Add to ORKGAn experimental study was made of the self-welding of various combinations of FBR materials (304 ss, Inconel 718, A286, Stellite 156, and Stellite 6) in sodium at 800 to 1100$sup 0$F for time periods up to 6 months and contact stresses of 2 to 148 ksi. Stresses required to separate the surfaces were determined. Self-welding was observed only at temperatures of 1050$sup 0$F and above, with the breakaway force being less than 5 ksi. (DLC
AbstractAustenitic stainless steels (SS) with appropriate mechanical and irradiation-resistant prope...
The property requirements for breeder reactor fuel cladding materials are extremely stringent. Alloy...
In the next-generation fast breeder reactor, improved 9Cr-1Mo steel and molten sodium will be used a...
This report gives a description of the activities in design, fabrication, construction, and assembli...
In the sodium fast reactors envisioned in the Generation IV program, fuel pins are expected to be ir...
Available information on the corrosion behavior and mechanical properties of structural materials in...
Design requirements for low friction materials in FFTF have led to an experimental sodium compatibil...
A sodium–water reaction takes place when high-pressured water vapor leaks into sodium through a tiny...
The friction, wear, and corrosion performance of several metallurgical coatings in 200 to 650/sup 0/...
Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer heat fr...
Measurements of the reaction of methane with sodium have been extended to 1400°F, where 100 ppm in h...
The alloys 316L(N) and Mod. 9Cr-1Mo steel are the major structural materials for fabrication of stru...
Metallographic evaluations of the CRBR core barrel forging material, creep rupture tested at 538/sup...
AbstractSodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer...
In Sodium Cooled Fast Reactors (SFRs), as a hypothetical Disruptive Core Accident (DCA) occurs, the ...
AbstractAustenitic stainless steels (SS) with appropriate mechanical and irradiation-resistant prope...
The property requirements for breeder reactor fuel cladding materials are extremely stringent. Alloy...
In the next-generation fast breeder reactor, improved 9Cr-1Mo steel and molten sodium will be used a...
This report gives a description of the activities in design, fabrication, construction, and assembli...
In the sodium fast reactors envisioned in the Generation IV program, fuel pins are expected to be ir...
Available information on the corrosion behavior and mechanical properties of structural materials in...
Design requirements for low friction materials in FFTF have led to an experimental sodium compatibil...
A sodium–water reaction takes place when high-pressured water vapor leaks into sodium through a tiny...
The friction, wear, and corrosion performance of several metallurgical coatings in 200 to 650/sup 0/...
Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer heat fr...
Measurements of the reaction of methane with sodium have been extended to 1400°F, where 100 ppm in h...
The alloys 316L(N) and Mod. 9Cr-1Mo steel are the major structural materials for fabrication of stru...
Metallographic evaluations of the CRBR core barrel forging material, creep rupture tested at 538/sup...
AbstractSodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer...
In Sodium Cooled Fast Reactors (SFRs), as a hypothetical Disruptive Core Accident (DCA) occurs, the ...
AbstractAustenitic stainless steels (SS) with appropriate mechanical and irradiation-resistant prope...
The property requirements for breeder reactor fuel cladding materials are extremely stringent. Alloy...
In the next-generation fast breeder reactor, improved 9Cr-1Mo steel and molten sodium will be used a...