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Proceedings Papers

Proceedings Volume Cover
2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
  • Nuclear Engineering Division
ISBN:
978-0-7918-5002-2
Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues

Smart Grids, Grid Stability, and Offsite and Emergency Power

Results of the Loss of Offsite Power Events Analysis
Andrija Volkanovski, Antonio Ballesteros Avila, Miguel Peinador Veira
ICONE 2016; V002T05A001https://doi.org/10.1115/ICONE24-60153
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Topics: Control rooms , Databases , Diesel generators , Emergencies , Errors , Failure , Inspection , Maintenance , Power grids
Trend Analysis of Loss of Offsite Power Events
Andrija Volkanovski, Antonio Ballesteros Avila, Miguel Peinador Veira
ICONE 2016; V002T05A002https://doi.org/10.1115/ICONE24-60154
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Topics: Trend analysis , Databases , Statistical analysis
Degraded Power Supplies
Maja Lundbäck, Mattias Karlsson
ICONE 2016; V002T05A003https://doi.org/10.1115/ICONE24-60255
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Topics: Countermeasures , Design , Electricity (Physics) , Nuclear power stations , Radiation (Physics) , Reliability , Robustness , Safety
Development and Technical Supporting System for Smart Grid in China
Wang Lin, Zhang Yujun
ICONE 2016; V002T05A004https://doi.org/10.1115/ICONE24-60514
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Topics: China , Smart grids , Power systems (Machinery)
Coordinated Control Strategy of Multiple FACTS Devices in 750kV Power Grid
Li Yunwei, Yujun Zhang, Hua Liu
ICONE 2016; V002T05A005https://doi.org/10.1115/ICONE24-60519
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Topics: Power grids , Wind power , Transients (Dynamics)
Effects of External Grid Disturbances to Nuclear Power Plants
Robert Arians, Simone Arnold, Christian Mueller, Claudia Quester, Dagmar Sommer
ICONE 2016; V002T05A006https://doi.org/10.1115/ICONE24-60563
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Topics: Nuclear power stations , Reliability , Electrical components , Power grids , Simulation , Damage , Electricity (Physics) , Optimization , Pressurized water reactors , Probabilistic safety assessment
Study on Power Transmission Plan of the Nuclear Power Base in Shandong Peninsula
Chengzhu Yin, Miao Wang
ICONE 2016; V002T05A007https://doi.org/10.1115/ICONE24-60645
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Topics: Nuclear power , Power grids , Construction , Stress , Circuits , Nuclear power stations , Electrical wires , Generators , Poles (Building) , Power stations
Long Term Operation Issues for Electrical Cable Systems in Nuclear Power Plants
Leonard S. Fifield, Robert Duckworth, Samuel W. Glass, III
ICONE 2016; V002T05A008https://doi.org/10.1115/ICONE24-60729
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Topics: Cables , Nuclear power stations , Insulation , Damage , Design , Heat , Licensing , Polymers , Radiation (Physics) , Temperature
Electric Power Supply of German NPPs: Defence in Depth, Protection Against External Hazards and Retrofitting as a Consequence of the Fukushima Accident
Sebastian A. Meiss
ICONE 2016; V002T05A009https://doi.org/10.1115/ICONE24-60987
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Topics: Defense industry , Electricity (Physics) , Fukushima nuclear disaster, Japan, 2011 , Hazards , Nuclear power stations , Accidents , Design , Alternating current (Electricity) , Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986 , Control systems
Results of the CSNI Task Group on the Robustness of Electrical Systems (ROBELSYS)
Pascal Regnier, Young Joon Choi, Toshiyuki Koganeya
ICONE 2016; V002T05A010https://doi.org/10.1115/ICONE24-61075
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Topics: Electronic systems , Robustness , Accidents , Computer software , Electricity (Physics) , Electronics , Fukushima nuclear disaster, Japan, 2011 , Safety , Simulation , Workshops (Work spaces)
IAEA Guidance on Enhancing the Safety of Electrical Power Systems
Alexander Duchac, Magnus Knutsson
