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Title: Report on the Progress of Weld Development of Irradiated Materials at the Oak Ridge National Laboratory

Abstract

This report summarizes recent welding activities on irradiated alloys in the advanced welding facility at the Radiochemical Engineering Development Center of Oak Ridge National Laboratory and the development of post-weld characterization capabilities and procedures that will be critical for assessing the ability of the advanced welding processes housed within the facility to make successful repairs on irradiated alloys. This facility and its capabilities were developed jointly by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program and the Electric Power Research Institute, Long Term Operations Program (and the Welding and Repair Technology Center), with additional support from Oak Ridge National Laboratory. The significant, on-going effort to weld irradiated alloys with high Helium concentrations and comprehensively analyze the results will eventually yield validated repair techniques and guidelines for use by the nuclear industry in extending the operational lifetimes of nuclear power plants.

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [1];  [2];  [2];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Electric Power Research Inst. (EPRI), Knovville, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1436035
Report Number(s):
ORNL/SPR-2018/833
TRN: US1900655
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; WELDED JOINTS; WELDING; IRRADIATION; ALLOYS

Citation Formats

Feng, Zhili, Miller, Roger G., Chen, Jian, Tang, Wei, Clark, Scarlett R., Gibson, Brian T., Vance, Mark Christopher, Frederick, Gregory, Tatman, Jonathan K., and Sutton, Benjamin J. Report on the Progress of Weld Development of Irradiated Materials at the Oak Ridge National Laboratory. United States: N. p., 2018. Web. doi:10.2172/1436035.
Feng, Zhili, Miller, Roger G., Chen, Jian, Tang, Wei, Clark, Scarlett R., Gibson, Brian T., Vance, Mark Christopher, Frederick, Gregory, Tatman, Jonathan K., & Sutton, Benjamin J. Report on the Progress of Weld Development of Irradiated Materials at the Oak Ridge National Laboratory. United States. doi:10.2172/1436035.
Feng, Zhili, Miller, Roger G., Chen, Jian, Tang, Wei, Clark, Scarlett R., Gibson, Brian T., Vance, Mark Christopher, Frederick, Gregory, Tatman, Jonathan K., and Sutton, Benjamin J. Sun . "Report on the Progress of Weld Development of Irradiated Materials at the Oak Ridge National Laboratory". United States. doi:10.2172/1436035. https://www.osti.gov/servlets/purl/1436035.
@article{osti_1436035,
title = {Report on the Progress of Weld Development of Irradiated Materials at the Oak Ridge National Laboratory},
author = {Feng, Zhili and Miller, Roger G. and Chen, Jian and Tang, Wei and Clark, Scarlett R. and Gibson, Brian T. and Vance, Mark Christopher and Frederick, Gregory and Tatman, Jonathan K. and Sutton, Benjamin J.},
abstractNote = {This report summarizes recent welding activities on irradiated alloys in the advanced welding facility at the Radiochemical Engineering Development Center of Oak Ridge National Laboratory and the development of post-weld characterization capabilities and procedures that will be critical for assessing the ability of the advanced welding processes housed within the facility to make successful repairs on irradiated alloys. This facility and its capabilities were developed jointly by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program and the Electric Power Research Institute, Long Term Operations Program (and the Welding and Repair Technology Center), with additional support from Oak Ridge National Laboratory. The significant, on-going effort to weld irradiated alloys with high Helium concentrations and comprehensively analyze the results will eventually yield validated repair techniques and guidelines for use by the nuclear industry in extending the operational lifetimes of nuclear power plants.},
doi = {10.2172/1436035},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {4}
}

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