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Wednesday, August 5, 2020 | History

2 edition of Probability-based evaluation of degraded reinforced concrete components in nuclear power plants found in the catalog.

Probability-based evaluation of degraded reinforced concrete components in nuclear power plants

Probability-based evaluation of degraded reinforced concrete components in nuclear power plants

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  • 23 Currently reading

Published by Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English

    Subjects:
  • Reinforced concrete -- Deterioration.,
  • Reinforced concrete construction -- Reliability.,
  • Nuclear power plants -- Materials -- Deterioration.

  • Edition Notes

    Other titlesProbability based evaluation of degraded reinforced concrete components in nuclear power plants.
    Statementprepared by J.I. Braverman ... [et al.].
    ContributionsBraverman, J. I., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Brookhaven National Laboratory., Oak Ridge National Laboratory., Georgia Institute of Technology. School of Civil and Environmental Engineering.
    The Physical Object
    FormatMicroform
    Paginationxv, 248 p.
    Number of Pages248
    ID Numbers
    Open LibraryOL18161293M

      Seismic Performance of Degraded Shear Walls for Long-Term Compliance Periods C. H. Hofmayer, S. Shteyngart, and P. Bezler, NUREG/CR, “Probability-Based Evaluation of Degraded Reinforced Concrete Components in Nuclear Power Plants,” Washington, DC: U.S. Nuclear Regulatory Commission, April Author: Luis Ibarra, Biswajit Dasgupta, Kuang Tsan Chiang. The management of aging in nuclear power plant concrete structures Article in JOM: the journal of the Minerals, Metals & Materials Society 61(7) .

    reinforced concrete structures used in nuclear power plants. There are totally three parts of the report. The first part focuses on responses of various materials under high temperatures including concrete and steel, the second part on structural performances, and the third on spalling damage of concrete under high Size: 7MB. This paper summarizes the results of a research program conducted during – to develop probability‐based analysis and design procedures for structures in nuclear plants. Limit states of concrete containments and shear walls are formulated.

    Purchase Non-Destructive Evaluation of Reinforced Concrete Structures - 1st Edition. Print Book & E-Book. ISBN ,   This paper describes the reliability analysis of a concrete containment for VVER under a high internal overpressure considering nonlinear behavior of reinforced concrete structure. The probabilistic safety assessment (PSA) aims at an assessment of the probability of the concrete structure failure under the excessive overpressure. The non-linear analysis of the concrete Cited by: 9.


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Probability-based evaluation of degraded reinforced concrete components in nuclear power plants Download PDF EPUB FB2

The probability-based degradation acceptance limits that are developed can be used as a tool for making risk-informed decisions regarding degradation of reinforced concrete members. This study is being conducted under Phase II of a multi-year research program sponsored by the Nuclear Regulatory Commission (NRC) to assess age-related degradation of structures and passive components for U.S.

nuclear power plants. basis for evaluating reinforced concrete structures in nuclear plants for continued service and for developing guidelines for in-service inspection and repair.

The probability-based degradation acceptance limits that are developed can be used as a tool for making risk-informed decisions regarding degradation of reinforced concrete members. This study is. Probability-Based Evaluation of Degraded Reinforced Concrete Components in Nuclear Power Plants: April ML (Package) NUREG/CR OPUS/PlotOPUS: An ORIGEN-S Post-Processing Utility and Plotting Program for SCALE: April ML NUREG V Report to Congress on Abnormal Occurrences: Fiscal Year April.

Get this from a library. Probability-based evaluation of degraded reinforced concrete components in nuclear power plants.

[J I Braverman; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.; Brookhaven National Laboratory.; Oak Ridge National Laboratory.; Georgia Institute of Technology. Probability-Based Evaluation of Degraded Reinforced Concrete Components in Nuclear Power Plants: NUREG/CR Recommendations on Fuel Parameters for Standard Technical Specifications for Spent Fuel Storage Casks: NUREG/CR Environmental Effects on Fatigue Crack Initiation in Piping and Pressure Vessel Steels: NUREG/CR 5.