ICONE 2016; V002T05A011https://doi.org/10.1115/ICONE24-61077
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Topics: Electricity (Physics) , Safety , Design , Nuclear power stations , Power systems (Machinery) , Electronic systems , Energy industry , Instrumentation , Probability
Dynamic Simulation Studies of Performed Additional Tests During FAT for Emergency Diesel Generators at Nuclear Power Plant
Salah K. Kanaan, Amer Omanovic
ICONE 2016; V002T05A012https://doi.org/10.1115/ICONE24-61084
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Topics: Diesel generators , Emergencies , Nuclear power stations , Simulation , Control equipment , Magnetization , Modeling , Safety , Circuits , Diesel engines

Advanced and Next Generation Reactors, Fusion Technology

Simulation Study of Dynamic Characteristic of Once-Through Steam Generator for CEFR
Ye Shangshang, Yang Hongyi, Wang Xiaokun
ICONE 2016; V002T06A001https://doi.org/10.1115/ICONE24-60017
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Topics: Boilers , Simulation , Steam , China , Convection , Critical heat flux , Fast neutron reactors , Film boiling , Flow (Dynamics) , Heart failure
Analysis of the Effects Caused by the Core Compaction Into LFR Reactor
Rosa Lo Frano, Pugliese Giovanni
ICONE 2016; V002T06A002https://doi.org/10.1115/ICONE24-60022
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Topics: Compacting , Buckling , Coolants , Deformation , Displacement , Earthquakes , Fast neutron reactors , Finite element methods , Finite element model , Fuels
Experimental Study of Steam Pressure Suppression by Condensation in a Water Tank at Sub-Atmospheric Pressure
Dahmane Mazed, Rosa Lo Frano, Donato Aquaro, Daniele Del Serra, Igor Sekachev, Francesco Orlandi
ICONE 2016; V002T06A003https://doi.org/10.1115/ICONE24-60029
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Topics: Condensation , Pressure , Steam , Water , Accidents , Vacuum , Temperature , Vessels , Atmospheric pressure , Boiling
Development of the Pump-Integrated Intermediate Heat Exchanger in Advanced Loop-Type Sodium-Cooled Fast Reactor for Demonstration
Katsunori Amano, Yasuhiro Enuma, Satoshi Futagami, Tomoyuki Inoue, Sota Watanabe
ICONE 2016; V002T06A004https://doi.org/10.1115/ICONE24-60064
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Topics: Heat exchangers , Pumps , Sodium fast reactors , Design , Safety , Coolants , Earthquakes , Leakage , Maintainability , Nuclear power
Research on Manufacturing Technology of China Experimental Fast Reactor Fuel Rod
Yu Hu, Jianhong Wang
ICONE 2016; V002T06A005https://doi.org/10.1115/ICONE24-60076
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Topics: China , Fast neutron reactors , Fuel rods , Manufacturing technology , Manufacturing , Welding , Wire , Cladding systems (Building) , Extruding , Fuels
Study on the Break Accidents of the HTR-PM Primary Loop
Minggang Lang, Ximing Sun, Yanhua Zheng
ICONE 2016; V002T06A006https://doi.org/10.1115/ICONE24-60113
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Topics: Accidents , Helium , Containment , Coolants , Pressure , Temperature , Boilers , Design , High temperature , Leakage
Transient Analysis on Helium Coolant Tube Break Accident of Dual-Functional Lithium Lead Test Blanket Module
Qian Sun, Tianji Peng, Zhiwei Zhou, Zhibin Chen, Jieqiong Jiang
ICONE 2016; V002T06A007https://doi.org/10.1115/ICONE24-60123
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Topics: Accidents , Coolants , Helium , Lithium , Transient analysis , Pressure , Shock (Mechanics) , China , Corners (Structural elements) , Flow (Dynamics)
Thermo-Hydraulic Analysis of the Optimized Helium Cooled Solid Breeder Blanket for CFETR
Shijie Cui, Dalin Zhang, Jie Chang, Wenxi Tian, Suizheng Qiu, G. H. Su
ICONE 2016; V002T06A008https://doi.org/10.1115/ICONE24-60144
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Topics: Helium , Temperature , Design , Temperature distribution , Ceramics , China , Computational fluid dynamics , Coolants , Cooling , Dynamic analysis
A Study on the Straight Double-Walled Tube Steam Generator Design Against Sodium-Water Reaction in DECs
