Skip to Main Content
American Society of Mechanical Engineers: Digital Collection Open Menu
Cart
header search
Search
Advanced Search
Skip Nav Destination

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:
978-0-7918-5001-5
Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors

Operations and Maintenance, Aging Management and Plant Upgrades

Experimental Investigation of Static Characteristics of Swing and Tilting Disc Check Valves
Jerzy Marcinkiewicz, Adam Adamkowski, Mariusz Lewandowski, Waldemar Janicki
ICONE 2016; V001T01A001https://doi.org/10.1115/ICONE24-60031
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Disks , Valves , Flow (Dynamics) , Fluid-dynamic forces , Pressure , Water
ASME Operation and Maintenance (OM) Code Overview
Ronald C. Lippy
ICONE 2016; V001T01A002https://doi.org/10.1115/ICONE24-60086
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: In-service testing , Maintenance , Mechanical engineers , Nuclear power plant maintenance , Power stations , Regulations , Testing
Instrument Health Monitoring for Extending Calibration Intervals of Safety Related Instruments
R. Steven Black, Aaron J. Hussey, Randall L. Bickford
ICONE 2016; V001T01A003https://doi.org/10.1115/ICONE24-60102
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Calibration , Instrumentation , Safety , Damage , Errors , Nuclear power stations , Testing , Maintenance , Reliability , Risk
Testing the Impact on Emergency Diesel Performance of Water in Diesel Fuel
Robert Cryer, Mark O’Connell
ICONE 2016; V001T01A004https://doi.org/10.1115/ICONE24-60214
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Diesel , Emergencies , Testing , Water , Diesel engines , Engines , Computer software , Contamination , Nuclear power stations , Simulation
Phased Array Ultrasonic Inspection Technique for Cast Austenitic Stainless Steel Parts of Nuclear Power Plants
Setsu Yamamoto, Jun Semboshi, Azusa Sugawara, Makoto Ochiai, Kentaro Tsuchihashi, Hiroyuki Adachi, Koji Higuma
ICONE 2016; V001T01A005https://doi.org/10.1115/ICONE24-60256
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Inspection , Nuclear power stations , Stainless steel , Echoes , Noise (Sound) , Electrical discharge machining , Ultrasonic testing , Algorithms , Data acquisition systems , Gages
Impact of Deviations Handling on Outages
Naoëlle Matahri
ICONE 2016; V001T01A006https://doi.org/10.1115/ICONE24-60293
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Nuclear power stations , Power stations , Safety
Benchmark Accelerated Aging of Harvested Hypalon/EPR and CSPE/XLPE Power and I&C Cable in Nuclear Power Plants
Robert C. Duckworth, Emily Frame, Leonard S. Fifield, Samuel W. Glass, III
ICONE 2016; V001T01A007https://doi.org/10.1115/ICONE24-60311
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cables , Nuclear power stations , Insulation , Light water reactors , Mechanical properties , Radiation (Physics) , Temperature , Amperes , Climate , Ethylene-propylene rubber
In-Plant 3D Positioning System Using Point Cloud Data for Remote Decontamination Machine
Yoshinori Satoh, Tetsuro Aikawa, Yuji Kawaguchi, Naoya Sakamoto, Masahiro Saito, Masayuki Kaneda, Hitoshi Sakai
ICONE 2016; V001T01A008https://doi.org/10.1115/ICONE24-60551
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Decontamination , Machinery , Structures , Fukushima nuclear disaster, Japan, 2011 , Nuclear power stations , Nuclear decommissioning , Radiation (Physics) , Surveillance equipment
The Application of an Integrated Head Assembly for Advanced Power Reactor 1400
Tae Kyo Kang, Won Ho Jo, Yeon Ho Cho, Sang Gyoon Chang, Dae Hee Lee
ICONE 2016; V001T01A009https://doi.org/10.1115/ICONE24-60860
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Manufacturing , Design , Cables , Nuclear power stations , Reactor vessels , China , Containment buildings , Cooling , Ducts , Fans
Non-Invasive On-Line Monitoring for Nuclear Power Plants Using Guided Waves Propagating in Steel Pipes With Different Types of Structural Complexity
Francesco Bertoncini, Mauro Cappelli, Francesco Cordella, Marco Raugi
ICONE 2016; V001T01A010https://doi.org/10.1115/ICONE24-60885
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Nuclear power stations , Pipes , Steel , Waves , Failure , In-service inspection , Inspection , Life extension , Radiation (Physics) , Robustness
Use of FEA Software in Evaluating Pump Vibration and Potential Remedial Actions to Abate Resonance in Industrial Vertical Pump/Motor Combinations
Michael Tompkins, Robert Stakenborghs, Gregory Kramer
ICONE 2016; V001T01A011https://doi.org/10.1115/ICONE24-60890
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computer software , Engines , Finite element analysis , Motors , Pumps , Resonance , Vibration , Screws , Electric motors , Generators
Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression
Chunzhen Yang, Jingquan Liu, Yuyun Zeng, Muhammad Saeed
ICONE 2016; V001T01A012https://doi.org/10.1115/ICONE24-61114
