Probability‐Based Design Criteria for Nuclear Plant Structures

Containment threats during severe accidents may arise due to fuel coolant interactions, hydrogen combustion, molten core-concrete interactions, and long-term pressure and temperature loading. The objective of the paper is to bring out important issues in the assessment of containment integrity during severe accidents for PWR and PHWR. The issues are identified by extensive review and synthesis of information from literature on severe accident phenomena, severe accident analysis and containment integrity assessment.

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“…Probability based structural analyses account for these variabilities/uncertainties in different ways [3,4,[31][32][33][34].…”

Section: A Probabilistic Structuralanalysismentioning

confidence: 99%

Issues on containment integrity during severe accidents

Bishnoi

Gupta

2010

2010 2nd International Conference on Reliability, Safety and Hazard - Risk-Based Technologies and Physics-of-Failure Methods (I

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“…Principal structural loads on NPPs have been identified in previous research to develop probability-based design criteria [7], and stochastic load models have been developed. The loads governing the design of major structural components and systems include dead load, operating live loads arising primarily from plant maintenance and refueling operations, reactions from the NSSS and other mechanical and electrical equipment, extreme environmental events (primarily earthquake and tornado), and accidents (pressurization and thermal effects).…”

Section: Time-dependent Reliability Assessmentmentioning

confidence: 99%

Probabilistic methods for assessing current and future performance of concrete structures in nuclear power plants

Ciampoli

Ellingwood

2002

Mat. Struct.

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Concrete safety-related structures and components in nuclear plants may be exposed to aggressive service and environmental effects that may cause their strength and stiffness to deteriorate over an extended period of service. A performance assessment of an existing structure subject to deterioration requires a consideration of likely degradation mechanisms, a framework for managing the inevitable uncertainties in operating or environmental loads, capacities, and nondestructive evaluation technologies, and tools for determining whether the observed degradation impacts the remaining service life or safety margin of the plant to any significant degree. Research is in progress to support the development of condition assessment tools and guidelines using modern structural reliability analysis methods

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“…Structural loads occur randomly in time and are random in their intensity. Structural load models and descriptive load statistics have been gathered in previous ,research to develop probability-based limit states design and condition assessment procedures for NPP structures (Hwang, et al, 1987;Ellingwood and Mori, 1993). piscrete load models.…”

Section: Probabilistic Models Of Loadsmentioning

confidence: 99%

“…Many of the loads for which nuclear power plant structures are designed can be modeled by such processes (Ellingwood, 1983;Hwang, et al, 1987). A summary of load statistics obtained from prior research is presented in Table 4.1.…”

Section: Nuregicr-5442mentioning

confidence: 99%