Hironori Kanda, Yasuhiro Enuma, Satoshi Futagami, Masaya Kawamura, Hiroshi Ushiki, Shinya Ogumo, Takashi Ichihara, Takashi Nakashima
ICONE 2016; V002T06A009https://doi.org/10.1115/ICONE24-60156
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Topics: Boilers , Design , Sodium , Water , Failure , Sodium fast reactors , Water leakage , Contact resistance , Temperature , Leakage
Design Approach for Mitigation of Air Ingress in High Temperature Gas-Cooled Reactor
Hiroyuki Sato, Hirofumi Ohashi, Shigeaki Nakagawa
ICONE 2016; V002T06A010https://doi.org/10.1115/ICONE24-60232
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Topics: Design , Very high temperature reactors , Oxidation , Accidents , Fuels , Rupture , Buoyancy , Cooling , Damage , Flow (Dynamics)
Identification Modeling of Accelerator Driven System Based on Growing and Pruning Radial Basis Function Network
Run Luo, Shifa Wu, Xinyu Wei, Fuyu Zhao
ICONE 2016; V002T06A011https://doi.org/10.1115/ICONE24-60328
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Topics: Modeling , Radial basis function networks , Artificial neural networks , Computation , Algorithms , Kalman filters , Simulation results , Transient analysis
Accurate Simulation of HTGR Steam Generator for Pressurized Loss of Forced Cooling Accident
Jianan Lu, Jiong Guo, Fu Li
ICONE 2016; V002T06A012https://doi.org/10.1115/ICONE24-60333
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Topics: Accidents , Boilers , Cooling , Simulation , Very high temperature reactors , Circuits , Heat capacity , Algorithms , Approximation , Boundary-value problems
Kinetic Monte Carlo Simulation of Hydrogen Diffusion in Tungsten
Xue Yang, Wasiu O. Oyeniyi
ICONE 2016; V002T06A013https://doi.org/10.1115/ICONE24-60352
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Topics: Diffusion (Physics) , Hydrogen , Simulation , Tungsten , Temperature , Modeling , Matlab , Simulation models , Simulation results
Characteristic Confirmation Test by Using HTTR and Investigation of Absorbing Thermal Load Fluctuation
Yuki Honda, Daisuke Tochio, Hiroyuki Sato, Shigeaki Nakagawa, Masato Ono, Yusuke Fujiwara, Shimpei Hamamoto, Kazuhiko Iigaki, Shoji Takada
ICONE 2016; V002T06A014https://doi.org/10.1115/ICONE24-60355
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Topics: Stress , Very high temperature reactors , Temperature , Graphite , Heat , Testing performance , Combined heat and power , Fuels , High temperature , Nuclear power stations
Nuclear, Solar and Desalination Working Together Symbiotically
Hamad Alwashmi, Jay F. Kunze
ICONE 2016; V002T06A015https://doi.org/10.1115/ICONE24-60362
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Topics: Solar energy , Fossil fuels , Combustion , Emissions , Energy / power systems , Fuels , Gases , Nuclear power , Solar power , Transportation systems
Effects of Applying the Implicit Particle Fuel Model for Pebble-Bed Reactors
Zhifeng Li, Liangzhi Cao, Hongchun Wu, Chenghui Wan, Tianliang Hu
ICONE 2016; V002T06A016https://doi.org/10.1115/ICONE24-60382
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Topics: Fuels , Particulate matter , Packing (Shipments) , Packings (Cushioning) , High temperature , Modeling , Monte Carlo methods , Simulation , Very high temperature reactors
Neutronics and Thermo-Hydraulic Analysis of Water-Cooled Blanket Based on PWR and SCWR Water Conditions for CFETR
Jie Cheng, Yingwei Wu, G. H. Su, Suizheng Qiu, Wenxi Tian
ICONE 2016; V002T06A017https://doi.org/10.1115/ICONE24-60392
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Topics: Pressurized water reactors , Supercritical water reactors , Water , China , Heat , Temperature , Bridges (Structures) , Ceramics , Computer simulation , Coolants
Analyses of Severe Accidents in GFR Demonstrator ALLEGRO With MELCOR 2.1
Petr Vácha, Ladislav Bělovský
ICONE 2016; V002T06A018https://doi.org/10.1115/ICONE24-60396
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Topics: Accidents , Fast neutron reactors , Safety , Cladding systems (Building) , Computer simulation , Computers , Coolants , Damage , Design , Failure
