Viewpoint Set on Nuclear Materials Science
Abstract
Materials science has historically played critical roles in developing today’s nuclear energy systems. The current mainstream nuclear materials such as the zirconium alloys for fuels and core components and the reactor pressure vessel (RPV) steels were essential enabling materials for present day nuclear power and they undergo continued science-based fine tuning. Discovery of void swelling and other radiation effect phenomena in a fast neutron spectrum is largely responsible for the development of modern nuclear steels with enhanced radiation tolerance and, to a certain extent, the struggle of fast spectrum reactor development. Understandings the effects of neutron irradiation and the operating thermochemical environment in heat-resistant alloys, core graphite, and SiC-coated particle fuels have enabled the high temperature helium cooled reactors as a passively safe nuclear energy technology that is now anticipating mass deployment.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division
- Chinese Academy of Sciences (CAS), Ningbo (China). Engineering Lab. of Specialty Fibers and Nuclear Energy Materials. Ningbo Inst. of Industrial Technology
- Wuhan Univ. of Technology (China). International School of Materials Science and Engineering
- Univ. of California, Davis, CA (United States). Dept. of Materials Science and Engineering
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1474708
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Scripta Materialia
- Additional Journal Information:
- Journal Volume: 143; Journal ID: ISSN 1359-6462
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; 22 GENERAL STUDIES OF NUCLEAR REACTORS
Citation Formats
Katoh, Yutai, Huang, Qing, Han, Young-Hwan, and Risbud, Subhash. Viewpoint Set on Nuclear Materials Science. United States: N. p., 2017.
Web. doi:10.1016/j.scriptamat.2017.08.028.
Katoh, Yutai, Huang, Qing, Han, Young-Hwan, & Risbud, Subhash. Viewpoint Set on Nuclear Materials Science. United States. https://doi.org/10.1016/j.scriptamat.2017.08.028
Katoh, Yutai, Huang, Qing, Han, Young-Hwan, and Risbud, Subhash. Wed .
"Viewpoint Set on Nuclear Materials Science". United States. https://doi.org/10.1016/j.scriptamat.2017.08.028. https://www.osti.gov/servlets/purl/1474708.
@article{osti_1474708,
title = {Viewpoint Set on Nuclear Materials Science},
author = {Katoh, Yutai and Huang, Qing and Han, Young-Hwan and Risbud, Subhash},
abstractNote = {Materials science has historically played critical roles in developing today’s nuclear energy systems. The current mainstream nuclear materials such as the zirconium alloys for fuels and core components and the reactor pressure vessel (RPV) steels were essential enabling materials for present day nuclear power and they undergo continued science-based fine tuning. Discovery of void swelling and other radiation effect phenomena in a fast neutron spectrum is largely responsible for the development of modern nuclear steels with enhanced radiation tolerance and, to a certain extent, the struggle of fast spectrum reactor development. Understandings the effects of neutron irradiation and the operating thermochemical environment in heat-resistant alloys, core graphite, and SiC-coated particle fuels have enabled the high temperature helium cooled reactors as a passively safe nuclear energy technology that is now anticipating mass deployment.},
doi = {10.1016/j.scriptamat.2017.08.028},
journal = {Scripta Materialia},
number = ,
volume = 143,
place = {United States},
year = {Wed Oct 04 00:00:00 EDT 2017},
month = {Wed Oct 04 00:00:00 EDT 2017}
}
Free Publicly Available Full Text
Publisher's Version of Record
Other availability
Search WorldCat to find libraries that may hold this journal
Cited by: 3 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:
Accident tolerant fuels for LWRs: A perspective
journal, May 2014
- Zinkle, S. J.; Terrani, K. A.; Gehin, J. C.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Reprint of: The development of cladding materials for the accident tolerant fuel system from the Materials Genome Initiative
journal, January 2018
- Liu, Zhen; Li, Yifan; Shi, Diwei
- Scripta Materialia, Vol. 143
Sputtering in a high-flux plasma environment
journal, January 2018
- Doerner, R. P.
- Scripta Materialia, Vol. 143
Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature service
journal, October 2016
- Tan, L.; Katoh, Y.; Tavassoli, A. -A. F.
- Journal of Nuclear Materials, Vol. 479
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
journal, May 2014
- Terrani, K. A.; Zinkle, S. J.; Snead, L. L.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Current status and recent research achievements in SiC/SiC composites
journal, December 2014
- Katoh, Y.; Snead, L. L.; Henager, C. H.
- Journal of Nuclear Materials, Vol. 455, Issue 1-3
On the status and prospects for nanostructured ferritic alloys for nuclear fission and fusion application with emphasis on the underlying science
journal, January 2018
- Odette, G. Robert
- Scripta Materialia, Vol. 143
The critical issues of SiC materials for future nuclear systems
journal, January 2018
- Li, Mian; Zhou, Xiaobing; Yang, Hui
- Scripta Materialia, Vol. 143
Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations
journal, January 2018
- Zinkle, S. J.; Snead, L. L.
- Scripta Materialia, Vol. 143
Small-scale mechanical testing on nuclear materials: bridging the experimental length-scale gap
journal, January 2018
- Hosemann, Peter
- Scripta Materialia, Vol. 143
Viewpoint: Nanoscale chemistry and crystallography are both the obstacle and pathway to advanced radiation-tolerant materials
journal, January 2018
- Parish, Chad M.; Wang, Kun; Edmondson, Philip D.
- Scripta Materialia, Vol. 143
Reprint of: Microstructural evolution of neutron irradiated 3C-SiC
journal, January 2018
- Sprouster, D. J.; Koyanagi, T.; Dooryhee, E.
- Scripta Materialia, Vol. 143
Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications
journal, November 2014
- Pint, B. A.; Dryepondt, S.; Unocic, K. A.
- JOM, Vol. 66, Issue 12
Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors
journal, September 2016
- Tan, L.; Snead, L. L.; Katoh, Y.
- Journal of Nuclear Materials, Vol. 478
Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085 °C temperature range
journal, February 2017
- Tallman, Darin J.; He, Lingfeng; Gan, Jian
- Journal of Nuclear Materials, Vol. 484
Materials selection for nuclear applications: Challenges and opportunities
journal, January 2018
- Hosemann, P.; Frazer, D.; Fratoni, M.
- Scripta Materialia, Vol. 143
Phase transformation on spark plasma sintered dense polycarbosilane-derived SiC without additive
journal, January 2018
- Lee, Yoonjoo; Lee, Ji Hwoan; Shin, Dong-Geun
- Scripta Materialia, Vol. 143
Preface and historical perspective on spark plasma sintering
journal, July 2013
- Risbud, Subhash H.; Han, Young-Hwan
- Scripta Materialia, Vol. 69, Issue 2
Works referencing / citing this record:
Influence of Metal Additives on Microstructure and Properties of Amorphous Metal–SiOC Composites
journal, April 2019
- Ming, Kaisheng; Su, Qing; Gu, Chao
- JOM, Vol. 71, Issue 7