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Sunday, August 9, 2020 | History

4 edition of Estimating probable flaw distributions in PWR steam generator tubes found in the catalog.

Estimating probable flaw distributions in PWR steam generator tubes

Estimating probable flaw distributions in PWR steam generator tubes

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Published by Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, [Supt. of Docs., U.S. G.P.O., distributor] in Washington, DC .
Written in English

    Subjects:
  • Steam-pipes -- Cracking,
  • Pressurized water reactors -- Materials -- Cracking,
  • Nuclear power plants -- Piping,
  • Stress corrosion

  • Edition Notes

    Statementprepared J.A. Gorman ... [et al.].
    ContributionsGorman, J. A., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Argonne National Laboratory.
    The Physical Object
    FormatMicroform
    Paginationxxxii, 152 p.
    Number of Pages152
    ID Numbers
    Open LibraryOL17593303M
    OCLC/WorldCa41289343

    Your customizable and curated collection of the best in trusted news plus coverage of sports, entertainment, money, weather, travel, health and lifestyle, combined with . @article{osti_, title = {Characterization of flaws in a tube bundle mock-up for reliability studies}, author = {Kupperman, D S and Bakhtiari, S}, abstractNote = {As part of an assessment of in-service inspection of steam generator tubes, the authors will assemble a steam generator mock-up for round robin studies and use as a test bed in evaluating emerging technologies.

    The modelling of the eddy current testing of U-bend steam generator tubes is a valuable tool for interpreting measured signals due to geometric distortions that . A 'read' is counted each time someone views a publication summary (such as the title, abstract, and list of authors), clicks on a figure, or views or downloads the full-text.

    According to the steam power plant operation manual this plant is able to operate at 25%, 50%, 75% and % of the total load installed, and some design parameters are established for this. Standard Test Methods for Accumulated Deposition in a Steam Generator Tube: D - Standard Guide for On-Line Monitoring Systems for Water Analysis: D - Standard Practice for Performing Pressure In-Line Coagulation-Flocculation-Filtration Test in Water: D - Standard Practice for Handling of High Purity Water Samples: D -


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Estimating probable flaw distributions in PWR steam generator tubes Download PDF EPUB FB2

Get this from a library. Estimating probable flaw distributions in PWR steam generator tubes. [J A Gorman; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.; Argonne National Laboratory.;].

The causes of steam generator tube plugging have evolved with time, as shown in Fig. 1 (Electric Power Research Institute, ).Early problems with wastage were found to be associated with the use of a low Na/PO 4 molar ratio phosphate water chemistry, and the problem was essentially eliminated with the introduction of all-volatile secondary-water treatment for pH Cited by:   A steam generator tube rupture (SGTR) in a pressurized water reactor (PWR) might cause a major source of large accidental release of radioactive aerosols into the environment during a severe accident involving core damage due to its potential to by-pass the reactor containment (Güntay et al.,Auvinen et al., ).

Currently no credit is Cited by: The obtained estimates can be used for flaw detection as well as efficient feature extractors in a defect classification scheme. Finally, we apply the proposed method to analyze rotating‐probe eddy‐current data from tube inspection of a steam generator in a nuclear power : Aleksandar Dogandžić, Ping Xiang.

Eddy current (EC) estimate of flaw size obtained from inservice inspection is often the primary means of assessing the structural integrity of steam generator tubes. Reliable prediction of failure pressure and leak rate in tubes with complex cracking requires more detailed information about the geometry and extent of degradation than is.

A typical CANDU nuclear steam generator usually consists of thousands of small-diameter SG tubes through which flows heavy water of high temperature and high pressure. The SG tubes are designed with nominal tube wall thickness ranging from to mm, depending on the type of tube alloy used.

In the present paper a steam generator tube example, the failure pressure of steam generator tubing with a deep fretting flaw, is used to illustrate how to characterize and propagate uncertainties, how to interpret the results, and how the acceptance criterion affects the overall probabilistic assessment.