Investigation of the Modified RELAP5 MOD 3.2 Capability to Simulate the Transients of the Fluoride-Salt High-Temperature Reactors
Limin Liu, Qiqi Yan, Dalin Zhang, Suizheng Qiu, G. H. Su
ICONE 2016; V002T06A019https://doi.org/10.1115/ICONE24-60429
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Topics: High temperature , Transients (Dynamics) , Accidents , Flow (Dynamics) , Fluids , Fuels , Heat , Specific heat , Steady state
Comparative Study on Neutronics Characteristics of a 1500 MWe Metal Fuel Sodium-Cooled Fast Reactor
Kazuya Ohgama, Gerardo Aliberti, Nicolas E. Stauff, Shigeo Ohki, Taek K. Kim
ICONE 2016; V002T06A020https://doi.org/10.1115/ICONE24-60455
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Topics: Fuels , Metals , Sodium fast reactors , Nuclear power , Approximation , Cycles , Design , Neutrons , Sensitivity analysis , Sodium
Activities of the Safety and Operation Project for the International Research and Development of the Sodium-Cooled Fast Reactor in the Generation IV International Forum
Takaaki Sakai, Lixia Ren, Haileyesus Tsige-Tamirat, Alfredo Vasile, Seok-Hun Kang, Yury Ashurko, Thomas Fanning
ICONE 2016; V002T06A021https://doi.org/10.1115/ICONE24-60502
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Topics: Industrial research , Safety , Sodium fast reactors , Testing , Design , Generation IV reactors , Licensing , Maintenance , Model validation , Nuclear power
iB1350: A Generation III.7 Reactor After the Fukushima Daiichi Accident
Takashi Sato, Keiji Matsumoto, Kenji Hosomi, Keisuke Taguchi
ICONE 2016; V002T06A022https://doi.org/10.1115/ICONE24-60523
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Topics: Accidents , Fukushima nuclear disaster, Japan, 2011 , Safety , Containment , Design , Emergency core cooling systems , Failure , Aircraft , Boiling water reactors , Construction
Confirmation of Seismic Integrity of HTTR Against 2011 Great East Japan Earthquake
Masato Ono, Kazuhiko Iigaki, Yosuke Shimazaki, Atsushi Shimizu, Hiroyuki Inoi, Daisuke Tochio, Shimpei Hamamoto, Tetsuo Nishihara, Shoji Takada, Kazuhiro Sawa, Toshinari Kondo, Keidai Kojima
ICONE 2016; V002T06A023https://doi.org/10.1115/ICONE24-60571
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Topics: Earthquakes , Inspection , Instrumentation , Very high temperature reactors , Damage , Earthquake resistant design , High temperature , Industrial research , Maintenance , Nuclear power
Impact of Testing Activities on Small Modular Reactor Total Capital Investment Cost
Giovanni Maronati, Bojan Petrovic, Jurie J. Van Wyk, Matthew H. Kelley, Chelsea C. White
ICONE 2016; V002T06A024https://doi.org/10.1115/ICONE24-60675
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Topics: Small modular reactors , Testing , Manufacturing , Construction , Design , Nuclear power stations , Computer software , Modular construction , Teams , Uncertainty
Assessment of SIMMER-III Code Based on Steam Generator Tube Rupture Experiments in LIFUS5/Mod2 Facility
Alessio Pesetti, Alessandro Del Nevo, Nicola Forgione
ICONE 2016; V002T06A025https://doi.org/10.1115/ICONE24-60711
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Topics: Boilers , Rupture , Water , Pressure , Underground injection , Vessels , Boundary-value problems , Computer simulation , Computers , Cooling
Experimental Investigation of Spiral Tubes Steam Generator Rupture Scenarios in LIFUS5/Mod2 Facility for ELFR
Alessio Pesetti, Alessandro Del Nevo, Nicola Forgione
ICONE 2016; V002T06A026https://doi.org/10.1115/ICONE24-60715
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Topics: Boilers , Rupture , Pressure , Water , Strain gages , Vessels , Deformation , Ejectors , Eutectic alloys , Fast neutron reactors
Test Section Design for SGTR Experimental Investigation in CIRCE Facility for HLMRS Supported by SIMMER-III Code
Alessio Pesetti, Mariano Tarantino, Nicola Forgione
ICONE 2016; V002T06A027https://doi.org/10.1115/ICONE24-60716
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Topics: Design , Rupture , Disks , Vessels , Boilers , Heat exchangers , Pressure , Transients (Dynamics) , Underground injection , Water
