Structural and stress analysis of nuclear piping systems
Description
The design of the strength of piping system is important in plant design, and its outline on the example of PWRs is reported. The standards and guides concerning the design of the strength of piping system are shown. The design condition for the strength of piping system is determined by considering the requirements in the normal operation of plants and for the safety design of plants, and the loads in normal operation, testing, credible accident and natural environment are explained. The methods of analysis for piping system are related to the transient phenomena of fluid, piping structure and local heat conduction, and linear static analysis, linear time response analysis, nonlinear time response analysis, thermal stress analysis and fluid transient phenomenon analysis are carried out. In the aseismatic design of piping system, it is desirable to avoid the vibration together with a building supporting it, and as a rule, to make it into rigid structure. The piping system is classified into high temperature and low temperature pipings. The formulas for calculating stress and the allowable condition, the points to which attention must be paid in the design of piping strength and the matters to be investigated hereafter are described. (Kako, I.)
Additional details
Publishing Information
- Journal Title
- Karyoku Genshiryoku Hatsuden
- Journal Volume
- 33
- Journal Issue
- 7
- Series
- Karyoku Genshiryoku Hatsuden.
- Journal Page Range
- 719-727
- ISSN
- 0387-1029
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 15006845
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- EARTHQUAKES; JAPAN; PIPELINES; PIPES; PLANNING; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RECOMMENDATIONS; SAFETY STANDARDS; SPECIFICATIONS; STRESS ANALYSIS; THERMAL STRESSES
- Descriptors DEC
- ASIA; COOLING SYSTEMS; DEVELOPED COUNTRIES; REACTOR COMPONENTS; REACTORS; SAFETY; STRESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS