يعرض 1 - 10 نتائج من 4,345 نتيجة بحث عن '"Reactor pressure vessel"', وقت الاستعلام: 1.72s تنقيح النتائج
  1. 1
    دورية أكاديمية
    The investigation of the carbon on irradiation hardening and defect clustering in RPV model alloy using ion irradiation and OKMC simulation

    المؤلفون: Yitao Yang, Jianyang Li, Chonghong Zhang

    المصدر: Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2071-2078 (2024)

    مصطلحات موضوعية: Irradiation hardening, Carbon, Reactor pressure vessel, OKMC simulation, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    Relation: http://www.sciencedirect.com/science/article/pii/S1738573324000160; https://doaj.org/toc/1738-5733

    URL الوصول: https://doaj.org/article/f20210bd9b9f4232a467594426d221b6

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  2. 2
    دورية أكاديمية
    Fracture analysis for nozzle cracks in nuclear reactor pressure vessel using FCPAS

    المؤلفون: Abdurrezzak Boz, Oğuzhan Demir

    المصدر: Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2292-2306 (2024)

    مصطلحات موضوعية: Fracture analysis, Stress intensity factors, Reactor pressure vessel, Nozzle cracks, Deflected cracks, Inclined cracks, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    Relation: http://www.sciencedirect.com/science/article/pii/S1738573324000421; https://doaj.org/toc/1738-5733

    URL الوصول: https://doaj.org/article/17193cc433774784a780ee8141031d88

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  3. 3
    دورية أكاديمية
    Grain Refinement of the HAZ Metal due to Welding

    المؤلفون: Chernobaeva, A. A.Aff1, IDS1063778823080021_cor1, Erak, D. Yu., Polyakova, R. O., Chebotaryov, O. D., Pesnya, Yu. E., Trofimchuk, V. V.

    المصدر: Physics of Atomic Nuclei. 86(8):1921-1927

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  4. 4
    دورية أكاديمية
    Comparison of Маster curve with normative method of estimating WWER-1000 reactor pressure vessel metal fracture toughness

    المؤلفون: V. M. Revka, L. I. Chyrko

    المصدر: Âderna Fìzika ta Energetika, Vol 25, Iss 1, Pp 58-65 (2024)

    مصطلحات موضوعية: wwer-1000 reactor pressure vessel, 15x2nmfa-a steel, surveillance specimens, radiation embrittlement, critical brittleness temperature, fracture toughness, master curve., Atomic physics. Constitution and properties of matter, QC170-197

    وصف الملف: electronic resource

    Relation: http://jnpae.kinr.kiev.ua/25.1/Articles_PDF/jnpae-2024-25-0058-Revka.pdf; https://doaj.org/toc/1818-331X; https://doaj.org/toc/2074-0565

    URL الوصول: https://doaj.org/article/ad60b45a377340299da35dab31778af8

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  5. 5
    مؤتمر
    Probabilistic Fracture Mechanics Analysis of the Beltline of A PWR Nuclear Power Plant Pressure Vessel

    المؤلفون: Muktadir, Md Sifatul, Datta, Debashis, Mollah, Abdus Sattar

    المصدر: 2021 International Conference on Automation, Control and Mechatronics for Industry 4.0 (ACMI) Automation, Control and Mechatronics for Industry 4.0 (ACMI), 2021 International Conference on. :1-5 Jul, 2021

    Relation: 2021 International Conference on Automation, Control and Mechatronics for Industry 4.0 (ACMI)

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  6. 6
    دورية أكاديمية
    Interaction of solute manganese and nickel atoms with dislocation loops in iron-based alloys irradiated with 2.8 MeV Fe ions at 400 °C

    المؤلفون: Nguyen Ba Vu Chinh, Kenta Murakami, Liang Chen, Phongsakorn Prak Tom, Xinrun Chen, Takashi Hashimoto, Taehyun Hwang, Akinori Furusawa, Tatsuya Suzuki

    المصدر: Nuclear Materials and Energy, Vol 39, Iss , Pp 101639- (2024)

    مصطلحات موضوعية: Reactor pressure vessel, Atom probe tomography, Solute cluster, Dislocation loop, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    Relation: http://www.sciencedirect.com/science/article/pii/S2352179124000620; https://doaj.org/toc/2352-1791

    URL الوصول: https://doaj.org/article/2d9dfd8ce33f4229aa8bf45f4c221c2f

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  7. 7
    دورية أكاديمية
    Characterization of fusion boundary between low alloy steel and stainless steel cladding

    المؤلفون: Tingguang Liu, Qingfeng Wu, Yonggang Fang, Yimei Wang, Qibao Chu, Yinqiang Chen, Donghua Tian, Yonghao Lu, Tetsuo Shoji

    المصدر: Journal of Materials Research and Technology, Vol 28, Iss , Pp 2363-2378 (2024)

    مصطلحات موضوعية: Reactor pressure vessel, Low alloy steel, Cladding, Fusion boundary, Carbide-depleted zone, Mining engineering. Metallurgy, TN1-997

    وصف الملف: electronic resource

    Relation: http://www.sciencedirect.com/science/article/pii/S2238785423032477; https://doaj.org/toc/2238-7854

    URL الوصول: https://doaj.org/article/18e1042d6486427dbb5bb4925bf16989

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  8. 8
    مؤتمر
    Improved visual inspection for nozzle inner radius based on panoramic imaging

    المؤلفون: Huang, Sanao, Xu, Ke, Wang, Ruixin, Hong, Maocheng

    المصدر: 2020 Joint 9th International Conference on Informatics, Electronics & Vision (ICIEV) and 2020 4th International Conference on Imaging, Vision & Pattern Recognition (icIVPR) Informatics, Electronics & Vision (ICIEV) and 2020 3rd International Conference on Imaging, Vision & Pattern Recognition (icIVPR), 2020 Joint 8th International Conference on. :1-8 Aug, 2020

    Relation: 2020 Joint 9th International Conference on Informatics, Electronics & Vision (ICIEV) and 2020 4th International Conference on Imaging, Vision & Pattern Recognition (icIVPR)

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  9. 9
    دورية أكاديمية
    Assessment of the three-dimensional flow field in the reactor pressure vessel in Hualong One nuclear power plants

    المؤلفون: Zonglan Wei, Songwei Li, Sijia Du, Yazhe Lu, Zhifang Qiu

    المصدر: Frontiers in Nuclear Engineering, Vol 3 (2024)

    مصطلحات موضوعية: computational fluid dynamics, reactor pressure vessel, flowrate distribution, data assimilation, turbulence model, Plasma physics. Ionized gases, QC717.6-718.8, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798

    وصف الملف: electronic resource

    Relation: https://www.frontiersin.org/articles/10.3389/fnuen.2024.1359616/full; https://doaj.org/toc/2813-3412

    URL الوصول: https://doaj.org/article/2840835329384c7e96ff62897706f970

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  10. 10
    دورية أكاديمية
    The effects of flux on the radiation-induced embrittlement of reactor pressure vessel steels: review of current understanding and application to high fluences

    المؤلفون: Susan Ortner, Paul Styman, Elliot Long

    المصدر: Frontiers in Nuclear Engineering, Vol 3 (2024)

    مصطلحات موضوعية: flux, embrittlement, reactor pressure vessel, steel, radiation, Plasma physics. Ionized gases, QC717.6-718.8, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798

    وصف الملف: electronic resource

    Relation: https://www.frontiersin.org/articles/10.3389/fnuen.2024.1339222/full; https://doaj.org/toc/2813-3412

    URL الوصول: https://doaj.org/article/7ebc8acbaf7f4c6e86c2ad0d24e1798c

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