Controlled biaxial strain-rate test results from unirradiated 20% CW 316 stainless steel cladding at constant temperature

Conference · Mon Jan 01 00:00:00 EST 1979

OSTI ID:6303708

Cannon, N. S.

Constant temperature controlled biaxial strain-rate (CBSR) tests were performed on unirradiated 20% CW 316 stainless steel reactor cladding. Tests were made at hoop strain-rates of 1.2 x 10/sup -5//s, 1.2 x 10/sup -4//s, 6 x 10/sup -4//s, and 1.2 x 10/sup -3//s. For each of these strain rates, tests were performed at 425/sup 0/C, 540/sup 0/C, and 650/sup 0/C. The data from these tests are examined and compared with previously reported tensile data. A simple relationship between tensile and CBSR tests is developed, allowing easy correlation of the CBSR results.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 6303708
• Report Number(s): HEDL-SA-1746-FP; CONF-790219-8; TRN: 79-013690
• Resource Relation: Conference: AIME annual meeting, New Orleans, LA, USA, 18 Feb 1979
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
FUEL CANS
REACTOR MATERIALS
TENSILE PROPERTIES
STAINLESS STEEL-316
STRAIN RATE
PERFORMANCE TESTING
STRAINS
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
STAINLESS STEELS
STEELS
TESTING
220300* - Nuclear Reactor Technology- Fuel Elements
360103 - Metals & Alloys- Mechanical Properties