Development of a thermal striping spectrum for use in evaluating pressurizer surge line fatigue
Creators
- 1. Structural Integrity Associates, Inc., San Jose, CA (USA)
- 2. Battelle Inst., Frankfurt (Germany, F.R.)
- 3. Electric Power Research Inst., Palo Alto, CA (USA)
Description
Data taken from the German HDR test facility have been evaluated to understand the thermal-hydraulic phenomena which occur during conditions of stratified flow in a pressurizer surge line. The temperature oscillations in the fluid layer between the hot and cold fluids can approach the maximum possible top-to-bottom temperature differential. The temperature oscillation at the pipe wall is considerably less than that in the fluid, being no more than about 50 percent of the maximum possible temperature difference. The location of this fluid interface changes with changing flow rate in the pipe. At lower flow rates, the magnitude of the temperature fluctuations decrease significantly. The ordered overall range pair cycle counting approach was used to determine pipe surface temperature fluctuation spectra. Stress analysis was conducted to determine the fatigue usage resulting from the developed spectra. This evaluation, conducted for typical plant startup operating conditions (surge line temperatures and flows), shows that thermal striping fatigue usage will be minimal
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (USA)
- ISBN
- 0-7918-0511-5
- Imprint Title
- Advances in dynamics of piping and structural components
- Imprint Pagination
- 83 p.
- Journal Page Range
- p. 23-28.
Conference
- Title
- 1990 pressure vessels and piping conference.
- Dates
- 17-21 Jun 1990.
- Place
- Nashville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22056077
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FATIGUE; HDR REACTOR; HYDRAULICS; PIPES; REACTOR SAFETY; STRESS ANALYSIS; TEMPERATURE DEPENDENCE; TEST FACILITIES; THERMODYNAMICS
- Descriptors DEC
- BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-900617--.