ASME STP-NU-035
Click here to purchase The tensile, creep and stress-rupture databases for alloy 800H (UNS N08810) were assembled and analyzed with the intent of extending the allowable stresses in ASME Section III, Subsection NH for service…
ASME STP-NU-037
Click here to purchase The current operating condition allowable stresses provided in ASME Section III, Subsection NHwere reviewed for consistency with the criteria used to establish the stress allowables and with theallowable stresses provided in…
ASME STP-NU-038
Click here to purchase This report reviews the current experience on various high temperature reactor intermediate heatexchanger (IHX) concepts. There are several different IHX concepts that could be envisioned forHTR/VHTR applications in a range of…
ASME STP-NU-039
Click here to purchase The GEN IV reactor concepts require structural components to operate at high temperatures in aregime where creep damage may occur and cracks may grow. The U.S. Nuclear RegulatoryCommission (NRC) has identified…
ASME STP-NU-040
Click here to purchase This report provides technical information necessary to update and expand appropriate ASME materials, construction and design codes for application in future Gen IV nuclear reactor systems that operate at elevated temperatures.…
ASME STP-NU-041
Click here to purchase STP-NU-018 [3] investigated existing creep-fatigue rules to improve the provisions on creep-fatigueevaluation of Mod.9Cr-1Mo steel in Subsection NH of ASME Boiler and Pressure Vessel CodeSection III [1]. All the rules investigated…
ASME STP-NU-042
Click here to purchase This report reviews the available information on Hastelloy XR and Inconel 617 materials. The bounding conditions were briefly summarized for the Next Generation Nuclear Plant (NGNP) that is the leading candidate…
ASME STP-NU-044
Click here to purchase This report identifies several Non Destructive Examination (NDE) technologies of advanced monitoring, diagnostics and prognostics systems (e.g., acoustic emission, ultrasonic, advanced material characterization) applicable to components of High Temperature Gas-cooled Reactors…
ASME STP-NU-045-1
Click here to purchase The Roadmap has been developed as a guide to the R&D and Code development tasks that could be considered in developing rules for High Temperature Gas-Cooled Reactors (HTGR). The primary focus…