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Support vector machines , Uncertainty , Modeling , Nuclear power stations , Algorithms , Carbon steel , In-service inspection , Maintenance , Pipes , Sampling methods

Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory

A Numerical Solution to the Point Kinetic Equations Using Diagonally Implicit Runge Kutta Method
Zhizhu Zhang, Yun Cai
ICONE 2016; V001T02A001https://doi.org/10.1115/ICONE24-60011
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computation , Differential equations , Runge-Kutta methods , Stiffness
Electron Beam Weldability of AA6061-T6 Aluminum Straps for U-Mo Follower Fuel Assembly Manufacturing
Soo-sung Kim, Yong-jin Jeong, Jong-man Park, Yoon-sang Lee, Chong-tak Lee
ICONE 2016; V001T02A002https://doi.org/10.1115/ICONE24-60041
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Aluminum , Cathode ray oscilloscopes , Electron beams , Fuels , Manufacturing , Exploding wires , Die cutting , Fillers (Materials) , Shearing (Deformation) , Welding
Comparative Study of Coated Particle Stresses With Different Coating Layer Performance
Rong Li, Bing Liu, Chunhe Tang
ICONE 2016; V001T02A003https://doi.org/10.1115/ICONE24-60046
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Coating processes , Coatings , Particulate matter , Stress , Fuels , Creep , Design , Irradiation (Radiation exposure) , Pressure , Shrinkage (Materials)
Preliminary Investigation of Physical Characteristics in a New Power Ramp Test Irradiation Rig
Liang Zhang, Liqing Qiu, Mingyan Tong
ICONE 2016; V001T02A004https://doi.org/10.1115/ICONE24-60052
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Irradiation (Radiation exposure) , Fuel rods , Fuels , Neutrons , Pressure , Computational methods , Curve fitting , Density , Heat , Neutron flux
Lattice Boltzmann Method for Solving Time-Dependent Radiation Transport and Reactor Criticality Problems
A. Gairola, Hitesh Bindra, Gaurav Agarwal, Suneet Singh
ICONE 2016; V001T02A005https://doi.org/10.1115/ICONE24-60058
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Lattice Boltzmann methods , Radiation (Physics) , Neutrons , Electromagnetic scattering , Radiation scattering , Scattering (Physics) , Dynamics (Mechanics)
Orientation Relationships of Delta Hydrides in Zirconium and Zircaloy-4
Anton Pshenichnikov, Juri Stuckert
ICONE 2016; V001T02A006https://doi.org/10.1115/ICONE24-60061
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Zirconium , Diffraction , Electron backscatter diffraction , Electrons , Grain boundaries , Spectra (Spectroscopy)
Improvement on the Manufacture of UO2 Pellet
Hao Fu
ICONE 2016; V001T02A007https://doi.org/10.1115/ICONE24-60089
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cavities , Density , Grinding , Manufacturing , Manufacturing technology , Pressure
Numerical Simulation of Different Sizes Missing Pellet Surface Effects on Thermal-Mechanical Behaviors in Nuclear Fuel Rods
Changbing Tang, Yongjun Jiao, Wenjie Li, Tao Qing, Yifei Miao, Ping Chen
ICONE 2016; V001T02A008https://doi.org/10.1115/ICONE24-60116
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computer simulation , Fuel rods , Cladding systems (Building) , Irradiation (Radiation exposure) , Nuclear fission , Stress , Creep , Temperature , Compressive stress , Failure
Effects of Cladding Material on Irradiation Performance of Monolithic Mini-Plates
Hakan Ozaltun
ICONE 2016; V001T02A009https://doi.org/10.1115/ICONE24-60120
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cladding systems (Building) , Irradiation (Radiation exposure) , Plates (structures) , Fuels , Stress , Aluminum , Alloys , Density , Diffusion (Physics) , Displacement
Oxygen Used as an Oxidizer in Acid In-Situ Leach Uranium: From Theory to Practice
Wensheng Liao, Yahui Tan, Limin Wang, Jianhua Li
ICONE 2016; V001T02A010https://doi.org/10.1115/ICONE24-60126
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Oxygen , Uranium , Pressure , Aluminum , Minerals , Precipitation , Hydrogen , Iron , Testing
The Preliminary Performance Study of ATF With M3 Fuel and Zr-4 Cladding
Yin Chunyu, Tu Teng, Changbing Tang, Yongjun Jiao
ICONE 2016; V001T02A011https://doi.org/10.1115/ICONE24-60150
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cladding systems (Building) , Fuels , Zirconium , Accidents , Carbon , Coating processes , Coatings , Design , Failure , Failure mechanisms
A Proposed Model to Describe the Relationship Between Online Burnup Assay and Economy and Safety of Pebble Bed Reactor
Yushi Tang, Liguo Zhang, Quiju Guo, Jianzhu Cao, Jiejuan Tong
ICONE 2016; V001T02A012https://doi.org/10.1115/ICONE24-60175
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Economics , Safety , Fuels , Gas cooled reactors , Irradiation (Radiation exposure) , Probability , Reliability
Neutron Up-Scattering Effect in Refined Energy Group Structure
Qingming He, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Tiejun Zu
ICONE 2016; V001T02A013https://doi.org/10.1115/ICONE24-60313
