Volumes | International Conference on Nuclear Engineering | American Society of Mechanical Engineers Digital Collection

2016 24th International Conference on Nuclear Engineering

June 26–30, 2016

Charlotte, North Carolina, USA

Conference Sponsors:

ISBN:

978-0-7918-5001-5

In This Volume

Operations and Maintenance, Aging Management and Plant Upgrades (12)
Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory (30)
Plant Systems, Structures, Components and Materials (38)
I&C, Digital Controls, and Influence of Human Factors (19)

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; V001T01A001doi:https://doi.org/10.1115/ICONE24-60031

Abstract

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Topics: Disks , Valves , Flow (Dynamics) , Fluid-dynamic forces , Pressure , Water

ASME Operation and Maintenance (OM) Code Overview

Ronald C. Lippy

ICONE 2016; V001T01A002doi:https://doi.org/10.1115/ICONE24-60086

Abstract

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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; V001T01A003doi:https://doi.org/10.1115/ICONE24-60102

Abstract

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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; V001T01A004doi:https://doi.org/10.1115/ICONE24-60214

Abstract

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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; V001T01A005doi:https://doi.org/10.1115/ICONE24-60256

Abstract

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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; V001T01A006doi:https://doi.org/10.1115/ICONE24-60293

Abstract

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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; V001T01A007doi:https://doi.org/10.1115/ICONE24-60311

Abstract

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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; V001T01A008doi:https://doi.org/10.1115/ICONE24-60551

Abstract

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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; V001T01A009doi:https://doi.org/10.1115/ICONE24-60860

Abstract

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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; V001T01A010doi:https://doi.org/10.1115/ICONE24-60885

Abstract

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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; V001T01A011doi:https://doi.org/10.1115/ICONE24-60890

Abstract

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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; V001T01A012doi:https://doi.org/10.1115/ICONE24-61114

Abstract

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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; V001T02A001doi:https://doi.org/10.1115/ICONE24-60011

Abstract

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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; V001T02A002doi:https://doi.org/10.1115/ICONE24-60041

Abstract

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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; V001T02A003doi:https://doi.org/10.1115/ICONE24-60046

Abstract

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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; V001T02A004doi:https://doi.org/10.1115/ICONE24-60052

Abstract

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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; V001T02A005doi:https://doi.org/10.1115/ICONE24-60058

Abstract

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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; V001T02A006doi:https://doi.org/10.1115/ICONE24-60061

Abstract

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Topics: Zirconium , Diffraction , Electron backscatter diffraction , Electrons , Grain boundaries , Spectra (Spectroscopy)

Improvement on the Manufacture of UO₂ Pellet

Hao Fu

ICONE 2016; V001T02A007doi:https://doi.org/10.1115/ICONE24-60089

Abstract

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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; V001T02A008doi:https://doi.org/10.1115/ICONE24-60116

Abstract

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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; V001T02A009doi:https://doi.org/10.1115/ICONE24-60120

Abstract

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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; V001T02A010doi:https://doi.org/10.1115/ICONE24-60126

Abstract

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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; V001T02A011doi:https://doi.org/10.1115/ICONE24-60150

Abstract

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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; V001T02A012doi:https://doi.org/10.1115/ICONE24-60175

Abstract

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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; V001T02A013doi:https://doi.org/10.1115/ICONE24-60313

Abstract

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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; V001T02A014doi:https://doi.org/10.1115/ICONE24-60330

Abstract

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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; V001T02A015doi:https://doi.org/10.1115/ICONE24-60331

Abstract

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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; V001T02A016doi:https://doi.org/10.1115/ICONE24-60338

Abstract

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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; V001T02A017doi:https://doi.org/10.1115/ICONE24-60365

Abstract

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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; V001T02A018doi:https://doi.org/10.1115/ICONE24-60372

Abstract

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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; V001T02A019doi:https://doi.org/10.1115/ICONE24-60401

Abstract

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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; V001T02A020doi:https://doi.org/10.1115/ICONE24-60443

Abstract

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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; V001T02A021doi:https://doi.org/10.1115/ICONE24-60505

Abstract

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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; V001T02A022doi:https://doi.org/10.1115/ICONE24-60583

Abstract

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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; V001T02A023doi:https://doi.org/10.1115/ICONE24-60627

Abstract

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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; V001T02A024doi:https://doi.org/10.1115/ICONE24-60659

Abstract

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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; V001T02A025doi:https://doi.org/10.1115/ICONE24-60661

Abstract

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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; V001T02A026doi:https://doi.org/10.1115/ICONE24-60747

Abstract

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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; V001T02A027doi:https://doi.org/10.1115/ICONE24-61031

Abstract

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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; V001T02A028doi:https://doi.org/10.1115/ICONE24-61093

Abstract

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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; V001T02A029doi:https://doi.org/10.1115/ICONE24-61130

Abstract

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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; V001T02A030doi:https://doi.org/10.1115/ICONE24-61135

Abstract

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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; V001T03A001doi:https://doi.org/10.1115/ICONE24-60010

Abstract

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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; V001T03A002doi:https://doi.org/10.1115/ICONE24-60043

Abstract

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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; V001T03A003doi:https://doi.org/10.1115/ICONE24-60051

