ASME STP-NU-019-1 PDF
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Verification of Allowable Stresses in ASME Section III Subsection NH for Grade 91 Steel
Description
STP-NU-019 Provides technical information to update and expand ASME materials, construction and design codes for application in Gen IV nuclear reactor systems.
View additional information document outcome derived agreement u.s. department energy (doe) asme standards technology, llc (asme st-llc) generation iv (gen iv) reactor materials project. provides technical necessary update expand appropriate materials, construction design codes application future gen nuclear systems operate elevated temperatures, emphasis grade 91 steel (9cr-1mo-v). stp-nu-019 systems.
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