Cracking of Cr-coated accident-tolerant fuel during normal operation and under power-ramping conditions
- Publication Date:
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1557906
- Resource Type:
- Publisher's Accepted Manuscript
- Journal Name:
- Nuclear Engineering and Design
- Additional Journal Information:
- Journal Name: Nuclear Engineering and Design Journal Volume: 353 Journal Issue: C; Journal ID: ISSN 0029-5493
- Publisher:
- Elsevier
- Country of Publication:
- Netherlands
- Language:
- English
Citation Formats
Hong, Kisik, Barber, J. R., Thouless, M. D., and Lu, Wei. Cracking of Cr-coated accident-tolerant fuel during normal operation and under power-ramping conditions. Netherlands: N. p., 2019.
Web. doi:10.1016/j.nucengdes.2019.110275.
Hong, Kisik, Barber, J. R., Thouless, M. D., & Lu, Wei. Cracking of Cr-coated accident-tolerant fuel during normal operation and under power-ramping conditions. Netherlands. https://doi.org/10.1016/j.nucengdes.2019.110275
Hong, Kisik, Barber, J. R., Thouless, M. D., and Lu, Wei. Fri .
"Cracking of Cr-coated accident-tolerant fuel during normal operation and under power-ramping conditions". Netherlands. https://doi.org/10.1016/j.nucengdes.2019.110275.
@article{osti_1557906,
title = {Cracking of Cr-coated accident-tolerant fuel during normal operation and under power-ramping conditions},
author = {Hong, Kisik and Barber, J. R. and Thouless, M. D. and Lu, Wei},
abstractNote = {},
doi = {10.1016/j.nucengdes.2019.110275},
journal = {Nuclear Engineering and Design},
number = C,
volume = 353,
place = {Netherlands},
year = {Fri Nov 01 00:00:00 EDT 2019},
month = {Fri Nov 01 00:00:00 EDT 2019}
}
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.nucengdes.2019.110275
https://doi.org/10.1016/j.nucengdes.2019.110275
Other availability
Search WorldCat to find libraries that may hold this journal
Cited by: 12 works
Citation information provided by
Web of Science
Web of Science
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.
Works referenced in this record:
Mechanical and thermomechanical properties of commercially pure chromium and chromium alloys
journal, February 2002
- Holzwarth, Uwe; Stamm, Hermann
- Journal of Nuclear Materials, Vol. 300, Issue 2-3
Multidimensional multiphysics simulation of nuclear fuel behavior
journal, April 2012
- Williamson, R. L.; Hales, J. D.; Novascone, S. R.
- Journal of Nuclear Materials, Vol. 423, Issue 1-3
Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding — A review
journal, August 1990
- Cox, B.
- Journal of Nuclear Materials, Vol. 172, Issue 3
Discussion: “Edge-Bonded Dissimilar Orthogonal Elastic Wedges Under Normal and Shear Loading” (Bogy, D. B., 1968, ASME J. Appl. Mech., 35, pp. 460–466)
journal, September 1969
- Dundurs, J.
- Journal of Applied Mechanics, Vol. 36, Issue 3
Cracking of thin bonded films in residual tension
journal, January 1992
- Beuth, J. L.
- International Journal of Solids and Structures, Vol. 29, Issue 13
The Grain-Size-Dependences of the Failure Mode and Ductility Transition Temperatures of Melted Chromium and Tungsten
journal, January 1972
- Thornley, J. C.; Wronski, A. S.
- Metal Science, Vol. 6, Issue 1
HRTEM and chemical study of an ion-irradiated chromium/zircaloy-4 interface
journal, June 2018
- Wu, A.; Ribis, J.; Brachet, J. -C.
- Journal of Nuclear Materials, Vol. 504
Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings
journal, October 2018
- Wagih, Malik; Spencer, Benjamin; Hales, Jason
- Annals of Nuclear Energy, Vol. 120
The Deformation and Ageing of Mild Steel: III Discussion of Results
journal, September 1951
- Hall, E. O.
- Proceedings of the Physical Society. Section B, Vol. 64, Issue 9
Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance
journal, March 2018
- Ševeček, Martin; Gurgen, Anil; Seshadri, Arunkumar
- Nuclear Engineering and Technology, Vol. 50, Issue 2
Mechanical analysis of surface-coated zircaloy cladding
journal, August 2017
- Lee, Youho; Lee, Jeong Ik; No, Hee Cheon
- Nuclear Engineering and Technology, Vol. 49, Issue 5
Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions
journal, December 2016
- Park, Dong Jun; Kim, Hyun Gil; Jung, Yang Il
- Journal of Nuclear Materials, Vol. 482
Cracking and relocation behavior of nuclear fuel pellets during rise to power
journal, October 1983
- Oguma, Masaomi
- Nuclear Engineering and Design, Vol. 76, Issue 1
Accident tolerant fuel cladding development: Promise, status, and challenges
journal, April 2018
- Terrani, Kurt A.
- Journal of Nuclear Materials, Vol. 501
High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings
journal, October 2015
- Park, Jung-Hwan; Kim, Hyun-Gil; Park, Jeong-yong
- Surface and Coatings Technology, Vol. 280
Cracking and spalling of the oxide layer developed in high-burnup Zircaloy-4 cladding under normal operating conditions in a PWR
journal, December 2018
- Hong, Kisik; Barber, J. R.; Thouless, M. D.
- Journal of Nuclear Materials, Vol. 512
Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating
journal, October 2015
- Kim, Hyun-Gil; Kim, Il-Hyun; Jung, Yang-Il
- Journal of Nuclear Materials, Vol. 465
AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding
journal, March 2018
- Bischoff, Jeremy; Delafoy, Christine; Vauglin, Christine
- Nuclear Engineering and Technology, Vol. 50, Issue 2
Influence of Outer Zirconia Transient Cracking and Spalling on Thermomechanical Behaviour of High Burnup Fuel Rod Submitted to RIA
journal, September 2006
- Georgenthum, Vincent; Desquines, Jean; Bessiron, Vincent
- Journal of Nuclear Science and Technology, Vol. 43, Issue 9
Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings
journal, August 2017
- Tang, Chongchong; Stueber, Michael; Seifert, Hans Juergen
- Corrosion Reviews, Vol. 35, Issue 3
Capabilities of TRANSURANUS code in simulating power ramp tests from the IFPE database
journal, April 2011
- Rozzia, D.; Adorni, M.; Del Nevo, A.
- Nuclear Engineering and Design, Vol. 241, Issue 4
A mechanism-based framework for the numerical analysis of creep in zircaloy-4
journal, February 2013
- Wang, H.; Hu, Z.; Lu, W.
- Journal of Nuclear Materials, Vol. 433, Issue 1-3
Designing Radiation Resistance in Materials for Fusion Energy
journal, July 2014
- Zinkle, S. J.; Snead, L. L.
- Annual Review of Materials Research, Vol. 44, Issue 1
Measurement of fracture toughness and interfacial shear strength of hard and brittle Cr coating on ductile steel substrate
journal, September 2008
- Yang, B. -Q.; Zhang, K.; Chen, G. -N.
- Surface Engineering, Vol. 24, Issue 5