Last edited by JoJohn
Thursday, October 8, 2020 | History

2 edition of TAC2D studies of Mark I containment drywell shell melt-through found in the catalog.

TAC2D studies of Mark I containment drywell shell melt-through

Jay J. Weingardt

TAC2D studies of Mark I containment drywell shell melt-through

by Jay J. Weingardt

  • 17 Want to read
  • 18 Currently reading

Published by Division of Reactor Accident Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English

    Subjects:
  • Boiling water reactors -- Accidents -- Computer simulation.,
  • Nuclear reactors -- Containment -- Computer simulation.

  • Edition Notes

    StatementJay J. Weingardt, Kenneth D. Bergeron.
    ContributionsBergeron, Kenneth D., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor Accident Analysis., Sandia National Laboratories.
    The Physical Object
    Paginationviii, 41, [19] p. :
    Number of Pages41
    ID Numbers
    Open LibraryOL15378210M

    The containment drywell (D/W) should have failed at 15 March , at the cable penetration seal due to high temperature caused by the fuel materials heating up on the floor of the D/W, which had The subsequent Reactor Safety Study, which was issued as the WASH report in (USNRC, ), concluded that a severe accident was “the only way that potentially large amounts of radioactivity could be released by melting the fuel in the reactor core.” All risk studies performed subsequent to WASH have found this to be the ://

      Fig. shows pressure suppression containment consisting of an annular wetwell and a drywell housing important parts of the safety systems. The wetwell heat sink capacity should be sufficient to absorb all the steam released during a LOCA and any additional decay heat generation heating up the emergency core coolant (ECC). MBA智库文档,领先的管理资源分享平台。分享管理资源,传递管理智慧。 ASME锅炉及压力容器规范 第III卷 核设施部件构造规则 第2册 混泥土安全壳规范

      • Mark-up a copy of G complete through Step • Mark-up a copy of OP complete to step EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. BOOTH OPERATOR CUE Multimedia Environmental Compliance Guide for Food Processors. THE GUIDE: WHAT IT Is; WHAT IT DOES I. I Why an Environmental Compliance Guide for Food Processors As food processors, you are regulated by a variety of federal laws administered by the U.S. Environmental Protection Agency (EPA) that impact human activities and the ://?Dockey=


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TAC2D studies of Mark I containment drywell shell melt-through by Jay J. Weingardt Download PDF EPUB FB2

TAC2D studies of Mark I containment drywell shell melt-through [Jay J Weingardt] on *FREE* shipping on qualifying :// Get this from a library. TAC2D studies of Mark I containment drywell shell melt-through. [Jay J Weingardt; Kenneth D Bergeron; U.S.

Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor Accident Analysis.; Sandia National Laboratories.] Numerous studies of the question have been undertaken. In the draft version of the US Nuclear Regulatory Commission's risk reference document, NUREG, the drywell shell melt-through issue was identified as being one of the most important contributors   Analyses of Mark I drywell shell melt-through Conference Weingardt, J J ; Bergeron, K D - Trans.

Nucl. Soc.; (United States) In the vent of a core meltdown accident and subsequent release of molten core debris (corium) onto the drywell floor of a boiling water reactor (BWR) and a Mark I containment design, the issues of corium spreading and The U.S.

Department of Energy's Office of Scientific and Technical Information   J.J. Weingardt and K.D. Bergeron, TAC2D studies of Mark I containment drywell shell melt-through, NUREG/CR, SAND (Aug.

[3] J. Cleveland and T. Kress, Anaiysis of the thermal re- sponse of a BWR Mark I shell to direct contact by molten core materials, Transactions of the Sixteenth Water Reac- tor Safety Information Meeting   J.J.

Weingardt and K.D. Bergeron, TAC2D studies of Mark-I containment drywell shell melt-through, Report NUREG/ CR, SAND, Sandia National Laboratories, August Recommended articles Citing articles (0) @article{osti_, title = {Analyses of corium spreading in Mark I containment geometry}, author = {Sienicki, J J and Chu, C C and Farmer, M T}, abstractNote = {An assessment of melt spreading in the Mark I system has been carried out using the MELTSPREAD-1 computer code together with supporting analyses.

