peng Xu

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peng Xu

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    20102025

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    • 2024

      Overview of the Neutron Radiography Reactor (NRAD) for Neutron Imaging and In-Core Experiment Capabilities at Idaho National Laboratory

      Xu, P., Craft, A. & Ruddell, M., Nov 17 2024, Proceedings of the Radiation Protection and Shielding Division 2024, RPSD 2024. American Nuclear Society, p. 100-101 2 p. (Proceedings of the Radiation Protection and Shielding Division 2024, RPSD 2024).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

    • 2022

      From FUMAC and ACTOF to ATF-TS: Contribution of IAEA CRPs to Advanced Technology Fuel Testing, Modelling and Simulation

      Zhang, J., Xu, P., Sim, K. S., Veshchunov, M. & Khaperskaia, A., 2022, Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference. American Nuclear Society, p. 382-389 8 p. (Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      1 Scopus citations
    • 2021

      Evaluation of Neutron-Irradiated Additively Manufactured Zircaloy-2

      Partezana, J. M., Cleary, W. T. & Xu, P., 2021, Zirconium in the Nuclear Industry: 19th International Symposium. Motta, A. T. & Yagnik, S. K. (eds.). ASTM International, p. 467-491 25 p. (ASTM Special Technical Publication; vol. STP 1622).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      1 Scopus citations
    • 2019

      Hot cell tensile testing of neutron irradiated additively manufactured type 316l stainless steel

      Freyer, P. D., Cleary, W. T., Ruminski, E. M., Joseph Long, C. & Xu, P., 2019, Minerals, Metals and Materials Series. Springer International Publishing, p. 1021-1038 18 p. (Minerals, Metals and Materials Series).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

    • 2018

      Cold spray coatings for accident tolerant Zr-alloy cladding in light water reactors

      Yeom, H., Maier, B., Johnson, G., Dabney, T., Lenling, M., Scallon, P., Romero, J., Walters, J., Xu, P., Shah, H. & Sridharan, K., 2018, AISTech 2018 Proceedings - Iron and Steel Technology Conference and Exposition. Association for Iron and Steel Technology, AISTECH, p. 1576-1579 4 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      3 Scopus citations

    • Hot cell tensile testing of neutron irradiated additively manufactured type 316L stainless steel

      Freyer, P. D., Cleary, W. T., Ruminski, E. M., Joseph Long, C. & Xu, P., 2018, Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Paraventi, D., Wright, M. & Jackson, J. H. (eds.). Springer International Publishing, p. 1021-1038 18 p. (Minerals, Metals and Materials Series; vol. Part F9).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      5 Scopus citations

    • Update on Westinghouse encore® accident tolerant fuel program

      Oelrich, R., Xu, P., Lahoda, E. & Deck, C., 2018, AISTech 2018 Proceedings - Iron and Steel Technology Conference and Exposition. Association for Iron and Steel Technology, AISTECH, p. 1311-1313 3 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

    • Uranium silicide and uranium silicide-nitride fuels: Assessing phase behavior for fabrication and in-reactor behavior

      Wilson, T. L., Adorno, D. L., Kocevski, V., Moore, E. E., White, J. T., Wood, E. S., Nelson, A. T., Xu, P., Middleburgh, S. C., McMurray, J. W. & Besmann, T. M., 2018, AISTech 2018 Proceedings - Iron and Steel Technology Conference and Exposition. Association for Iron and Steel Technology, AISTECH, p. 1318-1320 3 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

    • Westinghouse accident tolerant fuel materials

      Boylan, F., Xu, P., Romero, J. & Lahoda, E., Nov 15 2018, Advances in Ceramics for Environmental, Functional, Structural, and Energy Applications: Ceramic Transactions. Wiley Blackwell, Vol. 265. p. 1-6 6 p. (Advances in Ceramics for Environmental, Functional, Structural, and Energy Applications).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

    • 2017

      Modeling of SiC cladding behavior during severe accidents

      Luangdilok, W. & Xu, P., 2017, International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017. American Nuclear Society, p. 711-720 10 p. (International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017; vol. 2).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      2 Scopus citations
    • 2016

      Corrosion resistant coatings for zirconium-alloy cladding with improved accident tolerance

      Xu, P., Lahoda, E. J., Ray, S., Partezana, J. M., Sridharan, K. & Wolfe, D. E., 2016, Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance. American Nuclear Society, p. 1189-1196 8 p. (Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      4 Scopus citations

    • Development of zirconium-silicide coatings for accident tolerant zirconium-Alloy fuel cladding

      Yeom, H., Maier, B., Mariani, R., Bai, D., Xu, P. & Sridharan, K., 2016, International Congress on Advances in Nuclear Power Plants, ICAPP 2016. American Nuclear Society, p. 2126-2131 6 p. (International Congress on Advances in Nuclear Power Plants, ICAPP 2016; vol. 3).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      5 Scopus citations

    • Hydrothermal corrosion studies on nitride fuels

      Jaques, B. J., Watkins, J., Braine, T., Tyburska-Puschel, B., Xu, P., Lahoda, E. J. & Butt, D. P., 2016, Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance. American Nuclear Society, p. 1535-1544 10 p. (Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      1 Scopus citations

    • Manufacturability of U3Si2 and its high temperature oxidation behaviour

      Goddard, D. T., Mathers, D. P., Eaves, D. G., Xu, P., Lahoda, E. J. & Harp, J. M., 2016, Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance. American Nuclear Society, p. 31-39 9 p. (Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      2 Scopus citations

    • SiC cladding corrosion and mitigation

      Lahoda, E., Ray, S., Boylan, F., Xu, P. & Jacko, R., 2016, Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance. American Nuclear Society, p. 189-195 7 p. (Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      6 Scopus citations
    • 2012

      Uranium mononitride as a potential commercial LWR fuel

      Xu, P., Yan, J., Lahoda, E. J. & Ray, S., 2012, International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012. p. 2610-2617 8 p. (International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012; vol. 4).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      9 Scopus citations
    • 2011

      Grain boundary engineering and air oxidation behavior of alloy 690

      Xu, P., Zhao, L. Y., Sridharan, K. & Allen, T. R., 2011, 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011. p. 1847-1859 13 p. (15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011; vol. 3).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      1 Scopus citations

    • Pore structure analysis of nuclear graphites IG-110 and NBG-18

      Zheng, G. Q., Xu, P., Sridharan, K. & Allen, T. R., 2011, Advances in Materials Science for Environmental and Nuclear Technology II. p. 251-260 10 p. (Ceramic Transactions; vol. 227).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      7 Scopus citations

    • Radiation resistance of nanocrystalline silicon carbide

      Jamison, L., Xu, P., Sridharan, K. & Allen, T., 2011, Advances in Materials Science for Environmental and Nuclear Technology II. p. 161-168 8 p. (Ceramic Transactions; vol. 227).

      Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

      2 Scopus citations
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