معرفة
قاعدة البيانات العربية الرقمية "معرفة"
الرئيسية
الخدمات
معامل التأثير "آرسيف"
المفضلة
اتصل بنا
Language
English
العربية
تسجيل الدخول
بحث
تصفح
All
العنوان
المؤلفين / الأشخاص
المؤسسة
بحث
بحث متقدم
بحث متقدم
محددات البحث
الكل
المستخلص
المؤلفين/ الأشخاص
الدولة
المؤسسة
ردمد / ردمك
الموضوع الرئيسي
رقم السجل
المصدر
قائمة المحتويات
العنوان
الموضوعات
و
أو
ليس
الكل
المستخلص
المؤلفين/ الأشخاص
الدولة
المؤسسة
ردمد / ردمك
الموضوع الرئيسي
رقم السجل
المصدر
قائمة المحتويات
العنوان
الموضوعات
و
أو
ليس
الكل
المستخلص
المؤلفين/ الأشخاص
الدولة
المؤسسة
ردمد / ردمك
الموضوع الرئيسي
رقم السجل
المصدر
قائمة المحتويات
العنوان
الموضوعات
محددات الوثيقة
لها نص كامل
العبارة
تحتوي
مطابقة
أي كلمة
Language
العربية
الفرنسية
الإنجليزية
عدد الصفحات
مساوي
أقل من
أكبر من
الصفحات
نوع الوثيقة
مقالات
كتاب
فصل كتاب
دوريات
أطروحات عالمية
رسائل جامعية
أوراق مؤتمرات
عرض كتاب
تقرير إحصائي
التقارير السنوية
مؤتمر
المكنز
البرامج الأكاديمية والتدريب
الجوائز
المفاهيم و المصطلحات
مؤسسة
سؤال استطلاع
فتاوى
الشهادات التدريب
استطلاعات الرأي العام
القرارات الشرعية
ملف شخص
الحوكمة
النظام الأساسي
تقرير مدققي الحسابات
القوانين و التشريعات
تقارير الشركات
سلسلة كتب
التقارير الربعية
عرض مؤتمر
كتاب جامعي
فصل كتاب جامعي
من
2024
2023
2022
2021
2020
2019
2018
2017
2016
2015
2014
2013
2012
2011
2010
2009
2008
2007
2006
2005
2004
2003
2002
2001
2000
1999
1998
1997
1996
1995
1994
1993
1992
1991
1990
1989
1988
1987
1986
1985
1984
1983
1982
1981
1980
1979
1978
1977
1976
1975
1974
1973
1972
1971
1970
1969
1968
1967
1966
1965
1964
1963
1962
1961
1960
إلى
2024
2023
2022
2021
2020
2019
2018
2017
2016
2015
2014
2013
2012
2011
2010
2009
2008
2007
2006
2005
2004
2003
2002
2001
2000
1999
1998
1997
1996
1995
1994
1993
1992
1991
1990
1989
1988
1987
1986
1985
1984
1983
1982
1981
1980
1979
1978
1977
1976
1975
1974
1973
1972
1971
1970
1969
1968
1967
1966
1965
1964
1963
1962
1961
1960
تقييد النتائج
التخصصات الرئيسية
العلوم الهندسية و تكنولوجيا المعلومات
(321)
نوع البيانات
مقالات
(733)
اللغة
الإنجليزية
(733)
الدولة
مصر
(733)
المؤلفين / الأشخاص
مشتوا، نعمان
(3)
المصدر
Science and Technology of Nuclear Installations
(733)
الفترة:
نتائج البحث
(
151
-
200
من
733
)
الصلة
تاريخ النشر تصاعدي
تاريخ النشر تنازلي
العنوان تصاعدي
العنوان تنازلي
المؤلف تصاعدي
المؤلف تنازلي
مقالات
Prediction of Flow and Temperature Distributions in a High Flux Research Reactor Using the Porous Media Approach
By: Huang, Shanfang; Gong, Daxin; Clausse, Alejandro…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-13, 13 p.
مقالات
Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test
By: Gonfiotti, Bruno; Paci, Sandro; Kozlowski, Tomasz. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-25, 25 p.
مقالات
Engineering Design of a Voloxidizer with a Double Reactor for the Hull Separation of Spent Nuclear Fuel Rods
By: Lee, Jae-Won; Jeon, Sang-Chae; Uspuras, Eugenijus…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-12, 12 p.
مقالات
Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code
By: Mimouni, Stéphane; Mechitoua, Namane; Tiselj, Iztok…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-41, 41 p.
مقالات
Implementation and Comparison of High-Resolution Spatial Discretization Schemes for Solving Two-Fluid Seven-Equation Two-Pressure Model
By: Shan, Jianqiang; Clausse, Alejandro; Gou, Junli…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-14, 14 p.
