Horizontal loading test by whole model specimen simulating inner concrete structure of PWR type nuclear power plant
Creators
- 1. Ohbayashi-Gumi Ltd., Osaka (Japan)
Description
The Nuclear Power Engineering Test Center has performed a horizontal loading test by a whole model specimen simulating the inner concrete structure of a PWR type nuclear power plant in order to investigate restoring force characteristics of reactor buildings. This report describes the results of examination of applicability to the test results of analysis methods based on elastic theory. The analysis results of elastic stiffness, concrete cracking load, rebar yielding loads and ultimate strength were compared with the test results. According to this examination, it is recognized that even these analysis methods based on elastic theory are comparatively effective for analysis of an inner concrete structure of fairly complex configuration, although there are limits of the scope of applicability. (author)
Additional details
Additional titles
- Subtitle (English)
- Examination of applicability to test results of evaluation methods based on elastic analysis
Publishing Information
- Journal Title
- Obayashi-Gumi Gijutsu Kenkyusho-Ho
- Journal Issue
- no.30
- Series
- Obayashi-Gumi Gijutsu Kenkyusho-Ho.
- ISSN
- 0385-9657
- CODEN
- OBGKA
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 17007052
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT BUILDINGS; CRACKS; DEFORMATION; ELASTICITY; FAILURES; FINITE ELEMENT METHOD; MECHANICAL STRUCTURES; MOCKUP; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; REACTOR VESSELS; REINFORCED CONCRETE; SIMULATION; STATIC LOADS; STRESS ANALYSIS; YIELD STRENGTH
- Descriptors DEC
- BUILDING MATERIALS; BUILDINGS; COMPOSITE MATERIALS; CONCRETES; CONTAINERS; CONTAINMENT; ENRICHED URANIUM REACTORS; MATERIALS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; REINFORCED MATERIALS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS