ETR RADIATION DAMAGE SURVEILLANCE PROGRAMS. PROGRESS REPORT I

Technical Report · Fri Jan 27 04:00:00 EST 1961

OSTI ID:4077201

Graber, M J; Ronsick, J H

ABS>Data showing the change in mechanical properties of materials exposed to the neutron envirorment of the Engineering Test Reacter core are presented. The materials selected for testing, 2024, 6061, and 356 aluminum; Inconel X (single and double aged); Inconel 702; 17-4 PH, 304, 347, and AM-350 stainless steels; and Zircaloy-2, are those used for construction of reactor components and test facilities. The maximum radiation dosages received by the various materials ranged between 1.17 x lO/sup 20/ nvt ()1 Mev) for 6061 aluminum and 5.72 x lO/sup 21/ nvt ()1 Mev) for 304 stainless steel. (auth)

• Research Organization: Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-15-011705
• OSTI ID: 4077201
• Report Number(s): IDO-16628
• Country of Publication: United States
• Language: English

Related Subjects

ALUMINUM
ALUMINUM ALLOYS
CHROMIUM ALLOYS
COBALT ALLOYS
INCONEL ALLOYS
IRRADIATION
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
METALS, CERAMICS, AND OTHER MATERIALS
MOLYBDENUM ALLOYS
NEUTRON BEAMS
NICKEL ALLOYS
NIOBIUM ALLOYS
RADIATION DOSES
RADIATION EFFECTS
REACTORS
STAINLESS STEELS
TITANIUM ALLOYS
ZIRCALOY