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4 edition of Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of class 1E electrical cables found in the catalog.

Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of class 1E electrical cables

Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of class 1E electrical cables

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Published by Division of Engineering, 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:
  • Electric cables -- Testing.,
  • Nuclear power plants -- Electronic equipment -- Testing.

  • Edition Notes

    Other titlesAging, condition monitoring, and loss of coolant accident (LOCA) Tests of Class 1E electrical cables.
    Statementprepared by M.J. Jacobus.
    ContributionsU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering., Sandia National Laboratories.
    The Physical Object
    FormatMicroform
    Pagination3 v.
    ID Numbers
    Open LibraryOL14691855M

    Cable testing and static and/or dynamic performance monitoring are useful for verifying that neutron detectors are in good working condition. For static performance monitoring, data available in the plant computer may be used to look for drift and anomalies, that is, low-frequency output from the detectors. The dynamic response of neutron Cited by: 2. The Chernobyl disaster was a nuclear accident that occurred on Saturday 26 April , at the No. 4 reactor in the Chernobyl Nuclear Power Plant, near the city of Pripyat in the north of the Ukrainian SSR. It is considered the worst nuclear disaster in history and is one of only two nuclear energy disasters rated at seven—the maximum severity—on the International Nuclear Event Location: Chernobyl nuclear power plant, Pripyat, .

    Lecture 8: Loss-of-coolant accident (LOCA) phenomena G. F. Hewitt Imperial college London 2 Reactor Operational States • NORMAL OPERATION: Operation at full power. • OPERATIONAL TRANSIENTS: Startup and shutdown. On-line refuelling (AGR). • UPSET CONDITIONS: Unexpected faults, e.g. turbine trips. Loss of offsite power. Assessment of environmental qualification practices and condition monitoring techniques for low-voltage Aging, loss-of-coolant accident (LOCA), and high potential testing of damaged cables [microform] / prepa.

    The title of this regulatory guide is ‘Condition Monitoring Techniques for Electric Cables Used in Nuclear Power Plants’. Sources of further information. Cable ageing and condition monitoring have been the subject of numerous research and development (R&D) projects, reports, and standards produced by the worldwide nuclear power : H.M. Hashemian. May CANDU Safety - #16 - LOCA Rev. 0 2 Overview λ Event sequence for a large break loss-of-coolant accident with loss of emergency core cooling λ Acceptance criteria used to assess the results of the analysis λ Fuel and pressure tube behaviour during transient λ Fission product release λ ContainmentFile Size: KB.


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Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of class 1E electrical cables Download PDF EPUB FB2

@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. 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.]. 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. 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 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. T1 - Need for condition monitoring and diagnosis of electric wires and cables used in nuclear power plants. AU - Ohki, Yoshimichi. AU - Hirai, Naoshi.

AU - Yamamoto, Toshio. PY - /1/1. Y1 - /1/1. N2 - Electric cables in nuclear power plants have to function even after serious events such as a loss-of-coolant accident (LOCA).Cited by: 5.

at an assumed slight overpower condition. No power or other transient preceeds the accident. Peak core power density or linear power generation is at the maximum allowable value. 3.A double-ended rupture of one primary coolant loop is assumed (largest existing pipe) PWR: rupture of cold leg imposes most severe conditions.

Cable condition monitoring for nuclear power plants. continue to function after a loss of coolant accident Condition Monitoring, and Management of Aging of Low Voltage Cables in Nuclear.

To study the effect of thermal aging on the low voltage DC cables used in photovoltaic systems, XLPO based cable samples were thermally aged for. issued a state-of-the-art report on water reactor fuel behaviour in design-basis accident (DBA) conditions.

The report was limited to the oxidation, embrittlement and deformation of pressurised water reactor (PWR) fuel in a loss-of-coolant accident (LOCA).

This article is within the scope of WikiProject Energy, a collaborative effort to improve the coverage of Energy on Wikipedia.

If you would like to participate, please visit the project page, where you can join the discussion and see a list of open tasks. Start This article has been rated as Start-Class on the project's quality scale.

Mid This article has been rated as Mid-importance. Loss of coolant accident (LOCA) Those postulated accidents that result in a loss of reactor coolant at a rate in excess of the capability of the reactor makeup system from breaks in the reactor coolant pressure boundary, up to and including a break equivalent in size to the double-ended rupture of the largest pipe of the reactor coolant system.

rare events of loss of coolant accident and loss of flow accident. Accident histories werw calculated for the first week following the event. Figure 1. ARIES-AT cross section. LOCA occurs when one or more supply tubes outside the reactor are damaged or ruptured, preventing the coolant from reaching the first wall or plasma facing Size: KB.

and Loss-of-Coolant Accident Conditions NEA Final Report. For Official Use NEA/CSNI/R()2 Organisation de Coopération et de Développement Économiques Organisation for Economic Co -operation and Development 04 -May _____ _____ English - Or. English NUCLEAR ENERGY AGENCY COMMITTEE ON THE SAFETY OF NUCLEAR INSTALLATIONS File Size: 7MB.

TEST PLAN FOR HIGH-BURNUP FUEL BEHAVIOR UNDER LOSS-OF-COOLANT ACCIDENT CONDITIONS* H. Chung, L. A Neimark, and T. Kassner Argonne National Laboratory Argonne, IL ABSTRACT Excessive oxidation, Cited by: 1. 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 Cited 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.

The AEC and the Loss of. Engineered Safety Features FSAR Section UFSAR Page of 1 ENGINEEREDSAFETYFEATURES Independent and separate engineered safety features are provided for each unit.

Loss-of-coolant: Nuclear scientists have always felt that the greatest risk in operating a reactor is the loss-of-coolant accident.

If for some reason the flow of water is stopped or slowed -- for example if a pipe breaks -- the fissioning fuel rods could become so hot that they could melt.

On-line monitoring methods and aging management Since on-line monitoring (OLM) methods are passive, nonintrusive, and in situ (the instrument is not removed from the process), they can be used to monitor aging- related degradation and anomalies as they occur, they take into account installation and process condition effects on the monitored I&C.

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.

Best-estimate thermal-hydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors.

Evaluation of the capabilities and the performance of these codes can be accomplished by comparing the code predictions with measured experimental data obtained on different test facilities.

OECD/NEA Cited by: Thus, without any mitigation systems, this accident might result in exothermic chemical reactions of graphite and oxygen depending on the accident scenario and the design.

Having the knowledge on the amount of air inside the vessel one can investigate how to reduce air concentration via specifically designed mitigation by: 2.loss of coolant accident (loca) regulation. EPRI Fuel Reliability Januar y industry concerns with the proposed LOCA rulemaking.

package. LOCA implementation guidance and training materials are being prepared. Preliminary evaluations to determine high burnup fuel rod.