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1

Structural Alloys for Nuclear Energy Applications || Radiation and Thermomechanical Degradation Effects in Reactor Structural Alloys

Zinkle, Steven J.

Year:

2019

Language:

english

File:

PDF, 3.93 MB

english, 2019

2

Thermal diffusion of mixed valence Ce in 6 Li loaded silicate glass for neutron imaging

Moore, Michael E., Xue, Haizhou, Vilmercati, Paolo, Zinkle, Steven J., Mannella, Norman, Hayward, Jason P.

Journal:

Journal of Non-Crystalline Solids

Year:

2018

Language:

english

File:

PDF, 2.12 MB

english, 2018

3

Helium induced microstructure damage, nano-scale grain formation and helium retention behaviour of ZrC

Agarwal, Shradha, Bhattacharya, Arunodaya, Trocellier, Patrick, Zinkle, Steven J.

Journal:

Acta Materialia

Year:

2018

Language:

english

File:

PDF, 7.22 MB

english, 2018

4

Radiation effects in ceramics

Linn W. Hobbs, Frank W. Clinard Jr., Steven J. Zinkle, Rodney C. Ewing

Journal:

Journal of Nuclear Materials

Year:

1994

Language:

english

File:

PDF, 3.37 MB

english, 1994

5

Microstructure of Al2O3 and MgAl2O4 preimplanted with H, He, C and irradiated with Ar+ ions

Reiji Yamada, Steven J. Zinkle, G. Philip Pells

Journal:

Journal of Nuclear Materials

Year:

1994

Language:

english

File:

PDF, 6.31 MB

english, 1994

6

Preface

Glenn W. Hollenberg, Steven J. Zinkle, Ian J. Hastings

Journal:

Journal of Nuclear Materials

Year:

1995

Language:

english

File:

PDF, 35 KB

english, 1995

7

Aging effects on microstructural and mechanical properties of select refractory metal alloys for space-reactor applications

Keith J. Leonard, Jeremy T. Busby, Steven J. Zinkle

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 1.66 MB

english, 2007

8

Influence of thermal and radiation effects on microstructural and mechanical properties of Nb–1Zr

Keith J. Leonard, Jeremy T. Busby, Steven J. Zinkle

Journal:

Journal of Nuclear Materials

Year:

2011

Language:

english

File:

PDF, 3.36 MB

english, 2011

9

Defect formation in ion-irradiated Al2O3 and MgAl2O4: effects of grain boundaries and fusion transmutation products

Reiji Yamada, Steven J. Zinkle, G. Philip Pells

Journal:

Journal of Nuclear Materials

Year:

1992

Language:

english

File:

PDF, 1.58 MB

english, 1992

10

Potential and limitations of ceramics in terms of structural and electrical integrity in fusion environments

Chiken Kinoshita, Steven J. Zinkle

Journal:

Journal of Nuclear Materials

Year:

1996

Language:

english

File:

PDF, 1.07 MB

english, 1996

11

Nb-Base FS-85 Alloy as a Candidate Structural Material for Space Reactor Applications: Effects of Thermal Aging

Keith J. Leonard, Jeremy T. Busby, David T. Hoelzer, Steven J. Zinkle

Journal:

Metallurgical and Materials Transactions A

Year:

2009

Language:

english

File:

PDF, 1.25 MB

english, 2009

12

Prospects for accelerated development of high performance structural materials

Steven J. Zinkle, Nasr M. Ghoniem

Journal:

Journal of Nuclear Materials

Year:

2011

Language:

english

File:

PDF, 665 KB

english, 2011

13

Fusion materials science: Overview of challenges and recent progress

Zinkle, Steven J.

Journal:

Physics of Plasmas

Year:

2005

Language:

english

File:

PDF, 381 KB

english, 2005

14

High pressure synthesis of a hexagonal close-packed phase of the high-entropy alloy CrMnFeCoNi

Tracy, Cameron L., Park, Sulgiye, Rittman, Dylan R., Zinkle, Steven J., Bei, Hongbin, Lang, Maik, Ewing, Rodney C., Mao, Wendy L.

