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3 edition of Aging, loss-of-coolant accident (LOCA), and high potential testing of damaged cables found in the catalog.

Aging, loss-of-coolant accident (LOCA), and high potential testing of damaged cables

Aging, loss-of-coolant accident (LOCA), and high potential testing of damaged cables

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Published by Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, For sale by the U.S. G.P.O., Supt. of Docs. in Washington, DC .
Written in English

    Subjects:
  • Nuclear power plants -- Electric equipment -- Testing.,
  • Nuclear power plants -- Electric equipment -- Reliability.,
  • Electric cables -- Testing.,
  • Electric cables -- Reliability.

  • Edition Notes

    Other titlesAging, loss of coolant accident (LOCA), and high potential testing of damaged cables.
    Statementprepared by R.A. Vigil, M.J. Jacobus.
    ContributionsJacobus, Mark J., U.S. Nuclear Regulatory Commission. Division of Reactor Controls and Human Factors., Science and Engineering Associates., Sandia National Laboratories.
    The Physical Object
    FormatMicroform
    Paginationviii, 19, [41] p.
    Number of Pages41
    ID Numbers
    Open LibraryOL14706715M

    Recent relicensing called for a study of fuel cladding response to a Loss of Coolant Accident (LOCA). Focusing on the maximum cladding temperature achieved.[1], [2] To facilitate this a one- dimensional radial model was created to solve for the peak temperature in the core limited Size: 1MB. The attendant risks now were very real, she argued: “In a loss of coolant accident, cold water has to be injected as an emergency safety measure for core cooling.

    We would like to show you a description here but the site won’t allow more. The aging degradation and lifetime assessment of a domestic class 1E Ethylene-Propylene-Diene-Monomer (EPDM), which is a popular insulating elastomer for electrical cables in the nuclear power.

    Volume 9, Issue 1, March ISSN: (Print) In this issue Influence of annealing and aging treatments on the embrittlement of type ferritic stainless steel Microstructural examination of fuel rods subjected to a simulated large-break loss of coolant accident in reactor. A. Garlick Pages Abstract. Selected. rent regulations for Loss of Coolant Accidents (LOCA) that will be addressed through the implementation of new or revised regulations. The proposed regulations could result in a reduction of the allowable Equivalent Cladding Reacted from 17% to 4% at end-of-life conditions, and an additional 50% reduction by the invocation of a fuel cladding File Size: 2MB.


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Aging, loss-of-coolant accident (LOCA), and high potential testing of damaged cables Download PDF EPUB FB2

And damaged cables under Loss-of-Coolant Accident (LOCA) conditions. High potential testing at Vdc/mil on undamaged cables suggested that no damage was incurred on the selected virgin cables. During aging and LOCA testing, Okonite ethylene propylene rubber (EPR) cables with a bonded jacket experienced unexpected failures.

The failures appear. The test results indicate that most properly installed XLPO cables should be able to survive an accident after 60 years for total aging doses up to kGy and for moderate ambient temperatures on the order of sC (potentially higher or lower, depending on material specific activation energies).

The density of BIW insulation (Figure G-3) increased about 1% during aging. Accident radiation caused only a slight increase in the density of samples that had been aged for 9 months.

The BIW jacket (Figure G-4) had a consistent increase in density, reaching about 4% after k3y of aging. Aging failures appear to be primarily related to the level of thermal aging and the presence of a bonded jacket that ages more rapidly than the insulation.

For Brand Rex crosslinked polyolefin (XLPO) cables, the results suggest that 7 mils of insulation remaining should give the cables a high probability of surviving accident exposure following aging. The materials are subject to chemical and physical degradation under extended radiationthermal- oxidative conditions.

Of particular interest were the circumstances under which existing aging data could be used to predict whether aged materials should pass loss of coolant accident (LOCA.

Get this from a library. Aging, loss-of-coolant accident (LOCA), and high potential testing of damaged cables. [R A Vigil; Mark J Jacobus; U.S. Nuclear Regulatory Commission. Division of Reactor Controls and Human Factors.; Science and Engineering Associates.; Sandia National Laboratories.].

Get this from a library. Aging and loss-of-coolant accident (LOCA) testing of electrical connections. [Curtis F Nelson; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.; Sandia National Laboratories.].