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Electromagnetic scattering , Neutrons , Radiation scattering , Scattering (Physics) , S-matrix theory , Absorption , Cladding systems (Building) , Cross section (Physics) , Fuels , Resonance
Development of Plenum Temperature Model for Accident Analysis
Wenjie Li, Yongjun Jiao, Bingde Chen
ICONE 2016; V001T02A014https://doi.org/10.1115/ICONE24-60330
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Accidents , Temperature , Fuels , Heat transfer , Light water reactors , Computer software , Design , Fuel rods , Pressure , Resolution (Optics)
The Generation of Few-Group Constants for Fast Reactor Analysis
Xianan Du, Liangzhi Cao, Youqi Zheng
ICONE 2016; V001T02A015https://doi.org/10.1115/ICONE24-60331
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fast neutron reactors , Collapse , Anisotropy , Cross section (Physics) , Electromagnetic scattering , Neutrons , Radiation scattering , Scattering (Physics) , Spectra (Spectroscopy)
Measurements of Fine Structures in the Lead-Bismuth Eutectic Alloy Melts by Differential Scanning Calorimetry
Changqing Ye, Qiulin Li, Ping Wu, Guoyi Tang, Wei Liu
ICONE 2016; V001T02A016https://doi.org/10.1115/ICONE24-60338
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Differential scanning calorimetry , Eutectic alloys , Alloys , Signals , Embrittlement , Melting point , Steel , Temperature , Generation IV reactors , Melting
Development and Application of the 3-D Core Fuel Management Transport Program for HFETR
Lei Zhu, Shouhua Sun, Taozhong Xu
ICONE 2016; V001T02A017https://doi.org/10.1115/ICONE24-60365
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuel management , Computational methods , Approximation , Errors , Geometry , Manufacturing , Neutron flux , Pressurized water reactors , Simulation
Transient Physics Procedure and Preliminary Characteristics Analysis of Aqueous Homogeneous Reactor
Liangzi Wang, Yanqin Wei, Hongzhi Xiang, Xiangyang Li
ICONE 2016; V001T02A018https://doi.org/10.1115/ICONE24-60372
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Physics , Transients (Dynamics) , Fuels , Approximation , Biomedicine , Bubbles , Design , Feedback , Geometry , Isotopes
Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation
Yong Liu, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Qingming He
ICONE 2016; V001T02A019https://doi.org/10.1115/ICONE24-60401
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Eigenvalues , Physics , Resonance , Uncertainty analysis , Boiling water reactors , Computational methods , Cross section (Physics) , Light water reactors , Nuclear fission , Nuclides
MOCUM Code Verification and Sensibility Study Using C5G7 Benchmark
Xue Yang, Rajan Borse, Nader Satvat
ICONE 2016; V001T02A020https://doi.org/10.1115/ICONE24-60443
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Errors , Geometry , Manufacturing , Neutron flux , Screw threads , Simulation , Thread
Analysis and Prospect of the Duplex Fuel Pellets of LOWI Type for Water-Cooled Reactors
Songyang Li, Dingqu Wang, Wenli Guo, Yueyuan Jiang
ICONE 2016; V001T02A021https://doi.org/10.1115/ICONE24-60505
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels , Water , Design , Manufacturing , Nuclear fuels , Power density , Temperature , Annulus , Cutting , Geometry
Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel
Yangbin Deng, Dalin Zhang, Qing Lu, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G. H. Su
ICONE 2016; V001T02A022https://doi.org/10.1115/ICONE24-60583
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computer simulation , Fuels , Cladding systems (Building) , Plates (structures) , Power density , Computational fluid dynamics , Damage , Deformation , Delays , Fuel rods
Activation Analysis of the Reactor Pressure Vessel of HTR-PM Reactor Using FLUKA Code
Sheng Fang, Wenqian Li, Sida Sun, Hong Li
ICONE 2016; V001T02A023https://doi.org/10.1115/ICONE24-60627
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Activation analysis , Reactor vessels , Maintenance , High temperature , Irradiation (Radiation exposure) , Metals , Nuclides , Radiation sources , Radioisotopes
Preliminary Benchmark Validation of a Lattice Physics Code COSLATC
Tongrui Yang, Zhanquan Liu, Yuhang Yan, Shuo Li, Hui Yu, Yixue Chen
ICONE 2016; V001T02A024https://doi.org/10.1115/ICONE24-60659
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Physics , Fuels , Pressurized water reactors , Cores (Molding materials) , Design , Engines , Manufacturing , Nuclear engineering , Nuclear power , Software development
The Powerful MOC Module in Advanced Neutronics Lattice Code GALAXY
Xiaoming Chai, Xiaolan Tu, Wei Lu
ICONE 2016; V001T02A025https://doi.org/10.1115/ICONE24-60661
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Boundary-value problems , China , Computation , Geometry , Neutrons , Nuclear power , Shapes , Trajectories (Physics)
Effect of Cooling Rates on Mechanical Behavior of U-10Mo Monolithic Mini-Plate
Hee Seok Roh, Walid Mohamed
ICONE 2016; V001T02A026https://doi.org/10.1115/ICONE24-60747
