Mechanical properties and examination of cracking in TMI-2 pressure vessel lower head material

Conference · Wed Sep 01 00:00:00 EDT 1993

OSTI ID:10188801

Diercks, D R; Neimark, L A

Mechanical tests have been conducted on material from 15 samples removed from the lower head of the Three Mile Island unit 2 nuclear reactor pressure vessel. Measured properties include tensile properties and hardness profiles at room temperature, tensile and creep properties at temperatures of 600 to 1200{degrees}C, and Charpy V-notch impact properties at {minus}20 to +300{degrees}C. These data, which were used in the subsequent analyses of the margin-to-failure of the lower head during the accident, are presented here. In addition, the results of metallographic and scanning electron microscope examinations of cladding cracking in three of the lower head samples are discussed.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10188801
• Report Number(s): ANL/ET/CP-79638; CONF-9310111-1; ON: DE94001352; TRN: 93:023072
• Resource Relation: Conference: Conference and open forum for the presentation of significant results: achievements of the OECD Three Mile Island vessel investigation project,Boston, MA (United States),20-22 Oct 1993; Other Information: PBD: Sep 1993
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
THREE MILE ISLAND-2 REACTOR
PRESSURE VESSELS
TENSILE PROPERTIES
CREEP
CHARPY TEST
METALLOGRAPHY
CORIUM
REACTOR SAFETY
MELTDOWN
SAMPLING
CRACKS
210200
220900
360103
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MECHANICAL PROPERTIES