Results of examinations of pressure vessel samples and instrument nozzles from the TMI-2 lower head
Creators
- 1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
- 2. Argonne National Lab., IL (United States)
Description
Fifteen prism-shaped steel samples were removed from the lower head of the damaged TMI-2 reactor pressure vessel to assess the effects of approximately 19 metric tons of molten core debris that had relocated there during the 1979 loss-of-coolant accident. Metallographic examinations of the samples revealed that inside surface temperatures of 800 to 1,100 degree C were attained during the accident in an elliptical shaped ''hot spot'' ∼1 x 0.7 m. Tensile, creep, and Charpy V-notch specimens were also cut from the samples to assess the mechanical properties of the lower head material at temperatures up to the peak accident temperature. These properties were used in a margin to failure analysis of the lower head. Examinations of instrument nozzles removed from the lower head region assisted in defining the relocation scenario of the molten core debris and showed that the lower head was largely protected from catastrophic failure by a solidified layer around the molten core debris that acted as a partial thermal insulator
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE94002375; NTIS; US Govt. Printing Office Dep.Files
25028903.pdf
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(869.7 kB)
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Additional details
Publishing Information
- Imprint Pagination
- 28 p.
- Report number
- ANL/ET/CP--81036
Conference
- Title
- Water reactor safety information meeting.
- Dates
- 25-27 Oct 1993.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25028903
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CORIUM; EXPERIMENTAL DATA; FAILURE MODE ANALYSIS; LOSS OF COOLANT; MATERIALS TESTING; MECHANICAL PROPERTIES; MELTING; NOZZLES; PRESSURE VESSELS; REACTOR INSTRUMENTATION; RELIABILITY; STAINLESS STEEL-308L; TEMPERATURE MEASUREMENT; THERMAL INSULATION; THREE MILE ISLAND-2 REACTOR
- Descriptors DEC
- ACCIDENTS; ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CONTAINERS; CORROSION RESISTANT ALLOYS; DATA; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; LOW CARBON-HIGH ALLOY STEELS; NICKEL ALLOYS; NUMERICAL DATA; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; STAINLESS STEELS; STEEL-CR20NI11-L; STEELS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States); Organization for Economic Co-Operation and Development (OECD), 75 - Paris (France).
- Secondary number(s)
- CONF-931079--5.