Study of the behavior of thermal shield support system for the French CPO series plants
Creators
- 1. Electricite de France, Lyon (France)
- 2. Westinghouse Electric Corp., Pittsburgh, PA (United States). Systems and Major Products Div.
Description
Degradation/failure of thermal shield support system in PWRs has been observed in the US as well as in foreign plants. In almost all the cases, remedial actions were put in place at very high economic costs to the utilities only after the failures had occurred. This paper presents the results of a comprehensive study to predict the long term behavior of a thermal shield support system due to flow-induced vibratory loads and thermal transients. Excellent agreement from the system finite model between the measured plant test data on the barrel/thermal shield beam and shell mode frequencies and the flexure strains confirms the basic structural behavior and physics of the flow induced vibrations. Loads and stresses on the support bolts and the flexures were determined to predict the fatigue life of the components
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1784-9
- Imprint Title
- Fluid-structure interaction -- 1996. PVP-Volume 337
- Imprint Pagination
- 285 p.
- Journal Page Range
- p. 47-59.
Conference
- Title
- American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
- Dates
- 21-26 Jul 1996.
- Place
- Montreal (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28019026
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- FLUID-STRUCTURE INTERACTIONS; FRANCE; MECHANICAL VIBRATIONS; PWR TYPE REACTORS; SERVICE LIFE; SUPPORTS; SYSTEMS ANALYSIS; THEORETICAL DATA; THERMAL SHIELDS
- Descriptors DEC
- DATA; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; INFORMATION; LIFETIME; MECHANICAL STRUCTURES; NUMERICAL DATA; POWER REACTORS; REACTORS; SHIELDS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Secondary number(s)
- CONF-960706--.