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cooling , Mechanical behavior , Coolants , Stress , Heat transfer coefficients , Cladding systems (Building) , Finite element analysis , Flow (Dynamics) , Fuels , Numerical analysis
Characterizing the United States Nuclear Used Fuel Inventory Using the Cyclus Fuel Cycle Simulator
Cem Bagdatlioglu, Robert Flanagan, Erich Schneider
ICONE 2016; V001T02A027https://doi.org/10.1115/ICONE24-61031
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels , Nuclear fuel cycle , Simulation , Computer software , Modeling , Nuclear reactors , Uranium
The Influence of Microstructures on the Thermal Conductivity of Polycrystalline UO2
Enze Jin, Chen Liu, Heming He
ICONE 2016; V001T02A028https://doi.org/10.1115/ICONE24-61093
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Thermal conductivity , Grain size , Design , Finite element methods , Fuels , Irradiation (Radiation exposure) , Porosity
Hydraulic Balance Characteristics of an Innovative Bottom Nozzle Design With Angled Trailing Edge
Wenchi Yu
ICONE 2016; V001T02A029https://doi.org/10.1115/ICONE24-61130
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Nozzles , Flow (Dynamics) , Pressure drop , Computational fluid dynamics , Nuclear fuels
A Three-Dimensional Flux Expansion Nodal Method for Hexagonal Geometry Application
Yun Cai, Xingjie Peng, Qing Li, Kan Wang, Wei Sun, Zhaohu Gong
ICONE 2016; V001T02A030https://doi.org/10.1115/ICONE24-61135
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Geometry , Currents , Diffusion (Physics) , Eigenvalues , Flux (Metallurgy) , Neutrons , Polynomials

Plant Systems, Structures, Components and Materials

Creep Assessment of Large Size High Temperature Components Using Small Creep Test Specimens
Balhassn S. M. Ali
ICONE 2016; V001T03A001https://doi.org/10.1115/ICONE24-60010
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Creep , High temperature , Stress , Temperature , Damage , Design , Failure , High temperature materials , Nuclear power stations , Pipes
The Application of PSHA Method in the Determination of Beyond Design Basis Earthquake for New NPP Design
Ziduan Shang, Xiao Huang, Meng Chu, Lutong Zhang, Chunhua Wu
ICONE 2016; V001T03A002https://doi.org/10.1115/ICONE24-60043
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Earthquakes , Nuclear power stations , Economics , Engineering design , Engineering design processes , Modeling , Nuclear engineering , Regulations , Safety
Design of the Spent Fuel Storage Well of HTR-PM
Jinhua Wang, Bing Wang, Bin Wu, Yue Li
ICONE 2016; V001T03A003https://doi.org/10.1115/ICONE24-60051
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Spent fuel storage , Spent nuclear fuels , Storage , Fuels , Safety , Wells , Heat , Accidents , High temperature
Thermodynamic Performance Analysis of Megawatts Portable Nuclear Power System Based on Regenerative Brayton Cycle
Ersheng You, Lei Shi
ICONE 2016; V001T03A004https://doi.org/10.1115/ICONE24-60081
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Brayton cycle , Nuclear power , Compression , Temperature , Cycles , Design , Compressors , Fuels , Heat , Matlab
Structural Integrity Research for Reactor Pressure Vessel Under In-Vessel Retention of a Core Melt
Yongjian Gao, Yinbiao He, Ming Cao, Yuebing Li, Shiyi Bao, Zengliang Gao
ICONE 2016; V001T03A005https://doi.org/10.1115/ICONE24-60092
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Reactor vessels , Vessels , Finite element analysis , Creep , Materials properties , Nuclear power stations , Pressure , Accidents , Leakage , Load bearing capacity
New Structure Design for SCWR Internal Components
Qin Zhou, Yu Song, Xiaoxin Wang, Xiaotian Li
ICONE 2016; V001T03A006https://doi.org/10.1115/ICONE24-60111
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Supercritical water reactors , Irradiation (Radiation exposure) , Temperature , Thermal stresses , Damage , Finite element analysis , Mechanical properties , Nuclear reactor coolants , Pipes
Nuclear Systems for a Low Carbon Electrical Grid
Nima Fathi, Patrick McDaniel, Charles Forsberg, Cassiano de Oliveira
ICONE 2016; V001T03A007https://doi.org/10.1115/ICONE24-60128
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Carbon , Power grids , Hydrogen , Co-firing , Combined cycles , Electric power generation , Gas turbines , Nuclear power stations , Renewable energy , Storage
The Method of Specific Heat Capacity Measurement for Irradiated Zr-4 Alloy Capsule Material
Liang Chen, Hua Pang, Xiaoming Song, Lili Liu, Wenjie Li, Changbing Tang
ICONE 2016; V001T03A008https://doi.org/10.1115/ICONE24-60141
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Specific heat , Zirconium , China , Computer software , Differential scanning calorimetry , Temperature , Vents
Proposal for Evaluation With Strain-Based Criterion of Impact Phenomena Between Steel Structure and Tornado Missile
Yuko Sakamoto, Koji Shirai, Toshiko Udagawa, Shunsuke Kondo
ICONE 2016; V001T03A009https://doi.org/10.1115/ICONE24-60171