U.S. Nuclear Regulatory Commission, Probability-Based Evaluation of Degraded Reinforced Concrete Components in Nuclear Power Plants, NUREG/CR, April 6. American Concrete Institute (ACI), Building Code Requirements for Structural Concrete, ACI.

the structural performance of reinforced concrete members at nuclear power plants. The paper focuses on degradation of. reinforced concrete flexural members and shear walls due to the loss of steel reinforcing area and loss of concrete area.

(cracking/spalling). Report on Aging of Nuclear Power Plant Reinforced Concrete Structures (NUREG/CR) On this page: Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures.

evaluation of nuclear power plant reinforced concrete. In this paper, nuclear power plant concrete structures are described and their operating experience noted. Primary considerations related to management of their aging are noted: degradation mechanisms, damage modeling, and material performance; assessment and repair; and applications of structural reliability by:   @article{osti_, title = {Evaluating the Effects of Aging on Electronic Instrument and Control Circuit Boards and Components in Nuclear Power Plants}, author = {Hannaman, G William and Wilkinson, C Dan}, abstractNote = {The report describes potentially useful techniques for monitoring the aging of I&C boards.

The techniques have been grouped. A probability-based methodology is being developed in support of the NRC Structural Aging Program to assist in evaluating the reliability of existing concrete structures in nuclear power plants. To ensure the safe operation of nuclear power plants in the United States, it is essential to assess the effects of age-related degradation of plant structures, systems, and components.

This concern becomes even more important in view of the submittals of license renewal applications to the NRC under 10 CFR Part Cited by: NUCLEAR ENERGY AGENCY COMMITTEE ON THE SAFETY OF NUCLEAR INSTALLATIONS OECD-NEA WORKSHOP ON THE EVALUATION OF DEFECTS, REPAIR CRITERIA & METHODS OF REPAIR FOR CONCRETE STRUCTURES ON NUCLEAR POWER PLANTS Hosted by GRS at the DIN Institute in Berlin, Germany 10thth April, JT.

Aging effects in reinforced concrete structures brought on by severe service conditions may cause their structural capacities to deteriorate gradually over their service life. Research is being conducted to address aging management of safety-related reinforced concrete structures in nuclear power plants (NPPs).Cited by: Corrosion of steel reinforcement and spalling of concrete may lead to serious damage to a concrete structure member and to affect the durability of RC structures.

Thus age-related degradation of safety -related concrete structures in nuclear power plants may significantly affect the serviceability of plants. on Nuclear Power Plant Structures Reported by ACI Committee ACI R This report presents a design-oriented approach for considering thermal effect on reinforced concrete structur es.

Although the approach is intended to conform to the general provisions of Appendix E of ACIit is not restricted to nuclear power plant struct ures.

This study considers the applicability of existing statistical data for describing the resistance of steel and reinforced-concrete nuclear plant structures.

Probability distributions are recommended that can be used to assess the reliability of nuclear structures and to select appropriate resistance criteria for probability-based structural design. Degradation of performance and deterioration of different components of reinforced concrete (RC) structures increase with the age of structure.

This deterioration of reinforced component depends on several parameters. However, modeling service life of RC structure by considering all the parameters is a difficult job, as most of the parameters are uncertain in by: 5.

Nuclear Engineering and Design 59 () North-Holland Publishing Company PROBABILITY-BASED DESIGN CRITERIA FOR NUCLEAR STRUCTURES * Mayasandra K. RAVINDRA Sargent and Lundy, 55 East Monroe Street, Chicago, I1.USA This paper presents a methodology for developing probabilistic design criteria for nuclear by: 2.

Degradation effects on the behavior of indeterminate flexural reinforced concrete members are determined using a specific example of a propped cantilever beam. Fragility curves for the undegraded beam and the beam with degraded properties are calculated and compared for varying levels‘ of by: 3.

Nuclear Engineering and Design () North-Holland Probabilistic methods for condition assessment and life prediction of concrete structures in nuclear power plants Bruce R.

Ellingwood and Yasuhiro Mori Department of Civil Engineering, Johns Hopkins University, N. Charles Street, Baltimore, MDUSA Received 4 Novemberrevised Cited by: Data on the long-term performance of the reinforced concrete materials is of importance for demonstrating the durability of the nuclear power plant concrete structures and in predicting their performance under the influence of pertinent aging factors and environmental stressors.Design strength evaluation of RC beams under radiation environments for nuclear power plants Article in Nuclear Engineering and Design .