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HTR2014

 

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ISBN Number

  • 978-7-89395-349-1

 

HTR2014 Documents

 

ISO File

  • Download full proceeding DVD iso file here
    ( will require software to write to DVD)

 





 

HTR2014 keynote/plenary presentations

 

Session

Speaker

Topic

Keynote Session

WANG Dazhong

HTR development in China

 J.K. Park

IAEA’s Perspectives on Global Nuclear Power

Plenary Session 1:
National and international status and progress

ZHANG Zuoyi

HTR-PM project progress

Tom O'Connor

The United States Advanced Reactor Technologies Research and Development Program

N.N. Ponomarev-Stepnoy

High-Temperature Gas-Cooled Reactors in Russia: Status and Prospects

Hans E. Schweickardt

The Future of Nuclear Power in the Light of European Energy Policy

Finis Southworth, Vincent Chauvet

The GEMINI Initiative

Kunitomi Kazuhiko

Present status of HTTR project in JAEA

Yong Wan KIM

Nuclear Hydrogen and VHTR Technology Development in Korea

Carl Sink

Generation IV Reactors: Continued Progress toward the Future

Plenary Session 2:
Safety, licensing and technology

H. Larry Brey

Initial Start-up and Testing of the Fort St. Vrain HTGR - Lessons Learned which may be Useful to the HTR-PM

Frederik Reitsma

Post Fukushima action – A perspective from the IAEA

ZHU Lixin

Guideline for HTR-PM Safety Review

 Fred Silady

Working Towards Unified Safety Design Criteria for Modular High Temperature Gas-cooled Reactor Designs

LI Fu

HTR-PM Safety requirement and Licensing experience

Norbert Kohtz

Safety Requirement for HTR Process Heat Application

Plenary Session 3:
Equipment, supply and project implementation

GONG Bing

Introduction to Progress of HTR-PM Demonstration Project

WU Yulong

EPC experiences of HTR-PM Project

DONG Yujie

Technologies of HTR-PM

ZHANG Jie

The Progress of HTR-PM Fuel Plant

WU Xinxin

The Design and Research of HTR-PM Steam Generator

XUE Song

HTR, the New Challenge and Improvement for Equipment Manufacturers

SHI Guilian

Development and Design of Digital I&C System in HTR-PM

WANG Junsan

The technical solution of full scope training simulator of HTR-PM

Plenary Session 4:
Application and market

Karl Verforndern

Nuclear Cogeneration for Industrial Applications

CUI Shaozhang

Advancing the Commercialization of HTR: The Potential Applications, Market and Challenges

N.G. Kodochigov

HTGR Application / Markets Prospects in Russia

ZHANG Wei

Nuclear Energy Development: from Safer to Inherent Safety

Yukitaka Kato

Progresses in hydrogen production and application for establishment of low-carbon society in Japan

WANG Haitao

Future Development of Modular HTGR in China after HTR-PM

 

HTR2014 paper list

TRACK 1  National Research Programs and Industrial Projects

ID

Paper Title

Paper Authors

Session

HTR2014-11108

High Temperature Reactors for a proposed IAEA Coordinated Research Project on Energy Neutral Mineral Development Processes.

Nils Haneklaus, Frederik Reitsma, Harikrishnan Tulsidas.

IAEA

1-1

HTR2014-11125

Overview and Progress of High Temperature Reactor Pebble-bed Module Demonstration Project (HTR-PM).

FU Jian, JIANG Yingxue, CHENG Hongyong, CHENG Wei.

Shidao Bay, China

 

HTR2014-11183

Nuclear power more profitable than coal if funded with low cost capital: A South-African case study.

Dawid E. Serfontein. 

North West Univ., South Africa

1-2

HTR2014-11220

HTR System Integration in Europe and South Africa.

Ferry Roelofs, J. Ruer, P. Cuadrado Garcia, J. Cetnar, D. Knoche, J. Lapins, S. Kasselman, P. Stoker, M. Fütterer. 

SAIPEM, Netherlands

1-2

HTR2014-11234

The ARCHER Project.

S. Knol, M.A. Fütterer, F. Roelofs, N. Kohtz, M. Laurie, D. Buckthorpe, W. Scheuermann. 

NRG, Netherlands

1-1

HTR2014-11309

US HTGR Deployment Challenges and Strategies.

Farshid Shahrokhi, Lewis Lommers, John Mayer, Finis Southworth. 

