Last edited by Nikorr
Tuesday, July 14, 2020 | History

2 edition of Aging assessment of the Westinghouse PWR control rod drive system found in the catalog.

Aging assessment of the Westinghouse PWR control rod drive system

W. Gunther

Aging assessment of the Westinghouse PWR control rod drive system

by W. Gunther

  • 18 Want to read
  • 21 Currently reading

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

    Subjects:
  • Pressurized water reactors -- Equipment and supplies -- Reliability.,
  • Pressurized water reactors -- Reliability.,
  • Nuclear fuel rods -- Evaluation.,
  • Nuclear reactors -- United States -- Reliability.

  • Edition Notes

    Statementprepared by W. Gunther, K. Sullivan.
    ContributionsSullivan, K. 1950-, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering., Brookhaven National Laboratory.
    The Physical Object
    Pagination1 v. (various pagings) :
    ID Numbers
    Open LibraryOL15291899M

    Abstract. The effects of aging upon the Babcock Wilcox (B W) and Combustion Engineering (CE) control rod drive systems have been evaluated. For this study, the CRD system boundary included the control rod assemblies, guide tubes, control rod drive mechanism, control system components, rod position indication components, and cooling system. Westinghouse Electrical Maintenance Hints [westinghouse electric corporation] on *FREE* shipping on qualifying offers. over pages of reference to acceptable maintenance practice on the most commonly used types of industrial electrical apparatus5/5(1).

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    The present system of nuclear power generator technology was stone-age and intentionally chosen as archaic, inefficient, and obsolete. It was already know by Nikola Tesla—even before Enrico Fermi split the atom without realizing it, and while Einstein was still a second class patent clerk in the SwissFile Size: 9MB. Westinghouse SMR. The Westinghouse SMR (WSMR) was declared to be launched in February (POWERnews and Febru ).This reactor power is described as MWt and the electrical output could be more than MWe (Robert et al., ).The design uses many of the key features from the Westinghouse AP by:


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Aging assessment of the Westinghouse PWR control rod drive system by W. Gunther Download PDF EPUB FB2

A study of the effects of aging on the Westinghouse Control Rod Drive (CRD) System was performed as part of the Nuclear Plant Aging Research (NPAR) Program. The objectives of the NPAR Program are to provide a technical basis for identifying and evaluating the degradation caused by age in nuclear power plant systems, structures, and components.

@article{osti_, title = {Aging assessment of the Westinghouse PWR Control Rod Drive System}, author = {Gunther, W. and Sullivan, K.}, abstractNote = {A study of the effects of aging on the Westinghouse Control Rod Drive (CRD) System was performed as part of the Nuclear Plant Aging Research (NPAR) Program.

The objectives of the NPAR Program are to. Aging assessment of the Westinghouse PWR control rod drive system by W. Gunther. Published by Division of Engineering, Office of Nuclear Regulatory Research, U.S.

Nuclear Regulatory Commission, U.S. G.P.O. [distributor in Washington, DC. An aging assessment of the Westinghouse Pressurized Water Reactor (PWR) Control Rod System (CRD) has been completed as part of the US NRC's Nuclear Plant Aging Research, (NPAR) Program.

This study examined the design, construction, maintenance, and operation of the system to determine its potential for degradation as the plant ages. Aging of Control and Service Air Compressors and Dryers Used in Nuclear Power Plants: NUREG/CR Aging Assessment of the Westinghouse PWR Control Rod Drive System: NUREG/CR (EGG) Generic Issue Flexible Wedge Gate Valve Test Program: Phase II Results and Analysis: NUREG/CR (KEI No.

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Pumps for PWR Nuclear Power Plants, 6/ 7/ 3. NUREG/CR, Auxtltary Feedwater System Aging Study, 3/ AGING RELATED ISSUES AFW pumps may be operated at flow rates ranging from as low as 2% of best efficiency point (BEP). The mission of the Pressurized Water Reactor Owners Group is to improve the competitiveness of member plants through cost-effective resolution of issues common to more than one member, and to provide a superior regulatory interface in support of member activities.

This mission will be accomplished by maintaining a focus on the following objectives. Reactor internals operate in the environment inside the pressure vessel; this is favorable to the development of time-dependent or aging degradations. The main objective of this study is to assess the effects of aging degradations on pressurized-water reactor (PWR.

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The wearing of the thermal sleeve flange against the control rod drive mechanism (CRDM) penetration tubes is a known aging phenomenon experienced in some Westinghouse nuclear steam supply system (NSSS) and other similarly designed plants.

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DETECTION OF AGING EFFECTS. Inspection can be used to detect physical effects of degradation including cracking, fracture, wear, and distortion. The inspection technique is chosen based on the nature and extent of the expected damage. When I returned to graduate school in the '70's for advanced degrees, I had a professor that used to teach at the General Electric Power University tell me the Westinghouse T&D book was the only thing Westinghouse ever did that was better than what General Electric did.5/5(9).

Aging assessment of the Combustion Engineering and Babcock and Wilcox control rod drives Technical Report. The effects of aging upon the Babcock & Wilcox (B&W) and Combustion Engineering (CE) control rod drive systems have been evaluated.

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