Published August 2017
| Version v1
Miscellaneous
Risk evaluation method for faults displacement by engineering approach. (4) The analysis evaluation of equipment and piping system
Creators
- 1. MHI Nuclear Systems and Solution Engineering Co., Ltd., Kobe, Hyogo (Japan)
- 2. Mitsubishi Heavy Industries, Ltd., Tokyo (Japan)
- 3. Japan Atomic Power Co., Tokyo (Japan)
Description
The structural integrity of equipment and piping systems to a fault displacement depends on the damage state of a reactor building. When there is no damage in a reactor building, the supporting function of equipment and piping systems is maintained. In this case, FEM analysis can estimate the allowable state of the entire system of the important safety equipment. In this part, an example of the analysis evaluation for the equipment and piping systems, which are important for safety, in the case of loading a fault displacement and the influence on reactor cooling system are discussed. An evaluation by superposition to a fault displacement and an earthquake is not discussed in this report. (author)
Additional details
Additional titles
- Original title (Japanese)
- 断層変位に対するリスク評価と工学的な対応策.(4) 機器・配管系の解析評価事例
Publishing Information
- Imprint Title
- Proceedings of the 14th annual meeting of Japan Society of Maintenology
- Imprint Pagination
- 580 p.
- Journal Page Range
- p. 119-124
Conference
- Title
- 14. annual meeting of Japan Society of Maintenology
- Dates
- 2-4 Aug 2017
- Place
- Matsuyama, Ehime (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 50008211
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONSTRUCTION; DYNAMIC LOADS; EARTHQUAKES; FINITE ELEMENT METHOD; GEOLOGIC FAULTS; GROUND MOTION; NUCLEAR POWER PLANTS; PIPES; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR SHUTDOWN; REGULATORY GUIDES; RISK ASSESSMENT; SHELL MODELS
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; DOCUMENT TYPES; ENERGY SYSTEMS; GEOLOGIC FRACTURES; GEOLOGIC STRUCTURES; MATHEMATICAL MODELS; MATHEMATICAL SOLUTIONS; MOTION; NUCLEAR FACILITIES; NUCLEAR MODELS; NUMERICAL SOLUTION; POWER PLANTS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; SAFETY; SEISMIC EVENTS; SHUTDOWN; THERMAL POWER PLANTS; TUBES
Optional Information
- Notes
- 11 refs., 14 figs., 3 tabs. Imprint:#65E5##672C##4FDD##5168##5B66##4F1A##7B2C#14#56DE##5B66##8853##8B1B##6F14##4F1A##8981##65E8##96C6#