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Wednesday, May 6, 2020 | History

2 edition of Melt progression, oxidation, and natural convection in a severely damaged reactor core found in the catalog.

Melt progression, oxidation, and natural convection in a severely damaged reactor core

S. S. Dosanjh

Melt progression, oxidation, and natural convection in a severely damaged reactor core

by S. S. Dosanjh

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

    Subjects:
  • Nuclear reactor accidents -- United States -- Analysis.,
  • Nuclear reactors -- United States -- Safety measures -- Mathematical models.

  • Edition Notes

    Statementprepared by S.S. Dosanjh.
    ContributionsU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Sandia National Laboratories.
    The Physical Object
    Paginationxii, 76, 3 p. :
    Number of Pages76
    ID Numbers
    Open LibraryOL15362208M

    the core 3 High Reactor temperature Reactor not sized to take care of the core losses - Insufficient reactor core size 4 Reactor drawing more than rated current Reactor is drawing excessive harmonic currents - In the presence of a distorted supply voltage, the reactor draws harmonic currents - For 10% THDv, there is a 16% increase in IrmsFile Size: KB. the reactor. To cater such needs a simplified burnup calculation strategy to account for refueling and removal of molten salt fuel at any desired burnup has been identified in static molten salt reactor in batch mode as a first step of way forward. The features of in-house code ITRAN has been explored for such calculations. The effect of.

    Subtleties in the synthesis of materials can have a profound effect on the catalytic and photocatalytic properties of materials. Black TiO 2 nanotubes, demonstrating remarkable solar absorption, were synthesized using a stainless steel reactor. Using UVvis diffuse reflectance spectroscopy, XPS, EDS, ICP, and TEM, the change in electronic absorption of the TiO 2 nanotubes is explained by the Cited by: Numerous systems and back-up emergency core cooling systems are provided to ensure that reactor cooling water continues to flow through the reactor core to remove decay heat, even after the reactor has been shut down and the fission process has stopped. Only failure of all of these systems would allow the potential for a "severe core damage.

    High surface area ceria-titania materials were used as supports for manganese oxide for both warm-gas mercury capture and low temperature selective catalytic reduction. These materials exhibited excellent mercury capture capability at °C. Increasing manganese loadings improves the mercury capacities. In the presence of SO2, only a small decrease in mercury capacity was observed for the Cited by: Ion irradiation effects are studied on the Fe-based core-shell nanocluster (NC) films with core as Fe and shell as Fe3O4/Fe3N. These NC films were deposited on Si substrates to thickness of ∼ μm using a NC deposition system. The films were irradiated at room temperature with MeV Si2+ ions to ion fluences of and ions/cm2. It is found that the irradiation induces grain growth Cited by: 5.


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Melt progression, oxidation, and natural convection in a severely damaged reactor core by S. S. Dosanjh Download PDF EPUB FB2

Get this from a library. Melt progression, oxidation, and natural convection in a severely damaged reactor core. [S S Dosanjh; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Sandia National Laboratories.].

@article{osti_, title = {Melt propagation and oxidation in core debris beds}, author = {Dosanjh, S S}, abstractNote = {A two-dimensional model of melt progression, oxidation and natural convection in reactor core debris beds has been developed. Three fields are considered in the model: vapor, melt and solid.

Conservation equations are solved for the species of interest in each field. A nuclear meltdown (core meltdown, core melt accident, meltdown or partial core melt) is a severe nuclear reactor accident that results in core damage from overheating. The term nuclear meltdown is not officially defined by the International Atomic Energy Agency or by the Nuclear Regulatory Commission.

It has been defined to mean the accidental melting of the core of a nuclear reactor, however. Multi-dimensional approaches in severe accident modelling and analyses. of melt progression, across the core or in the lower plenum, In the model, the non - or little - damaged reactor.

As the reactor core material melts and relocates, the molten debris pool may be formed in the lower plenum of the reactor vessel or in the lower region of the core (Cho et al.,Cho et al.,Lee and Suh,Suh, a, Suh, b). If fission products are released from the molten pool, heat source in relocated material may Cited by: 4.

This paper is concerned with the development of approaches for assessment of core debris heat transfer and Control Rod Guide Tube (CRGT) cooling effectiveness in case of a Boiling Water Reactor (BWR) severe accident.

We consider a hypothetical scenario with stratified (metal layer atop) melt pool in the lower plenum. Effective Convectivity Model (ECM) and Phase-Change ECM (PECM) Cited by: 2.