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Missiles , Steel , Japan Society of Mechanical Engineers , Pressurized water reactors , Accidents , Carbon steel , Containment , Deformation , Fracture (Materials) , Fracture (Process)
Research on Tensile Properties of Ni-Base Super Alloy GH3128
Xi Zhao, Yu Zhou, Kun Yuan
ICONE 2016; V001T03A010https://doi.org/10.1115/ICONE24-60174
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Tensile strength , Fracture (Materials) , Fracture (Process) , Plasticity , Temperature , Tension , Very high temperature reactors , Ductile fracture , Heat exchangers
Moisture Separation for Nuclear Turbine Plant Efficiency and Reliability Improvement
Ryota Takahashi, Issaku Fujita, Taichi Nakamura, Jiro Kasahara, Taichi Yoshii, Naoki Inoue, Keigo Nishida
ICONE 2016; V001T03A011https://doi.org/10.1115/ICONE24-60216
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Reliability , Separation (Technology) , Turbines , Molten salt reactors , Light water reactors , Cycles , Rankine cycle , Steam , Pressure , Computational fluid dynamics
AP1000® Submergence Testing of Service Level I Protective Coatings
Matthew R. Beenken, Christina L. Rocco, Timothy S. Andreychek
ICONE 2016; V001T03A012https://doi.org/10.1115/ICONE24-60228
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Protective coatings , Testing , Coatings , Containment , Temperature , Accidents , Coolants , Design , Fluids , Pressure
Fault Diagnosis of Feedwater Pump in Nuclear Power Plants Using Parameter-Optimized Support Vector Machine
Rui Yu, Xianling Li, Mo Tao, Zhiwu Ke
ICONE 2016; V001T03A013https://doi.org/10.1115/ICONE24-60334
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fault diagnosis , Feedwater , Nuclear power stations , Pumps , Support vector machines , Circuits , Condition monitoring , Signals , Vibration
Effect of Bolt Clamping Force and Constraint Arrangement on Structural Strength of Bolted Joint
Jianfeng Mao, Shiyi Bao, Luo Lijia, Zengliang Gao
ICONE 2016; V001T03A014https://doi.org/10.1115/ICONE24-60409
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Bolted joints , Computer simulation , Deformation , Finite element methods , Plates (structures) , Failure mechanisms , Friction , Hardware , Shear stress , Simulation
First-Principles Study of Atomic Hydrogen and Oxygen Adsorption on Doped-Iron Nanoclusters
Nishith K. Das, T. Shoji
ICONE 2016; V001T03A015https://doi.org/10.1115/ICONE24-60516
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Hydrogen , Iron , Oxygen , Zirconium , Metals , Atoms , Alloys , Clusters (Chemistry) , Density functional theory , Electron configuration
Establishing a Construction Method of an Automatic Fire Suppression System for Cable Tray Fires
Koji Shirai, Mikimasa Iwata, Yutaka Goda, Tsukasa Miyagi
ICONE 2016; V001T03A016https://doi.org/10.1115/ICONE24-60599
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cables , Construction , Fire , Bubbles , Circuit breakers , Circuits , Cooling , Countermeasures , Electricity (Physics) , Failure
Numerical Simulation of Fretting Wear of Heat-Transfer Tubes in Steam Generator Under Random Excitation Forces
Lichen Tang, Hao Qian, Yongcheng Xie, Yi Jing, Yongzhong Huo
ICONE 2016; V001T03A017https://doi.org/10.1115/ICONE24-60630
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Boilers , Computer simulation , Heat transfer , Random excitation , Wear , Displacement , Finite element methods , Finite element model , Fluids , Friction
3D Linear Bifurcation Analysis of Steel Containment Vessel
Jay Schmidt, Bernd Laskewitz
ICONE 2016; V001T03A018https://doi.org/10.1115/ICONE24-60673
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Bifurcation , Containment vessels , Steel , Shells , Stability , Buckling , Containment , Stress , ASME Boiler and Pressure Vessel Code , ASME Standards
Seismic Qualification of Equipment: A PRA-Consistent Framework
Payel Chatterjee, Abhinav Gupta
ICONE 2016; V001T03A019https://doi.org/10.1115/ICONE24-60674
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Damage , Earthquakes , Excitation , Failure , Nuclear power stations , Probabilistic risk assessment , Spectra (Spectroscopy) , Spectral sensitivity , Testing
Study on Differences in Floor Response Spectra due to the Seismic Input Approach
Jana Sue Bochert, Henry Schau, Timo Schmitt
ICONE 2016; V001T03A020https://doi.org/10.1115/ICONE24-60703
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Spectra (Spectroscopy) , Soil , Wave propagation , Rocks
Effect of Soil Structure Interaction on the Seismic Fragility of a Nuclear Reactor Building
Samer El-Bahey, Yasser Alzeni
ICONE 2016; V001T03A021https://doi.org/10.1115/ICONE24-60714
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Nuclear reactors , Soil , Safety , Earthquake risk , Earthquakes , Damage , Design , Nuclear power stations , Accounting , Chaos
Fracture Resistance of Cast Austenitic Stainless Steels
Y. Chen, W-Y. Chen, A. S. Rao, Z. Li, Y. Yang, B. Alexandreanu, K. Natesan
