Development of Technology for Structural Integrity Evaluation
Description
The purpose of this study is a development of seismic safety and structural integrity evaluation method of the structure in the Nuclear Power plant (NPP). The purpose of 1st sub-Topic is the development and improvement of the seismic safety evaluation methodology for the Nuclear Power Plant structures and safety related equipment. The purpose of 2nd sub-topic is the increasing of structure and equipment seismic capacity through the reducing of seismic force. The purpose of 3rd sub-topic is the development of 3-D nonlinear finite element analysis program for prestressed concrete containment building. The last purpose if the evaluation of the failure mechanism of containment structure and structure capacity and the assessment of integrity of containment through the of leakage test. As a result of this research, there are many research results were produced. The scenario earthquake developing method was developed and the effect of the structures and equipment was analyzed. The effectiveness of isolation system was determined and optimum isolation systems for each equipment were selected. The NUCAS-3D program for the 3 dimensional numerical analysis of containment building using the embedded tendon element and rebar element was developed. The tension behavior of containment building was examined and the leakage rate of the concrete crack was determined. The results of this research can be successfully used for many fields of integrity of NPP site. It can be used for development of design earthquake for the seismic design and safety evaluation and establishment of seismic safety evaluation program and seismic capacity improvement program for existing NPP. In case of seismic isolation part, it can be used for the application to the selection of optimum isolation devices for equipment isolation and to the effective evaluation of each seismic isolation devices. In containment analysis part, it can be used for ultimate pressure capacity evaluation of prestressed concrete containment and safety assessment of containment building with aging material or structural damage. Finally, the ultimate pressure assessment of KSNP containment, basic data for containment failure criteria evaluation, basic data for design and authorization for containment and the tension failure behavior analysis of RC structure were possible for using the containment performance part
Availability note (English)
Available from INIS in electronic form; Also available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)Files
37104846.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 216 p.
- Report number
- KAERI/RR--2521/2004
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 37104846
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CONTAINMENT BUILDINGS; DESIGN; EVALUATION; NUCLEAR POWER PLANTS; PERFORMANCE TESTING; SAFETY; SEISMIC ISOLATION
- Descriptors DEC
- BUILDINGS; CONTAINMENT; NUCLEAR FACILITIES; POWER PLANTS; TESTING; THERMAL POWER PLANTS
Optional Information
- Notes
- 26 refs, 175 figs, 32 tabs