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Tuesday, July 14, 2020 | History

2 edition of An assessment of steam-explosion-induced containment failure found in the catalog.

An assessment of steam-explosion-induced containment failure

An assessment of steam-explosion-induced containment failure

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  • 28 Currently reading

Published by Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, D.C .
Written in English

    Subjects:
  • Nuclear reactors -- Containment -- Accidents.,
  • Nuclear reactors -- Containment -- Explosion.,
  • Nuclear power plants -- Risk assessment.

  • Edition Notes

    Statementprepared by T.G. Theofanous ... [et al.] ; prepared for Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
    ContributionsTheofanous, T. G., University of California, Santa Barbara. Dept. of Chemical and Nuclear Engineering., Science Applications International Corporation., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.
    The Physical Object
    FormatMicroform
    Pagination1 v. (various pagings)
    ID Numbers
    Open LibraryOL14699480M


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An assessment of steam-explosion-induced containment failure Download PDF EPUB FB2

Get this from a library. An assessment of steam-explosion-induced containment failure. [T G Theofanous; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; University of California, Santa Barbara.

Department of Chemical and Nuclear Engineering.;]. @article{osti_, title = {Probability of in-vessel steam explosion-induced containment failure for a KWU PWR}, author = {Esmaili, H and Khatib-Rahbar, M and Zuchuat, O}, abstractNote = {During postulated core meltdown accidents in light water reactors, there is a likelihood for an in-vessel steam explosion when the melt contacts the coolant in the lower plenum.

A variety of probabilistic models to quantify the likelihood of steam explosion induced alphamode) containment failure from core melt accidents in commercial light water reactors have been proposed in the past. In many respects, these models and associated mechanistic considerations were complimentary.

Comments on “An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV” October Nuclear science and engineering: the journal of the American Nuclear Society. Theofanous B et al () An assessment of steam explosion-induced containment failure, Part I: Probabilistic effects.

Nucl Sci Eng – Google Scholar Author: Günter Kessler, Anke Veser. Introduction. A steam explosion is a type of a fuel-coolant interaction (FCI), which results from the rapid and intense heat transfer that may follow the interaction between the molten material and the coolant (Berthoud, ; Corradini et al., ; Sehgal et al., ; Turland and Dobson, ).Such an interaction can occur when the melt is poured into the coolant, when the Cited by: 1.

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. Performance of nuclear power-plant protective barriers under internal explosion and external impact M. Corrodini, D.

Swenson, D. Woodfin, and L. Voolker, "Analysis of containment failure by a steam explosion following a postulated core and E. Rumdle, "An assessment of steam-explosion-induced containment failure, Nucl.

Sci. Eng., 97, No Cited by: 2. The containment failure probability is the same as the probability of the failure of electric power to function. The tree in Figure or Figure could be combined with the containment failure mode tree in Figure Download: Download full-size image; FIGURE Reduced event tree for a large by: 4.

The Nuclear Energy Agency (NEA) is a semi-autonomous body within the Organisation for Economic Co-operation and Development (OECD), located in the Paris area in France. The objective of the Agency. An assessment of steam-explosion-induced containment failure – Description/Abstract, A variety of probabilistic models to quantify the likelihood of steam explosion induced containment failure from core melt accidents in commercial light water reactors have been proposed in the past.

Cited by Probability of in-vessel steam explosion-induced containment failure for a KWU PWR. SciTech Connect. Esmaili, H.; Khatib-Rahbar, M.; Zuchuat, O. During postulated core meltdown accidents in light water reactors, there is a likelihood for an in-vessel steam explosion when the melt contacts the coolant in the lower plenum.

A number of mathematical and statistical techniques as well as specific data relevant to the risk and safety analysis of nuclear systems are provided as appendices.

References [Hol79a] J. Holdren, K. Anderson, P. Gleick, I. Mintzer, and G. Morris, "Risk of Renewable Energy Sources: A Critique of the Inhaber Report," ERGEnergy and. In the past, the issue of in-vessel steam explosions causing the upper head failure of the reactor vessel was mainly concerned in LWR (WASH, ).

In this so called alpha mode containment failure it is considered that the ejected upper head could endanger the. Potential failure modes of the containment that have been identified in PSA studies can to be grouped under the following headings: Containment Bypass Interfacing-systems LOCA Failure to isolate containment Steam generator tube rupture Containment function failed before or at the onset of core degradation, e.g., failure by an external.

Nuclear Power – Operation, Safety and Environment CNEN has introduced in Standard NE– (CNEN, ) the requirement for risk management, where the operating organization should develop, implement and continuously refine a model for managing the risk associated with various operational configurations.

- Evaluation of Ex-Vessel Steam Explosion Induced Containment Failure Probability for Japanese BWR Moriyama, K. / American Nuclear Society | Gedruckte Ausgabe. A M.D.B StephensE 1F G MECHANICSH I USCM NrEffects of microscopic inhomogeneities on the failure and fracture behavior of disordered and reinforced materialsO J.D.P Goddard R.M.S.

Thesis, University of Southern CaliforniaS U PublishedV ThesisW NX NY N[ Stephens, M.D.\ Goddard, J.D.