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Wednesday, July 29, 2020 | History

2 edition of Cladding swelling and rupture models for LOCA analysis found in the catalog.

Cladding swelling and rupture models for LOCA analysis

D. A. Powers

Cladding swelling and rupture models for LOCA analysis

by D. A. Powers

  • 244 Want to read
  • 20 Currently reading

Published by Division of Systems Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, National Technical Information Service in Washington, D.C, Springfield, Va .
Written in English

    Subjects:
  • Nuclear fuel claddings,
  • Pressurized water reactors -- Cooling,
  • Water cooled reactors -- Accidents

  • Edition Notes

    StatementD.A. Powers, R.O. Meyer
    ContributionsMeyer, R. O., U.S. Nuclear Regulatory Commission. Division of Systems Safety
    The Physical Object
    Paginationxviii, 114 p. :
    Number of Pages114
    ID Numbers
    Open LibraryOL14947763M

    Forgeron T, Brachet JC, Barcelo F, Castaing A, Hivroz J, Mardon J, Bernaudat C () Experiment and modeling of advanced fuel rod cladding behavior under LOCA conditions: alpha-beta phase transformation kinetics and EDGAR methodology ASTM STP , pp – Google Scholar. shrinking, swelling, cupping, warping, bowing or twisting, and generally won’t show a raised grain. The higher grades of Douglas Fir are quite refined with sound, tight knots making it suitable for shelving, cladding and panelling. It is dimensional stable and recognised for its strength-to-weight ratio. Its high specific gravity.

    Parameters Influencing the Secondary Hydrogenation of Zr-Sn and Zr-Nb Alloys During Steam Oxidation Under LOCA and Severe Accident Conditions. Mirco K. Grosse, Martin Steinbrueck, Rupture Frequency of CANDU Experiences From Structural Dynamic Analysis Projects of BWR Plants Within the Scope of Power Uprate Projects Using FEA. Platinum Roofing Ltd carry out cladding and sheeting repair to all types of commercial units and retail parks accross the country on an as and when basis as well as offering regular maintenance contracts for Tenants, Landlords, Estate agencies & Surveyors.

    MortarGives masonry units a water & air tight seal igmentsCan be added to mortar to create any range of colors%Can be added to mortar to create any range of colorsAdmixtureAdded to mortar to extend the useful workable life%Added to mortar to extend the useful workable lifeWytheA vertical layer of bricks or masonry unit, one layer thick%A vertical layer of . Cladding-pumped fibers are double clad, meaning that the fiber's coating acts as a second cladding, allowing the first cladding to function as a waveguide. Double-clad fibers typically have a low-NA single mode (SM) or large-mode-area (LMA) core for the emitted light and a high-NA, multimode first cladding for the pump light.


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Cladding swelling and rupture models for LOCA analysis by D. A. Powers Download PDF EPUB FB2

Cladding swelling and rupture models for LOCA analysis (OCoLC) Material Type: Government publication, National government publication: Document Type: Book: All Authors / Contributors: D A Powers; R O Meyer; U.S. Nuclear Regulatory Commission.

Division. NUREG "Cladding, Swelling And Rupture - Models For LOCA Analysis" (Generic Letter ) GL UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. January 3, ALL POWER REACTOR LICENSEES Gentlemen: Our letter of Decem asked for written comments to the draft report of NUREG.

Buy Cladding swelling and rupture models for LOCA analysis by Powers, D. A (ISBN:) from Amazon's Book Store. Everyday low prices and free delivery on eligible : D.

A Powers. D.A. Powers, R.O. Meyer, "Cladding Swelling and Rupture Models for LOCA Analysis", NUREG, BEMUSE Phase V Report, "Uncertainty and Sensitivity Analysis of a LB-LOCA in ZION Nuclear. The results demonstrate the importance of modeling the thermal-hydraulic effects due to grids, and clad swelling and rupture to correctly predict the clad temperature response during the reflood phase of large break LOCA.

The RELAP5 models and the test results are described in this paper. In Fig. 11 the rupture (burst) temperature versus hoop stress data for new alloys are compared to the database for Zircaloy-4, which is a collection of cladding rupture data for a variety of materials and pressurization conditions.

The comparison shows that the four values for relatively soft FeCrAl alloys, i.e., T35Y, Kanthal-AF, and T35Y2 Cited by: @article{osti_, title = {Thermal-hydraulic effects of clad swelling and rupture during reflood}, author = {Nithianandan, C.K.

and Biller, J.R.}, abstractNote = {During a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), the cladding of some fuel rods may undergo swelling and rupture.