AREVA, USA

1-1

HTR2014-11377

Review of PSI studies on reactor physics and thermal fluid dynamics of pebble bed reactors.

Horst-Michael Prasser. 

PSI, Switzerland

1-1

HTR2014-11456

Future Development of Modular HTGR in China after HTR-PM

Zhang Zuoyi, Wang Haitao, Dong Yujie, Li Fu

INET, China

 

TRACK 2  Industrial Applications and Markets

ID

Paper Title

Paper Authors

Session

HTR2014-21104

ARCHER HTR Technology in support of a Coal to Liquid Process – An Economic Feasibility View. 

PW Stoker, JIJ Fick, F Conradie.

North-West Univ., South Africa

2-1

HTR2014-21208

Substitute Energy Carriers from Refinement of Coal using HTR-Module.

Heiko Barnert, Kurt Kugeler, Michael Will. 

ARGE KT, Austria

2-1

HTR2014-21233

JAEA's R&D on the Thermochemical Hydrogen Production IS Process.

Seiji Kasahara, Nobuyuki Tanaka, Hiroki Noguchi, Jin Iwatsuki, Hiroaki Takegami, Xing L. Yan, Shinji Kubo. 

JAEA, Japan

2-2

HTR2014-21295

Bimetallic catalysts for HI decomposition in the iodine-sulfur thermochemical cycle. 

Laijun WANG, Songzhi HU, Lufei Xu, Daocai LI, Qi HAN, Songzhe CHEN, Ping ZHANG, Jingming XU. 

INET, China

2-2

HTR2014-21320

Monitoring of the AMB rotor and electrical fault diagnosis in HTR. 

Zhao Jingjing, Sun Zhe, Yan Xunshi, Shi Zhengang. 

INET, China

2-3

HTR2014-21325

Study on in-situ electrochemical impedance spectroscopy measurement of anodic reaction in SO2 depolarized electrolysis process.

 

XUE Lulu, ZHANG Ping, CHEN Songzhe, WANG Laijun. 

INET, China

2-2

HTR2014-21327

Finite Element Analysis of the Rotor System of a Magnetically Suspended Compound Molecule Pump.

Pingfan Liu, Lei Zhao, Zhengang Shi, Guojun Yang. 

INET, China

 

HTR2014-21329

Viscosity of HI-I2-H2O solution at atmosphere pressure.

 

Songzhe Chen, Mengxue Gao, Ping Zhang, Laijun Wang, Jingming Xu. 

INET, China

2-3

HTR2014-21339

STATUS OF NUCLEAR HEAT AND HYDROGEN SYSTEMS CONCEPT STUDY.

Won Jae Lee, Yoon Ho Choi, Jae Mun Han, Jin Ki Ham, Su Jin ChoiSang Il Lee, Je Ho Park, Jae Sak Koo. 

KAERI, Korea

2-2

HTR2014-21345

SC-HTGR Performance Impact for Arid Sites.

L. Lommers, J. Geschwindt, F. Southworth, F. Shahrokhi. 

AREVA, USA

2-3

HTR2014-21359

The Future of Nuclear Power in the Light of European Energy Policy.

Hans E. Schweickardt.

Alpiq, Switzerland

plenary session

1

HTR2014-21371

For a Global HTR Marketing Initiative.

Alexandre Bredimas, Francesco Venneri, Matthew Richards. 

Strane Innovation, France

2-1

HTR2014-21416

Viability of HTR-10 As A Primary Driver of an Energy Complex for Remote Settlement.

Dr. Philip, T. Choong 

Choong-Hsia Foundation Inc., USA

2-1

HTR2014-21431

Conceptual evaluation of hybrid energy system comprising wind-biomass-nuclear plants for load balancing and for production of renewable synthetic transport fuels.

Johan Carlsson, David Shropshire, Robert S. Cherry, Arturs Purvins, Ioulia T. Papaionnoua.

JRC-ITU, Netherlands

2-1

HTR2014-21436

GTHTR300 cost reduction through design upgrade and cogeneration.

Xing L. Yan, Hiroyuki Sato, Yu Kamiji, Atsuhiko Terada, Yoshiyuki Imai, Yukio Tachibana, Kazuhiko Kunitomi. 

JAEA, Japan

2-3

HTR2014-21454

Aspects of nuclear process heat application of very high temperature reactors (VHTR).

W.T. Jansing, K. Kugeler.

Juelich, Germany

 

TRACK 3  Fuel and Waste

ID

Paper Title

Paper Authors

Session

HTR2014-30264

Comparison of fission product release predictions using PARFUME with results from the AGR-1 safety tests. 

