Abstract: A method for operating a nuclear reactor in order to produce electricity, such that the reactor is controlled so that, during a transient power occurrence for at least one of: a linear power density of the nuclear fuel rod remains lower than a limit linear power density, the limit linear power density being greater than 430 W/cm, and a variation of linear power density of the nuclear fuel rod remains lower than a limit variation, the limit variation being greater than 180 W/cm.

Abstract: The present invention relates to a fuel rod for a nuclear plant and a plenum spring arranged to be provided in a fuel rod. The fuel rod (1) comprises a cladding tube (2) sealed at its ends by end plugs (3, 4), a plurality of fuel pellets (5) stacked on each other inside the cladding tube (2) such that they form a column of pellets and said plenum spring (6) arranged to hold with a spring force the column of pellets against the lower second end of the cladding tube (2) during operation. The plenum spring (6) comprises a first length variable part (8) which abuts the uppermost located fuel pellet (5) in the column of pellets with an end portion (9), a second part (10) which allows engagement of the plenum spring (6) against an inner surface of the cladding tube (2) by a radially outwardly directed pressure and a third part (11) which allows releasing of the second part (10) of the plenum spring (6) in the cladding tube (2) during operation of the nuclear plant.

Abstract: Method of fabricating a fuel rod, comprising providing an effective amount of a metal oxide in the fuel rod to generate steam and mitigate the tendency for secondary hydriding. Fuel rods fabricated according to the method of the invention are also provided.

Abstract: A method of controlling the gas atmosphere in a welding chamber includes detecting the absence of a fuel rod from the welding chamber and, in response thereto, initiating the supplying of a flow of argon gas to the chamber to purge air therefrom. Further, the method includes detecting the entry of a fuel rod in the welding chamber and, in response thereto, terminating the supplying of the flow of argon gas to the chamber and initiating the supplying of a flow of helium gas to the chamber to purge argon gas therefrom and displace the argon gas in the chamber. Also, the method includes detecting the withdrawal of the fuel rod from the welding chamber and, in response thereto, terminating the supplying of the flow of helium gas to the chamber and initiating the supplying of argon to the chamber to purge the air therefrom.

Abstract: A nuclear fuel assembly comprising a plurality of fuel rods, each fuel rod comprising a cladding tube closed at both ends and filled with cylindrical nuclear fuel pellets such as sintered uranium dioxide or uranium plutonium dioxide. All or nearly all of the cylindrical pellets are coated with a refractory boride coating of sufficient thickness to prevent mechanical interaction between the pellets and the tube. The isotopic composition of the boron in the refractory boride is adjusted for each batch of fuel pellets, rods, or assemblage of rods so that the initial excess reactivity, k, of the batch, when assembled in a reactor core, is nearly zero.

Abstract: A nuclear fuel rod has a sheath closed by end plugs and a stack of fuel pellets in the sheath. The stack is retained in abutment against one of the end plugs during handling of the fuel rod by a radially expandable element having a cross-sectional area in rest condition such as it frictionally engages an internal surface of said sheath. When the fuel rod is brought to the reactor operating temperature, the radially expandable element is contracted clear of frictional contact by temperature responsive means of a shape memory alloy operatively associated with said radially expandable element and having a transformation temperature above atmospheric temperature.