Last edited by Mikagor
Saturday, August 8, 2020 | History

2 edition of effects of Fe-Ni-Co-V structural alloys on fusion reactor neutronic performance found in the catalog.

effects of Fe-Ni-Co-V structural alloys on fusion reactor neutronic performance

Oak Ridge National Laboratory. Engineering Physics Division.

effects of Fe-Ni-Co-V structural alloys on fusion reactor neutronic performance

by Oak Ridge National Laboratory. Engineering Physics Division.

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  • 12 Currently reading

Published by Dept. of Energy, Oak Ridge National Laboratory, for sale by the National Technical Information Service] in Oak Ridge, Tenn, [Springfield, Va .
Written in English

    Subjects:
  • Fusion reactors -- Design and construction.,
  • Alloys -- Effect of radiation on.,
  • Building materials -- Effect of radiation on.

  • Edition Notes

    StatementJ. M. Barnes ... [et al.], Computer Sciences Division.
    SeriesORNL/TM ; 6543, ORNL/TM -- 6543.
    ContributionsBarnes, J. M. 1943-, Union Carbide Corporation. Computer Sciences Division.
    The Physical Object
    Paginationiii, 11 p. ;
    Number of Pages11
    ID Numbers
    Open LibraryOL18016278M


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Effects of Fe-Ni-Co-V structural alloys on fusion reactor neutronic performance by Oak Ridge National Laboratory. Engineering Physics Division. Download PDF EPUB FB2

Operating temperature is of primary importance for the thermomechanical and radiation degradation of materials. Thermal creep is generally very pronounced for operating temperatures that exceed T M (where T M is the melting temperature of the structural alloy), and may become significant at operating temperatures as low as ~ –T ty degradation due to thermal Cited by: 1.

Alloys used for the reactor vessel, primary/secondary piping, IHX, and SGs must comply with relevant national construction codes such as the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Division 5 for high-temperature reactors or the RCC-MRX (design and construction rules for mechanical components in high Author: Stuart A.

Maloy, Ken Natesan, David E. Holcomb, Concetta Fazio, Pascal Yvon. From a safety point of view, it is important to study the damages and reliability of molten salt reactor structural alloy materials, which are subjected to extreme environments due to neutron.

@article{osti_, title = {Water-cooled blanket concepts for the Blanket Comparison and Selection Study}, author = {Morgan, G D and Bowers, D A and Jung, J and Misra, B and Ruester, D E}, abstractNote = {The primary goal of the Blanket Comparison and Selection Study (BCSS) was to select a limited number of blanket concepts for fusion power reactors, to serve as the focus for the U.S.

High strength, high conductivity copper alloys are prime candidates for high heat flux applications in fusion energy systems. This chapter reviews the physical and mechanical properties of.

Development and study of chemical vapor deposited tantalum base alloys. NASA Technical Reports Server (NTRS) Meier, G.

H.; Bryant, W. A technique for the chemical vapor deposition of alloys was process, termed pulsing, involves the periodic injection of reactant gases into a previously-evacuated reaction chamber where they blanket the substrate almost.

Control of molten salt corrosion of fusion structural materials by metallic beryllium. NASA Astrophysics Data System (ADS) Calderoni, P.; Sharpe, P.; Nishimura, H.; Terai, T.

A series of tests have been performed between and at the Safety and Tritium Applied Research facility of the Idaho National Laboratory to demonstrate chemical compatibility between the molten salt.

ORNL/TM/ Advanced High Temperature Reactor Systems and Economic Analysis September Status. Rev 0 Septem Prepared by D. Holcomb F. Peretz A. Qualls. Full text of "Materials studies for magnetic fusion energy applications at low temperatures - VIII" See other formats. Full text of "Materials studies for magnetic fusion energy applications at low temperatures, IV / edited by R.P.

Reed and N.J. Simon ; sponsored by Department of Energy, Office of Fusion. Multiple factors will influence the ultimate choice of a nuclear fuel cycle, including (1) the pace and scale of nuclear power deployment and (2) evolving technical, economic, and safety performance of fuel reprocessing methods, reactor types (both LWR and fast spectrum reactors), and disposal pathways for waste streams, and (3) the relative.

J Radiation Effects to Reactor Structural Materials The Development of Advanced Primary First Wall Alloys The severe environment of future fusion reactors is expected to drasti-cally limit the lifetime of the first wall structures if currently available The absence of water from the chemical processing system reduces the potential for criticality outside of the reactor based on moderator exclusion.

24 Fluoride salts, due to their chemical stability, have the potential to corrode most structural metal alloys, but some alloys have been developed that are resistant to against corrosive attack.

Reactor configuration affects A thrcugh the addition of structural materials. Effect of an inner blanket. With an inner blanket (Figure ), neutrons enter as if from multiple cores.

StructuralAlloysforNuclearEnergyApplicationsStructuralAlloysforNuclearEnergyApplicationsEditedbyG. Polevoy, V.B., V.V.

Leontyev, A.V. Ovchinnikov, O.B. Tarasova, Institute of Physics and Power Engineering, "The Features of Neutronic Calculations for the Fast Reactor with the Reflector-Moderator," Anniversary Specialist Conference on Nuclear Power Engineering in Space, May, ; High-Temperature Fuel Compositions and Structural Materials.

Alloy Oxidation Introduction Doping Effect Internal Oxidation and Catastrophic Oxidation Sequences in Alloy Oxidation Scaling of Binary and Ternary Alloys Reactive Element Effects on the Oxidation Behavior of Alloys Hot Corrosion Protective Coatings for High-Temperature Applications Conclusion References.

Selective conversion is sought to produce useful products such as acetylene, carbon black, or high performance carbon materials The focus is on reactor development so existing pathways to integration of any necessary catalysts should be clearly demonstrated in the proposal.

No clear effects of hydrogen on the mechanical behavior have been found for single-phase TiAl, whereas two-phase alloys with Ti,AI showed embrittlement probably due to the gettering effect of Ti,AI. More work is necessary for a clear understanding of the embrittling mechanisms (Eliezer et al., ; Thompson, ).

Applications. Free essays, homework help, flashcards, research papers, book reports, term papers, history, science, politics. This effect was actually observed using the Mössbauer effect.

The maximal deviation from time dilation was, thus the precision was much higher than that () of the Ives–Stilwell experiments. Such experiments were performed by Hay et al. (),[8] Champeney et al. (, ),[9][10] Kündig ().[11].