Metallurgical examinations of TMI-2 nozzle and guide tube specimens
Creators
- 1. CEA Centre d'Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie
Description
Parts from nozzles and guide tubes were sent to CEA-Saclay for complementary metallurgical examinations in order to estimate the peak temperatures and the nature of thermal and chemical interaction between corium and nozzles or guide tube. Two nozzles and the guide tube appear to have been destructively affected by molten fuel whereas another piece of nozzle exhibited only limited damage to the instrumentation string. Inconel melting temperature (1400 deg C) was reached near the ablated end of examined nozzles. In addition to melting, nozzle degradation mechanisms were: Cr, Mn depletion due to extensive oxidation, chemical interaction with Al and Ti, penetration by Ag-In-Cd; as regards 304 SS guide tube, penetration by Mn-Cr-Si oxides and Ag-In-Cd as well as Cr, Mn, Si depletion. 6 figs., 6 tabs., 3 refs
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development.
- Imprint Place
- Paris (France)
- ISBN
- 92-64-14134-0
- Imprint Title
- Three Mile Island reactor pressure vessel investigation project. Achievements and significant results
- Imprint Pagination
- 402 p.
- Journal Page Range
- p. 239-253.
Conference
- Title
- Conference on Three Mile Island Vessel Investigation Project.
- Dates
- 20-22 Oct 1993.
- Place
- Boston (United States).
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 26008544
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CEA SACLAY; CORIUM; IN CORE INSTRUMENTS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; MELTDOWN; MELTING; METALLOGRAPHY; MICROSTRUCTURE; NOZZLES; NUCLEAR FUELS; OXIDATION; REACTOR VESSELS; SYSTEM FAILURE ANALYSIS; THERMAL SHOCK; THREE MILE ISLAND-2 REACTOR
- Descriptors DEC
- ACCIDENTS; CEA; CHEMICAL REACTIONS; CONTAINERS; CRYSTAL STRUCTURE; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FRENCH ORGANIZATIONS; FUELS; MATERIALS; NATIONAL ORGANIZATIONS; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; SYSTEMS ANALYSIS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS