Author: Erhard A. Fischer
Publisher:
ISBN:
Category :
Languages : en
Pages : 30
Book Description
Analysis of Experimental Fission Gas Behavior Data in Fast Reactor Fuel Under Steady State and Transient Conditions
Analysis of Fission-gas Behavior with the Stars Code
Author: Eugene E. Gruber
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 36
Book Description
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 36
Book Description
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.
Analysis of the Behavior of Fission Product Gas in Solid Fast Reactor Oxide Fuel Under Transient Heating Conditions
Author: José Walderley Coêlho Dias
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 472
Book Description
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 472
Book Description
Aspects of Nuclear Reactor Safety
Author: Peter von der Hardt
Publisher: Harwood Academic Publishers
ISBN: 9783718600168
Category : Technology & Engineering
Languages : en
Pages : 664
Book Description
Publisher: Harwood Academic Publishers
ISBN: 9783718600168
Category : Technology & Engineering
Languages : en
Pages : 664
Book Description
The Behavior of Fission-Gas in Fuels
Steady-state and Transient Fission Gas Release and Swelling Model for LIFE-4. [LMFBR].
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The fuel-pin modeling code LIFE-4 and the mechanistic fission gas behavior model FASTGRASS have been coupled and verified against gas release data from mixed-oxide fuels which were transient tested in the TREAT reactor. Design of the interface between LIFE-4 and FASTGRASS is based on an earlier coupling between an LWR version of LIFE and the GRASS-SST code. Fission gas behavior can significantly affect steady-state and transient fuel performance. FASTGRASS treats fission gas release and swelling in an internally consistent manner and simultaneously includes all major mechanisms thought to influence fission gas behavior. The FASTGRASS steady-state and transient analysis has evolved through comparisons of code predictions with fission-gas release and swelling data from both in- and ex-reactor experiments. FASTGRASS was chosen over other fission-gas behavior models because of its availability, its compatibility with the LIFE-4 calculational framework, and its predictive capability.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The fuel-pin modeling code LIFE-4 and the mechanistic fission gas behavior model FASTGRASS have been coupled and verified against gas release data from mixed-oxide fuels which were transient tested in the TREAT reactor. Design of the interface between LIFE-4 and FASTGRASS is based on an earlier coupling between an LWR version of LIFE and the GRASS-SST code. Fission gas behavior can significantly affect steady-state and transient fuel performance. FASTGRASS treats fission gas release and swelling in an internally consistent manner and simultaneously includes all major mechanisms thought to influence fission gas behavior. The FASTGRASS steady-state and transient analysis has evolved through comparisons of code predictions with fission-gas release and swelling data from both in- and ex-reactor experiments. FASTGRASS was chosen over other fission-gas behavior models because of its availability, its compatibility with the LIFE-4 calculational framework, and its predictive capability.
Theory of Fission Product Fractionation in Reactor Fuel Experiments
Experiments on the Release of Fission Products from Molten Reactor Fuels
Author: G. E. Creek
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 38
Book Description
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 38
Book Description