Journal:

Nature Communications

Year:

2017

Language:

english

File:

PDF, 373 KB

english, 2017

15

Effects of temperature on the irradiation responses of Al 0.1 CoCrFeNi high entropy alloy

Yang, Tengfei, Xia, Songqin, Guo, Wei, Hu, Rong, Poplawsky, Jonathan D., Sha, Gang, Fang, Yuan, Yan, Zhanfeng, Wang, Chenxu, Li, Congyi, Zhang, Yong, Zinkle, Steven J., Wang, Yugang

Journal:

Scripta Materialia

Year:

2018

Language:

english

File:

PDF, 2.09 MB

english, 2018

16

Overview of the U.S. Fusion Materials Sciences Program

Zinkle, Steven J.

Journal:

Fusion Science & Technology

Year:

2005

Language:

english

File:

PDF, 1000 KB

english, 2005

17

Primary radiation damage: A review of current understanding and models

Nordlund, Kai, Zinkle, Steven J., Sand, Andrea E., Granberg, Fredric, Averback, Robert S., Stoller, Roger E., Suzudo, Tomoaki, Malerba, Lorenzo, Banhart, Florian, Weber, William J., Willaime, Francois

Journal:

Journal of Nuclear Materials

Year:

2018

Language:

english

File:

PDF, 10.18 MB

english, 2018

18

Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of Low-Cr ODS FeCrAl alloys

Massey, Caleb P., Dryepondt, Sebastien N., Edmondson, Philip D., Terrani, Kurt A., Zinkle, Steven J.

Journal:

Journal of Nuclear Materials

Year:

2018

Language:

english

File:

PDF, 4.63 MB

english, 2018

19

First principle study of magnetism and vacancy energetics in a near equimolar NiFeMnCr high entropy alloy

Li, Congyi, Yin, Junqi, Odbadrakh, Khorgolkhuu, Sales, Brian C., Zinkle, Steven J., Stocks, G. Malcolm, Wirth, Brian D.

Journal:

Journal of Applied Physics

Year:

2019

Language:

english

File:

PDF, 3.05 MB

english, 2019

20

The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys

Massey, Caleb P., Edmondson, Philip D., Unocic, Kinga A., Yang, Ying, Dryepondt, Sebastien N., Kini, Anoop, Gault, Baptiste, Terrani, Kurt A., Zinkle, Steven J.

Journal:

Journal of Nuclear Materials

Year:

2020

Language:

english

File:

PDF, 4.66 MB

english, 2020

21

Advanced materials for fusion technology

Steven J. Zinkle

Journal:

Fusion Engineering and Design

Year:

2005

Language:

english

File:

PDF, 311 KB

english, 2005

22

Dynamic observation of the collapse process of a stacking fault tetrahedron by moving dislocations

Yoshitaka Matsukawa, Steven J Zinkle

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 411 KB

english, 2004

23

Microstructural and mechanical property changes with aging of Mo–41Re and Mo–47.5Re alloys

Keith J. Leonard, Jeremy T. Busby, Steven J. Zinkle

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 3.02 MB

english, 2007

24

Anomaly in dependence of radiation-induced vacancy accumulation on grain size

Yi Yang, Hanchen Huang, Steven J. Zinkle

Journal:

Journal of Nuclear Materials

Year:

2010

Language:

english

File:

PDF, 738 KB

english, 2010

25

Long term degradation of electrical insulation of Al2O3 under high flux fission reactor irradiation

Tatsuo Shikama, Steven J. Zinkle

Journal:

Journal of Nuclear Materials

Year:

1998

Language:

english

File:

PDF, 196 KB

english, 1998

26

Irradiation effects in ceramics for fusion reactor applications

Tatsuo Shikama, Kazuhiro Yasuda, Shin Yamamoto, Chiken Kinoshita, Steven J Zinkle, Eric R Hodgson

