Scoping calculations for TMI-2 lower head instrument tube failure
Creators
- 1. Idaho National Engineering Lab., Idaho Falls, ID (United States)
Description
Tube ejection and tube rupture were both examined as possible failure mechanisms of the TMI-2 instrument tubes. Failures by creep or from exceeding the ultimate strength of the tube material were considered for both mechanisms. Metallurgical examinations indicated that welds did not melt; therefore, margins to failure for the weld were calculated. Tube weld failure results show large margins to failure, making a tube ejection analysis unnecessary. Temperature and pressure conditions in ex-vessel tubes were required for the tube rupture analysis. Evaluation of melt flow through the tubes revealed that melt did not penetrate outside the lower head. Thus, ex-vessel tube failure analyses used coolant temperatures, along with an appropriate pressure condition. A force equilibrium calculation showed that very large margins to failure exist for tube rupture. 4 figs., 13 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. 349-361.
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
- 26008552
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORIUM; FAILURE MODE ANALYSIS; FAILURES; FRACTURE MECHANICS; GUIDE TUBES; MATHEMATICAL MODELS; MELTDOWN; NOZZLES; REACTOR VESSELS; THERMAL STRESSES; THREE MILE ISLAND-2 REACTOR
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENRICHED URANIUM REACTORS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; STRESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS