Criteria and guidelines for predicting concrete containment leakage

Technical Report · Sat Apr 01 04:00:00 EST 1989

OSTI ID:6343886

Dameron, R A; Dunham, R S; Rashid, Y R; Sullaway, M F

This report draws on five years of EPRI-sponsored research for developing a test validated methodology for predicting the overpressure behavior of concrete containments. The evidence discovered during this comprehensive research program points to leakage as the dominant failure mode for concrete containments, so the thrust of this report is to present the bases and justification of this failure mode and of the development of a simplified criteria for predicting concrete containment leakage. First, an overview of the experimental and analytical evidence is presented. Second, liner tearing mechanisms that have been exhibited in a variety of tests are examined in detail in order to postulate a simplified approach for predicting liner tearing. The simplified approach that has been developed consists of guidelines for performing simplified 2D analysis of containments to produce global liner strain predictions in the absence of structural discontinuities. These predictions are used with sets of curves of strain magnification factors which are due to strain concentration near structural discontinuities, strain gage length effects, and liner stress triaxiality conditions. The report gives examples of how the strain concentration factor curves were developed, and it describes step-by-step instructions for using the methodology along with a comprehensive example application for a reinforced concrete and a prestressed concrete containment. 16 refs., 58 figs.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA); ANATECH Research Corp., San Diego, CA (USA)
• OSTI ID: 6343886
• Report Number(s): EPRI-NP-6260-M
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
220900 -- Nuclear Reactor Technology-- Reactor Safety
A CODES
ACCIDENTS
BUILDING MATERIALS
COMPUTER CODES
CONCRETES
CONTAINERS
CONTAINMENT
DATA
DOCUMENT TYPES
EXPERIMENTAL DATA
FAILURE MODE ANALYSIS
INFORMATION
LEAKS
LOADING
MATERIALS
MATERIALS HANDLING
NUMERICAL DATA
PRESSURE VESSELS
PRESTRESSED CONCRETE
PROGRESS REPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR SAFETY
RECOMMENDATIONS
REINFORCED CONCRETE
REINFORCED MATERIALS
SAFETY
SCALE MODELS
STRAINS
STRESS INTENSITY FACTORS
STRUCTURAL MODELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS