Personal information

Other IDs

ResearcherID: R-9357-2018
Loop profile: 2001269

Biography

Dr. Peng Wang, is an Associate Research Scientist at the University of Michigan, in the Department of Nuclear Engineering and Radiological Science. Dr. Wang’s research is currently concentrated on materials for advanced nuclear energy systems, and radiation materials science, including the environmental effect of irradiation on the corrosion phenomenon of zirconium and steel, and ATF concepts application in an LWR environment. He has extensive experience in developing and conducting the in-situ irradiation-corrosion experiment using a particle accelerator. He has also led a DOE-NEUP project on hydrothermal corrosion and radiation effects of SiC in light water reactor environment.

Activities

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Employment (2)

University of Michigan: Ann Arbor, MI, US

Employment
Source: check_circle
University of Michigan

University of Michigan: Ann Arbor, MI, US

2012-03-09 to 2015-08-31 | Research Fellow (Nuclear Engineering and Radiological Sciences)
Employment
Source: Self-asserted source
Peng Wang

Education and qualifications (2)

University of Manchester: Manchester, Manchester, GB

2007-09-01 to 2011-09-01 | Ph.D (School of Materials)
Education
Source: Self-asserted source
Peng Wang

University of Manchester: Manchester, Manchester, GB

2003-09-01 to 2007-07-01 | M. Eng (School of Materials)
Education
Source: Self-asserted source
Peng Wang

Works (16)

Discerning the effect of various irradiation modes on the corrosion of Zircaloy-4

Journal of Nuclear Materials
2025-01 | Journal article
DOI: 10.1016/j.jnucmat.2024.155505
Contributors: Peng Wang; Bruce Kammenzind; Richard Smith; Arthur Motta; Matthieu Aumand; Damien Kaczorowski; Mukesh Bachhav; Gary Was
Source: check_circle
Crossref

Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water

Journal of Nuclear Materials
2024-05 | Journal article
DOI: 10.1016/j.jnucmat.2024.154987
Contributors: Logan Joyce; Peng Wang; Rajnikant V. Umretiya; Andrew Hoffman; Yi Xie
Source: check_circle
Crossref

ULTRAFLOW Shield: A New Spacer Grid Coating for BWR Fuel

TopFuel 2022 Light Water Reactor Fuel Performance Conference
2022 | Conference paper
DOI: 10.13182/topfuel22-38899
Contributors: Karsten Nowotka; Petra-Britt Hoffmann; Artur Hasselbach; Roland Geier; Sean Gray; Peng Wang; Gary Was
Source: Self-asserted source
Peng Wang

Ion irradiation induced amorphization of precipitates in Zircaloy

Journal of Nuclear Materials
2022-12 | Journal article
DOI: 10.1016/j.jnucmat.2022.153988
Part of ISSN: 0022-3115
Contributors: Peng Wang
Source: Self-asserted source
Peng Wang

Advanced Fuels Campaign 2022 Accomplishments

2022-11 | Report
OTHER-ID: 1906490
Contributors: King, Phyllis L (ORCID:0000000297411476); ; Medema, Heather D
Source: Self-asserted source
Peng Wang via DOE OSTI.GOV

Reproducing shadow corrosion on Zircaloy-2 using in-situ proton irradiation

Journal of Nuclear Materials
2022-01 | Journal article
DOI: 10.1016/j.jnucmat.2021.153406
Part of ISSN: 0022-3115
Source: Self-asserted source
Peng Wang

Emulation of neutron damage with proton irradiation and its effects on microstructure and microchemistry of Zircaloy-4

Journal of Nuclear Materials
2021-12 | Journal article
DOI: 10.1016/j.jnucmat.2021.153281
Part of ISSN: 0022-3115
Source: Self-asserted source
Peng Wang

Corrosion behavior of ferritic FeCrAl alloys in simulated BWR normal water chemistry

Journal of Nuclear Materials
2021-03 | Journal article
DOI: 10.1016/j.jnucmat.2020.152744
Contributors: Peng Wang; Slavica Grdanovska; David M. Bartels; Gary S. Was
Source: check_circle
Crossref

Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water

Journal of Nuclear Materials
2020-05 | Journal article
DOI: 10.1016/j.jnucmat.2020.152108
Part of ISSN: 0022-3115
Source: Self-asserted source
Peng Wang

Determination of dose rate effects on Zircaloy oxidation using proton irradiation and oxygen transport modeling

Journal of Nuclear Materials
2019-09 | Journal article
DOI: 10.1016/j.jnucmat.2019.05.039
Contributors: Michael Reyes; Peng Wang; Gary Was; Jaime Marian
Source: check_circle
Crossref

The oxidation of alloy 690 in simulated pressurized water reactor primary water

Corrosion Science
2017-09 | Journal article
DOI: 10.1016/j.corsci.2017.07.004
Part of ISSN: 0010-938X
Source: Self-asserted source
Peng Wang

Oxidation of Zircaloy-4 during in situ proton irradiation and corrosion in PWR primary water

Journal of Materials Research
2015-05-14 | Journal article
DOI: 10.1557/jmr.2014.408
Part of ISSN: 0884-2914
Part of ISSN: 2044-5326
Source: Self-asserted source
Peng Wang

A facility for studying irradiation accelerated corrosion in high temperature water

Journal of Nuclear Materials
2014-08 | Journal article
DOI: 10.1016/j.jnucmat.2014.03.022
Part of ISSN: 0022-3115
Source: Self-asserted source
Peng Wang

How the crystallography and nanoscale chemistry of the metal/oxide interface develops during the aqueous oxidation of zirconium cladding alloys

Acta Materialia
2012-12 | Journal article
DOI: 10.1016/j.actamat.2012.09.021
Part of ISSN: 1359-6454
Source: Self-asserted source
Peng Wang

Studies Regarding Corrosion Mechanisms in Zirconium Alloys

Journal of ASTM International
2011 | Journal article
DOI: 10.1520/jai103246
Part of ISSN: 1546-962X
Source: Self-asserted source
Peng Wang

Plasma electrolytic oxidation of a zirconium alloy under AC conditions

Surface and Coatings Technology
2010-04 | Journal article
DOI: 10.1016/j.surfcoat.2009.11.042
Part of ISSN: 0257-8972
Source: Self-asserted source
Peng Wang

Peer review (34 reviews for 5 publications/grants)

Review activity for Acta materialia. (1)
Review activity for Corrosion science. (8)
Review activity for Journal of Materials Science and Technology. (1)
Review activity for Journal of nuclear materials. (21)
Review activity for Nuclear engineering and technology. (3)
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