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ویرایش: 1
نویسندگان: Hong Jiang (eds.)
سری:
ISBN (شابک) : 9789811023132, 9789811023149
ناشر: Springer Singapore
سال نشر: 2017
تعداد صفحات: 912
زبان: English
فرمت فایل : PDF (درصورت درخواست کاربر به PDF، EPUB یا AZW3 تبدیل می شود)
حجم فایل: 34 مگابایت
کلمات کلیدی مربوط به کتاب مجموعه مقالات بیستمین کنفرانس هسته ای حوزه اقیانوس آرام: جلد 3: انرژی هسته ای، همجوشی هسته ای، مهندسی هسته ای، جامعه شناسی زیست محیطی، پزشکی هسته ای
در صورت تبدیل فایل کتاب Proceedings of The 20th Pacific Basin Nuclear Conference: Volume 3 به فرمت های PDF، EPUB، AZW3، MOBI و یا DJVU می توانید به پشتیبان اطلاع دهید تا فایل مورد نظر را تبدیل نمایند.
توجه داشته باشید کتاب مجموعه مقالات بیستمین کنفرانس هسته ای حوزه اقیانوس آرام: جلد 3 نسخه زبان اصلی می باشد و کتاب ترجمه شده به فارسی نمی باشد. وبسایت اینترنشنال لایبرری ارائه دهنده کتاب های زبان اصلی می باشد و هیچ گونه کتاب ترجمه شده یا نوشته شده به فارسی را ارائه نمی دهد.
این سومین جلسه از مجموعه سه جلسه بیستمین کنفرانس هسته ای حوزه اقیانوس آرام (PBNC) است. این جلد موضوعات راکتور نیرو و ساختمان های جدید، مدیریت پسماند، کسب مزایای پزشکی و بیولوژیکی و برنامه دانشجویی را پوشش می دهد. به عنوان یکی از مهمترین و تاثیرگذارترین مجموعه کنفرانس های علوم و فناوری هسته ای، بیستمین PBNC در پکن برگزار شد و موضوع این نشست "هسته ای: قدرت بخشیدن به توسعه حوزه اقیانوس آرام و جهان». این دانشمند برجسته هسته ای و کارشناسان فنی، مدیران ارشد صنعت، مقامات ارشد دولتی و رهبران سازمان انرژی بین المللی از سراسر جهان گرد هم آمد. این کتاب به عنوان یک مرجع مفید نه تنها برای متخصصان و عموم مردم برای دانستن بیشتر در مورد صنعت هسته ای، بلکه برای سیاست گذاران برای تنظیم یا ایجاد استراتژی های انرژی عمل می کند.
This is the third in a series of three proceedings of the 20th Pacific Basin Nuclear Conference (PBNC). This volume covers the topics of Power Reactor and New Buildings, Waste Management, Acquiring Medical and Biological Benefits and Student program. As one in the most important and influential conference series of nuclear science and technology, the 20th PBNC was held in Beijing and the theme of this meeting was “Nuclear: Powering the Development of the Pacific Basin and the World”. It brought together outstanding nuclear scientist and technical experts, senior industry executives, senior government officials and international energy organization leaders from all across the world. The book serves as a useful reference not only for the professionals and public to know more about nuclear industry, but also for policymakers to adjust or make energy strategies.
