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Saturday, August 1, 2020 | History

4 edition of Aging and loss-of-coolant accident (LOCA) Testing of electrical connections found in the catalog.

Aging and loss-of-coolant accident (LOCA) Testing of electrical connections

Aging and loss-of-coolant accident (LOCA) Testing of electrical connections

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Published by U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English

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

  • Edition Notes

    Statementprepared by C.F. Nelson (Sandia National Laboratories) ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
    ContributionsSandia National Laboratories., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
    The Physical Object
    FormatMicroform
    Paginationxv, 93 p.
    Number of Pages93
    ID Numbers
    Open LibraryOL17580713M
    OCLC/WorldCa40221090

    Morton, DP, Pan, YA & Tejada, JJ , ' Modeling loss of coolant accident frequencies and break sizes ', Transactions of the American Nuclear Society, vol. , no. PART 2, pp. Modeling loss of coolant accident frequencies and break : David P. Morton, Ying An Pan, Jeremy J. Tejada. standing of material characterization, operator requirements and best practices. First, lessons learned from existing plants and from EPRI’s 30+ years of research and development.

    LOCA - Loss of coolant accident. Looking for abbreviations of LOCA? It is Loss of coolant accident. Loss of coolant accident listed as LOCA. PKL I and PKL II programs were focused on the study of Large Break Loss of Coolant Accidents (LBLOCAs) and Small Break Loss of Coolant Accidents.   Aging Nuclear Structures Hazard Reevaluation at Existing U.S. Nuclear Power Plants in Response to the Fukushima Daiichi Nuclear Power Plant Loss of Coolant Accident. World Environmental issues, Nuclear power, Management methods, Existing buildings, Aging (material), Maryland, Baltimore, United.

    May CANDU Safety - #12 - Large Rev. 0 2 Overview λ Event sequence for a large break loss-of-coolant accident (LOCA) λ Acceptance criteria used to assess the results of the analysis λ Normal operating conditions λ Fuel and pressure tube behaviour during the transient λ Fission product release behaviour λ Containment behaviourFile Size: KB.   Dr. A Gopalakrishnan | All this points to the likelihood that what Kakrapar Unit-1 is undergoing is a small Loss-of-Coolant Accident (LOCA) in progress. It is most likely that one or more pressure tubes (PT) in the reactor (which contain the fuel bundles) have cracked open, leaking hot primary system heavy-water coolant into the containment housing.


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Aging and loss-of-coolant accident (LOCA) Testing of electrical connections Download PDF EPUB FB2

@article{osti_, title = {Aging, Loss-of-Coolant Accident (LOCA), and high potential testing of damaged cables}, author = {Vigil, R A and Jacobus, M J}, abstractNote = {Experiments were conducted to assess the effects of high potential testing of cables and to assess the survivability of aged and damaged cables under Loss-of-Coolant Accident (LOCA) conditions.

@article{osti_, title = {Aging and loss-of-coolant accident (LOCA) testing of electrical connections}, author = {Nelson, C F}, abstractNote = {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.

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 coolant system is used. Aging, loss-of-coolant accident (LOCA), and high potential testing of damaged cables Author: R A Vigil ; Mark J Jacobus ; U.S.

Nuclear Regulatory Commission. 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.].

The reactor is isolated after the initiation of the accident, i.e. the regular heat sink is removed.

PWR: Upon initiation of Aging and loss-of-coolant accident book accident the steam generators are isolated on the secondary side by closing the steam supply valves and the feedwater valves. BWR: Upon receipt of a reactor-vessel low-water.

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).

Evaluation of a PWR Spent Fuel Pool Accident Response to Loss-of-Coolant Inventory Scenarios Using MELCOR K.C. Wagner and R.O. Gauntt, SANDIA Letter Report, Revision 4, Completed June ; pages. MELCOR was used to simulate complete- and partial-loss-of-coolant accidents in a PWR spent fuel pool.

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 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 on the. 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. Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through the Elicitation Process (NUREG).

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 Coolant Accident. Loss of coolant accidents. Loss of coolant accidents (LOCAs) which are analysed, range from very small leaks from the reactor coolant system boundary to the complete severance of the largest pipe (discharge area approximately 1 m 2) in the primary coolant recirculation loop.

The system response varies considerably with the size of leak. 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. The licensing analysis of the loss-of-coolant accident (LOCA) in the NIST research reactor (NBSR) is found in the Safety Analysis Report (SAR) (NIST, a). Chapter 6 of the SAR discusses the emergency cooling system (ECS), and Chapter 13 discusses the low probability of a Cited by: 1.

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.

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.

A loss of coolant accident (LOCA) round robin test program was conducted to evaluate experimental variations and experimental practices associated with the post quench ductility and breakaway. Graduate Thesis Or Dissertation Study on Depressurized Loss of Coolant Accident and its Mitigation Method Framework at Very High Temperature Gas Cooled Reactor Public Deposited.

Analytics this accident might result in exothermic chemical reactions of graphite and oxygen depending on the accident scenario and the design.

Having the knowledge Cited by: 2. 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.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.loss of coolant accident and loss of flow accident analysis of the aries-at design E.

A. Mogahed, L. El-Guebaly, A. Abdou, P. Wilson, D. Henderson and the ARIES Team Fusion Technology Institute.