Abstract: Chemical thermodynamics and transport processes are inextricably linked in light-water reactor fuel rods. Two regimes can be identified, separated by their temperatures. During normal operation, the temperature at the center of the U02 pellet usually does not exceed lOOOOC, and most of the important chemistry takes place at the periphery, which is separated from the Zircaloy cladding by a thin(tens of microns) gas-filled gap. The temperatures here are typically 350-6OOOC. In a serious accident resulting in loss of cooling water circulating in the reactor's primary circuit, Severe fuel damage may occur. Conditions in this regime encompass temperatures from-1000 to 3000OC, the state of water is steam rather than liquid, and the...
The zirconium cladding in typical light-water reactor nuclear fuels oxidizes during normal operation...
This paper presents an investigation of transient heat transfer, which may occur in nuclear reactors...
The paper describes which chemical interactions may occur in a LWR fuel rod bundle containing (Ag, I...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
The analysis of the behavior of light water reactor (LWR) fuel rods is described.The properties of r...
Improvement of the nuclear fuel exploitation has been one of the main objectives of reactor technolo...
This chapter briefly describes the fundamental concepts of heat transfer and hydraulic resistance in...
This chapter briefly describes the fundamental concepts of heat transfer and hydraulic resistance in...
Heat removal from fuel rods poses one of the primary considerations in reactor design. Fuel rod desi...
The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element ...
Selected values are presented for the high temperature physical and mechanical properties of fuel el...
A series of separate-effects tests is being carried out on Zircaloy PWR fuel rod cladding to study t...
International audienceThe ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF...
International audienceThe ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF...
In a nuclear reactor severe accident, fission products, after release from the fuel, along with rela...
The zirconium cladding in typical light-water reactor nuclear fuels oxidizes during normal operation...
This paper presents an investigation of transient heat transfer, which may occur in nuclear reactors...
The paper describes which chemical interactions may occur in a LWR fuel rod bundle containing (Ag, I...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
The analysis of the behavior of light water reactor (LWR) fuel rods is described.The properties of r...
Improvement of the nuclear fuel exploitation has been one of the main objectives of reactor technolo...
This chapter briefly describes the fundamental concepts of heat transfer and hydraulic resistance in...
This chapter briefly describes the fundamental concepts of heat transfer and hydraulic resistance in...
Heat removal from fuel rods poses one of the primary considerations in reactor design. Fuel rod desi...
The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element ...
Selected values are presented for the high temperature physical and mechanical properties of fuel el...
A series of separate-effects tests is being carried out on Zircaloy PWR fuel rod cladding to study t...
International audienceThe ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF...
International audienceThe ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF...
In a nuclear reactor severe accident, fission products, after release from the fuel, along with rela...
The zirconium cladding in typical light-water reactor nuclear fuels oxidizes during normal operation...
This paper presents an investigation of transient heat transfer, which may occur in nuclear reactors...
The paper describes which chemical interactions may occur in a LWR fuel rod bundle containing (Ag, I...