Droplet breakup at swelled and ruptured locations plays an. @article{osti_, title = {Life time estimation for cladding tube crackings by absorber swelling in PWR RCCA rodlets}, author = {Matsuoka, Takanori and Yonezawa, Toshio and Nakamura, Kazuhiro and Myojin, Hisashige and Shimizu, Juntarou and Nagata, Tadahisa}, abstractNote = {On-site rodlet outer diameter measurement and hot cell examination of typical.

Powers, R. Meyer, Cladding Swelling and Rupture Models for LOCA Analysis, NUREG, US Nuclear Regulatory Commission, Fundamental Aspects of Nuclear Reactor Fuel Elements Article. Introduction.

The fuel rod behavior under transient and accident conditions is one of the major safety concerns in PWRs analysis. Consequences of various Design Base Accidents (DBA) such as LOCA and RIA are required to be examined and qualified under defined safety criteria in order to avoid severe core damage (Barré et al., ).During transient and accident conditions, Cited by: 3.

In the LOCA safety analysis, a cladding failure or burst criterion is needed to predict the temperature and time at which cladding ruptures, and also. Swelling Cladding. Both the fuel and cladding can swell.

Cladding covers the fuel to form a fuel pin and can be deformed. It is normal to fill the gap between the fuel and the cladding with helium gas to permit better thermal contact between the fuel and the cladding.

During use the amount of gas inside the fuel pin can increase because of the formation of noble gases (krypton and. Realistic Large Break LOCA Analysis ANP(NP) Rev.

0 Page ii Nature of Changes Item Page 1. All Description and Justification This is a new document. AREVA NP Inc. Sequoyah Units 1 and 2 HTP Fuel Realistic Large Break LOCA Analysis ANP(NP) Rev. 0 Page iii Contents.

However, cladding perforation is an important consideration because of its radiological implications, i.e., the release of radioactive fission products from the fuel.

There are two failure modes that could potentially cause cladding perforation during the LOCA: tensile failure and creep rupture. WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAPNP Volume 1, Rev.

0 Sections Code Qualification Document for Best Estimate Small Break LOCA Analysis Volume 1: Models and Corr. — — — — —, NUREG, “Cladding, Swelling and Rupture Models for LOCA Analysis,” April — — — — —, NUREG (FEMA-REP-1), “Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of.

The SiC cladding shows large swelling by irradiation. It increases the gap size and decreases cladding thermal conductivity. The mechanism of relaxation of stress is also different from the Zircaloy cladding. The experimental data for SiC materials are still insufficient to construct the models, especially for evaluating fracture behavior.

Loca Phenomena [Autosaved] - Free download as Powerpoint Presentation .ppt), PDF File .pdf), Text File .txt) or view presentation slides online. Scribd is the world's largest social reading and publishing site. However, cladding perforation is an important consideration because of its radiological implications, i.e., the release of radioactive fission products from the fuel.

There are two failure modes that could potentially cause cladding perforation during the. Fig. 9Calculation of Sub-Channel Blockage References 1 E. Hindle UKAEA Springfields unpublished work 2 R.

Chapman Multi-rod burst test program Progress report January–June NUREG/CR, ORNL/NUREG/TM March 3 S. Kawasaki, H. Uetsuka, and T.

Furuta Multi-rod burst tests under loss of coolant conditions OECD-NEA. The purpose of this paper is to present the basic principles and relevant advances in the computational modeling of abdominal aortic aneurysms and endovascular aneurysm repair, providing the community with up-to-date state of the art in terms of numerical analysis and biomechanics.

Frameworks describing the mechanical behavior of the aortic wall already by: MOXY-MOD32, Thermal Analysis Swelling and Rupture of BWR Fuel Elements During LOCA: iaea MSM-SOURCE, Neutron Source Generator for MCNP from Proton Neutron Interaction: nesc MUCHA, Fuel Rod Pair Thermohydraulics During LOCA and ECCSA for LWR: nea MULTI-KENO, Criticality Safety Analysis by Monte-Carlo: nea"One local resident, Angela Blakely, told STV News at the time that yellow cladding on the corners of the building was behind the speed with which the fire spread, saying it took "five minutes"." "The Irvine blaze led Westminster's environment, transport and regional affairs committee to carry out an inquiry in