The chemical reactions occurring among materials in a LWR core meltdown accident produce in each stage of the accident a number of effects on the chem Cited by: 2. Materials for nuclear reactor core applications.

Materials for nuclear reactor core applications. Paper The high-temperature oxidation of AGR fuel cladding Authors: R. Lobb, BSc, PhD. Lobb. Search for articles by this author, and H. Evans, BSc. The design criteria for harmonic reactors are driven by the harmonic spectrum provided along with current rating, inductance, temperature rise, taps and impulse rating.

The following considerations apply equally to both the single phase harmonic reactor and the three phase harmonic reactor when used in. A benchmark exercise based on the TMI-2 plant has been launched by the Working Group on the Analysis and Management of Accidents (WGAMA) of OECD/CSNI, in conjunction with.

Start studying Nuclear energy. Learn vocabulary, terms, and more with flashcards, games, and other study tools. Severe overheating of the core of a nuclear reactor resulting in the core melting and radiation escaping.

generators powering the water pumps were flooded allowing the core to. For APR, External Reactor Vessel Cooling (ERVC) is adopted as a primary severe accident management strategy for in-vessel retention (IVR) of corium.

The ERVC is a method of IVR by submerging the reactor vessel exterior. At the early stage of the APR design, only ex-vessel cooling, cooling of the core melt outsideCited by: 5. The Thermal-Hydraulics of a Boiling Water Nuclear Reactor [Lahey, Richard T., Jr., Moody, F.

J.] on *FREE* shipping on qualifying offers. The Thermal-Hydraulics of a Cited by: SPECIFIC PROCESSES AFFECTING THE COURSE OF EVENTS IN CORE MELT ACCIDENTS Melt progression 55 Hydrogen formation 55 Evaporation and nucleation 56 Reactions in the reactor coolant system 57 Aerosol nucleation 57 Condensation and chemisorption on aerosol particles 60 Agglomeration of aerosol particles MELCOR is a lumped-parameter control volume model that was originally developed to model severe accidents in reactor cores, including uncovering of the reactor core, fuel damage, hydrogen generation, and release of radioactive material from a variety of accident initiators including unrecovered LOCA, station blackout, and other unrecovered.

between the rate of heat transfer in a melt and the rate of mass transfer. MELT SPECIES MIXEDNESS During normal operating practice, the slag and alloy are sampled once each, at any ad-hoc time, once the flow of the melt through the tapping launder is fully developed.

To determine if significant spatial. ll5 TITLE: CORE MELT TECHNOLOGY FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET Laboratory OBJECTIVE: In severe reactor accidents in which molten core material escapes the reactor pressure vessel and falls into the reactor cavity, thermal and chemical interactions between the high-temperature core debris and structure.

2 Confinement Effects on Nucleate Boiling and Critical Heat Flux in Buoyancy-Driven Microchannels K.J.L. Geisler a, *, A. Bar-Cohen b aGeneral Dynamics Advanced Information Systems, Bloomington, MNUSA bUniversity of Maryland, Department of Mechanical Engineering, College Park, MDUSA *Corresponding author.

E-mail address: [email protected] (K.J.L. Geisler). If the specific surface energy for aluminum oxide is J/m2 and its modulus of elasticity is ( GPa), compute the critical stress required for the propagation of an internal crack of length mm.

Gubbins, T. Masters and F. Nimmo A i Δρ bod Δρ mod ρ +Δρ H f outer core inner core layer r ρ r i+d 3 1 2 r Figure 1. Cartoon of proposed density profiles for the lowermost outer core based on the assumption that changes in V P are due mainly to changes in density rather than bulk modulus.

T1 - Investigation on upper bounds of recriticality energetics of hypothetical core disruptive accidents in sodium cooled fast reactors. AU - Maschek, Werner. AU - Li, Rui. AU - Matzerath Boccaccini, Claudia. AU - Gabrielli, Fabrizio.

AU - Morita, Koji. PY - /1/1. Y1 - /1/1Cited by: 1.The first deviations in the results are registered after the initiation of in-core melt progression and material relocation phenomena, resulting in core geometry change.

More important deviations can be obtained in the late phase core degradation, e.g on the total corium mass in vessel lower plenum.In an AC Welding machine alternating current is supplied from single-phase transformers, either with variable _____ or with a variable inductance in each arc circuit to obtain desired current values.