Amanote Research
Register
Sign In
Selection of 347 Stainless Steel for Use in the Pm-1 Reactor Pressure Vessel
doi 10.2172/4141723
Full Text
Open PDF
Abstract
Available in
full text
Date
November 1, 1959
Authors
C. Canitz
Publisher
Office of Scientific and Technical Information (OSTI)
Related search
Low Activation-Modified High Manganese-Nitrogen Austenitic Stainless Steel for Fast Reactor Pressure Vessel Cladding
Nuclear Science
Creep of 347 Stainless Steel in Hydrogen. Final Report
Feasibility Study for Inplace Annealing of the Pm-2a Reactor Vessel
Master Order of HRP Grade 347 Stainless Steel
Toughness Evaluation of 1/2 Mo Steel Using for Pressure Vessel
Tetsu-To-Hagane/Journal of the Iron and Steel Institute of Japan
Alloys
Condensed Matter Physics
Metals
Theoretical Chemistry
Materials Chemistry
Physical
Evaluation Technique of Neutron-Irradiation Embrittlement in Welded Light Water Reactor Pressure Vessel Steel.
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
3d-Ap Observation of Nano-Carbides in Surveillance Test Specimen of Nuclear Reactor Pressure Vessel Steel
Materia Japan
Redistribution of Residual Stress by Thermal Shock in Reactor Pressure Vessel Steel Clad With Nickel Alloy
International Journal of Pressure Vessels and Piping
Mechanics of Materials
Materials Science
Mechanical Engineering
Creep Properties of a Type 308 Stainless Steel Pressure Vessel Weld With Controlled Residual Elements
