Published 2003
| Version v1
Computer medium
Fatigue effect of RCS branch line with thermal stratification
Description
The load due to the thermal stratification of branch lines, which are connected to reactor coolant system, has not been considered in the design stage. Thermal stratification has been identified as mechanical fluctuations have been observed in a number of operating power plants. Enhanced inspection program has been generally applied to maintain the integrity of these piping lines without any plant specific fatigue analysis. To evaluate the thermal load, in this study, three-dimensional analysis was performed for a branch line of reactor coolant system. In addition, a new supplemental methodology of fatigue effect was proposed based on the ASME Section NB-3000. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- ICONE-11: Proceedings of the 11th international conference on nuclear engineering
- Imprint Pagination
- [3610 p.]
- Journal Page Range
- [5 p.]
Conference
- Title
- 11. international conference on nuclear engineering
- Acronym
- ICONE-11
- Dates
- 20-23 Apr 2003
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 35045087
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FATIGUE; PIPES; PWR TYPE REACTORS; STRATIFICATION; THERMAL ANALYSIS; THERMAL STRESSES; TURBULENCE
- Descriptors DEC
- ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; STRESSES; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Track No. 03, Session 3-19, ICONE-36541; 8 refs., 7 figs., 1 tab.