RELAP5-3D Simulation of Natural Circulation in Fast Reactors With Lead-Bismuth Eutectic Alloy Coolant
Alex Matev
ICONE 2016; V002T06A028https://doi.org/10.1115/ICONE24-60734
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Topics: Coolants , Eutectic alloys , Fast neutron reactors , Simulation , Nuclear reactors , Design , Fuels , Nuclear fission , Safety , Simulation results
A Methodology for the Integration of Passive System Reliability With Success Criteria in a Probabilistic Framework for Advanced Reactors
Acacia J. Brunett, Dave Grabaskas, Matthew Bucknor, Stefano Passerini
ICONE 2016; V002T06A029https://doi.org/10.1115/ICONE24-60749
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Topics: Reliability , Safety , Feedback , Industrial research , Light water reactors , Nuclear power , Performance , Prisms (Optics) , Probabilistic risk assessment , Risk
A Methodology for the Integration of a Mechanistic Source Term Analysis in a Probabilistic Framework for Advanced Reactors
Dave Grabaskas, Acacia J. Brunett, Matthew Bucknor
ICONE 2016; V002T06A030https://doi.org/10.1115/ICONE24-60759
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Topics: Containment , Fuels , Industrial research , Light water reactors , Nuclear power , Performance , Probabilistic risk assessment , Radioisotopes , Reliability , Risk
A Methodology for the Development of a Reliability Database for an Advanced Reactor Probabilistic Risk Assessment
Dave Grabaskas, Acacia J. Brunett, Matthew Bucknor
ICONE 2016; V002T06A031https://doi.org/10.1115/ICONE24-60760
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Topics: Databases , Probabilistic risk assessment , Reliability , Boundary-value problems , Event history analysis , Failure mechanisms , Gages , Heat exchangers , Industrial research , Light water reactors
Start-Up Simulation of the Improved TOPAZ-II Space Power System
Wenwen Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su
ICONE 2016; V002T06A032https://doi.org/10.1115/ICONE24-60829
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Topics: Power systems (Machinery) , Simulation , Heat pipes , Coolants , Ducts , Neutrons , Physics , Pipes , Pumps , Secondary cells
Improvement of Exchanging Method of Neutron Startup Source of High Temperature Engineering Test Reactor
Hiroaki Sawahata, Yosuke Shimazaki, Etsuo Ishitsuka, Kazunori Yamazaki, Yoshinori Yanagida, Yusuke Fujiwara, Shoji Takada, Masayuki Shinozaki, Shimpei Hamamoto, Daisuke Tochio
ICONE 2016; V002T06A033https://doi.org/10.1115/ICONE24-60842
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Topics: High temperature , Neutrons , Containers , Fuels , Leakage , Machinery , Neutron sources , Radiation (Physics) , Transportation systems , Cooling
Thermal Mixing Behavior in the Annulus of Co-Axial Double-Walled Piping in HTGR
Daisuke Tochio, Yusuke Fujiwara, Masato Ono, Masanori Shinohara, Shimpei Hamamoto, Kazuhiko Iigaki, Shoji Takada
ICONE 2016; V002T06A034https://doi.org/10.1115/ICONE24-60843
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Topics: Annulus , Pipes , Very high temperature reactors , Helium , Temperature , Flow (Dynamics) , Coolants , Cooling systems , Gas flow , Gases
Loss of Core Cooling Test Without One Cooling Line in Vessel Cooling System (VCS) of High Temperature Engineering Test Reactor (HTTR)
Yusuke Fujiwara, Takahiro Nemoto, Daisuke Tochio, Masanori Shinohara, Masato Ono, Shimpei Hamamoto, Kazuhiko Iigaki, Shoji Takada
ICONE 2016; V002T06A035https://doi.org/10.1115/ICONE24-60858
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Topics: Cooling , Cooling systems , High temperature , Vessels , Temperature , Reactor vessels , Concretes , Heat , Helium , Control systems
New IAEA Coordinated Research Project on Thermal-Hydraulics of Supercritical Water Cooled Reactors
Katsumi Yamada, Laurence Leung, Walter Ambrosini
ICONE 2016; V002T06A036https://doi.org/10.1115/ICONE24-60876
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Topics: Thermal hydraulics , Water , Carbon reinforced plastics , Supercritical water reactors , Collaboration , Performance , Databases