ICONE 2016; V001T03A022https://doi.org/10.1115/ICONE24-60736
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fracture (Materials) , Stainless steel , Neutrons , Irradiation (Radiation exposure) , Ferrites (Magnetic materials) , Fracture toughness , Alloys , Embrittlement , Light water reactors , Corrosion resistance
Vortexing and Air Withdrawal Evaluations for Storage Tanks Using Physical Hydraulic Model Studies
Amie Humphrey Facendola, Ludwig Haber, Andrew Johansson
ICONE 2016; V001T03A023https://doi.org/10.1115/ICONE24-60768
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Storage tanks , Flow (Dynamics) , Pumps , Water , Density , Design , Emergencies , Engineers , Fluids , Nozzles
Corrosion of 9% Cr Ferritic/Martensitic Steels in Flowing Pb-Bi Eutectic With 10−7 Mass% Dissolved Oxygen at 450 and 550 °C
Valentyn Tsisar, Carsten Schroer, Olaf Wedemeyer, Aleksandr Skrypnik, Jürgen Konys
ICONE 2016; V001T03A024https://doi.org/10.1115/ICONE24-60826
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Corrosion , Martensitic steel , Oxygen , Steel , Oxidation , Metals
Corrosion in Steel T91 Caused by Flowing Lead–Bismuth Eutectic at 400°C and 10−7 Mass% Solved Oxygen
Carsten Schroer, Valentyn Tsisar, Olaf Wedemeyer, Aleksandr Skrypnik, Jürgen Konys
ICONE 2016; V001T03A025https://doi.org/10.1115/ICONE24-60845
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Corrosion , Oxygen , Steel , Cross section (Physics) , Flow (Dynamics) , Martensitic steel , Oxidation
Numerical Simulation of the Head of the Direct Action Solenoid Valve Under the High Temperature Condition
Qianfeng Liu, FuLong Zhao, Hanliang Bo
ICONE 2016; V001T03A026https://doi.org/10.1115/ICONE24-60854
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computer simulation , High temperature , Solenoids , Valves , Temperature , Hydraulic control , Hydraulic drive systems , Intellectual property , Patents
Radiation-Induced Electrolytic Corrosion of LWRS: (Part 1) — Basic Mechanism and Implications in Degradation Phenomena
Genn Saji
ICONE 2016; V001T03A027https://doi.org/10.1115/ICONE24-60894
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Electrolytic corrosion , Light water reactors , Radiation (Physics) , Water , Boiling water reactors , Pressurized water reactors , Water chemistry , Flow (Dynamics) , Reactive-ion etching , Corrosion
Radiation-Induced Electrolytic Corrosion of LWRS: (Part 2) — Verification of In- and Out-Core Redox Potential Differences
Genn Saji
ICONE 2016; V001T03A028https://doi.org/10.1115/ICONE24-60895
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Electrolytic corrosion , Light water reactors , Radiation (Physics) , Water , Boiling water reactors , Equilibrium (Physics) , Fittings , Pressurized water reactors , Reactive-ion etching , Water chemistry
Design of SC Walls and Connections in Nuclear Facilities
Amit H. Varma, Saahastaranshu R. Bhardwaj, Sanjeev R. Malushte
ICONE 2016; V001T03A029https://doi.org/10.1115/ICONE24-60962
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Nuclear power stations , Steel , Failure , Quality control , Shear (Mechanics) , Stress , Wall panels , Accidents , Buckling
Design of Heat-Pipe Heat Exchanger (HPHE) for a Coal-to-Liquid Fuel Process Using Nuclear Energy
Mubenga Carl Tshamala, Robert T. Dobson
ICONE 2016; V001T03A030https://doi.org/10.1115/ICONE24-60994
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Coal , Design , Fuels , Heat exchangers , Heat pipes , Nuclear power , Heat , Boilers , Renewable energy , Steam
Design of the Process and Effluent Radiation Monitoring System of HTR-PM
Feng Xie, Wenqian Li, Zhihui Li, Jianzhu Cao, Hong Li, Jiejuan Tong, Haitao Wang
ICONE 2016; V001T03A031https://doi.org/10.1115/ICONE24-61008
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Radiation measurement , Pressurized water reactors , Very high temperature reactors , Carbon , Coolants , Dust , Fuels , Helium , Nuclear fission
Integrity Assessment of Mechanical Components Subjected to Mixed Mode Cracking
Lingfu Zeng, Chouping Luo, Lennart G. Jansson
ICONE 2016; V001T03A032https://doi.org/10.1115/ICONE24-61097
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fracture (Process) , Fracture (Materials) , Pipes , Failure , Finite element analysis , Metals , Nuclear power , Stress , Tension
A Study of Axial Compression in the ASME B&PV Code for Pipe Supports and Restraints
Phillip E. Wiseman, Zara Z. Hoch
ICONE 2016; V001T03A033https://doi.org/10.1115/ICONE24-61101
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Compression , Pipes , Stress , ASME Boiler and Pressure Vessel Code , Buckling , Design , ASME Standards , Elastic analysis , Mechanical engineers , Stability
HIPed Hard Facings for Nuclear Applications: Materials, Key Potential Defects and Mitigating Quality Control Measures
John Sulley, David Stewart
ICONE 2016; V001T03A034https://doi.org/10.1115/ICONE24-61106
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Foundry coatings , Quality control , Hardening , Wear , Erosion , Stress , Cobalt , Contamination , Corrosion resistance , Crack propagation
