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SPECIAL SECTION: SELECTED PAPERS FROM THE 2018 INTERNATIONAL YOUTH NUCLEAR CONGRESS

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

[+] Author and Article Information
Felix Boldt

Gesellschaft für Anlagen- und
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

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 5(2), 020904 (Mar 15, 2019) (8 pages) Paper No: NERS-18-1065; doi: 10.1115/1.4042118 History: Received August 01, 2018; Revised November 20, 2018

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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Figures

Grahic Jump Location
Fig. 1

Terminal solid solubility limits for from TESPA-ROD in comparison with data from McMinn [9]

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Fig. 2

Comparison of TESPA-ROD calculation results and the XRD measurements of ANL thermal cycling tests [22] taken from Ref. [23]

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Fig. 3

Temperature profile of ANL cycling tests used for TESPA-ROD calculation [22] taken from Ref. [23]

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Fig. 4

Temp of cladding and environment

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Fig. 5

Hydrogen and hydride behavior during the transient

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Fig. 6

Cladding temperature evolution of cladding and cask's outer surface over full simulation time

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Fig. 7

Cladding temperature evolution during the heat-up transient

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Fig. 8

Heat flux from during the heat-up transient

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Fig. 9

Cladding hoop stresses over the full transient

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Fig. 10

Cladding hoop stress during the heat-up transient

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Fig. 11

Cladding hoop strain over the full simulation

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Fig. 12

Cladding hoop strain during the transient

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Fig. 13

Ratio of radial and circumferential hydrides and dissolved hydrogen in cladding (reorientation threshold: 90 to 110 MPa)

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Fig. 14

Shares of radial and circumferential hydrides and dissolved hydrogen in the cladding during the heat-up transient (reorientation threshold: 90 MPa to 110 MPa)

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Fig. 15

Ratio of radial and circumferential hydrides and dissolved hydrogen in the cladding (reorientation threshold: 75 to 85 MPa)

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Fig. 16

Shares of radial and circumferential hydrides and dissolved hydrogen in the cladding during the heat-up transient (reorientation threshold: 75 MPa to 95 MPa)

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