SciTech Connect

Title: Examination of relocated fuel debris adjacent to the lower head of the TMI-2 reactor vessel

Examination of relocated fuel debris adjacent to the lower head of the TMI-2 reactor vessel As part of the Three Mile Island Unit 2 (TMI-2) Vessel Investigation Project, funded by the Organization for Economic Cooperation and Development, physical, metallurgical, and radiochemical examinations were performed on samples of previously molten material that had relocated to the lower plenum of the TMI-2 reactor during the accident of 28 March 1979. This report presents the results of those examinations and some limited analysis of these results as required for the interpretation of the data. Principal conclusions of the examinations are that the bulk lower head debris is homogeneous and composed primarily of (U,Zr)O{sub 2}. This molten material reached temperatures greater than 2,600 C and probably reached the lower head as a liquid or slurry at temperatures below the peak temperature. A debris bed was formed, which was composed of particular debris above a monolithic melt that solidified on the lower head.
Authors: ; ;
Publication Date:
OSTI Identifier:OSTI ID: 10140801
Report Number(s):NUREG/CR--6195; EGG--2732
ON: TI94009590; IN: TMI V(92)EG10; TRN: 94:007558
DOE Contract Number:AC07-76ID01570
Resource Type:Technical Report
Resource Relation:Other Information: PBD: Mar 1994
Research Org:Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Org:Nuclear Regulatory Commission, Washington, DC (United States)
Country of Publication:United States
Language:English
Subject: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; THREE MILE ISLAND-2 REACTOR; CORIUM; CHEMICAL COMPOSITION; REACTOR ACCIDENTS; SAMPLING; METALLURGY; SCANNING ELECTRON MICROSCOPY; RADIOCHEMICAL ANALYSIS; METALLOGRAPHY; MICROSTRUCTURE; URANIUM OXIDES; THORIUM OXIDES; DENSITY; EXPERIMENTAL DATA 220900; 210200; REACTOR SAFETY; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED