Published March 2005 | Version v1
Report Open

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)

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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