يعرض 1 - 10 نتائج من 670 نتيجة بحث عن '"Reactor vessel"', وقت الاستعلام: 0.82s تنقيح النتائج
  1. 1
    دورية أكاديمية
    Uncertainty analysis of molten corium In-Vessel Retention under External Reactor Vessel Cooling

    المؤلفون: Shihao Wu, Dong Wang, Yapei Zhang, Yukun Zhou, Wenxi Tian, Suizheng Qiu, G.H. Su

    المصدر: International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 4, Pp 159-167 (2023)

    مصطلحات موضوعية: Uncertainty analysis, In-Vessel Retention, External Reactor Vessel Cooling, Safety margin, Influence level, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    Relation: http://www.sciencedirect.com/science/article/pii/S2468605024000036; https://doaj.org/toc/2468-6050

    URL الوصول: https://doaj.org/article/a49d483f4e8a4ee5aa12fc30e4ce11b3

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  2. 2
    مؤتمر
    Development and Application of Intelligent Expert System for Cold Functional Test of Reactor Vessel Open in Nuclear Power Plant

    المؤلفون: Liao, Tongtong, Zhai, Bajing, Han, Lijie

    المصدر: 2020 Chinese Automation Congress (CAC) Automation Congress (CAC), 2020 Chinese. :4956-4958 Nov, 2020

    Relation: 2020 Chinese Automation Congress (CAC)

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  3. 3
    دورية أكاديمية
    Influence of Certain Metallurgical Factors on the Lifetime of Weld Joints of Metal of VVER-1000 and VVER-1200 Reactor Vessels

    المؤلفون: Chernobaeva, A. A., Erak, D. Yu., Tarasova, A. P.Aff1, IDS1063778822080063_cor3, Papina, V. B.

    المصدر: Physics of Atomic Nuclei. 85(8):1323-1334

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  4. 4
    دورية أكاديمية
    Analysis of dismantling process and disposal cost of waste RVCH

    المؤلفون: Younkyu Kim, Sunkyu Park, TaeWon Seo

    المصدر: Nuclear Engineering and Technology, Vol 55, Iss 1, Pp 45-51 (2023)

    مصطلحات موضوعية: Nuclear Power Plant, Reactor vessel closure head, Dismantling, Decontamination, Waste disposal, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    Relation: http://www.sciencedirect.com/science/article/pii/S1738573322004399; https://doaj.org/toc/1738-5733

    URL الوصول: https://doaj.org/article/b2b39e8cbbfd425ea662a64459a0e272

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  5. 5
    دورية أكاديمية
    Experimental Investigation on CHF along Elliptic-shaped Lower Head Wall and Influencing Factor under IVR-ERVC Condition

    المؤلفون: HE Yihai;WANG Gang;KUANG Bo;LUO Yuejian;WU Xiaoli

    المصدر: Yuanzineng kexue jishu, Vol 56, Iss 11, Pp 2465-2473 (2022)

    مصطلحات موضوعية: in vessel retention through external reactor vessel cooling, elliptic-shaped lower head, critical heat flux, influencing factor, Nuclear engineering. Atomic power, TK9001-9401, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798

    وصف الملف: electronic resource

    Relation: https://www.aest.org.cn/CN/10.7538/yzk.2021.youxian.0972; https://doaj.org/toc/1000-6931

    URL الوصول: https://doaj.org/article/001f9f92b8cb458bad1057a77247bb8c

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  6. 6
    مؤتمر
    Prediction of nuclear reactor vessel water level using deep neural networks

    المؤلفون: Koo, Young Do, Na, Man Gyun, Kim, Kyung-Suk, Kim, Chang-Hwoi

    المصدر: 2018 International Conference on Electronics, Information, and Communication (ICEIC) Electronics, Information, and Communication (ICEIC), 2018 International Conference on. :1-3 Jan, 2018

    Relation: 2018 International Conference on Electronics, Information, and Communication (ICEIC)

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  7. 7
    دورية أكاديمية
    On component isolation of conceptual advanced reactors

    المؤلفون: Samyog Shrestha, Efe G. Kurt, Arun Prakash, Ayhan Irfanoglu

    المصدر: Nuclear Engineering and Technology, Vol 54, Iss 8, Pp 2974-2988 (2022)

    مصطلحات موضوعية: Component isolation, Reactor vessel, MASTODON, Nuclear, Friction pendulum, Soil-structure interaction, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    Relation: http://www.sciencedirect.com/science/article/pii/S1738573322000845; https://doaj.org/toc/1738-5733

    URL الوصول: https://doaj.org/article/e0f771beffa54f41a911176286e3406d

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  8. 8
    دورية أكاديمية
    On Experimental Procedure Development for Evaluating the Effect of Biaxial Loading on the Static Crack Resistance Characteristics of Reactor Vessel Steels

    المؤلفون: Pokrovs’kyi, V. V., Sidyachenko, V. G.Aff1, IDs11223022003943_cor2, Ezhov, V. M.

    المصدر: Strength of Materials. 54(2):188-198

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  9. 9
    دورية أكاديمية

    لا يتم عرض هذه النتيجة على الضيوف.

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  10. 10
    دورية أكاديمية
    Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate

    المؤلفون: Min Seop Song, Il Woong Park, Eung Soo Kim, Yeon-Gun Lee

    المصدر: Nuclear Engineering and Technology, Vol 54, Iss 1, Pp 72-83 (2022)

    مصطلحات موضوعية: External reactor vessel cooling, Natural circulation flow, MARS-KS1.5, CFD analysis, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    Relation: http://www.sciencedirect.com/science/article/pii/S1738573321004605; https://doaj.org/toc/1738-5733

    URL الوصول: https://doaj.org/article/dfa7accb6f1640579f0822aa08fd00d4

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