The creep rupture data in this collection were determined for the high temperature reactor projects (the direct cycle helium turbine project, the nuclear process heat project and the district heating
This work investigates the quality of the ENDF 56 Fe cross-section libraries for describing the transport of fast neutrons in iron. We have used the D(d,n) 3 He reaction with a puls
The Alloy 617 creep rupture data were determined for the high temperature reactor projects (the direct cycle helium turbine project, the nuclear process heat project and the district heating project)