Preliminary Analysis of the Post-Disassembly Expansion Phase and Structural Response Under Unprotected Loss of Flow Accident in Prototype Sodium Cooled Fast Reactor
Yuichi Onoda, Ken-ichi Matsuba, Yoshiharu Tobita, Tohru Suzuki
ICONE 2016; V002T06A037https://doi.org/10.1115/ICONE24-60893
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Topics: Accidents , Engineering prototypes , Flow (Dynamics) , Sodium fast reactors , Energetics , Reactor vessels , Energy generation , Robustness , Stress , Design
CFD Pre-Test Analysis and Design of the NACIE-UP BFPS Fuel Pin Bundle Simulator
R. Marinari, I. Di Piazza, M. Tarantino, F. Magugliani, A. Alemberti, W. Borreani, P. B. Ghionzoli
ICONE 2016; V002T06A038https://doi.org/10.1115/ICONE24-60914
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Topics: Computational fluid dynamics , Design , Fuels , Temperature , Fast neutron reactors , Flow (Dynamics) , Manufacturing , Pins (Engineering) , Safety , Engineering simulation
iB1350: Innovative Passive Containment Cooling System for the iB1350
Takashi Sato, Keiji Matsumoto, Nobuhiro Hara
ICONE 2016; V002T06A039https://doi.org/10.1115/ICONE24-60919
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Topics: Containment , Cooling systems , Pipes , Suction , Gases , Steam , Pressure , Vents , Accidents , Boiling
Influencing Factors of the HTR-10 Core Dynamics in Reactivity Insertion ATWS Tests
Feng Gou, Fubing Chen, Yujie Dong
ICONE 2016; V002T06A040https://doi.org/10.1115/ICONE24-61081
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Topics: Dynamics (Mechanics) , Scram , Transients (Dynamics) , Heat , High temperature , Safety , Sensitivity analysis , Simulation , Temperature
Study on Typical Initial Event of ATWS for Small Modular Reactor
Zhang Dan, Ran Xu, Qiu Zhifang, Zhou Ke, Feng Li
ICONE 2016; V002T06A041https://doi.org/10.1115/ICONE24-61166
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Topics: Small modular reactors , Pressurized water reactors , Transients (Dynamics) , Accidents , Data acquisition systems , Design , Nuclear reactor coolants , Pressure , Safety , Scram

Safety, Security, and Cyber Security

Preliminary Study of Function Determination and Capacity of ACP600’s Reactor Emergency Borating System
Shu Zhang, Xiaohua Zhang
ICONE 2016; V002T07A001https://doi.org/10.1115/ICONE24-60024
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Topics: Emergencies , Design , Safety , Nuclear power stations , Accidents , Boron , China , Concretes , Feedback , Pressurized water reactors
The Effect on the Support Seismic Loads of Primary Equipment With Different Reactor Coolant Pump
Ye Xianhui, Cai Fengchun, Lan Bin, Zhang Yixiong
ICONE 2016; V002T07A002https://doi.org/10.1115/ICONE24-60091
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Topics: Nuclear reactor coolants , Pumps , Stress , Computational methods , Economics , Nuclear design , Safety , Seismic analysis
Research on Thermal Hydraulic Characteristics of Passive Containment Cooling System for Ship Nuclear Power Platform
Chunhui Dai, Jun Wu, Sichao Tan, Zhenxing Zhao, Qi Xiao, Zhouyang Liu, Yong Liu
ICONE 2016; V002T07A003https://doi.org/10.1115/ICONE24-60173
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Topics: Containment , Cooling systems , Nuclear power , Ships , Steam , Heat , Seawater , Heat transfer , Pressure , Accidents
Preparation for a New Experimental Program Addressing Core-Material-Relocation Behavior During Severe Accident With BWR Design Conditions: Conduction of Preparatory Tests Applying Non-Transfer-Type Plasma Heating Technology
Yuta Abe, Ikken Sato, Akihiro Ishimi, Toshio Nakagiri, Yuji Nagae
ICONE 2016; V002T07A004https://doi.org/10.1115/ICONE24-60249
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Topics: Accidents , Boiling water reactors , Design , Heat conduction , Heating , Plasmas (Ionized gases) , Blades , Rods , Uncertainty
Development of Transient and Safety Analysis Method for ATF With SiC
Fumie Sebe, Masato Yamada, Yutaka Takeuchi, Kazuo Kakiuchi, Kazunari Okonogi
ICONE 2016; V002T07A005https://doi.org/10.1115/ICONE24-60250
