Rapid heating tensile tests of hydrogen-charged high-energy-rate-forged 316L stainless steel

Technical Report · Fri May 19 04:00:00 EDT 1989

DOI:https://doi.org/10.2172/5734840· OSTI ID:5734840

Mosley, W C

316L stainless steel is a candidate material for construction of equipment that will be exposed to tritium. Proper design of the equipment will require an understanding of how tritium and its decay product helium affect mechanical properties. This memorandum describes results of rapid heating tensile testing of hydrogen-charged specimens of high-energy-rate-forged (HERF) 316L stainless steel. These results provide a data base for comparison with uncharged and tritium-charged-and-aged specimens to distinguish the effects of hydrogen and helium. Details of the experimental equipment and procedures and results for uncharged specimens were reported previously. 3 refs., 10 figs.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 5734840
• Report Number(s): WSRC-RP-89-268; SRL-HTS--89-0022; ON: DE90000591
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
ALLOYS
AUSTENITIC STEELS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
ELONGATION
EMBRITTLEMENT
HEAT RES
HIGH ALLOY STEELS
HYDROGEN EMBRITTLEMENT
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
MATERIALS TESTING
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
STAINLESS STEEL-316L
STAINLESS STEELS
STEEL-CR17NI12MO3-L
STEELS
TESTING
TRITIUM
ULTIMATE STRENGTH
YEARS LIVING RADIOISOTOPES