A Parametric Study for the Seismic Response Analysis of a Nuclear Reactor Building by Using a Three-Dimensional Finite Element Model
Byunghyun Choi, Akemi Nishida, Norihiro Nakajima
ICONE 2016; V001T03A035https://doi.org/10.1115/ICONE24-61128
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Finite element model , Nuclear reactors , Earthquakes , Industrial research , Uncertainty , High temperature , Nuclear power , Nuclear power stations , Scientific computing , Simulation
Environmentally Assisted Cracking Susceptibility Assessment of AP1000® RCP Flywheel Retainer Ring A 289 18Cr-18Mn Steel Material Through Slow Strain Rate Testing Under Simulated Primary Water Environment
Gutti V. Rao
ICONE 2016; V001T03A036https://doi.org/10.1115/ICONE24-61139
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Flywheels , Fracture (Process) , Steel , Testing , Water , Design , Lithium , Alloys , Boron , Coolants
Predictive Methods in the Assessment of Alloy 600 PWSCC Failures in Operating Pressurized Water Reactors
Gutti V. Rao
ICONE 2016; V001T03A037https://doi.org/10.1115/ICONE24-61141
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Failure , Pressurized water reactors , Manufacturing , Base metals , Grain size , Indium alloys , Residual stresses , Stress , Temperature
On Experimental Simulation of Passive Evaporation-and-Condensation Systems of Reactor Thermal Shielding
Alexander N. Gershuni, Alexander P. Nishchik, Evgeviy N. Pis’mennyi, Victor G. Razumovskiy, Igor L. Pioro
ICONE 2016; V001T03A038https://doi.org/10.1115/ICONE24-61159
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Condensation , Evaporation , Heat shielding , Simulation , Heat , Cooling , Heat pipes , Reliability , Safety , Vapors

I&C, Digital Controls, and Influence of Human Factors

Real-Time State Identification of Boiling Water Reactors Using Relevance Vector Machines
Miltiadis Alamaniotis, Mauro Cappelli
ICONE 2016; V001T04A001https://doi.org/10.1115/ICONE24-60048
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Boiling water reactors , Machinery , Signals , Sensors
FLEX Loss of Instrumentation Guidance for PWRs Enhances Severe Accident Diagnostics
Robert J. Lutz, Jr., James Lynde, Steven Pierson
ICONE 2016; V001T04A002https://doi.org/10.1115/ICONE24-60055
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Accidents , Instrumentation , Pressurized water reactors , Design , Cooling , Containment , Spent nuclear fuels , Accident management , Alternating current (Electricity) , Damage
Design of Control Systems for Accelerator Driven Sub-Critical System
Zhiyong He, Wenjuan Cui, Qiang Zhao, Yichuan He, Yuxi Luo
ICONE 2016; V001T04A003https://doi.org/10.1115/ICONE24-60075
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Control systems , Design , Redundancy (Engineering) , Neutrons , Reliability , Spallation (Nuclear physics) , Conceptual design , Cooling , Machinery , Nuclear power stations
Electronics for Instrumentation and Controls in Accelerator Driven Sub-Critical System
Wenjuan Cui, Zhiyong He, Qiang Zhao, Yichuan He, Yuxi Luo
ICONE 2016; V001T04A004https://doi.org/10.1115/ICONE24-60082
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Electronics , Instrumentation , Neutrons , Redundancy (Engineering) , Reliability , Errors , Heavy metals , Nuclear industry , Protons , Radiation damage
A Study About Safety I&C System Software V&V in Nuclear Power Plant
Pengfei Gu, Shengchao Wang, Weihua Chen, Suyuan Yu
ICONE 2016; V001T04A005https://doi.org/10.1115/ICONE24-60125
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computer software , Nuclear power stations , Safety , China , Design , Instrumentation , Maintenance , Pressurized water reactors , Software development , Software verification
Parameter Optimization for AP1000 Steam Generator Feedwater Control System Using Particle Swarm Optimization Algorithm
Shifa Wu, Pengfei Wang, Jiashuang Wan, Xinyu Wei, Fuyu Zhao
ICONE 2016; V001T04A006https://doi.org/10.1115/ICONE24-60148
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Algorithms , Boilers , Control systems , Feedwater , Optimization , Particle swarm optimization , Nuclear power stations , Simulation , Water , Control equipment
Water Level Control for Steam Generator in Nuclear Power Based on Port-Controlled Hamiltonian Method
Mo Tao, Rui Yu, Xianling Li, Zhiwu Ke, Zhenxing Zhao, Qi Xiao
ICONE 2016; V001T04A007https://doi.org/10.1115/ICONE24-60274
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Boilers , Nuclear power , Water , Control modeling , Control equipment , Control systems , Energy dissipation , Equilibrium (Physics) , Modeling , Process control
Control Policy for Shared Objects in HTR-PM: Toward the Collision and Deadlock Avoidance
Shuqiao Zhou, Xiaojin Huang, Jia Qianqian
ICONE 2016; V001T04A008https://doi.org/10.1115/ICONE24-60406
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Collisions (Physics) , Design , Nuclear power stations , Turbines , Very high temperature reactors , Control systems , Delays , Fuels , Steam turbines