Blaise P. Collin, David A. Petti, Paul A. Demkowicz, John T. Maki. 

INL, USA

3-7

HTR2014-31092

Preliminary Results of the Combined Third and Fourth Very High Temperature Gas-Cooled Reactor Irradiation in the Advanced Test Reactor.

Michael E. Davenport, A. Joseph Palmer, David A. Petti. 

INL, USA

3-4

HTR2014-31093

Comparative Study of Laboratory-Scale and Prototypic Production-Scale Fuel Fabrication Processes and Product Characteristics. 

Douglas W. Marshall. 

INL, USA

3-3

HTR2014-31101

Evaluation of the Mechanical Performance of Silicon Carbide in TRISO Fuel at High Temperatures.

Nadia Rohbeck, Ping Xiao.

Univ. of Manchester, UK

3-3

HTR2014-31102

Analysis of Fission Gas Release-to-Birth Ratio Data from the AGR Irradiations.

Jeffrey J. Einerson, Binh T. Pham, Dawn M. Scates, John T. Maki, David A. Petti. 

INL, USA

3-4

HTR2014-31103

Determination of the Quantity of I-135 Released from the AGR Experiment Series.

Dawn M. Scates, John B. Walter, Edward L. Reber, James W. Sterbentz, David A. Petti. 

INL, USA

3-4

HTR2014-31109

The Kinetics of Fission Products Release from Microfuel Taking into Account the Trapped Fraction and Limited Solubility Effects. 

A. S. Ivanov, A. A. Rusinkevich. 

Kurchatov, Russia

3-7

HTR2014-31117

Investigation of the Feasibility of Utilizing Gamma Emission Computed Tomography in Evaluating Fission Product Migration in Irradiated TRISO Fuel Experiments.

Jason M. Harp, Paul A.Demkowicz. 

INL, USA

3-6

HTR2014-31135

Performance of AGR-1 High-Temperature Reactor Fuel During Post-Irradiation Heating Tests. 

Robert N. Morris, Charles A. Baldwin, Paul A. Demkowicz, John D. Hunn, Edward L. Reber. 

ORNL, USA

3-6

HTR2014-31149

KüFA Accident Testing of HTR Fuel Pebbles irradiated in the High Flux Reactor in Petten. 

O. Seeger, M. Laurie, A. El Abjani, J. Ejton, D. Boudaud, P. Carbol, V.V. Rondinella, M. Fütterer, H.-J. Allelein.  JRC-ITU, Germany

3-5

HTR2014-31158

Activation Product Analysis and Disposal Suggestions for Decommissioning High Temperature Reactor Pebble Bed Module (HTR-PM).

Sida Sun, Sheng Fang, Tao Liu, Jianzhu Cao, Hong Li. 

INET, China

3-8

HTR2014-31168

The Research Status for Decommissioning and Radioactive Waste Minimization of HTR-PM.

Wenqian Li, Hong Li, Jianzhu Cao, Jiejuan Tong. 

INET, China

3-8

HTR2014-31177

Prediction of Fission Product Release during the LOFC Experiments at the HTTR.

D. Shi, A. Xhonneux, S. Ueta, K. Verfondern, H.-J. Allelein. 

FZJ, Germany

3-7

HTR2014-31182

Irradiation Performance of AGR-1 High Temperature Reactor Fuel.

Paul A. Demkowicz, John D. Hunn, Scott A. Ploger, Robert N. Morris, Charles A. Baldwin, Jason M. Harp, Philip L. Winston, Tyler J. Gerczak, Isabella J. van Rooyen, Fred C. Montgomery, Chinthaka M. Silva.

INL, USA

3-5

HTR2014-31203

Irradiation Testing of TRISO-Coated Particle Fuel in Korea.

Bong Goo Kim, Sunghwan Yeo, Kyung-Chai Jeong, Sung-Ho Eom, Yeon-Ku Kim, Woong Ki Kim, Young Woo Lee, Moon Sung Cho, Yong Wan Kim. 

KAERI, Korea

3-4

HTR2014-31213

Irradiation Performance of HTGR Fuel in WWR-K Research Reactor. 

Shohei Ueta, Asset Shaimerdenov, Shamil Gizatulin, Lyudmila Chekushina, Masaki Honda, Masashi Takahashi,Kenichi Kitagawa, Petr Chakrov, Nariaki Sakaba. 