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Topics: Safety , Transients (Dynamics) , Accidents , Oxidation , Water , Transient analysis , Cladding systems (Building) , Fuels , High temperature , Hydrogen
Safety Assessment of Fuel Storage Ponds Following Cooling Faults
Jonathan Webb, Charles Bridgford
ICONE 2016; V002T07A006https://doi.org/10.1115/ICONE24-60267
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Topics: Cooling , Fuel storage , Safety , Water , Temperature , Containment , Cooling systems , Spent nuclear fuels , Concretes , Cracking (Materials)
Review of Experimental Studies on the Heat Transfer Behaviour of Volumetrically-Heated Pool With Different Boundary Conditions and the Influence of Crust Formation
Xiaoyang Gaus-Liu, Alexei Miassoedov, Stephan Gabriel
ICONE 2016; V002T07A007https://doi.org/10.1115/ICONE24-60268
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Topics: Boundary-value problems , Heat transfer , Accident management , Cooling , Geometry , Heat flux , Light water reactors , Vessels
Development of Error Reduction Methods in Aerosol Measurement for Pool Scrubbing Experiment
HaoMin Sun, Yasuteru Sibamoto, Yuria Okagaki, Taisuke Yonomoto
ICONE 2016; V002T07A008https://doi.org/10.1115/ICONE24-60359
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Topics: Aerosols , Errors , Air flow , Particulate matter , Water , Bubbles , Accidents , Decontamination , Filters , Light scattering
Analysis on Safety System Operating Characteristic of SCWR
Liang Liu, Tao Zhou, Jie Chen, Ali Shahzad Muhammad, Juan Chen, Bangyang Xia
ICONE 2016; V002T07A009https://doi.org/10.1115/ICONE24-60501
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Topics: Safety , Supercritical water reactors , Control systems , Accidents , Flow (Dynamics) , Oscillations , Passive control , Pressure control , Water
Advanced Cooling Tube Mobile Heat Exchanger in the Outer Shape of a Fuel Assembly for Spent Fuel Pool Cooling
Matthias Reuter, Leo Ornot, Torsten Maier, Thomas Fuchs, Kerstin Gauter, Markus Reck, Joseph Redmond
ICONE 2016; V002T07A010https://doi.org/10.1115/ICONE24-60676
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Topics: Cooling , Fuels , Heat exchangers , Manufacturing , Shapes , Spent nuclear fuels , Nuclear power stations , Fukushima nuclear disaster, Japan, 2011 , Geometry , Inventions
Cyber Attack Detection of I&C Systems in NPPS Based on Physical Process Data
Jianghai Li, Xiaojin Huang
ICONE 2016; V002T07A011https://doi.org/10.1115/ICONE24-60773
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Topics: Nuclear power stations , Computer security , Defense industry , Control systems , Security , Accidents , Encryption , Failure , Instrumentation , Principal component analysis
Development of Hydrogen Treatment System in Severe Accident: Part 2 — Study on Reaction Characteristic of a Hydrogen Processing Unit
Chikako Iwaki, Daigo Kittaka, Toshihiro Yoshii, Motoshige Yagyu, Masato Okamura, Masashi Tanabe, Fumihiko Ishibashi
ICONE 2016; V002T07A012https://doi.org/10.1115/ICONE24-60917
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Topics: Accidents , Hydrogen , Metals , Pipes , Pressure , Temperature , Vents , Boiling water reactors , Filters , Oxidation
Methodology for Fragility Evaluation of a Seawall Against Tsunami Effects: Part 1 — Overflow and Physical Damage Associated With Tsunami Wave Pressure
Hideki Kaida, Yoshinori Miyagawa, Naoto Kihara
ICONE 2016; V002T07A013https://doi.org/10.1115/ICONE24-60927
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Topics: Damage , Pressure , Seawalls , Tsunamis , Waves , Nuclear power stations , Accidents , Compressive strength , Concretes , Density
Application of Fuzzy Weighted Support Vector Regression to Accidents Condition Monitoring of Nuclear Power Plant
B. T. Jiang, J. W. Hines, F. Y. Zhao
ICONE 2016; V002T07A014https://doi.org/10.1115/ICONE24-60983
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Topics: Accidents , Condition monitoring , Nuclear power stations , Support vector machines , Artificial neural networks , Fuels , Temperature , Transients (Dynamics) , Boron , Computers

Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues

