Comparison of the radial effects of burnup on fast reactor MOX fuel microstructure and solid fission products
- Authors:
- Publication Date:
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1594211
- Resource Type:
- Publisher's Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Name: Journal of Nuclear Materials Journal Volume: 531 Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- Netherlands
- Language:
- English
Citation Formats
Parrish, Riley J., Cappia, Fabiola, and Aitkaliyeva, Assel. Comparison of the radial effects of burnup on fast reactor MOX fuel microstructure and solid fission products. Netherlands: N. p., 2020.
Web. doi:10.1016/j.jnucmat.2020.152003.
Parrish, Riley J., Cappia, Fabiola, & Aitkaliyeva, Assel. Comparison of the radial effects of burnup on fast reactor MOX fuel microstructure and solid fission products. Netherlands. https://doi.org/10.1016/j.jnucmat.2020.152003
Parrish, Riley J., Cappia, Fabiola, and Aitkaliyeva, Assel. Wed .
"Comparison of the radial effects of burnup on fast reactor MOX fuel microstructure and solid fission products". Netherlands. https://doi.org/10.1016/j.jnucmat.2020.152003.
@article{osti_1594211,
title = {Comparison of the radial effects of burnup on fast reactor MOX fuel microstructure and solid fission products},
author = {Parrish, Riley J. and Cappia, Fabiola and Aitkaliyeva, Assel},
abstractNote = {},
doi = {10.1016/j.jnucmat.2020.152003},
journal = {Journal of Nuclear Materials},
number = C,
volume = 531,
place = {Netherlands},
year = {2020},
month = {4}
}
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.jnucmat.2020.152003
https://doi.org/10.1016/j.jnucmat.2020.152003
Other availability
Search WorldCat to find libraries that may hold this journal
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:
Constitution and thermodynamics of the Mo-Ru, Mo-Pd, Ru-Pd and Mo-Ru-Pd systems
journal, September 1989
- Kleykamp, H.
- Journal of Nuclear Materials, Vol. 167
Development and Verifications of Fast Reactor Fuel Design Code CEPTAR
journal, October 2006
- Ozawa, T.; Abe, T.
- Nuclear Technology, Vol. 156, Issue 1
Solubility and migration of fission product barium in oxide fuel
journal, January 1979
- Sari, C.; Walker, C. T.; Schumacher, G.
- Journal of Nuclear Materials, Vol. 79, Issue 1
Materials Challenges for Generation IV Nuclear Energy Systems
journal, June 2008
- Allen, T. R.; Sridharan, K.; Tan, L.
- Nuclear Technology, Vol. 162, Issue 3
Characterization of alloy particles extracted from spent nuclear fuel
journal, January 2012
- Cui, D.; Rondinella, V. V.; Fortner, J. A.
- Journal of Nuclear Materials, Vol. 420, Issue 1-3
The chemical state of the fission products in oxide fuels
journal, April 1985
- Kleykamp, H.
- Journal of Nuclear Materials, Vol. 131, Issue 2-3, p. 221-246
The Chemical State of Fission Products in Oxide Fuels at Different Stages of the Nuclear Fuel Cycle
journal, March 1988
- Kleykamp, Heiko
- Nuclear Technology, Vol. 80, Issue 3
EBSD and TEM characterization of high burn-up mixed oxide fuel
journal, January 2014
- Teague, Melissa; Gorman, Brian; Miller, Brandon
- Journal of Nuclear Materials, Vol. 444, Issue 1-3
Microstructural characterization of high burn-up mixed oxide fast reactor fuel
journal, October 2013
- Teague, Melissa; Gorman, Brian; King, Jeffrey
- Journal of Nuclear Materials, Vol. 441, Issue 1-3
Behavior of Fission Products Zirconium and Barium in Fast Reactor Fuel Irradiated to High Burnup
journal, September 1999
- Sato, Isamu; Furuya, Hirotaka; Arima, Tatsumi
- Journal of Nuclear Science and Technology, Vol. 36, Issue 9
Irradiation performance of PFBR MOX fuel after 112GWd/t burn-up
journal, June 2014
- Venkiteswaran, C. N.; Jayaraj, V. V.; Ojha, B. K.
- Journal of Nuclear Materials, Vol. 449, Issue 1-3
Development of a mixed oxide fuel pin performance analysis code “CEDAR”: Models and analyses of fuel pin irradiation behavior
journal, December 2014
- Uwaba, Tomoyuki; Mizuno, Tomoyasu; Nemoto, Junichi
- Nuclear Engineering and Design, Vol. 280
A Liquid-Metal Reactor Core Demonstration Experiment Using HT-9
journal, June 1993
- Bridges, Alvia E.; Waltar, Alan E.; Leggett, Robert D.
- Nuclear Technology, Vol. 102, Issue 3
Fission product behaviour in phenix fuel pins at high burnup
journal, June 1992
- Tourasse, M.; Boidron, M.; Pasquet, B.
- Journal of Nuclear Materials, Vol. 188
Utilization of dual-column focused ion beam and scanning electron microscope for three dimensional characterization of high burn-up mixed oxide fuel
journal, April 2014
- Teague, Melissa; Gorman, Brian
- Progress in Nuclear Energy, Vol. 72
Characterization of solid fission products in 13.7% FIMA MOX fuel using electron microscopy techniques
journal, October 2019
- Parrish, Riley J.; Wright, Karen E.; Winston, Alexander J.
- Journal of Nuclear Materials, Vol. 524
Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel
journal, January 2014
- Teague, Melissa; Tonks, Michael; Novascone, Stephen
- Journal of Nuclear Materials, Vol. 444, Issue 1-3
Radial microstructural evolution in low burnup fast reactor MOX fuel
journal, September 2019
- Parrish, Riley J.; Liu, Xiang; Winston, Alexander
- Journal of Nuclear Materials, Vol. 523
Metallic fission-product inclusions in irradiated oxide fuels
journal, February 1968
- Bramman, J. I.; Sharpe, R. M.; Thom, D.
- Journal of Nuclear Materials, Vol. 25, Issue 2, p. 201-215
Fuel performance of hollow pellets for fast breeder reactors
journal, September 2015
- Ishimi, Akihiro; Katsuyama, Kozo; Kihara, Yoshiyuki
- Journal of Nuclear Science and Technology, Vol. 53, Issue 7
TEM characterization of high burnup fast-reactor MOX fuel
journal, December 2019
- Parrish, Riley; Winston, Alexander; Harp, Jason
- Journal of Nuclear Materials, Vol. 527
Behavior of metallic fission products in uranium–plutonium mixed oxide fuel
journal, August 1999
- Sato, I.; Furuya, H.; Arima, T.
- Journal of Nuclear Materials, Vol. 273, Issue 3