The development of the design method of nuclear piping system supported by elasto-plastic support structures (Part 1)
Creators
- 1. Japan Atomic Power Co. (Japan)
- 2. Hitachi Works, Hitachi Ltd. (Japan)
- 3. Toshiba Corporation (Japan)
- 4. Mitsubishi Heavy Industries, Ltd. (Japan)
- 5. Hitachi Engineering Co. Ltd. (Japan)
- 6. Ishikawajima-Harima Heavy Industries Co. Ltd. (Japan)
- 7. Mitsubishi Atomic Power Industries, Inc. (Japan)
Description
The conventional aseismic design method of nuclear piping system is very conservative because of the accumulation of various safety factors in the design process, and nuclear piping systems are thought to have a large safety margin. Considering this situation, we promoted research to further rationalize nuclear power plants by reducing the amount of support structures and reducing the piping seismic response through vibration energy absorption resulting from the elasto-plastic behavior of piping support structures. The research has the following three stages. In the first stage, we select conventional piping support structures in Japanese light-water reactors that exhibit elasto-plastic behavior, and study the displacement dependency and the vibration frequency dependency on the stiffness and the energy absorption by testing their model. In the second stage, we make a piping test model with support structures whose characteristics have already been obtained, and perform vibration tests on a shaking table. In this way, we analyze the piping vibration characteristics by sinusoidal wave sweep tests and the piping response characteristics by seismic wave vibration tests, when the support structures are in an elasto-plastic condition. In the third stage, a general method is developed to evaluate the characteristics of the support structures obtained in the tests and it is applied to the evaluation of the characteristics of general support structures. A simplified analysis method is developed to evaluate the piping seismic response using the piping model test result. To expand the results mentioned above, we are developing a seismic design method of piping systems that allows support structures to have elasto-plastic behaviour. This paper reports the results of experiments conducted under the joint research program of Japanese electric power companies with support elements in the first stage and those with piping models in the second stage
Additional details
Publishing Information
- Publisher
- Elsevier
- Imprint Place
- Amsterdam (Netherlands)
- ISBN
- 0-444-81515-5
- Imprint Title
- Transactions of the 12. international conference on Structural Mechanics in Reactor Technology (SMiRT). Volume K2: Seismic response analysis and design
- Imprint Pagination
- 400 p.
- Journal Page Range
- p. 193-198
Conference
- Title
- 12. international conference on Structural Mechanics in Reactor Technology
- Acronym
- SMiRT 12
- Dates
- 15-20 Aug 1993
- Place
- Stuttgart (Germany)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36032964
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ELASTICITY; FLEXIBILITY; MECHANICAL TESTS; MECHANICAL VIBRATIONS; PIPES; PLASTICITY; REACTOR COOLING SYSTEMS; SAFETY MARGINS; SEISMIC EFFECTS; SEISMIC ISOLATION; SUPPORTS; WATER COOLED REACTORS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL STRUCTURES; REACTOR COMPONENTS; REACTORS; TENSILE PROPERTIES; TESTING; TUBES
Optional Information
- Notes
- 13 figs, 1 tab