Reliability Analysis and Availability Enhancements for Redundant Systems With Reparable Components
Shuqiao Zhou, Duo Li, Chao Guo
ICONE 2016; V001T04A009https://doi.org/10.1115/ICONE24-60408
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Chain , China , Construction , Control systems , Event history analysis , Maintenance , Nuclear power stations , Redundancy (Engineering) , Very high temperature reactors
Program of Human-Machine Interface Verification and Validation of HTR-PM in China
Jia Qianqian, Chao Guo, Qu Ronghong, Zhang Liangju
ICONE 2016; V001T04A010https://doi.org/10.1115/ICONE24-60483
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: China , Construction , Design , Gas cooled reactors , High temperature , Machinery , Steam , Steam turbines
Testing and Reliability Modelling of Safety Software for Digital Reactor Protection System of HTR-PM
Chao Guo, Huasheng Xiong, Duo Li, Shuqiao Zhou
ICONE 2016; V001T04A011https://doi.org/10.1115/ICONE24-60535
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computer software , Modeling , Reactor protection systems , Reliability , Safety , Testing , Nuclear power stations , Event history analysis , China , Data mining
Assessment on an Intelligent Controller of Marine Condenser
Gong Xian, Sun Jianhua, Zou Hai
ICONE 2016; V001T04A012https://doi.org/10.1115/ICONE24-60657
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Condensers (steam plant) , Intelligent control systems , Water , Cooling , Steam , Vacuum , Supercooling , Condensed matter , Control systems , Temperature
A Novel Feature Extraction Scheme for NPP Initiating Event Identification
Ting-Han Lin, Shun-Chi Wu, Hwai-Pwu Chou
ICONE 2016; V001T04A013https://doi.org/10.1115/ICONE24-60672
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Feature extraction , Nuclear power stations , Sensors
Intelligent Plant Configuration Management Using Wireless Sensors
Vivek Agarwal, John W. Buttles, Lawrence Beaty, Joseph Naser
ICONE 2016; V001T04A014https://doi.org/10.1115/ICONE24-60815
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Sensors , Nuclear power stations , Safety , Engineering prototypes , Errors , Hazards , Radiation (Physics) , Surveillance , Construction , Control systems
Video Monitoring System Availability in Radiation Accident Condition
Shou-long Xu, Shu-liang Zou
ICONE 2016; V001T04A015https://doi.org/10.1115/ICONE24-60848
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Accidents , Monitoring systems , Radiation (Physics) , Sensors , Complementary metal oxide semiconductors , Integrated circuits , Ionizing radiation , Noise (Sound) , Signal processing , Brightness (Photometry)
Overview on the Standard Requirements for the Separation Measures and Practical Implementation in the I&C Design: Return of Experience
Antonio Ciriello, Stefan Kümmerling, Johannes Pickelmann
ICONE 2016; V001T04A016https://doi.org/10.1115/ICONE24-60879
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Separation (Technology) , Instrumentation , Nuclear power stations , Safety
Approach for the Evaluation of the Impact of Potential Software Failures in Software-Based Instrumentation and Control (I&C) Equipment in Nuclear Power Plants
Hervé Mbonjo, Manuela Jopen, Birte Ulrich, Dagmar Sommer
ICONE 2016; V001T04A017https://doi.org/10.1115/ICONE24-60897
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computer software , Failure , Instrumentation , Nuclear power stations , Failure mechanisms , Safety , Failure mode and effects analysis
Development and Testing of Fault-Diagnosis Algorithms for Reactor Plant Systems
Austin L. Grelle, Young S. Park, Richard B. Vilim
ICONE 2016; V001T04A018https://doi.org/10.1115/ICONE24-61024
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Algorithms , Fault diagnosis , Testing , Sensors , Computer software , Pressurized water reactors , Chain , Collaboration , Computer simulation , Control systems
Predictive Modeling of Acoustic Signals From Thermoacoustic Power Sensors (TAPS)
Christopher M. Dumm, Jeffrey S. Vipperman, Jorge V. Carvajal, Melissa M. Walter, Luke Czerniak, Amy S. Ruane, Paolo Ferroni, Michael D. Heibel
ICONE 2016; V001T04A019https://doi.org/10.1115/ICONE24-61034
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Acoustics , Modeling , Sensors , Signals , Waves , Instrumentation , Nuclear fission , Nuclear reactors , Radiation (Physics) , Sodium
All Years

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

  • Crossref Logo
  • Crossref Open Funder Registry Logo
  • Crossref Open Cited-By Logo
  • Crossref Crossmark Logo
  • Crossref Similarity Check Logo
  • Chorus Logo
  • Counter Logo
  • Cope Logo
  • STM Logo
Copyright © 2025 The American Society of Mechanical Engineers
This Feature Is Available To Subscribers Only

or Create an Account

Close Modal
Close Modal
This site uses cookies. By continuing to use our website, you are agreeing to our privacy policy.
Accept