Abstract
Known disadvantages of high-dense α-U metal fuel (intense radiation growth and radiation swelling, poor compatibility with steel claddings) can be reduced to the minimum by "constructive" approaches based on mechanical restraint of radiation growth and swelling and also on application of protective layers on fuel columns and claddings. Effectiveness of these methods has been confirmed during irradiation of full-sized fuel pins with high-dense metal fuel (γeff≥12.5g h.a./cm3) in the BOR-60 and BN-350 reactors.
Highlights
Potential advantages of nuclear U-metal fuel over nonmetal fuels are well-known (Emelyanov and Evstyukhin, 1969) in such important initial parameters as: Density by heavy atoms Thermal conductivity During production technological effectiveness is high enough due to low strength and high plasticity of metal uranium at rather low temperatures Technological effectiveness is during postirradiation reprocessingActual differences of metal fuels from non-metal fuels are well-known in the following initial characteristics of practical importance: Intense radiation growth: ∆ (G = )) B, %
Known disadvantages of high-dense α-U metal fuel can be reduced to the minimum by “constructive” approaches based on mechanical restraint of radiation growth and swelling and on application of protective layers on fuel columns and claddings
Effectiveness of these methods has been confirmed during irradiation of full-sized fuel pins with high-dense metal fuel in the BOR-60 and BN-350 reactors
Summary
Potential advantages of nuclear U-metal fuel over nonmetal fuels (oxide, carbide, nitride) are well-known (Emelyanov and Evstyukhin, 1969) in such important initial parameters as:. Actual differences of metal fuels (in particular, highdense fuels with minimum content of alloying additives) from non-metal fuels are well-known in the following initial characteristics of practical importance:. These initial data of high-dense metal fuels are usually considered unfavorable and prevent their application in the BN reactors under conditions of successful operation of oxide, carbide and nitride fuel pins. This study deals with influence of some of these unfavorable initial properties characterizing high-dense metal fuels on radiation-thermal effects in experimental fuel pins as applied to their operation in the BN-type reactors to solve tasks inpro
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