Front Matter....Pages i-xiv
Front Matter....Pages 1-1
Analysis and Design of the Common Raft for a Chinese Third-Generation Nuclear Power Plant....Pages 3-15
A Fatigue-Crack Propagation Analysis Program and Its Application....Pages 17-27
A Study on the Tensile Properties of Materials at Elevated Temperature in RCC-M....Pages 29-41
Analysis Method of the Temperature for the Heavy Reflector....Pages 43-53
Analysis on Super-Long Frame Structure of Main Building of Conventional Island....Pages 55-68
Application of an Adaptive COMET Method to a PWR Benchmark Problem with Gadolinium....Pages 69-84
Calculation and Analysis of Cavitation for Low-Head Safety Injection Pump....Pages 85-92
Coupled Neutronics and Thermal–Hydraulics Analysis of Annular Fuel Assembly for SCWR....Pages 93-104
Dynamic Sliding Mode Control of Nuclear Steam Generator Water Level Using LPV Schemes....Pages 105-119
Experimental Study on Secondary Passive Residual Heat Removal System....Pages 121-141
I2S-LWR Concept Update....Pages 143-151
Main Building of Conventional Island Performance Assessment Based on Different Methods of Elasto-Plastic Analysis....Pages 153-167
Monte Carlo Study on Radial Burnup and Isotope Distribution....Pages 169-177
Numerical Instability Study of Supercritical Water Flowing Upward in Two Heated Parallel Channels....Pages 179-185
Numerical Investigations of the Helium Flow in Mini-Scale Gaps....Pages 187-200
Numerical Simulation on Water Hammer Phenomenon for Single Feedwater Line....Pages 201-217
Power Transients of the HTR-10 During Reactivity Insertion ATWS Tests....Pages 219-229
Research on Controlling Conditions of Cooling Water from Small Modular Reactors at Coastal Site....Pages 231-238
Steam Hammer Calculation and Study of Nuclear Island Main Steam Pipe Network....Pages 239-255
Front Matter....Pages 257-266
Study on Improvement of Capacity Expansion of Spent Fuel Pit Cooling System in PWR Nuclear Power Plants....Pages 1-1
Study on Standards Applicable for Primary and Secondary Water Chemical Analysis in the Third-Generation PWR....Pages 267-274
Study on the Localization of Instrumentation Installation Materials for AP1000....Pages 275-281
The Affection Analysis of Cross Talk on Power Range Measured Signal....Pages 283-290
The CFD Simulation on Grid-Spacer and Wire for Lead-Cooled Fast Reactor....Pages 291-298
Development of a 3D Core Calculation Code: COCO....Pages 299-311
The Gen-III Nuclear Power Technology in the World....Pages 313-320
The Methodology to Compensate Ex-core Nuclear Instrument Signal by In-core Nuclear Instrument Signal....Pages 321-328
The Numerical Simulation Research of Gas–Liquid Two-Phase Flow in Small-Break Loss-of-Coolant Accidents....Pages 329-337
The Resistance Characteristics Study of Emergency Feedwater System....Pages 339-348
The Setting of RPN Power Range Calculation Parameters in Fuqing Nuclear Power Plant....Pages 349-356
Transient Analyses of Main Steam Line Break Accident for High-Power Passive Reactor....Pages 357-364
Transmutation Analysis of Nuclear Waste in a Gas Fast Reactor....Pages 365-373
“Practical Elimination on Large Release of Radioactive Materials” and Safety Performance Research on HPR1000....Pages 375-383
Front Matter....Pages 385-397
Research on Treatment of Simulated Nuclear Power Plant Waste Liquid....Pages 399-399
An Introduction to Sanmen Nuclear Power Plant’s Radwaste Management Information System....Pages 401-411
Analysis of Liquid Effluents Discharge Method Under Normal Condition of One Inland NPP in the Northern Areas of China....Pages 413-424
Application Method Study of Erica Model and R&D128 Model in Radiological Impact Assessment of Terrestrial Organisms....Pages 425-430
Derivation of Activity Limits of Spent Radioactive Source for Near-Surface Disposal....Pages 431-440
Development and Application of Gamma-Radioactivity Nondestructive Measurement System for Complex Radiation Field....Pages 441-451
Front Matter....Pages 453-467
Development of the Concrete Cask Storage System for PWR Spent Nuclear Fuel in Korea....Pages 399-399
Evaluation of Algorithms of Dispersion Coefficients with a Field Tracer Experiment over Complex Terrain....Pages 469-472