Application of MELTSPREAD-1 confirms the calculation of shell survival in a wet Feasibility study for improved steady-state initialization algorithms for the RELAP5 computer code [micr RELAP5/MOD3 assessment using the semiscale 50% feed line break test S-FS [microform] / prepared by E.

TAC2D studies of Mark I containment drywell shell melt-through [microform] / Jay J. Weingardt, Kenneth Safety of Nuclear Power Reactors. The risks from western nuclear power plants, in terms of the consequences of an accident or terrorist attack, are minimal compared with other commonly accepted risks.

Nuclear power plants are very robust. News and information on nuclear power, nuclear energy, nuclear energy for sustainable development, uranium mining, uranium enrichment, nuclear generation   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 :// TAC2D studies of Mark I contaiment drywell shell melt-through.

about the survivability of the BWR Mark I containment boundary in the event of a core-melt accident. Since TAC2D is a two Analyses of Mark I drywell shell melt-through. the BWR Mark I containment boundary in the event of a severe accident resulting in corium spreading to the drywell shell.

Since TAC2D is a two   d X 2 d t = K, where X is the layer thickness or total oxygen mass gain in both α – Zr(O) and ZrO 2 layers. In addition the temperature dependent kinetic constant verifies an Arrhenius formulation: K = A e − B / R T where T is the wall temperature and R is the perfect gas constant.

For typical transient sequences, the diffusion of oxygen into the Zircaloy tends to limit the oxidation   Fukushima Commentary 1 10/23//25/ Arnie Gundersen profits on Japan fears, Japanese renewables, Japan blasts WHO, apocalyptic rumor make headlines, Mainichi gets it wrong, Japanese economic collapse, nuclear robot inspection, real disaster in Japan, tsunami refugees ignored, what is a Becquerel?, unit 2 phantom melt-through, Fukushima meltdowns, and cold   I am currently compiling an update for the Fukishima Nuclear Accident as of March The situation is developing very quickly and commenters on this thread (March 16 updates) are doing an excellent job at posting regular ile, here is a guest post from Luke Weston.

Looks like we need an update post on the situation with the Fukushima nuclear power ://   The BWR Mark I (used at Fukushima I) has a Primary Containment system comprising a free-standing bulb-shaped drywell of 30 mm steel backed by a reinforced concrete shell, and connected to a torus-shaped wetwell beneath it containing the suppression pool A high pressure test of a mixed-scaled model ( in geometry and in shell thickness) of a steel containment vessel (SCV), representing an improved boiling water reactor (BWR) Mark II containment, was conducted on Decemberat Sandia National Laboratories.

This paper describes the preliminary results of the high pressure ://?q="Bwr. 2 Background on Japanese and U.S. Nuclear Plants. This chapter is intended to provide non-expert readers with basic information about nuclear power plant 1 design, operation, and regulation in Japan and the United States.

This information will be useful for understanding the technical discussions in subsequent report :// shows the inner structures of a BWR Mark I containment. The 3-D geometry model for the GASFLOW-MPI simulation is shown in Fig.

The length (X), width (Y) and height (Z) of the computational. 4 Fukushima Daiichi Nuclear Accident. The focus of this chapter is on the Maaccident at the Fukushima Daiichi nuclear plant: the accident time line key events during the accident, actions taken to bring the plant’s reactors to cold shutdown, and challenges faced in taking those ://The FASt TEst Reactor (FASTER) plant is a sodium-cooled fast spectrum test reactor design that was developed as part of an advanced demonstration and test reactor study, and provides high levels NRC on Containment Failure Due to Drywell Shell Melt-through (pdf): There are two basic types of meltthrough to consider.

First is the possibility of basemat meltthrough (the China Syndrome) This failure mode is not generally catastrophic, because of the long time available for emergency response actions and the possibility of some