The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions

M. Nedim Cinbiz; Nicholas Brown; Kurt A. Terrani; Rick R. Lowden; Donald Erdman

doi:10.1007/978-3-319-52333-0_32

The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions

M. Nedim Cinbiz, Nicholas Brown, Kurt A. Terrani, Rick R. Lowden, Donald Erdman

Radiation Effects and Microstructural An

Research output: Chapter in Book/Report/Conference proceeding › Chapter › peer-review

1 Scopus citations

Abstract

This study investigates the failure mechanisms of advanced oxidation resistant FeCrAl nuclear fuel cladding at high-strain rates, similar to conditions characteristic of design basis reactivity initiated accidentReactivity initiated accidents (RIAs). During a postulated RIA, the nuclear fuel cladding may be subjected to complex loading which can cause multiaxial strain states ranging from plane-strain to equibiaxial tension. To achieve those accident conditions, the samples were deformed by the expansion of high strength Inconel alloy tube under pre-specified pressure pulses, simulating strains rates occurring in a postulated RIA. The mechanical response of the advanced claddings, in the unirradiated state with ample ductility, was compared to that of hydrided zirconium-based nuclear fuel cladding. The hoop strain evolution pulses were collected in situ; the permanent diametral strains of both accident tolerant fuelAccident-tolerant fuel (ATF) claddings and the current nuclear fuel alloys were determined after rupture. Both zirconium-based alloys and FeCrAl alloysFeCrAl alloys exhibited ductile behavior. FeCrAl model alloys without microstructural control and strengthening mechanism were used in this demonstration study that showed reduced diametral strain (less than 0.15) compared to the diametral strain for the unirradiated zirconium-based alloy (approximately 0.2).

Original language	English
Title of host publication	Minerals, Metals and Materials Series
Publisher	Springer International Publishing
Pages	355-365
Number of pages	11
Edition	9783319523330
DOIs	https://doi.org/10.1007/978-3-319-52333-0_32
State	Published - 2017

Publication series

Name	Minerals, Metals and Materials Series
Number	9783319523330
ISSN (Print)	2367-1181
ISSN (Electronic)	2367-1696

Funding

This work was supported by the US Department of Energy Office of Nuclear Energy (DOE-NE) Advanced Fuels Campaign (AFC). The authors thank Daniel M. Wachs of Idaho National Laboratory for his oversight of this area. Authors are also thankful to Ken Yueh from Electric Power Research Institute for his useful insights during the construction of the mechanical test device. Also, we are thankful to Stephanie Curlin for profilometry, Aida Amroussia for SEM pictures, and Tom Geer and Sun Zhiqian for optical micrographs. Acknowledgements This work was supported by the US Department of Energy Office of Nuclear Energy (DOE-NE) Advanced Fuels Campaign (AFC). The authors thank Daniel M. Wachs of Idaho National Laboratory for his oversight of this area. Authors are also thankful to Ken Yueh from Electric Power Research Institute for his useful insights during the construction of the mechanical test device. Also, we are thankful to Stephanie Curlin for profilometry, Aida Amroussia for SEM pictures, and Tom Geer and Sun Zhiqian for optical micrographs.

Funders	Funder number
DOE-NE
U.S. Department of Energy
Office of Nuclear Energy

Keywords

Accident-tolerant fuel
FeCrAl alloys
High strain rate
Modified burst test
Reactivity initiated accident

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10.1007/978-3-319-52333-0_32

Cite this

Nedim Cinbiz, M., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In Minerals, Metals and Materials Series (9783319523330 ed., pp. 355-365). (Minerals, Metals and Materials Series; No. 9783319523330). Springer International Publishing. https://doi.org/10.1007/978-3-319-52333-0_32

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abstract = "This study investigates the failure mechanisms of advanced oxidation resistant FeCrAl nuclear fuel cladding at high-strain rates, similar to conditions characteristic of design basis reactivity initiated accidentReactivity initiated accidents (RIAs). During a postulated RIA, the nuclear fuel cladding may be subjected to complex loading which can cause multiaxial strain states ranging from plane-strain to equibiaxial tension. To achieve those accident conditions, the samples were deformed by the expansion of high strength Inconel alloy tube under pre-specified pressure pulses, simulating strains rates occurring in a postulated RIA. The mechanical response of the advanced claddings, in the unirradiated state with ample ductility, was compared to that of hydrided zirconium-based nuclear fuel cladding. The hoop strain evolution pulses were collected in situ; the permanent diametral strains of both accident tolerant fuelAccident-tolerant fuel (ATF) claddings and the current nuclear fuel alloys were determined after rupture. Both zirconium-based alloys and FeCrAl alloysFeCrAl alloys exhibited ductile behavior. FeCrAl model alloys without microstructural control and strengthening mechanism were used in this demonstration study that showed reduced diametral strain (less than 0.15) compared to the diametral strain for the unirradiated zirconium-based alloy (approximately 0.2).",