مقالات
Calculation of Lead-Iron Double-Layer Thickness for Gamma-Ray Shielding by MATLAB Program
By: Lekchaum, Sarai; Serikov, Arkady; Locharoenrat, Kitsakorn. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-7, 7 p.
مقالات
Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal at Zero Power Benchmark Cases with NODAL3 Code
By: Sembiring, Tagor Malem; Pinem, Surian; Serikov, Arkady…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-8, 8 p.
مقالات
Development and Application of the Power Plant Real-Time Temperature and Stress Monitoring System
By: Duda, Piotr; Holbert, Keith E.. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-7, 7 p.
مقالات
Seismic Vulnerability Assessment of Site-Vicinity Infrastructure for Supporting the Accident Management of a Nuclear Power Plant
By: Katona, Tamás János; Zio, Enrico; Vilimi, A.. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-7, 7 p.
مقالات
Feasibility Studies on Pyro-SFR Closed Fuel Cycle and Direct Disposal of Spent Nuclear Fuel in Line with the Latest National Policy and Strategy of Korea
By: Khan, Muhammad Minhaj; Lee, Jae Min; Serikov, Arkady…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-17, 17 p.
مقالات
Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer
By: Khatry, Jivan; Ojovan, Michael I.; Aydogan, Fatih. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-15, 15 p.
مقالات
Investigation and Assessment of the CFD for Horizontal Flow in the VHTR Core
By: Shengyuan, Yan; Habiyaremye, Jean Luc; Pandey, Manmohan…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-6, 6 p.
مقالات
Uncertainty and Sensitivity Analysis of Void Reactivity Feedback for 3D BWR Assembly Model
By: Slavickas, Andrius; Uspuras, Eugenijus; Pandey, Manmohan…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-9, 9 p.
مقالات
Assessment of RELAPSCDAPSIMMOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test
By: Allison, C. M.; Serikov, Arkady; Hohorst, J. K.…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-12, 12 p.
مقالات
Shielding Verifications for a Gamma Irradiation Facility Considering the Installation of a New Automatic Product Loading System
By: Rodriguez Gual, Maritza; Mesquita, Amir Zacarias; Ojovan, Michael I.…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-6, 6 p.
مقالات
Equipment Layout Improvement for Large-Scale Hot Cell Facility Logistics
By: Yu, Seungnam; Lim, Jaehoon; Sborchia, Carlo…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-11, 11 p.
مقالات
Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor
By: Su, Guanghui; Tiselj, Iztok; Qiu, Suizheng…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-15, 15 p.
مقالات
Dynamic Behavior Analysis of Touchdown Process in Active Magnetic Bearing System Based on a Machine Learning Method
By: Sun, Zhe; Yan, Xunshi; Uspuras, Eugenijus…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-11, 11 p.
مقالات
SUSD3D Computer Code as Part of the XSUN-2017 Windows Interface Environment for Deterministic Radiation Transport and Cross-Section Sensitivity-Uncertainty Analysis
By: Kodeli, Ivan A.; Giusti, Valerio; Slavič, Slavko. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-16, 16 p.
مقالات
Diffusion Behaviors of Hydrogen Isotopes in Incoloy 800H: A First-Principles Study
By: Li, Hong; Cao, Jianzhu; Ojovan, Michael I.…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-6, 6 p.
مقالات
Study on the Confidence and Reliability of the Mean Seismic Probability Risk Model
By: Wang, Xiao-Lei; Uspuras, Eugenijus; Lu, Da-Gang. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-9, 9 p.
مقالات
STH-CFD Codes Coupled Calculations Applied to HLM Loop and Pool Systems
By: Angelucci, M.; Martelli, D.; Kozlowski, Tomasz…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-13, 13 p.
مقالات
Separation of Electrolytic Reduction Product from Stainless Steel Wire Mesh Cathode Basket via Salt Draining and Reuse of the Cathode Basket
By: Choi, Eun-Young; Lee, Jeong; Hur, Jin-Mok…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-9, 9 p.
مقالات
Development and Application of a New High-Efficiency Sparse Linear System Solver in the Thermal-Hydraulic System Analysis Code
By: Ge, Li; Pandey, Manmohan; Shan, Jianqiang…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-10, 10 p.
مقالات
Comprehensive Uncertainty Quantification in Nuclear Safeguards
By: Bonner, E.; Burr, Tom; Melikhov, Oleg I.…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-16, 16 p.
مقالات
First-Principles Study on Various Point Defects Formed by Hydrogen and Helium Atoms in Tungsten
By: Zhao, Qiang; Zhang, Zheng; Uspuras, Eugenijus…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-9, 9 p.
مقالات
Quantitative Analysis of Oxygen Gas Exhausted from Anode through In Situ Measurement during Electrolytic Reduction
By: Choi, Eun-Young; Hur, Jin-Mok; Holbert, Keith E.…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-7, 7 p.
