Introduction to Generation IV nuclear reactors

Investigation of microstructure and liquid lead corrosion behavior of a Fe-18Ni-16Cr-4Al base alumina-forming austenitic stainless steel

“…In the near future, a number of advanced energy systems will operate at a rather high temperature level in order to improve the thermal efficiency and decrease the CO 2 emission. For example, the service temperature of ultrasupercritical power plant will increase from the current level of 600°C to 700°C [1], some advanced nuclear energy systems will also operate at temperature between 600 to 700°C [2]. It is important to develop new grade high temperature steels for the core component application in these energy systems, as the strength of current applied steels cannot meet the service requirement if the operation temperature is higher than 600 to 650°C [3][4][5].…”

Investigation of the Cs2(Mo,Te)O4 Solid Solution and Implications on the Joint Oxyde-Gaine System in Fast Neutron Reactors

“…The Generation IV International Forum is currently investigating innovative nuclear reactor designs which should lead to improved safety, sustainability, and efficiency. 1 Among the considered designs, fast neutron reactors (FNRs), such as the sodium-cooled and lead-cooled reactors, are very promising as they would allow achieving higher thermal efficiencies than currently used Light-Water Reactors (LWRs), by operating at higher temperatures. Mixed uranium–plutonium oxide (or MOX) pellets, enclosed inside a stainless steel cladding, are currently the preferred choice for the fuel in these reactors.…”

Dual layer SiC coating on matrix graphite sphere prepared by pack cementation and fluidized‐bed chemical vapor deposition

“…Matrix graphite (MG) is one of the most important and main composition materials of the spherical fuel elements of pebble‐bed high‐temperature gas‐cooled reactors, which can maintain its excellent mechanical and thermal properties in high‐temperature environments . According to the next‐generation nuclear plants’ statements, inherent safety is one of the most important features of the HTGRs . Intrusion of water or air into the reactor core systems does not result in substantive degradation of the capability to contain radioactive materials and maintain a shutdown condition.…”