This paper describes the fuel rod response in a pool type liquid metal fast breeder reactor, in shutdown natural convection heat removal. The fuel rod response is studied resorting to a finite element technique; the transient temperature and thermal stresses profiles are found.For this aim the code FENHT (Finite Element Nuclear Heat Transfer), has been developed: it is based on a one-dimensional three nodal finite element subdivion of the fuel rod and the solution of the pertinent heat transfer equations is performed by the Crank-Nicholson integration method. Although the strongly non linearities, arising from the thermal properties of the system and from the boundary conditions,the computing time is very low and the numerical solution isre...
Heat removal from fuel rods poses one of the primary considerations in reactor design. Fuel rod desi...
This paper presents capacity of the passive decay heat removal system (DHRS) operated under the natu...
The focus of the present research activity was the experimental and numerical investigations, aiming...
This paper describes the fuel rod response in a pool type liquid metal fast breeder reactor, in shut...
This paper describes the code capability related to the safety requirements in nuclear plants. The ...
Natural convection in enclosures have been studied numerically to provide insight into the scaling l...
Existing methods of thermal analysis of a wire wrapped rod bundle of a Liquid Metal Fast Breeder Rea...
The study, in situations involving accidents, of heat transfer in fuel rods is of known importance, ...
A numerical solution for two-dimensional transient thermal stresses in a liquid metal cooled nuclear...
The aim of this paper is to provide an analytical determination of temperature and thermal stress in...
AbstractIn this article we used ABAQUS software to study temperature and heat flux changes in a nucl...
The aim of this paper is to perform, by mean of the finite volume method, a numerical solution of th...
Sodium-cooled reactors (SFR) have always been recognized as one of the most promising candidates for...
Cooling of spent nuclear fuel rods are conventionally done using water as the coolant, however it in...
The purpose of this work was to develop and validate a design tool for the transients that are of in...
Heat removal from fuel rods poses one of the primary considerations in reactor design. Fuel rod desi...
This paper presents capacity of the passive decay heat removal system (DHRS) operated under the natu...
The focus of the present research activity was the experimental and numerical investigations, aiming...
This paper describes the fuel rod response in a pool type liquid metal fast breeder reactor, in shut...
This paper describes the code capability related to the safety requirements in nuclear plants. The ...
Natural convection in enclosures have been studied numerically to provide insight into the scaling l...
Existing methods of thermal analysis of a wire wrapped rod bundle of a Liquid Metal Fast Breeder Rea...
The study, in situations involving accidents, of heat transfer in fuel rods is of known importance, ...
A numerical solution for two-dimensional transient thermal stresses in a liquid metal cooled nuclear...
The aim of this paper is to provide an analytical determination of temperature and thermal stress in...
AbstractIn this article we used ABAQUS software to study temperature and heat flux changes in a nucl...
The aim of this paper is to perform, by mean of the finite volume method, a numerical solution of th...
Sodium-cooled reactors (SFR) have always been recognized as one of the most promising candidates for...
Cooling of spent nuclear fuel rods are conventionally done using water as the coolant, however it in...
The purpose of this work was to develop and validate a design tool for the transients that are of in...
Heat removal from fuel rods poses one of the primary considerations in reactor design. Fuel rod desi...
This paper presents capacity of the passive decay heat removal system (DHRS) operated under the natu...
The focus of the present research activity was the experimental and numerical investigations, aiming...