Suggested Guide for Geotechnical Sampling and Testing of Backfill and Borrow for Safety Related Nuclear Structures
Nasser Massoudi
ICONE 2016; V002T08A001https://doi.org/10.1115/ICONE24-60004
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Topics: Construction , Cycles , Delays , Design , Licensing , Nuclear industry , Nuclear power stations , Quality control , Regulations , Roads
Nuclear Air Cleaning Codes and Standards Development and Use in the United States
Ronald R. Bellamy
ICONE 2016; V002T08A002https://doi.org/10.1115/ICONE24-60119
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Topics: Engineering standards , Nuclear power stations , Safety , Testing , Accidents , Activated carbon , ASME Standards , ASTM International , Boiling water reactors , Construction
Comparison of the ASME, RCC-M and ISO Requirements for Welding Qualifications and Welding Quality
Marcello Consonni, Andrew Wasylyk, Stéphane Leclerc, Walter Sperko, Philippe Malouines
ICONE 2016; V002T08A003https://doi.org/10.1115/ICONE24-60282
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Topics: Welding , Engineering standards , ASME Boiler and Pressure Vessel Code , Boilers , Japan Society of Mechanical Engineers , Nuclear power stations , Pressure , Pressure vessels , Welding operators
Strategies to Prevent Benign Transients From Becoming Serious Accidents
Samuel Miranda
ICONE 2016; V002T08A004https://doi.org/10.1115/ICONE24-60472
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Topics: Accidents , Plant design , Safety , Transients (Dynamics)
Regulatory Actions That Hinder Development of Effective Risk Reduction Measures by the Nuclear Industry for Enhanced Severe Accident Prevention and Mitigation Measures After Fukushima
Sunil Nijhawan
ICONE 2016; V002T08A005https://doi.org/10.1115/ICONE24-60700
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Topics: Fukushima nuclear disaster, Japan, 2011 , Nuclear industry , Risk reduction , Safety , Accidents , Public utilities , Risk , Silence , Damage , Emergencies
Development of “Proactive Safety Review Guideline for Continuous Improvement on Nuclear Power Plants”
Yoshiyuki Narumiya, Koji Okamoto, Shingo Ueno, Kentaro Hayashi, Takahiro Kuramoto
ICONE 2016; V002T08A006https://doi.org/10.1115/ICONE24-60821
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Topics: Nuclear power stations , Safety , Nuclear power
Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 1 — Current Status and Path Forward
Tai Asayama, Shigeru Takaya
ICONE 2016; V002T08A007https://doi.org/10.1115/ICONE24-60936
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Topics: Fast neutron reactors , Japan Society of Mechanical Engineers , Reliability , Design , In-service inspection , Buckling , Design methodology , Engineering standards , Inspection , Stress
Development of Rules on Concrete Containment Vessels for NPP
Tomohiro Nishizawa, Takao Nishikawa, Katsuki Takiguchi, Hiroyuki Sugita, Yasuo Hijioka, Hirokazu Tsuji
ICONE 2016; V002T08A008https://doi.org/10.1115/ICONE24-60958
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Topics: Concretes , Containment vessels , Nuclear power stations , Construction , Design , Prestressed concrete , Reinforced concrete , Reliability , Safety , Steel
Outline of Specification for Composite SC Walls in Nuclear Facilities
Saahastaranshu R. Bhardwaj, Amit H. Varma, Taha Al-Shawaf
ICONE 2016; V002T08A009https://doi.org/10.1115/ICONE24-60960
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Topics: Composite materials , Nuclear power stations , Design , Shear (Mechanics) , Steel , Failure , Safety , Accidents , Anchorage , Bending (Stress)
Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 2 — Development of a Code Case for Seismic Buckling Evaluation Based on LRFD
Shigeru Takaya, Naoto Sasaki, Tai Asayama, Yoshio Kamishima
ICONE 2016; V002T08A010https://doi.org/10.1115/ICONE24-60964
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Topics: Buckling , Fast neutron reactors , Japan Society of Mechanical Engineers , Reliability , Design , Stress , Probability , Vessels , Civil engineering , Earthquake risk
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