Last edited by Gardalmaran
Sunday, May 17, 2020 | History

4 edition of The probability of containment failure by direct containment heating in Surry found in the catalog.

The probability of containment failure by direct containment heating in Surry

The probability of containment failure by direct containment heating in Surry

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  • 2 Currently reading

Published by Division of Systems Research, 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:
  • Surry Power Station (Va.),
  • Nuclear reactors -- Virginia -- Containment,
  • Pressurized water reactors -- Accidents -- Virginia,
  • Nuclear power plants -- Risk assessment -- Virginia

  • Edition Notes

    Statementprepared by M.M. Pilch ... [et al.].
    ContributionsPilch, M., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Sandia National Laboratories.
    The Physical Object
    FormatMicroform
    Paginationxxi, 88, [162] p.
    Number of Pages162
    ID Numbers
    Open LibraryOL17453459M
    OCLC/WorldCa37114464

    Historical Perspectives and Insights on Reactor Consequence Analyses Prepared By Hossein P. Nourbakhsh November Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC QRA calculation, namely the ‘Red Book’, the ‘Yellow Book’ and the ‘Green Book’. The ‘Red Book’, describing the methods for determining and processing probabilities, is to be used to derive scenarios leading to a loss of containment event [CPR12E]. The ‘Yellow Book’ describesFile Size: 3MB.

      To help IT professionals in these decisions, we comprised a short list of 5 mistakes to avoid when outlining a containment project specification. 1. Assumptions. Everyone knows the saying around assumptions and it holds true with every containment project. In order to ensure a well-specified containment project, the fewer assumptions are always. The SARNET2 (severe accidents Research NETwork of Excellence) project started in April for 4 years in the 7th Framework Programme (FP7) of the European Commission (EC), following a similar first project in FP6. Forty-seven organisations from 24 countries network their capacities of research in the severe accident (SA) field inside SARNET to resolve the most important remaining Cited by: 1.

    • Detailed direct causes (DDC) (left side): The detailed direct cause is the event or collection of events that led to the direct cause • Direct causes (DC) left side(): The immediate causes of the necessary and sufficient causes (NSCs). For a given NSC, the list of direct causes tends to File Size: 2MB. Unit I of Surry Power Station, Figures 6 and 7 show the probability of early containment failure conditional on core damage obtained in NUREG-1 compared to the IPE results. These probabilities include events that cause structural failure of For example, direct containment heating is an important failure mode for PWRs withAuthor: W.T. Pratt, J. Lehner, A. Camp, E. Chow.


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The probability of containment failure by direct containment heating in Surry Download PDF EPUB FB2

@article{osti_, title = {The probability of containment failure by direct containment heating in surry}, author = {Pilch, M M and Allen, M D and Bergeron, K D and Tadios, E L and Stamps, D W and Spencer, B W and Quick, K S and Knudson, D L}, abstractNote = {In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the reactor coolant system (RCS) at high Cited by:   The probability of containment failure by direct containment heating in surry Showing of pages in this report.

PDF Version Also Available for by: The probability of containment failure by direct containment heating in Zion Technical Report Pilch, M M ; Yan, H ; Theofanous, T G This report is the first step in the resolution of the Direct Containment Heating (DCH) issue for the Zion Nuclear Power Plant using the Risk Oriented Accident Analysis Methodology (ROAAM).

In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the reactor coolant system (RCS) at high pressure, the expulsion of molten core debris may pressurize the reactor containment building (RCB) beyond its failure by: Containment Failure by Direct Containment Heating in Surry”; and NUREG, “The Probability of Containment Failure by Direct Containment Heating in Zion,” documented resolution of the issue for all large dry and subatmospheric PWR containments, on a plant specific basis.

As a result of this research, we now know that the threat to containment integrity. (), The Probability of Containment Failure by Direct Containment Heating in Surry, NUREG/CR, U.S. Regulatory Commission. Google Scholar Roush, M. L., Modarres, M.

and Hunt, R. N., Application of Goal Trees to Evaluation of the Impact of Information upon Plant by: 2. Since the purpose of the present analysis is the evaluation of the probability of failure of a nuclear power plant containment subjected to acci- dental aircraft impact, the conservative assumption of normal impact is introduced here.

