In advanced nuclear systems, the chemical compatibility of the fuel and cladding is imperative for safe operation of a reactor. Therefore, it is essential to limit the interdiffusion between the fuel and cladding. To better understand the compatibility of metallic fuel and cladding at the highest possible operating temperatures in a sodium fast reactor, diffusion experiments were conducted at 700˚C using fuel alloys and various advanced stainless steel claddings that would be employed at these high temperatures. The various annealed diffusion couples were analyzed using scanning electron microscopy to investigate the kinetics of the fuel-cladding interactions and to identify the types of phases that formed. Relatively large diffusion zones ...
The swelling, corrosion and high-temperature embrittlement behavior of the fast-neutron sodium-coole...
The Reduced Enrichment for Research and Test Reactors (RERTR) program has been developing low enrich...
U-Mo alloys are being developed as low enrichment monolithic fuel under the Reduced Enrichment for R...
Advanced cladding materials are being considered for high-temperature applications in Generation IV ...
U-Zr metallic fuels cladded in Fe-alloys are being considered for application in an advanced sodium-...
One of the challenges facing the development of ultra-high burnup fast reactors, such as the Travell...
Monolithic fuel system with U-10 wt.% Mo (U10Mo) fuel alloy has been developed for the Materials Man...
Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technolog...
Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technolog...
Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technolog...
Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technolog...
Metallic nuclear fuels are being looked at as part of the Global Nuclear Energy Program for transmut...
Chemical interaction between TRIGA fuel and Type-304 stainless steel cladding at relatively high tem...
Interdiffusion experiments have been conducted to investigate the compatibility of various austeniti...
Metallic fuels are proposed for use in advanced sodium cooled fast reactors. The experience basis fo...
The swelling, corrosion and high-temperature embrittlement behavior of the fast-neutron sodium-coole...
The Reduced Enrichment for Research and Test Reactors (RERTR) program has been developing low enrich...
U-Mo alloys are being developed as low enrichment monolithic fuel under the Reduced Enrichment for R...
Advanced cladding materials are being considered for high-temperature applications in Generation IV ...
U-Zr metallic fuels cladded in Fe-alloys are being considered for application in an advanced sodium-...
One of the challenges facing the development of ultra-high burnup fast reactors, such as the Travell...
Monolithic fuel system with U-10 wt.% Mo (U10Mo) fuel alloy has been developed for the Materials Man...
Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technolog...
Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technolog...
Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technolog...
Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technolog...
Metallic nuclear fuels are being looked at as part of the Global Nuclear Energy Program for transmut...
Chemical interaction between TRIGA fuel and Type-304 stainless steel cladding at relatively high tem...
Interdiffusion experiments have been conducted to investigate the compatibility of various austeniti...
Metallic fuels are proposed for use in advanced sodium cooled fast reactors. The experience basis fo...
The swelling, corrosion and high-temperature embrittlement behavior of the fast-neutron sodium-coole...
The Reduced Enrichment for Research and Test Reactors (RERTR) program has been developing low enrich...
U-Mo alloys are being developed as low enrichment monolithic fuel under the Reduced Enrichment for R...