The development of design method of nuclear piping system supported by elasto-plastic support structures (part 2)
Creators
- 1. Japan Atomic Power Co., Tokyo (Japan)
- 2. Hitachi Ltd., Ibaraki (Japan). Hitachi Works
- 3. Toshiba Corp., Yokohama (Japan)
- 4. Mitsubishi Heavy Industries Ltd., Nagasaki (Japan)
- 5. Hitachi Engineering Co. Ltd., Ibaraki (Japan)
- 6. Ishikawajima-Harima Heavy Industries Co. Ltd., Yokohama (Japan)
Description
The conventional seismic 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 situations, research program was promoted to furthermore rationalize nuclear power plants by reducing the amount of support structures and reducing the piping's seismic response through vibration energy absorption resulting from the elasto-plastic behavior of piping support structures. The research had the following three stages. In the first stage, we selected conventional piping support structures in light-water reactors that exhibited elasto-plastic behavior, and studied the effect of displacement and the vibration frequency on the stiffness and on the energy absorption by testing these models. In the second stage, vibration tests were performed using piping models with support structures on shaking tables. The piping vibration characteristics were clarified by sinusoidal sweep tests and the piping response characteristics by seismic wave vibration tests when the support structures were in an elasto-plastic condition. In the third stage, a general method was developed to evaluate the characteristics of a variety of support structures in the tests. A simplified analysis method was also developed to evaluate the piping seismic response using the piping model test result. To expand the results mentioned above, we also established a new seismic design method of piping systems that allowed support structures to have elasto-plastic behavior. This paper reports the newly developed seismic design method based on the results of experiments conducted under the joint research program of Japanese electric power companies (The Japan Atomic Power Co., Hokkaido EPC, Tohoku EPC, Tokyo EPC, Chubu EPC, Hokuriku EPC, Kansai EPC, Chugoku EPC, Shikoku EPC, Kyushu EPC) and nuclear plant makers (Hitachi Ltd., Toshiba Co., MHI Ltd., HEC Ltd. and IHI). (author). 1 ref., 9 figs., 2 tabs
Additional details
Publishing Information
- Publisher
- Editora de Universidade Federal do Rio Grande do Sul.
- Imprint Place
- Porto Alegre, RS (Brazil)
- ISBN
- 85-7025-351-6
- Imprint Title
- Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 3
- Imprint Pagination
- 647 p.
- Journal Page Range
- p. 459-464.
Conference
- Title
- 13. International Conference on Structural Mechanics in Reactor Technology.
- Dates
- 13-18 Aug 1995.
- Place
- Porto Alegre, RS (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 27053991
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S58: GEOSCIENCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DUCTS; EARTHQUAKES; ELASTICITY; GROUND MOTION; NUCLEAR POWER PLANTS; PIPELINES; PIPES; RESTRAINTS; RISK ASSESSMENT; SAFETY; SEISMIC EFFECTS; SEISMIC EVENTS; SEISMOLOGY; SOIL-STRUCTURE INTERACTIONS; STRAINS; SUPPORTS; TUBES
- Descriptors DEC
- MECHANICAL PROPERTIES; MECHANICAL STRUCTURES; MOTION; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Notes
- Imprint:Conference organized by the International Association for Structural Mechanics in Reactor Technology and Universidade Federal do Rio Grande do Sul.