This assumption also simplifies the analysis significantly. Analysis of engine and fuselage impact Cited by: 6. a reassessment of low probability containment failure modes and phenomena in a long-term station blackout acacia brunett, richard denning, and tunc aldemir*.

The mode of containment failure (i.e., gross failure versus leakages through failure of penetrations) also influences the amount of radioactive materials inside the containment that would be released to the environment.

The likelihood and severity of many challenges to containment integrity such as direct containment heating (DCH) and core-concrete. An aboveground storage tank has leaked flammable liquid into the surrounding diked containment area. A foam stream is directed against the side of the tank. Foam is running down the side of the tank and covering the spilled fuel in the containment area.

COVID Resources. Reliable information about the coronavirus (COVID) is available from the World Health Organization (current situation, international travel).Numerous and frequently-updated resource results are available from this ’s WebJunction has pulled together information and resources to assist library staff as they consider how to handle coronavirus.

Pilch MM et al () The probability of containment failure by direct containment heating in Surry, NUREG/CR Sandia National Laboratories, Albuquerque, NM Google Scholar Cited by: 1. Get this from a library.

The probability of containment failure by direct containment heating in Zion: [supplement]. [M Pilch; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Sandia National Laboratories.;].

containment building failure of a Pressurized Water Reactor (PWR) during a hypothetical severe accident will represent a major risk to the public health and safety due to the probability of radioactive release.

One of the potential contributors to the early pressurization and failure of the containment is direct containment heating (DCH).File Size: KB. The Probability of Mark-I containment failure by melt-attack of the liner [microform] / prepared by T.G.

Theofanous [et al.] Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission: Supt. of Docs., U.S.

G.P.O. [distributor] Washington, DC Australian/Harvard Citation. Pilch and U.S. Nuclear Regulatory Commission, The Probability of Containment Failure by Direct Containment Heating in Surry,NUREG/CR, SAND J.

Binder, L. McUmber, and B. Spencer, Direct Containment Heating Integral Effects Tests at 1/40 Scale in Zion Nuclear Power Plant Geometry, Argonne National Laboratory Cited by: 1.

• Commission containment performance goals –Probability of containment failure given core damage should not exceed approximately This is not a requirement in and of itself. –Containment should maintain its role as a reliable leak-tight barrier for a minimum of 24 hours following the onset of File Size: KB.

The Probability of liner failure in a Mark-I containment. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission: For sale by the U.S.

G.P.O., Supt. of Docs. Experimental results of tests to investigate the effects of hole diameter resulting from bottom head failure on Direct Containment Heating (DCH) in the Surtsey Test Facility Article Mar The probability for early containment failure and bypass, which are necessary conditions for appreciable health impacts, is 2% in the PWR with the high risk of core damage and 15% in the other two PWRs, versus about 50% in the BWRs.

Scenarios of core melt with high primary pressure: direct containment heating (DCH – due to the violent expulsion of part of the molten core from the vessel and to its fragmentation in the atmosphere with consequent combustion and heat production) and destructive forces on the vessel (due to the expulsion of molten material from the vessel at.Reliability Based Pressure Containment Uprating Elie Dib, Elie Dib.

Intecsea (UK) Ltd., Knaphill, Surrey, England, UK. Search for other works by this author on: This Site. PubMed. Google Scholar. Sherif El-Gebaly, The results present a burst pressure with an indication of a safety factor and associated with a probability of failure.

A Author: Elie Dib, Sherif El-Gebaly, Frank Drennan.Direct Containment Heating Direct containment heating (DCH) is the collective term for everything that can happen if the core melts through the bottom of the reactor vessel —a large increase in pressure and the production of large amounts of hydrogen.

Direct containment heating is possible for hours after core damage. Although thisFile Size: KB.