Two-loop quantitative uncertainty. In the NRC staff prepared RG“Basis for Plugging Degraded PWR Steam Generator Tubes,” (NRC Regulatory Guide, ) describing an acceptable technical basis for the development of tube repair criteria.

This RG is generally cited in licensee and industry documentation as the bases for the TS tube repair criterion in plant TS. Purchase Aging and Life Extension of Major Light Water Reactor Components - 1st Edition. Print Book & E-Book. ISBNBooks at Amazon. The Books homepage helps you explore Earth's Biggest Bookstore without ever leaving the comfort of your couch.

Here you'll find current best sellers in books, new releases in books, deals in books, Kindle eBooks, Audible audiobooks, and. It is necessary to know the number of flaws and their size distribution in order to calculate the probability of failure or to estimate the amount of leakage through the tube wall of steam.

@article{osti_, title = {Steam generator tube inspection in Japan}, author = {Fukui, Shigetaka}, abstractNote = {Steam generator tube inspection was first carried out in at Mihama Unit-1 that is first PWR plant in Japan, when the plant was brought into the first annual inspection.

At that time, inspection was made on sampling basis, and only bobbin coil probe. Inservice inspections - inservice inspection requirements - material considerations - inservice inspection reliability.

Summary, conclusions and recommendations. Counter Measures For Tube Failures In Pressurized Water Reactor Steam Generators. Steam generator tube degradation - recirculating type steam generators - once-through steam generators. The Electric Power Research Institute (EPRI) conducts research, development, and demonstration projects for the benefit of the public in the United States and internationally.

As an independent, nonprofit organization for public interest energy and environmental research, we focus on electricity generation, delivery, and use in collaboration with the electricity sector, its.

Technical Report: Evaluation of sampling plans for in-service inspection of steam generator tubes. Volume 2, Comprehensive analytical and Monte Carlo simulation results for several sampling plans. The growth of flaws in steam generator tubes was predicted using statistical approaches.

Probabilistic distributions of the flaw size and the probability of burst. @article{osti_, title = {Steam generator tube integrity program: Annual report, August September Volume 2}, author = {Diercks, D R and Bakhtiari, S and Kasza, K E and Kupperman, D S and Majumdar, S and Park, J Y and Shack, W J}, abstractNote = {This report summarizes work performed by Argonne National Laboratory on the Steam Generator Tube.

Books online: Aging and Life Extension of Major Light Water Reactor Components,We use cookies to provide essential features and services. By using our website you agree to our use of cookies.

× 0. Close menu. SmartSellTM - The New Way to sell Online we won't be beaten by anyone. Development of modern steam engine (Watt) A.D. Development of high-pressure steam engine (Trevithick) A.D. Development of the automobile engine (Daimler) A.D.

Operation of first nuclear power plant A.D. The Industrial Revolution began when James Watt invented the steam engine in. The following documents describe other recent reactor operating experience with steam generator tubes: IN“Failure to Detect Freespan Cracks in PWR Steam Generator Tubes,” dated June 5, IN and IN supplement 1, “Recent Experience With Plugged Steam Generator Tubes” dated January 8, and July, 17.

Straight tube, shell-and-tube waste heat boilers frequently develop tube and tube sheet failures due to the imposition of unequal stresses. A primary cause of this is the uneven distribution of hot gases across the face of the tube sheet. The tubes involved tend to come loose, creating leakage problems.of the steam generator, especially if the release is from a fully pressurized reactor coolant system.

Consequently, the integrity of the steam generator tubes must be ensured with high confidence. A rupture of a steam generator tube during power operation of .Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2: Oct Steam Generator Tube Leaks or Ruptures Concurrent with Containment Bypass from Main Steam Line or Feedwater Line Breaches.

Methodology for Estimating Fabrication Flaw Density and Distribution – Reactor Pressure Vessel Welds.