Irradiation effects on reactor structural materials. Semiannual progress report, 1 August 1974--31 January 1975

Technical Report · Sat Feb 01 04:00:00 EST 1975

OSTI ID:7346636

Steele, L E

This report, covering research for the period, 1 August 1974 - 31 January 1975 includes: (1) the effect of hold time on fatigue crack propagation in neutron irradiated 20% cold worked Type 316 stainless steel; (2) high fluence assessments of 0.03% copper plate from 30-ton A533-B demonstration melt; (3) examination of microstructures of Inconel 718, Incoloy 800, PH13-8Mo, Mo and Nb after irradiation in EBR-II; (4) fluence dependence of ion damage in nickel; (5) ion-simulated irradiation-induced creep of reactor structural alloys; and (6) notch ductility and strength of Type 316 stainles steel submerged arc weld deposits. (GRA)

• Research Organization: Naval Research Lab., Washington, D.C. (USA)
• OSTI ID: 7346636
• Report Number(s): AD-A-010510; NRL-MR-3010
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BEAMS
CARBON STEELS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DUCTILITY
ELEMENTS
HEAT RESISTING ALLOYS
INCOLOY 800
INCOLOY ALLOYS
INCONEL 718
INCONEL ALLOYS
ION BEAMS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL PROPERTIES
METALS
MOLYBDENUM ALLOYS
NEUTRON BEAMS
NICKEL
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
NUCLEON BEAMS
PARTICLE BEAMS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STAINLESS STEEL-316
STAINLESS STEELS
STEEL-ASTM-A533-B
STEELS
TENSILE PROPERTIES
TRANSITION ELEMENTS
WELDED JOINTS
YIELD STRENGTH