Author: C. E Dickerman
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 102
Book Description
Meltdown tests on single metallic un-irradiated fuel elements in TREAT are described. The fuel elements (EBRII, Mark I fuel pins, EBR-II fuel pins with refractory Nb or Ta cladding, and Fermi-1 fuel pins) are tested in an inert atmosphere, with no coolant. The fuel elements are exposed to reactor power bursts of 200 msec to 25 sec duration, under conditions simulating fast reactor operations. For these tests, the type of power burst, the integrated power, the fuel enrichment, the maximum cladding temperature, and the effects of the test on the fuel element are recorded.
Studies of Fast Reactor Fuel Element Behavior Under Transient Heating to Failure
Author: C. E Dickerman
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 102
Book Description
Meltdown tests on single metallic un-irradiated fuel elements in TREAT are described. The fuel elements (EBRII, Mark I fuel pins, EBR-II fuel pins with refractory Nb or Ta cladding, and Fermi-1 fuel pins) are tested in an inert atmosphere, with no coolant. The fuel elements are exposed to reactor power bursts of 200 msec to 25 sec duration, under conditions simulating fast reactor operations. For these tests, the type of power burst, the integrated power, the fuel enrichment, the maximum cladding temperature, and the effects of the test on the fuel element are recorded.
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 102
Book Description
Meltdown tests on single metallic un-irradiated fuel elements in TREAT are described. The fuel elements (EBRII, Mark I fuel pins, EBR-II fuel pins with refractory Nb or Ta cladding, and Fermi-1 fuel pins) are tested in an inert atmosphere, with no coolant. The fuel elements are exposed to reactor power bursts of 200 msec to 25 sec duration, under conditions simulating fast reactor operations. For these tests, the type of power burst, the integrated power, the fuel enrichment, the maximum cladding temperature, and the effects of the test on the fuel element are recorded.
Studies of Fast Reactor Fuel Element Behavior Under Transient Heating to Failure
Author: C. E Dickerman
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 52
Book Description
The in-pile experimental survey reported here is one undertaken on uranium dioxide fuel samples as an extension of previous tests in the Transient Reactor Test Facility (TREAT) on metallic, fast-reactor fuel samples. Oxide test specimens were pseudo-EBR-II elements that were clad with EBR-II cladding thickness, of EBR-II fuel length, and thermally bonded to cladding with inert gas (rather than sodium). Samples were exposed to transient power bursts of the order of 0.5-sec. duration, in the absence of coolant, with production of heating rates up to the order of 4000 degrees C/sec. Radial temperature profiles in the fuel during power bursts were estimated to be comparatively uniform. Cladding temperature lagged behind the fuel temperature, thermal equilibrium between fuel and clad being reached about 2 sec. after the peak of the power pulse. Sample cooling was predominantly by thermal radiation.
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 52
Book Description
The in-pile experimental survey reported here is one undertaken on uranium dioxide fuel samples as an extension of previous tests in the Transient Reactor Test Facility (TREAT) on metallic, fast-reactor fuel samples. Oxide test specimens were pseudo-EBR-II elements that were clad with EBR-II cladding thickness, of EBR-II fuel length, and thermally bonded to cladding with inert gas (rather than sodium). Samples were exposed to transient power bursts of the order of 0.5-sec. duration, in the absence of coolant, with production of heating rates up to the order of 4000 degrees C/sec. Radial temperature profiles in the fuel during power bursts were estimated to be comparatively uniform. Cladding temperature lagged behind the fuel temperature, thermal equilibrium between fuel and clad being reached about 2 sec. after the peak of the power pulse. Sample cooling was predominantly by thermal radiation.
STUDIES OF FAST REACTOR FUEL ELEMENT BEHAVIOR UNDER TRANSIENT HEATING TO FAILURE. II. INPILE EXPERIMENTS ON UO2 SAMPLES IN THE ABSENCE OF COOLANT.
STUDIES OF FAST REACTOR FUEL ELEMENT BEHAVIOR UNDER TRANSIENT HEATING TO FAILURE. III. IN-PILE EXPERIMENTS ON IRRADIATED UO$sub 2$ FUEL PINS IN THE ABSENCE OF COOLANT.
Studies of Fast Reactor Fuel Element Behavior Under Transient Heating to Failure
Nuclear Science Abstracts
Nuclear Science Abstracts
Reactor Technology
Studies Related to Predicting Coolant Behavior for Fast Reactor Safety
Author: Ralph P. Stein
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 84
Book Description
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 84
Book Description