مقالات
CFD Analysis of a Decay Tank and a Siphon Breaker for an Innovative Integrated Passive Safety System for a Research Reactor
By: Lee, Kwon-Yeong; Yoon, Hyun-Gi; Paladino, Domenico…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-9, 9 p.
مقالات
Probabilistic Dose Assessment from SB-LOCA Accident in Ujung Lemahabang Using TMI-2 Source Term
By: Sunarko, Hidemasa; Su’ud, Zaki; Clausse, Alejandro…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-8, 8 p.
مقالات
Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength
By: Lu, Zhenming; Liu, Bing; Uspuras, Eugenijus…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-6, 6 p.
مقالات
The Optimization of Radiation Protection in the Design of the High Temperature Reactor-Pebble-Bed Module
By: Sun, Sida; Serikov, Arkady; Fang, Sheng…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-15, 15 p.
مقالات
Source Term Study on Tritium in HTR-PM: Theoretical Calculations and Experimental Design
By: Cao, Jianzhu; Xie, Feng; Ojovan, Michael I.…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-11, 11 p.
مقالات
Analysis of Precooling Injection Transient of Steam Generator for High Temperature Gas Cooled Reactor
By: Shi, Lei; Yamano, H.; Zheng, Yanhua…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-8, 8 p.
مقالات
Nuclear Waste Management Decision-Making Support with MCDA
By: Schwenk-Ferrero, A.; Andrianov, A.; Podofillini, Luca. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-20, 20 p.
مقالات
Analyses of the TIARA 43 MeV Proton Benchmark Shielding Experiments Using the ARES Transport Code
By: Zhang, Bin; Miró, Rafael; Chen, Yixue…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-5, 5 p.
مقالات
Assessment of the MARS Code Using the Two-Phase Natural Circulation Experiments at a Core Catcher Test Facility
By: Lee, Dong Hun; Choi, Su Ryong; Ojovan, Michael I.…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-13, 13 p.
مقالات
Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model
By: Shi, Hao; Cai, Qi; Serikov, Arkady…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-13, 13 p.
مقالات
Design and Development Framework of Safety-Critical Software in HTR-PM
By: Guo, Chao; Xiong, Huasheng; Xiaojin, Huang…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-9, 9 p.
مقالات
Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code
By: Yousif, Eltayeb; Zhang, Zhijian; Mavko, Borut…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-13, 13 p.
مقالات
R&D on a Nonlinear Dynamics Analysis Code for the Drop Time of the Control Rod
By: Lu, Dao-gang; Wang, Yuanpeng; Kozlowski, Tomasz…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-6, 6 p.
مقالات
Analysis of Seismic Soil-Structure Interaction for a Nuclear Power Plant (HTR-10)
By: Zhou, Qin; Ojovan, Michael I.; Wang, Haitao…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-13, 13 p.
مقالات
Temperature Dependence of Thermophysical Properties of Full-Scale Corium of Fast Energy Reactor
By: Skakov, Mazhyn K.; Mukhamedov, Nurzhan Ye.; Uspuras, Eugenijus…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-7, 7 p.
مقالات
FM-DBEM Simulation of 3D Microvoid and Microcrack Graphite Models
By: Wang, HongTao; Wang, Haitao; Cizelj, Leon…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-14, 14 p.
مقالات
Three Design Basis Accidents’ Analysis on the HTR-10GT
By: Lang, Minggang; Yamano, H.; Dong, Yujie…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-13, 13 p.
مقالات
Preliminary CFD Assessment of an Experimental Test Facility Operating with Heavy Liquid Metals
By: Lomonaco, Guglielmo; Cizelj, Leon; Tarantino, Mariano…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-11, 11 p.
مقالات
Using Wireless Sensor Networks to Achieve Intelligent Monitoring for High-Temperature Gas-Cooled Reactor
By: Li, Jianghai; Clausse, Alejandro; Xiaojin, Huang…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-8, 8 p.
مقالات
Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant
By: Dong, Zhe; Zhang, Zuoyi; Zio, Enrico…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-19, 19 p.
مقالات
The Electric Current Effect on Electrochemical Deconsolidation of Spherical Fuel Elements
By: Chen, Xiaotong; Lu, Zhenming; Zhao, Hongsheng…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-6, 6 p.
مقالات
Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems
By: Šadek, Siniša; Grgić, Davor; Šimić, Zdenko…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-16, 16 p.
مقالات
Effects of Different Operating Temperatures on the Tensile Properties of the Grid Plate Hardfaced with Colmonoy in a Pool Type Sodium Fast Reactor
By: Balaguru, S.; Murali, Vela; Lee, Hyeong-Yeon…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-9, 9 p.
«
1
2
3
4
5
6
7
8
9
10
»