High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient

Mackenzie Ridley; Caleb Massey; Sam Bell; Nathan Capps

doi:10.1016/j.anucene.2023.110012

High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient

Mackenzie Ridley, Caleb Massey, Sam Bell, Nathan Capps

Research output: Contribution to journal › Article › peer-review

3 Scopus citations

Abstract

In-situ strain measurements of fuel cladding can enable high-throughput data collection and validation to support accelerated qualification of cladding materials. In this work, 3D digital image correlation was used to map strain for both Zircaloy-4 (Zry-4) and Cr-coated Zry-4 during two types of cladding rupture experiments: isobaric temperature ramp tests at 5 °C/s and isothermal pressure jump tests at 600 °C. Zry-4 strain data initially showed a temperature dependence expected for creep deformation, yet a shift to a new plastic deformation mechanism not reported in literature dominated during the finals seconds prior to rupture. Cr-coated Zry-4 did not show the change in deformation mechanism at the end of life and showed a delay in measurable creep deformation. Stress dependences were similar for Zry-4 and Cr/Zry-4 during pressure jump tests. Cr-coatings were found to decrease the strain rate during both testing scenarios. Creep parameters were calculated to support modelling efforts regarding design basis accidents.

Original language	English
Article number	110012
Journal	Annals of Nuclear Energy
Volume	193
DOIs	https://doi.org/10.1016/j.anucene.2023.110012
State	Published - Dec 1 2023

Funding

This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US Government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). The authors would like to thank B. Johnston and A. Willoughby from ORNL for experimental support, and B. Garrison and Y. Yang for technical review at ORNL. This work was supported through the Advanced Fuels Campaign by the Office of Nuclear Energy within the United States Department of Energy.

Funders	Funder number
Nuclear Energy
U.S. Department of Energy
Oak Ridge National Laboratory

Access to Document

10.1016/j.anucene.2023.110012

Cite this

@article{8ae02f78a7d742a79b5e373cf87d06f7,

title = "High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient",

abstract = "In-situ strain measurements of fuel cladding can enable high-throughput data collection and validation to support accelerated qualification of cladding materials. In this work, 3D digital image correlation was used to map strain for both Zircaloy-4 (Zry-4) and Cr-coated Zry-4 during two types of cladding rupture experiments: isobaric temperature ramp tests at 5 °C/s and isothermal pressure jump tests at 600 °C. Zry-4 strain data initially showed a temperature dependence expected for creep deformation, yet a shift to a new plastic deformation mechanism not reported in literature dominated during the finals seconds prior to rupture. Cr-coated Zry-4 did not show the change in deformation mechanism at the end of life and showed a delay in measurable creep deformation. Stress dependences were similar for Zry-4 and Cr/Zry-4 during pressure jump tests. Cr-coatings were found to decrease the strain rate during both testing scenarios. Creep parameters were calculated to support modelling efforts regarding design basis accidents.",

author = "Mackenzie Ridley and Caleb Massey and Sam Bell and Nathan Capps",

note = "Publisher Copyright: {\textcopyright} 2023 Elsevier Ltd",

year = "2023",

month = dec,

day = "1",

doi = "10.1016/j.anucene.2023.110012",

language = "English",

volume = "193",

journal = "Annals of Nuclear Energy",

issn = "0306-4549",

publisher = "Elsevier",

}

TY - JOUR

T1 - High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient

AU - Ridley, Mackenzie

AU - Massey, Caleb

AU - Bell, Sam

AU - Capps, Nathan

PY - 2023/12/1

Y1 - 2023/12/1

N2 - In-situ strain measurements of fuel cladding can enable high-throughput data collection and validation to support accelerated qualification of cladding materials. In this work, 3D digital image correlation was used to map strain for both Zircaloy-4 (Zry-4) and Cr-coated Zry-4 during two types of cladding rupture experiments: isobaric temperature ramp tests at 5 °C/s and isothermal pressure jump tests at 600 °C. Zry-4 strain data initially showed a temperature dependence expected for creep deformation, yet a shift to a new plastic deformation mechanism not reported in literature dominated during the finals seconds prior to rupture. Cr-coated Zry-4 did not show the change in deformation mechanism at the end of life and showed a delay in measurable creep deformation. Stress dependences were similar for Zry-4 and Cr/Zry-4 during pressure jump tests. Cr-coatings were found to decrease the strain rate during both testing scenarios. Creep parameters were calculated to support modelling efforts regarding design basis accidents.

AB - In-situ strain measurements of fuel cladding can enable high-throughput data collection and validation to support accelerated qualification of cladding materials. In this work, 3D digital image correlation was used to map strain for both Zircaloy-4 (Zry-4) and Cr-coated Zry-4 during two types of cladding rupture experiments: isobaric temperature ramp tests at 5 °C/s and isothermal pressure jump tests at 600 °C. Zry-4 strain data initially showed a temperature dependence expected for creep deformation, yet a shift to a new plastic deformation mechanism not reported in literature dominated during the finals seconds prior to rupture. Cr-coated Zry-4 did not show the change in deformation mechanism at the end of life and showed a delay in measurable creep deformation. Stress dependences were similar for Zry-4 and Cr/Zry-4 during pressure jump tests. Cr-coatings were found to decrease the strain rate during both testing scenarios. Creep parameters were calculated to support modelling efforts regarding design basis accidents.

UR - http://www.scopus.com/inward/record.url?scp=85165342052&partnerID=8YFLogxK

U2 - 10.1016/j.anucene.2023.110012

DO - 10.1016/j.anucene.2023.110012

M3 - Article

AN - SCOPUS:85165342052

SN - 0306-4549

VL - 193

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

M1 - 110012

ER -

High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient

Abstract

Funding

Access to Document

Other files and links

Fingerprint

Cite this