RADIATION DAMAGE STUDIES PROGRAM. ETR LOOP MATERIALS PROGRESS REPORT III

Technical Report · Mon Sep 15 04:00:00 EDT 1958

OSTI ID:4299681

Watanabe, H T

The results are summarized of physical tests on irradiated materials that have some attraction for use in high-pressure equipment intended for operations in the reactor. The materials selected for test were 16-1 Croloy, Hastelloy-X, Inconel-702, Inconel-X (singleaged), Inconel-X (double-aged), K- Monel, 410 stainless steel, 414 stainless steel, AM-350 stainless steel and Zircaloy-2. In progress reports published to date on effects of neutron irradiation on these materials, it is conceded that most alloys will increase in strength and brittleness with increase in irradiation time. This paper will present the latest observations of these irradiation effects. (For preceding period see IDO16409.) (auth)

• Research Organization: Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-13-001784
• OSTI ID: 4299681
• Report Number(s): IDO-16475
• Country of Publication: United States
• Language: English

Related Subjects

ALUMINUM ALLOYS
BRITTLENESS
CHROMIUM ALLOYS
COPPER ALLOYS
CROLOY
ETR
HASTELLOY
IN PILE LOOPS
INCONEL ALLOYS
MATERIALS TESTING
MOLYBDENUM ALLOYS
MONEL
NEUTRONS
NICKEL ALLOYS
NIOBIUM ALLOYS
PRESSURE
RADIATION EFFECTS
RADIATION EFFECTS ON MATERIALS
REACTORS
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
TITANIUM ALLOYS
ZIRCALOY