Influences of Additives on the Performances of the Cementation of Simulated Radioactive Fluoride Liquid Wastes....Pages 473-485
Minor Actinides Incineration in a Small Molten Salt Fast Reactor....Pages 487-496
Overview of Radioactive Waste Treatment in Domestic Nuclear Power Plants of Pressurized Water Reactor....Pages 497-506
Solidification of Simulated α-HLLW in Iron Phosphate Glass-Ceramics....Pages 507-514
Study on Effect of Density Heterogeneity for Nuclear Waste Drum Samples in Segmented Gamma Scanning Analysis....Pages 515-523
Study on In-Drum Drying Technology of Waste Concentrates....Pages 525-534
Study on Radioactive Contaminated Soil Remediation Technologies and Selection Principles....Pages 535-546
The Importance of Influence Factors of the Fly Ash Cement Solidification....Pages 547-554
The Influence of Thermal Irradiation Synchronously Aging on the Structure of Modified Sodium Bentonite....Pages 555-561
The Introduction of the Safety Assessment of HLW Disposal in 2014–2017 in China....Pages 563-575
The Melting Treatment of Radioactive Steel Scrap from Decommissioning Nuclear Facility....Pages 577-587
The Radioactive Waste Minimization of Tianwan NPP Units 3&4....Pages 589-596
The Management Status and Advices of Radioactive Solid Waste from Development and Utilization of Mineral Resources....Pages 597-606
The Study of Microwave Ashing for Spent Radioactive Resin....Pages 607-616
Preliminary Study on the Vitrification of Molten Salt Reactor Radwastes Containing Fluorides by Phosphate Glass....Pages 617-621
Front Matter....Pages 623-633
An Organic Adsorbent Resin for Ga-68 Generator....Pages 635-635
Assessment of Production Channels of Isotopes for Combined PET/SPECT Imaging....Pages 637-639
Front Matter....Pages 641-646
2D Multi-group Transport Calculation on Hexagonal Geometry with the Method of Characteristics....Pages 647-647
Front Matter....Pages 649-659
A Detection of 226Ra Concentration in Water Around a Decommissioned Uranium Mine in Hunan Province....Pages 647-647
A Study of Spray Application by a Fire Truck for the Mitigation of Severe Accident Outside the Nuclear Power Plant....Pages 661-669
Application of Planar Laser-Induced Fluorescence to Measurement of Concentration Field in the Downcomer....Pages 671-680
Assessing the Conservatism in EPZ Determined on Plume Centerline Dose: A CALPUFF-Based Method Used in Level 3 PSA....Pages 681-690
Preparation and Properties of Multifunctional Pt/Ce0.7Zr0.3O2 Honeycomb Catalyst for Detritiation....Pages 691-704
Classification Methodologies for Nuclear Spent Fuel Forensic....Pages 705-710
Developing a Conceptual Design of Suction-Based Ex-containment Radioactive Release Barrier System and Defining its Design Limits....Pages 711-721
Development and Validation of Subchannel Code SUBSC....Pages 723-742
Wall Temperature Fluctuation Under Flow Pulsation in a Vertical Tube....Pages 743-756
Experimental Study on Natural Circulation Flow in Rectangular Channel Under Rolling....Pages 757-769
High-Heat-Flux Heat Removal Using a Porous-Micro-Channel....Pages 771-780
Neutronics Characteristics Study of Conceptual Space Heat-Pipe-Cooled Fast Reactor Core....Pages 781-789
Numerical Simulation on Thermal Stratification in the Containment after LOCA....Pages 791-798
Optimal Control Rod for Boron-Free Small Modular PWR....Pages 799-807
Power Optimization of Steam Generators Under Fault Conditions....Pages 809-815
Propagation of Nuclear Data Uncertainties for PWR Burnup Calculation....Pages 817-833
Research on Multi-objective Optimization Method for Maintenance Decision of Nuclear Power Plant....Pages 835-844
Simulation Analysis of Condensation Heat Transfer Inside C-type Tubes Based on RELAP5/MOD3.2....Pages 845-864
Sodium-Cooled Fast Breed Reactor Fuel Failure Detection Based on Cover Gas Monitoring....Pages 865-879
Study on Two-Phase Flow Instabilities in Straight and Helical Tubes....Pages 881-892
Front Matter....Pages 893-903
Validation of the Cross-Calibration Multispectral Infrared Thermography in Surface Temperature Measurements....Pages 647-647
Validation of Wall Friction Model in Multidimensional Component of Mars with Two-Phase Flow Experiments Describing ECC Behavior in Downcomer....Pages 905-928
....Pages 929-943