Abstract

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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; V001T03A004doi:https://doi.org/10.1115/ICONE24-60081

Abstract

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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; V001T03A005doi:https://doi.org/10.1115/ICONE24-60092

Abstract

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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; V001T03A006doi:https://doi.org/10.1115/ICONE24-60111

Abstract

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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; V001T03A007doi:https://doi.org/10.1115/ICONE24-60128

Abstract

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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; V001T03A008doi:https://doi.org/10.1115/ICONE24-60141

Abstract

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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; V001T03A009doi:https://doi.org/10.1115/ICONE24-60171

Abstract

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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; V001T03A010doi:https://doi.org/10.1115/ICONE24-60174

Abstract

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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; V001T03A011doi:https://doi.org/10.1115/ICONE24-60216

Abstract

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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; V001T03A012doi:https://doi.org/10.1115/ICONE24-60228

Abstract

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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; V001T03A013doi:https://doi.org/10.1115/ICONE24-60334

Abstract

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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; V001T03A014doi:https://doi.org/10.1115/ICONE24-60409

Abstract

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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; V001T03A015doi:https://doi.org/10.1115/ICONE24-60516

Abstract

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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; V001T03A016doi:https://doi.org/10.1115/ICONE24-60599

Abstract

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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; V001T03A017doi:https://doi.org/10.1115/ICONE24-60630

Abstract

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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; V001T03A018doi:https://doi.org/10.1115/ICONE24-60673

Abstract

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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; V001T03A019doi:https://doi.org/10.1115/ICONE24-60674

Abstract

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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; V001T03A020doi:https://doi.org/10.1115/ICONE24-60703

Abstract

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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; V001T03A021doi:https://doi.org/10.1115/ICONE24-60714

Abstract

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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; V001T03A022doi:https://doi.org/10.1115/ICONE24-60736

Abstract

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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; V001T03A023doi:https://doi.org/10.1115/ICONE24-60768

Abstract

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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; V001T03A024doi:https://doi.org/10.1115/ICONE24-60826

Abstract

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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; V001T03A025doi:https://doi.org/10.1115/ICONE24-60845

Abstract

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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; V001T03A026doi:https://doi.org/10.1115/ICONE24-60854

Abstract

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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; V001T03A027doi:https://doi.org/10.1115/ICONE24-60894

Abstract

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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; V001T03A028doi:https://doi.org/10.1115/ICONE24-60895

Abstract

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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; V001T03A029doi:https://doi.org/10.1115/ICONE24-60962

Abstract

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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; V001T03A030doi:https://doi.org/10.1115/ICONE24-60994

Abstract

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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; V001T03A031doi:https://doi.org/10.1115/ICONE24-61008

Abstract

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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; V001T03A032doi:https://doi.org/10.1115/ICONE24-61097

Abstract

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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; V001T03A033doi:https://doi.org/10.1115/ICONE24-61101

Abstract

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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; V001T03A034doi:https://doi.org/10.1115/ICONE24-61106

Abstract

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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; V001T03A035doi:https://doi.org/10.1115/ICONE24-61128

Abstract

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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; V001T03A036doi:https://doi.org/10.1115/ICONE24-61139

Abstract

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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; V001T03A037doi:https://doi.org/10.1115/ICONE24-61141

Abstract

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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; V001T03A038doi:https://doi.org/10.1115/ICONE24-61159

Abstract

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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; V001T04A001doi:https://doi.org/10.1115/ICONE24-60048

Abstract

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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; V001T04A002doi:https://doi.org/10.1115/ICONE24-60055

Abstract

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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; V001T04A003doi:https://doi.org/10.1115/ICONE24-60075

Abstract

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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; V001T04A004doi:https://doi.org/10.1115/ICONE24-60082

Abstract

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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; V001T04A005doi:https://doi.org/10.1115/ICONE24-60125

Abstract

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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; V001T04A006doi:https://doi.org/10.1115/ICONE24-60148

Abstract

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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; V001T04A007doi:https://doi.org/10.1115/ICONE24-60274

Abstract

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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; V001T04A008doi:https://doi.org/10.1115/ICONE24-60406

Abstract

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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; V001T04A009doi:https://doi.org/10.1115/ICONE24-60408

Abstract

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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; V001T04A010doi:https://doi.org/10.1115/ICONE24-60483

Abstract

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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; V001T04A011doi:https://doi.org/10.1115/ICONE24-60535

Abstract

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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; V001T04A012doi:https://doi.org/10.1115/ICONE24-60657

Abstract

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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; V001T04A013doi:https://doi.org/10.1115/ICONE24-60672

Abstract

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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; V001T04A014doi:https://doi.org/10.1115/ICONE24-60815

Abstract

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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; V001T04A015doi:https://doi.org/10.1115/ICONE24-60848

Abstract

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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; V001T04A016doi:https://doi.org/10.1115/ICONE24-60879

Abstract

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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; V001T04A017doi:https://doi.org/10.1115/ICONE24-60897

Abstract

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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; V001T04A018doi:https://doi.org/10.1115/ICONE24-61024

Abstract

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Topics: Algorithms , Fault diagnosis , Testing , Sensors , Computer software , Pressurized water reactors , Chain , Collaboration , Computer simulation , Control systems