Residual stress and strain examination in Peach Bottom fuel test elements

Wallroth, C F; Miller, C M; Saurwein, J J

Title: Residual stress and strain examination in Peach Bottom fuel test elements

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Abstract

An examination of residual stresses and strains has been carried out experimentally on structural graphite components removed from Peach Bottom High-Temperature Gas-Cooled Reactor (HTGR) fuel elements. The purpose of this work is to confirm predicted stress distributions. Twenty-nine teledial fuel elements (of six- and eight-hole design) were irradiated in the Peach Bottom HTGR to fluences of less than or equal to 4 x 10/sup 25/ n/m/sup 2/ (E greater than 29 fJ) and time-average temperatures up to 1100/sup 0/C. The irradiation history was modeled with HTGR design codes. Performance predictions were verified by in-pile thermocouples and fuel burnup measurements. The predicted irradiation-induced strains were found to be in quantitative agreement with postirradiation measurements (less than or equal to 0.5 percent shrinkage over a 70-mm diameter). As a result of the temperature distribution in the teledial bodies, compressive stresses were predicted at the periphery and tensile stresses in the inner zones. A total of 19 graphite bodies from 8 different fuel elements were examined destructively for structural integrity and residual stresses.

Authors:: Wallroth, C F; Miller, C M; Saurwein, J J

Publication Date:: Fri May 20 00:00:00 EDT 1977

Research Org.:: General Atomic Co., San Diego, CA (USA)

OSTI Identifier:: 7317955

Report Number(s):: GA-A-14324; CONF-770807-22
TRN: 77-015731

DOE Contract Number:: EY-76-C-03-0167-017

Resource Type:: Conference

Resource Relation:: Conference: 4. international conference on structural mechanics in reactor technology, San Francisco, CA, USA, 15 Aug 1977

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL ELEMENTS; STRESS ANALYSIS; HTGR TYPE REACTORS; BURNUP; DESTRUCTIVE TESTING; GRAPHITE; PEACH BOTTOM-1 REACTOR; PHYSICAL RADIATION EFFECTS; CARBON; ELEMENTS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; MATERIALS TESTING; NONMETALS; POWER REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; 210300* - Power Reactors, Nonbreeding, Graphite Moderated

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                    Wallroth, C F, Miller, C M, and Saurwein, J J. Residual stress and strain examination in Peach Bottom fuel test elements.  United States: N. p., 1977. 
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                    Wallroth, C F, Miller, C M, & Saurwein, J J. Residual stress and strain examination in Peach Bottom fuel test elements.  United States.

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                    Wallroth, C F, Miller, C M, and Saurwein, J J. 1977.  
        "Residual stress and strain examination in Peach Bottom fuel test elements".  United States.  https://www.osti.gov/servlets/purl/7317955.

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@article{osti_7317955,

  title        = {Residual stress and strain examination in Peach Bottom fuel test elements},

  author       = {Wallroth, C F and Miller, C M and Saurwein, J J},

  abstractNote = {An examination of residual stresses and strains has been carried out experimentally on structural graphite components removed from Peach Bottom High-Temperature Gas-Cooled Reactor (HTGR) fuel elements. The purpose of this work is to confirm predicted stress distributions. Twenty-nine teledial fuel elements (of six- and eight-hole design) were irradiated in the Peach Bottom HTGR to fluences of less than or equal to 4 x 10/sup 25/ n/m/sup 2/ (E greater than 29 fJ) and time-average temperatures up to 1100/sup 0/C. The irradiation history was modeled with HTGR design codes. Performance predictions were verified by in-pile thermocouples and fuel burnup measurements. The predicted irradiation-induced strains were found to be in quantitative agreement with postirradiation measurements (less than or equal to 0.5 percent shrinkage over a 70-mm diameter). As a result of the temperature distribution in the teledial bodies, compressive stresses were predicted at the periphery and tensile stresses in the inner zones. A total of 19 graphite bodies from 8 different fuel elements were examined destructively for structural integrity and residual stresses.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/7317955},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Fri May 20 00:00:00 EDT 1977},

  month        = {Fri May 20 00:00:00 EDT 1977}

}

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