMAL ANALYSIS
                                            
                                        
                                    
                                
                            
                        220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BURNUP
COOPERATION
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENTS
FUEL PELLETS
FUEL PINS
FUELS
INTERNATIONAL COOPERATION
IRRADIATION
LIQUID METAL COOLED REACTORS
MATERIALS
MIXED CARBIDE FUELS
NUCLEAR FUELS
PELLETS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TESTING
THERMAL ANALYSIS