Simplified Design Criteria for Very High Temperature Applications in Generation IV Reactors

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The goal of this activity is to provide simplified criteria which can be used in rapid feasibility assessments of the structural viability of very high temperature components in conceptual and early preliminary design phases for Generation IV reactors. The current criteria in ASME Code Section III, Subsection NH, hereafter referred to as NH, (and Code Case N-201 for core support structures) are difficult and require a complex deconstruction of finite element analysis results for their implementation. Further, and most important, times, temperatures and some materials of interest to the very high temperature Generation IV components are not covered by the ... continued below

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McGreevy, TE December 15, 2004.

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Description

The goal of this activity is to provide simplified criteria which can be used in rapid feasibility assessments of the structural viability of very high temperature components in conceptual and early preliminary design phases for Generation IV reactors. The current criteria in ASME Code Section III, Subsection NH, hereafter referred to as NH, (and Code Case N-201 for core support structures) are difficult and require a complex deconstruction of finite element analysis results for their implementation. Further, and most important, times, temperatures and some materials of interest to the very high temperature Generation IV components are not covered by the current provisions of NH. Future revisions to NH are anticipated that will address very high temperature Generation IV components and materials requirements but, until that occurs interim guidance is required for design activities to proceed. These simplified criteria are for design guidance and are not necessarily in rigorous compliance with NH methodology. Rather, the objective is for criteria which address the early design needs of very high temperature Generation IV components and materials. The intent is to provide simplified but not overly conservative design methods. When more rigorous criteria and methods are incorporated in NH, the degree of conservatism should obviously be reduced. These criteria are based on currently available information. Although engineering judgments have been made in the formulation of these criteria they are not intended to require additional development or testing prior to implementation as a tool for use in conceptual and early preliminary design. Appendices are provided herein that contain useful information. The simplified methods were developed specifically with Alloy 617 in mind; however, they could be applied for the same intended purpose for other materials such as 9Cr-1Mo, Alloy 800H, etc. However, supporting design curves, stress allowables, and isochronous curves may/were not available at this time for temperatures of approximately 1000 C. Appendix A is a brief summary of the Simplified Methods that follow. Appendix B contains charts and plots of allowable stress values for Alloy 617. Appendix C contains the suggested creep-fatigue design curves for Alloy 617 at 950-1000 C, and Appendix D contains isochronous stress-strain curves for Alloy 617 at 927 & 982 C.

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  • Report No.: ORNL/TM-2004/308
  • Grant Number: DE-AC05-00OR22725
  • DOI: 10.2172/885743 | External Link
  • Office of Scientific & Technical Information Report Number: 885743
  • Archival Resource Key: ark:/67531/metadc892743

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  • December 15, 2004

Added to The UNT Digital Library

  • Sept. 23, 2016, 2:42 p.m.

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  • Dec. 1, 2016, 7:59 p.m.

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McGreevy, TE. Simplified Design Criteria for Very High Temperature Applications in Generation IV Reactors, report, December 15, 2004; [Tennessee]. (digital.library.unt.edu/ark:/67531/metadc892743/: accessed September 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.