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2016 24th International Conference on Nuclear Engineering

June 26–30, 2016

Charlotte, North Carolina, USA

Conference Sponsors:

ISBN:

978-0-7918-5002-2

In This Volume

Smart Grids, Grid Stability, and Offsite and Emergency Power (12)
Advanced and Next Generation Reactors, Fusion Technology (41)
Safety, Security, and Cyber Security (14)
Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues (10)

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; V002T05A001doi:https://doi.org/10.1115/ICONE24-60153

Abstract

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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; V002T05A002doi:https://doi.org/10.1115/ICONE24-60154

Abstract

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Topics: Trend analysis , Databases , Statistical analysis

Degraded Power Supplies

Maja Lundbäck, Mattias Karlsson

ICONE 2016; V002T05A003doi:https://doi.org/10.1115/ICONE24-60255

Abstract

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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; V002T05A004doi:https://doi.org/10.1115/ICONE24-60514

Abstract

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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; V002T05A005doi:https://doi.org/10.1115/ICONE24-60519

Abstract

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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; V002T05A006doi:https://doi.org/10.1115/ICONE24-60563

Abstract

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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; V002T05A007doi:https://doi.org/10.1115/ICONE24-60645

Abstract

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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; V002T05A008doi:https://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; V002T05A009doi:https://doi.org/10.1115/ICONE24-60987

Abstract

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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; V002T05A010doi:https://doi.org/10.1115/ICONE24-61075

Abstract

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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; V002T05A011doi:https://doi.org/10.1115/ICONE24-61077

Abstract

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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; V002T05A012doi:https://doi.org/10.1115/ICONE24-61084

Abstract

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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; V002T06A001doi:https://doi.org/10.1115/ICONE24-60017

Abstract

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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; V002T06A002doi:https://doi.org/10.1115/ICONE24-60022

Abstract

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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; V002T06A003doi:https://doi.org/10.1115/ICONE24-60029

Abstract

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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; V002T06A004doi:https://doi.org/10.1115/ICONE24-60064

Abstract

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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; V002T06A005doi:https://doi.org/10.1115/ICONE24-60076

Abstract

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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; V002T06A006doi:https://doi.org/10.1115/ICONE24-60113

Abstract

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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; V002T06A007doi:https://doi.org/10.1115/ICONE24-60123

Abstract

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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; V002T06A008doi:https://doi.org/10.1115/ICONE24-60144

Abstract

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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; V002T06A009doi:https://doi.org/10.1115/ICONE24-60156

Abstract

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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; V002T06A010doi:https://doi.org/10.1115/ICONE24-60232

Abstract

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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; V002T06A011doi:https://doi.org/10.1115/ICONE24-60328

Abstract

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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; V002T06A012doi:https://doi.org/10.1115/ICONE24-60333

Abstract

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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; V002T06A013doi:https://doi.org/10.1115/ICONE24-60352

Abstract

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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; V002T06A014doi:https://doi.org/10.1115/ICONE24-60355

Abstract

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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; V002T06A015doi:https://doi.org/10.1115/ICONE24-60362

Abstract

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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; V002T06A016doi:https://doi.org/10.1115/ICONE24-60382

Abstract

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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; V002T06A017doi:https://doi.org/10.1115/ICONE24-60392

Abstract

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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; V002T06A018doi:https://doi.org/10.1115/ICONE24-60396

Abstract

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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; V002T06A019doi:https://doi.org/10.1115/ICONE24-60429

Abstract

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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; V002T06A020doi:https://doi.org/10.1115/ICONE24-60455

Abstract

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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; V002T06A021doi:https://doi.org/10.1115/ICONE24-60502

Abstract

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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; V002T06A022doi:https://doi.org/10.1115/ICONE24-60523

Abstract

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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; V002T06A023doi:https://doi.org/10.1115/ICONE24-60571

Abstract

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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; V002T06A024doi:https://doi.org/10.1115/ICONE24-60675

Abstract

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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; V002T06A025doi:https://doi.org/10.1115/ICONE24-60711

Abstract

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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; V002T06A026doi:https://doi.org/10.1115/ICONE24-60715

Abstract

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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; V002T06A027doi:https://doi.org/10.1115/ICONE24-60716

Abstract

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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; V002T06A028doi:https://doi.org/10.1115/ICONE24-60734

Abstract

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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; V002T06A029doi:https://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; V002T06A030doi:https://doi.org/10.1115/ICONE24-60759

Abstract

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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; V002T06A031doi:https://doi.org/10.1115/ICONE24-60760

Abstract

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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; V002T06A032doi:https://doi.org/10.1115/ICONE24-60829

Abstract

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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; V002T06A033doi:https://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; V002T06A034doi:https://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; V002T06A035doi:https://doi.org/10.1115/ICONE24-60858

Abstract

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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; V002T06A036doi:https://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; V002T06A037doi:https://doi.org/10.1115/ICONE24-60893

Abstract

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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; V002T06A038doi:https://doi.org/10.1115/ICONE24-60914

Abstract

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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; V002T06A039doi:https://doi.org/10.1115/ICONE24-60919

Abstract

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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; V002T06A040doi:https://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; V002T06A041doi:https://doi.org/10.1115/ICONE24-61166

Abstract

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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; V002T07A001doi:https://doi.org/10.1115/ICONE24-60024

Abstract

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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; V002T07A002doi:https://doi.org/10.1115/ICONE24-60091

Abstract

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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; V002T07A003doi:https://doi.org/10.1115/ICONE24-60173

Abstract

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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; V002T07A004doi:https://doi.org/10.1115/ICONE24-60249

Abstract

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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; V002T07A005doi:https://doi.org/10.1115/ICONE24-60250

Abstract

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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; V002T07A006doi:https://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; V002T07A007doi:https://doi.org/10.1115/ICONE24-60268

Abstract

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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; V002T07A008doi:https://doi.org/10.1115/ICONE24-60359

Abstract

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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; V002T07A009doi:https://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; V002T07A010doi:https://doi.org/10.1115/ICONE24-60676

Abstract

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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; V002T07A011doi:https://doi.org/10.1115/ICONE24-60773

Abstract

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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; V002T07A012doi:https://doi.org/10.1115/ICONE24-60917

Abstract

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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; V002T07A013doi:https://doi.org/10.1115/ICONE24-60927

Abstract

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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; V002T07A014doi:https://doi.org/10.1115/ICONE24-60983

Abstract

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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; V002T08A001doi:https://doi.org/10.1115/ICONE24-60004

Abstract

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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; V002T08A002doi:https://doi.org/10.1115/ICONE24-60119

Abstract

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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; V002T08A003doi:https://doi.org/10.1115/ICONE24-60282

Abstract

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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; V002T08A004doi:https://doi.org/10.1115/ICONE24-60472

Abstract

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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; V002T08A005doi:https://doi.org/10.1115/ICONE24-60700

Abstract

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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; V002T08A006doi:https://doi.org/10.1115/ICONE24-60821

Abstract

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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; V002T08A007doi:https://doi.org/10.1115/ICONE24-60936

Abstract

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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; V002T08A008doi:https://doi.org/10.1115/ICONE24-60958

Abstract

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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; V002T08A009doi:https://doi.org/10.1115/ICONE24-60960

Abstract

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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; V002T08A010doi:https://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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