Helium embrittlement model and program plan for weldability of ITER materials

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Description

This report presents a refined model of how helium embrittles irradiated stainless steel during welding. The model was developed based on experimental observations drawn from experience at the Savannah River Site and from an extensive literature search. The model shows how helium content, stress, and temperature interact to produce embrittlement. The model takes into account defect structure, time, and gradients in stress, temperature and composition. The report also proposes an experimental program based on the refined helium embrittlement model. A parametric study of the effect of initial defect density on the resulting helium bubble distribution and weldability of tritium aged ... continued below

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40 p.

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Louthan, M. R., Jr.; Kanne, W.R. Jr.; Tosten, M.H.; Rankin, D.T. & Cross, B.J. February 1, 1997.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 49 times . More information about this report can be viewed below.

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Description

This report presents a refined model of how helium embrittles irradiated stainless steel during welding. The model was developed based on experimental observations drawn from experience at the Savannah River Site and from an extensive literature search. The model shows how helium content, stress, and temperature interact to produce embrittlement. The model takes into account defect structure, time, and gradients in stress, temperature and composition. The report also proposes an experimental program based on the refined helium embrittlement model. A parametric study of the effect of initial defect density on the resulting helium bubble distribution and weldability of tritium aged material is proposed to demonstrate the roll that defects play in embrittlement. This study should include samples charged using vastly different aging times to obtain equivalent helium contents. Additionally, studies to establish the minimal sample thickness and size are needed for extrapolation to real structural materials. The results of these studies should provide a technical basis for the use of tritium aged materials to predict the weldability of irradiated structures. Use of tritium charged and aged material would provide a cost effective approach to developing weld repair techniques for ITER components.

Physical Description

40 p.

Notes

INIS; OSTI as DE97060154

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  • Other Information: PBD: Feb 1997

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  • Other: DE97060154
  • Report No.: WSRC-TR--97-0031
  • Grant Number: AC09-96SR18500
  • DOI: 10.2172/525045 | External Link
  • Office of Scientific & Technical Information Report Number: 525045
  • Archival Resource Key: ark:/67531/metadc689657

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • February 1, 1997

Added to The UNT Digital Library

  • Aug. 14, 2015, 8:43 a.m.

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  • Feb. 9, 2016, 5:52 p.m.

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Louthan, M. R., Jr.; Kanne, W.R. Jr.; Tosten, M.H.; Rankin, D.T. & Cross, B.J. Helium embrittlement model and program plan for weldability of ITER materials, report, February 1, 1997; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc689657/: accessed October 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.