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Nedim Cinbiz, M, Brown, N, Terrani, KA, Lowden, RR & Erdman, D 2017, The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. in Minerals, Metals and Materials Series. 9783319523330 edn, Minerals, Metals and Materials Series, no. 9783319523330, Springer International Publishing, pp. 355-365. https://doi.org/10.1007/978-3-319-52333-0_32

The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. / Nedim Cinbiz, M.; Brown, Nicholas; Terrani, Kurt A. et al.
Minerals, Metals and Materials Series. 9783319523330. ed. Springer International Publishing, 2017. p. 355-365 (Minerals, Metals and Materials Series; No. 9783319523330).

Research output: Chapter in Book/Report/Conference proceeding › Chapter › peer-review

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T1 - The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions

AU - Nedim Cinbiz, M.

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PY - 2017

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N2 - This study investigates the failure mechanisms of advanced oxidation resistant FeCrAl nuclear fuel cladding at high-strain rates, similar to conditions characteristic of design basis reactivity initiated accidentReactivity initiated accidents (RIAs). During a postulated RIA, the nuclear fuel cladding may be subjected to complex loading which can cause multiaxial strain states ranging from plane-strain to equibiaxial tension. To achieve those accident conditions, the samples were deformed by the expansion of high strength Inconel alloy tube under pre-specified pressure pulses, simulating strains rates occurring in a postulated RIA. The mechanical response of the advanced claddings, in the unirradiated state with ample ductility, was compared to that of hydrided zirconium-based nuclear fuel cladding. The hoop strain evolution pulses were collected in situ; the permanent diametral strains of both accident tolerant fuelAccident-tolerant fuel (ATF) claddings and the current nuclear fuel alloys were determined after rupture. Both zirconium-based alloys and FeCrAl alloysFeCrAl alloys exhibited ductile behavior. FeCrAl model alloys without microstructural control and strengthening mechanism were used in this demonstration study that showed reduced diametral strain (less than 0.15) compared to the diametral strain for the unirradiated zirconium-based alloy (approximately 0.2).

AB - This study investigates the failure mechanisms of advanced oxidation resistant FeCrAl nuclear fuel cladding at high-strain rates, similar to conditions characteristic of design basis reactivity initiated accidentReactivity initiated accidents (RIAs). During a postulated RIA, the nuclear fuel cladding may be subjected to complex loading which can cause multiaxial strain states ranging from plane-strain to equibiaxial tension. To achieve those accident conditions, the samples were deformed by the expansion of high strength Inconel alloy tube under pre-specified pressure pulses, simulating strains rates occurring in a postulated RIA. The mechanical response of the advanced claddings, in the unirradiated state with ample ductility, was compared to that of hydrided zirconium-based nuclear fuel cladding. The hoop strain evolution pulses were collected in situ; the permanent diametral strains of both accident tolerant fuelAccident-tolerant fuel (ATF) claddings and the current nuclear fuel alloys were determined after rupture. Both zirconium-based alloys and FeCrAl alloysFeCrAl alloys exhibited ductile behavior. FeCrAl model alloys without microstructural control and strengthening mechanism were used in this demonstration study that showed reduced diametral strain (less than 0.15) compared to the diametral strain for the unirradiated zirconium-based alloy (approximately 0.2).

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M3 - Chapter

AN - SCOPUS:85042449994

T3 - Minerals, Metals and Materials Series

SP - 355

EP - 365

BT - Minerals, Metals and Materials Series

PB - Springer International Publishing

ER -

Nedim Cinbiz M, Brown N, Terrani KA, Lowden RR, Erdman D. The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In Minerals, Metals and Materials Series. 9783319523330 ed. Springer International Publishing. 2017. p. 355-365. (Minerals, Metals and Materials Series; 9783319523330). doi: 10.1007/978-3-319-52333-0_32

The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions

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