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Development of Friction Stir Processing for Repair of Nuclear Dry Cask Storage System Canisters

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Friction Stir Welding and Processing IX

Part of the book series: The Minerals, Metals & Materials Series ((MMMS))

Abstract

The Nuclear Regulatory Commission has identified chloride-induced stress corrosion cracking (CISCC) of austenitic stainless steel dry cask storage systems (DCSS) as an area of great concern. Friction stir processing (FSP) was used to repair laboratory-generated stress corrosion cracking (SCC) in representative stainless steel 304 coupons. Results of this study show FSP is a viable method for repair and mitigation CISCC. This paper highlights lessons learned and techniques developed to apply FSP to crack repair in sensitized thick section stainless steel 304. These include: development of process parameters, welding at low spindle speed, use of weld power and temperature control and optimization of these controls. NDE and destructive analysis are also presented to demonstrate effectiveness of the developed methods for SCC crack repair.

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References

  1. Hanson B, Alsaed H, Stockman C, Enos D, Meyer R, Sorenson K (2012) Gap analysis to support extended storage of used nuclear fuel. http://www.energy.gov/sites/prod/files/Gap%20Analysis%20Rev%200%20Final.pdf

  2. (2012) NRC INFORMATION NOTICE 2012-20: potential chloride-induced stress corrosion cracking of austenitic stainless steel and maintenance of dry cask storage system canisters. http://www.nrc.gov/docs/ML1231/ML12319A440.pdf

  3. Sutton B, Ross K, Grant G, Cannell G, Frederick G, Couch R (2017) Friction stir processing of degraded austenitic stainless steel nuclear fuel dry cask storage system canisters. In: Friction stir weld and processing IX, San Diego

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Authors and Affiliations

  1. Electric Power Research Institute, 1300 W WT Harris Blvd, Charlotte, NC, USA

    Ben Sutton, Greg Frederick & Robert Couch

  2. Pacific Northwest National Laboratory, 902 Battelle Blvd, Richland, WA, USA

    Ken Ross & Glenn Grant

  3. Fluor Enterprises, Inc., 1200 Jadwin Ave, Richland, WA, USA

    Gary Cannell

Authors
  1. Ken Ross
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  2. Ben Sutton
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  3. Glenn Grant
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  4. Gary Cannell
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  5. Greg Frederick
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  6. Robert Couch
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Corresponding author

Correspondence to Ken Ross .

Editor information

Editors and Affiliations

  1. Brigham Young University , Provo, Utah, USA

    Yuri Hovanski

  2. Denton, Texas, USA

    Rajiv Mishra

  3. Tohoku University , Sendai, Japan

    Yutaka Sato

  4. Pacific Northwest National Laboratory , Richland, Washington, USA

    Piyush Upadhyay

  5. University of Wisconsin Green Bay , Green Bay, Wisconsin, USA

    David Yan

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© 2017 The Minerals, Metals & Materials Society

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Ross, K., Sutton, B., Grant, G., Cannell, G., Frederick, G., Couch, R. (2017). Development of Friction Stir Processing for Repair of Nuclear Dry Cask Storage System Canisters. In: Hovanski, Y., Mishra, R., Sato, Y., Upadhyay, P., Yan, D. (eds) Friction Stir Welding and Processing IX. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-319-52383-5_5

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