JAEA, Japan

3-3

HTR2014-31252

Implications of Results from the Advanced Gas Reactor Fuel Development and Qualification Program on Licensing of Modular HTGRs.

David Petti. 

INL, USA

3-1

HTR2014-31254

Detection and Analysis of Particles with Failed SiC in AGR-1 Fuel Compacts. 

John D. Hunn, Charles A. Baldwin, Tyler J. Gerczak, Fred C. Montgomery, Robert N. Morris, Chinthaka M. Silva, Paul A. Demkowicz, Jason M. Harp, Scott A. Ploger 

ORNL, USA

3-6

HTR2014-31255

Investigation of the Fission Products Silver, Palladium and Cadmium in Neutron Irradiated SiC using a Cs-Corrected HRTEM.

I. J. van Rooyen, E. J. OlivierJ. H Neethling. 

INL, USA

3-5

HTR2014-31261

Progress in Solving the Elusive Ag Transport Mechanism in TRISO Coated Particles: “What is new?”.

I. J. van Rooyen, H. Nabielek, J. H Neethling, M. J. Kania, D. A. Petti.  INL, USA

3-5

HTR2014-31262

Performance of Coated Particle Fuel in a Thorium Molten Salt Reactor with Solid Fuel.

Jun LIN, Tianbao ZHU, Haiqing ZHANG, Hongxia XU, Yang ZOU, Heinz NABIELEK, Zhiyong ZHU. Shanghai Institute of Applied Physics, China

 

HTR2014-31267

Study on the efficient disintegration of HTGR fuel elements by electrochemical method.

Piao Nan, Chen Ji, Xiao Cuiping, Wen Mingfen, Chen Jing. 

Liaoning Shihua Univ., China

3-2

HTR2014-31281

Temperature Analysis and Failure Probability of the Fuel Element in HTR-PM.

Yang Lin, Liu Bing, Tang Chunhe.  State Nuclear Power Technology R&D Centre, China

3-7

HTR2014-31304

Investigation of the fluidized bed-chemical vapor deposition (FB-CVD) process using CFD-DEM method.

Malin Liu, Rongzheng Liu, Yuanyun Wen, Bing Liu, Youlin Shao. 

INET, China

3-2

HTR2014-31306

The development of a material for uranium sorption in NH3/N environment.

Chen Xiaotong, He Linfeng, Liu Bing, Tang Yaping. 

INET, China

3-2

HTR2014-31314

Error Analysis of Ceramographic Sample Preparation for Coating Thickness Measurement of Coated Fuel Particles.

Xiaoxue Liu, Ziqiang Li, Hongsheng Zhao, Kaihong Zhang, Chunhe Tang.  INET, China

3-2

HTR2014-31347

Effect of Orientation on Microstructure and Hardness of Graphite Matrix for HTGR.

Sunghwan Yeo, Sungok Kim, Moon Sung Cho, Young-Woo Lee. 

KAERI, Korea

3-1

HTR2014-31363

Preparation of SiC and Ag/SiC coatings on TRISO surrogate particles by Pulsed Laser Deposition. 

Martin Lustfeld, Anne-Maria Reinecke, Ana Ruiz-Moreno, Wolfgang Lippmann, Antonio Hurtado. 

JRC-ITU, Germany

3-1

HTR2014-31364

Status of Research on Pebble Bed HTR Fuel Fabrication Technology in Indonesia. 

M. Rachmawati, Sarjono, Ridwan, R. Langenati. 

National Nuclear Energy Agency, Indonesia

3-1

HTR2014-31382

Comparison of fission product release predictions using PARFUME with results from the AGR-1 irradiation experiment.

Blaise P. Collin, David A. Petti, Paul A. Demkowicz, John T. Maki. 

INL, USA

3-6

HTR2014-31398

Strategy Study on Treatment and Disposal of the Radioactive Graphite Waste of HTR. 

Li Junfeng, Ma Tao, Wang Jianlong.

INET, China

3-8

HTR2014-31399

Advances in HTGR Wastewater Treatment System Design.

Li Junfeng, Qiu Yu, Wang Jianlong, Jia Fei. 

INET, China

3-8

HTR2014-31411

Carbon Dust Filtration in Three Different Nuclear Process EnvironmentsA comparison the challenges Carbon Dust Filtration Presents Under Different Process Conditions. 

Chris Chadwick.

Porvair Filtration Group

3-8

HTR2014-31418

Test Results of PBMR Fuel Spheres.