Journal:

Journal of Nuclear Materials

Year:

1999

Language:

english

File:

PDF, 207 KB

english, 1999

27

Structural materials for fission & fusion energy

Steven J. Zinkle, Jeremy T. Busby

Journal:

Materials Today

Year:

2009

Language:

english

File:

PDF, 1.30 MB

english, 2009

28

Tensile property of low activation vanadium alloy after liquid lithium exposure

Takuya Nagasaka, Takeo Muroga, Meimei Li, David T. Hoelzer, Steven J. Zinkle, Martin L. Grossbeck, Hideki Matsui

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 393 KB

english, 2006

29

Microstructural and mechanical property changes in the Ta-base T-111 alloy following thermal aging

Keith J. Leonard, Jeremy T. Busby, Steven J. Zinkle

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 2.94 MB

english, 2007

30

Preparation and Characterization of 17O-Enriched Alumina for Nuclear Fusion Damage Experiments

Hyoun-Ee Kim, Steven J. Zinkle, William R. Allen

Journal:

Journal of the American Ceramic Society

Year:

1990

Language:

english

File:

PDF, 584 KB

english, 1990

31

Preparation of Magnesium Aluminate Spinel Containing Controlled Amounts of 17O Isotope

Hyoun-Ee Kim, Steven J. Zinkle, William R. Allen

Journal:

Journal of the American Ceramic Society

Year:

1991

Language:

english

File:

PDF, 365 KB

english, 1991

32

Evaluation of irradiation facility options for fusion materials research and development

Zinkle, Steven J., Möslang, Anton

Journal:

Fusion Engineering and Design

Year:

2013

Language:

english

File:

PDF, 844 KB

english, 2013

33

Effects of ion irradiation on Zr52.5Cu17.9Ni14.6Al10Ti5 (BAM-11) bulk metallic glass

Perez-Bergquist, Alejandro G., Bei, Hongbin, Leonard, Keith J., Zhang, Yanwen, Zinkle, Steven J.

Journal:

Year:

2014

Language:

english

File:

PDF, 1.72 MB

english, 2014

34

From Bytes to Ingots: Expedient Design of Structural Materials for Advanced Nuclear Energy Systems

Journal:

MRS Proceedings

Year:

2007

Language:

english

File:

PDF, 4.64 MB

english, 2007

35

Electrical conductivity of alumina after heavy irradiation in a high-flux fission reactor

Zinkle, Tatsuo Shikama, Steven J.

Journal:

Philosophical Magazine B

Year:

2001

Language:

english

File:

PDF, 276 KB

english, 2001

36

[AIP SPACE TECHNOLOGY AND APPLICATIONS INTERNAT.FORUM-STAIF 2004: Conf.on Thermophys.in Microgravity; Commercial/Civil Next Gen.Space Transp.; 21st Symp.Space Nuclear Power & Propulsion; Human Space Explor.; Space Colonization; New Frontiers & Future Concepts - Albuquerque, New Mexico (USA) (8-11 February 2004)] AIP Conference Proceedings - Radiation Effects in Refractory Alloys

Zinkle, Steven J.

Year:

2004

Language:

english

File:

PDF, 192 KB

english, 2004

37

Deformation Mechanisms in Ferritic/martensitic Steels Irradiated in HFIR

Hashimoto, Naoyuki, Zinkle, Steven J., Klueh, Ronald L., Rowcliffe, Arthur F., Shiba, Kiyoyuki

Journal:

MRS Proceedings

Year:

2000

Language:

english

File:

PDF, 4.20 MB

english, 2000

38

Applicability of copper alloys for DEMO high heat flux components

Zinkle, Steven J

Journal:

Physica Scripta

Year:

2016

Language:

english

File:

PDF, 2.21 MB

english, 2016

39

Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials

Ang, Caen, Silva, Chinthaka, Shih, Chunghao, Koyanagi, Takaaki, Katoh, Yutai, Zinkle, Steven J.

