Actions for Results of examinations of pressure vessel samples and instrument nozzles from the TMI-2 lower head [electronic resource].
Results of examinations of pressure vessel samples and instrument nozzles from the TMI-2 lower head [electronic resource].
- Published
- Paris : Organisation for Economic Co-operation and Development, 1993.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- 28 pages : digital, PDF file
- Additional Creators
- Argonne National Laboratory, Organisation for Economic Co-operation and Development, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- 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°C were attained during the accident in an elliptical shaped ``hot spot`` ≈1 × 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.
- Report Numbers
- E 1.99:anl/et/cp--81036
E 1.99: conf-931079--5
conf-931079--5
anl/et/cp--81036 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
10/01/1993.
"anl/et/cp--81036"
" conf-931079--5"
"DE94002375"
21. water reactor safety information meeting,Bethesda, MD (United States),25-27 Oct 1993.
Neimark, L.A.; Korth, G.E.; Diercks, D.R. - Funding Information
- W-31109-ENG-38
View MARC record | catkey: 14365912