During operation of light water reactors, the Zircaloy fuel rod cladding is susceptible for hydrogen uptake. When the local solubility limit of hydrogen in Zircaloy is reached, additional hydrogen precipitates as zirconium hydride, which affects the ductility of the fuel rod cladding. Especially, the radially aligned hydrides enhance embrittlement, while circumferential (azimuthal) hydrides have a less detrimental effect. In this work, the influence of high temperatures during the dry storage period on hydride dissolution and precipitation is demonstrated. Therefore, in a descriptive example scenario being discussed, the simulation of a limited heat removal from the cask will heat up the dry storage cask for days and causes dissolution of hydrides in the cladding. Depending on the threshold stress for reorientation, the following cooldown results on different hydride precipitation behavior. The threshold stress leads to an enhanced or delayed precipitation of radial hydrides. The GRS fuel rod code TESPA-ROD is equipped with a new model for hydrogen solubility and applied to long-term storage transients. In this article, hydride refers to zirconium hydrides formed inside the fuel rod cladding.
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April 2019
Research-Article
Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD
Felix Boldt
Felix Boldt
Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) gGmbH,
Boltzmannst. 14,
Garching 85748, Germany;
Reaktorsicherheit (GRS) gGmbH,
Boltzmannst. 14,
Garching 85748, Germany;
Chair of Nuclear Technology,
Department of Mechanical Engineering,
Technical University of Munich,
Boltzmannstr. 15,
Garching 85748, Germany
e-mail: felix.boldt@grs.de
Department of Mechanical Engineering,
Technical University of Munich,
Boltzmannstr. 15,
Garching 85748, Germany
e-mail: felix.boldt@grs.de
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Felix Boldt
Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) gGmbH,
Boltzmannst. 14,
Garching 85748, Germany;
Reaktorsicherheit (GRS) gGmbH,
Boltzmannst. 14,
Garching 85748, Germany;
Chair of Nuclear Technology,
Department of Mechanical Engineering,
Technical University of Munich,
Boltzmannstr. 15,
Garching 85748, Germany
e-mail: felix.boldt@grs.de
Department of Mechanical Engineering,
Technical University of Munich,
Boltzmannstr. 15,
Garching 85748, Germany
e-mail: felix.boldt@grs.de
Manuscript received August 1, 2018; final manuscript received November 20, 2018; published online March 15, 2019. Assoc. Editor: Fidelma Di Lema.
ASME J of Nuclear Rad Sci. Apr 2019, 5(2): 020904 (8 pages)
Published Online: March 15, 2019
Article history
Received:
August 1, 2018
Revised:
November 20, 2018
Citation
Boldt, F. (March 15, 2019). "Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD." ASME. ASME J of Nuclear Rad Sci. April 2019; 5(2): 020904. https://doi.org/10.1115/1.4042118
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