Journal:

Scripta Materialia

Year:

2016

Language:

english

File:

PDF, 673 KB

english, 2016

40

Electrical conductivity of alumina after heavy irradiation in a high-flux fission reactor

Shikama, Tatsuo, Zinkle, Steven J.

Journal:

Philosophical Magazine B

Year:

2001

Language:

english

File:

PDF, 1.01 MB

english, 2001

41

Phase stability, swelling, microstructure and strength of Ti3SiC2-TiC ceramics after low dose neutron irradiation

Ang, Caen, Zinkle, Steven, Shih, Chunghao, Silva, Chinthaka, Cetiner, Nesrin, Katoh, Yutai

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.94 MB

english, 2017

42

Challenges in Developing Materials for Fusion Technology - Past, Present and Future

Journal:

Fusion Science & Technology

Year:

2012

Language:

english

File:

PDF, 856 KB

english, 2012

43

Modeling of dislocation channel width evolution in irradiated metals

Doyle, Peter J., Benensky, Kelsa M., Zinkle, Steven J.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 4.36 MB

english, 2017

44

Summary of the Varying Temperature Irradiation Experiment in HFIR

Muroga, Takeo, Watanabe, Hideo, Fukumoto, Ken-Ichi, Satou, Manabu, Kimura, Akihiko, Zinkle, Steven J., Hashimoto, Naoyuki, Hoelzer, David T., Qualls, A. Lou

Journal:

Fusion Science & Technology

Year:

2003

Language:

english

File:

PDF, 629 KB

english, 2003

45

Improving atomic displacement and replacement calculations with physically realistic damage models

Nordlund, Kai, Zinkle, Steven J., Sand, Andrea E., Granberg, Fredric, Averback, Robert S., Stoller, Roger, Suzudo, Tomoaki, Malerba, Lorenzo, Banhart, Florian, Weber, William J., Willaime, Francois, D

Journal:

Nature Communications

Year:

2018

Language:

english

File:

PDF, 2.94 MB

english, 2018

46

Modeling the impact of radiation-enhanced diffusion on implanted ion profiles

Doyle, Peter J., Benensky, Kelsa M., Zinkle, Steven J.

Journal:

Journal of Nuclear Materials

Year:

2018

Language:

english

File:

PDF, 4.14 MB

english, 2018

47

Development of novel Cu-Cr-Nb-Zr alloys with the aid of computational thermodynamics

Yang, Ying, Wang, Ling, Snead, Lance, Zinkle, Steven J.

Journal:

Materials & Design

Year:

2018

Language:

english

File:

PDF, 3.98 MB

english, 2018

48

[American Institute of Aeronautics and Astronautics 2018 Joint Propulsion Conference - Cincinnati, Ohio ()] 2018 Joint Propulsion Conference - Production and Hot Hydrogen Testing of Subscale Molybdenum Cermets for Nuclear Thermal Propulsion

Duffin, Taylor G., Benensky, Kelsa M., Zinkle, Steven J., Barnes, Marvin W., Tucker, Dennis S.

Language:

english

File:

PDF, 1.23 MB

english

49

Irradiation responses and defect behavior of single-phase concentrated solid solution alloys

Yang, Tengfei, Li, Congyi, Zinkle, Steven J., Zhao, Shijun, Bei, Hongbin, Zhang, Yanwen

Journal:

Journal of Materials Research

Year:

2018

Language:

english

File:

PDF, 964 KB

english, 2018

50

Complexity modeling and analysis of chaos and other fluctuating phenomena

Brechtl, Jamieson, Xie, Xie, Liaw, Peter K., Zinkle, Steven J.

Journal:

Chaos, Solitons & Fractals

Year:

2018

Language:

english

File:

PDF, 3.18 MB

english, 2018