Experiments were performed to assess the aging degradation and loss-of-coolant accident (LOCA) behavior of electrical cables subjected to long-term aging exposures. Four different cable types were tested in both the U.S. and France: (1) U.S.

2 conductor with ethylene propylene rubber (EPR) insulation and a Hypalon jacket. After aging, the cables in each chamber were exposed to a sequential accident profile consisting of kGy of high dose rate gamma irradiation followed by a simulated design basis loss-of-coolant accident (LOCA) steam exposure.

This paper presents selected results of the LOCA by: 3. A loss-of-coolant accident (LOCA) is a mode of failure for a nuclear reactor; if not managed effectively, the results of a LOCA could result in reactor core damage. Each nuclear plant's emergency core cooling system (ECCS) exists specifically to deal with a LOCA.

Nuclear reactors generate heat internally; to remove this heat and convert it into useful electrical power, a coolant system is used. Get this from a library. Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of class 1E electrical cables.

[Mark J Jacobus; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.; Sandia National Laboratories.]. Malcolm Joyce, in Nuclear Engineering, Loss-of-coolant accidents. Loss-of-coolant accidents (LOCAs) are a type of reactor accident that has been studied extensively.

They are the prominent scenario that protection systems and operational practice are designed to respond to. abstractNote = {Experiments were performed to assess the aging degradation and loss-of-coolant accident (LOCA) behavior of electrical cables subjected to long-term aging exposures.

Four different cable types were tested in both the U.S. and France: (1) U.S. 2 conductor with ethylene propylene rubber (EPR) insulation and a Hypalon jacket.

Experiments were performed to assess the aging degradation and loss-of-coolant accident (LOCA) behavior of electrical cables subjected to long-term aging exposures. Four different cable types were tested in both the U.S. and France: (1) U.S. 2 conductor with ethylene propylene rubber (EPR) insulation and a Hypalon by: 3.

Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables: Summary of results. Nuclear Engineering and Design () 75 North-Holland, Amsterdam SMALL BREAK LOSS OF COOLANT ACCIDENTS: BOTYOM AND SIDE BREAK P.G.

HARDY and H.J. RICHTER Dartmouth College, Thayer School of Engineering, Hanover, New HampshireUSA Received 17 December A loss of coolant accident (LOCA) in a nuclear reactor can be caused, e.g., by a small break in Cited by: 3. @article{osti_, title = {Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of class 1E electrical cables}, author = {Jacobus, M J}, abstractNote = {This report describes the results of aging, condition monitoring, and accident testing of miscellaneous cable types.

Three sets of cables were aged for up to 9 months under simultaneous thermal ([approx equal][degrees. Get this from a library.

Long-term aging and loss-of-coolant accident (LOCA) testing of electrical cables: U.S./French cooperative research program. [C F Nelson; Sandia National Laboratories.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

Division of Engineering Technology.; Institut de protection et de sureté nucléaire (France). This report presents the results of an experimental program to determine the aging and loss-of-coolant accident (LOCA) behavior of electrical connections in order to obtain an initial scoping of their performance.

Ten types of connections commonly used in nuclear power plants were : C. Nelson. An Excellent book describing in good scientific way a hypothetical scenario of a Nuclear Catastrophe due to L.O.C.A.[Loss Of Coolant Accident] and Big Corruption in Nuclear Industry This book must be a mandatory reading in International "Atomic" Energy Agency,National Nuclear Energy Commissions,Nuclear Physicists & Engineers and educated Public This book Must re-published 5/5(1).

A history of the peak cladding temperature during a calculated loss of coolant accident is presented in Fig. 13 where the effect of the heat-transfer coefficient after rewetting is shown.

A heat-transfer coefficient of 15 Btu/hr-ft 2 -°F is sufficient to halt the increase in cladding temperature and any larger value of h will begin the cooling.This report documents calculations of the fuel cladding temperature during loss-of-coolant accidents in the NBSR.

The probability of a pipe failure is small and procedures exist to minimize the loss of water and assure emergency cooling water flows into the reactor core during such an by: 1.Professor Wilson gives the background to the concern being expressed about the risks associated with the possible loss of coolant from a nuclear reactor.