Konstantin Koshcheev, Alexander Diakov, Igor Beltyukov, Andrey Barybin, Mikhail Chernetsov.

Institute of Nuclear Materials, Russia

3-3

TRACK 4  Materials and Components

ID

Paper Title

Paper Authors

Session

HTR2014-41129

Design and Experiment of Auxiliary Bearing for Helium Blower of HTR-PM. 

YANG Guojun, SHI Zhengang, LIU Xingnan, ZHAO Jingjing.

INET, China

4-6

HTR2014-41152

Flow characteristics of helium gas going through a 90°elbow for flow measurement. 

Beibei Feng, Shiming Wang, Xingtuan Yang, Shengyao Jiang. 

INET, China

4-6

HTR2014-41170

High Temperature Test of 800HT Printed Circuit Heat Exchanger in HELP. 

Chan Soo Kim, Sung-Deok Hong, Jaesool Shim, Min Hwan Kim.

KAERI, Korea

4-1

HTR2014-41171

AGR core models and their application to HTRs and RBMKs. 

Samuel Baylis.

EDF Energy, UK

4-3

HTR2014-41198

HTGR Metallic Reactor Internals Core Shell Cutting & Machining Anti-deformation Technique Study. 

Xing Huiping, Xue Song. 

Shanghai No.1 Machine Tools Work , China

4-7

HTR2014-41199

Evaluation of the Control Rod Super Alloy Material of HTR-PM. 

Li Pengjun, Yan He, Diao Xingzhong. 

INET, China

4-1

HTR2014-41202

The Study on Helium Atmosphere Isolation in HTR Maintenance

Dong Zhen, Zhao Songlei, Yang Mingyi.

Shidao Bay, China

 

HTR2014-41235

Corrosion tests of high temperature alloys in impure helium. 

Jan Berka, Jana Kalivodova, Monika Vilemova, Zuzana Skoumalova, Petr Brabec.

Research Centre Rez & Institute of Chemical Technology in Prague, Czech

4-1

HTR2014-41236

Irradiation test plan of oxidation-resistant graphite in WWR-K Research Reactor. 

Junya Sumita, Taiju Shibata, Nariaki Sakaba.

JAEA, Japan

4-3

HTR2014-41243

Design on Hygrometry System of Primary Coolant Circuit of HTR-PM. 

Sun Yanfei, Zhong Shuoping, Huang Xiaojin.

INET, China

4-6

HTR2014-41257

Properties of Alloy 617 for Heat Exchanger Design. 

R. N. Wright, L. J. Carroll, J. K. Benz, J. K. Wright, T. M. Lillo, N. J. Lybeck.  INL, USA

4-1

HTR2014-41258

ARCHER Project: Progress on Material and Component Activities for the Advanced High Temperature Reactor. 

D.E.Buckthorpe.

Manchester Univ., UK

4-2

HTR2014-41275

Investigation on wear behavior of graphite ball under different pneumatic conveying environments. 

Chen Zhipeng, Zheng Yanhua, Shi Lei, Yu Suyuan.

INET, China

4-3

HTR2014-41277

Research on Moisture Absorption Performance of Carbon Material Used in HTGR. 

WEI Liqiang, LU Zhenming, CHEN Xiaotong, LIU Ling, CHEN Xiaoming. 

INET, China

4-3

HTR2014-41311

Thermal Analysis and Structural Design of Deposition Test Section of 10MW High Temperature Gas-cooled reactor-test Module (HTR-10). 

Wang Xiaoding, Liu Yanfang. 

DongFang Electric, China

4-6

HTR2014-41330

A Simulation Model for Tensile Fracture Procedure Analysis of Graphite Material based on Damage Evolution. 

Erqiang Zhao, Hongtao Wang, Shaopeng Ma.

Beijing Institute of Technology, China

4-4

HTR2014-41331

Experimental research of the yielding behavior of a graphite cylinder subjected to line loading. 

Hetong Liu, Qinwei Ma, Hongtao Wang, Shaopeng Ma.

Beijing Institute of Technology, China

4-4

HTR2014-41334

Oxidation Protective SiC Coating on Graphite for VHTR Core Support Structure. 

Jae-Won Park, Eung-Seon Kim, Jae-Un Kim, William E. Windes.

KAERI, Korea

4-4

HTR2014-41336

A TDS Study of High-Temperature N2 Adsorbed and N+ Ion Implanted Nuclear Carbon Materials. 

Mingyang Li, Zhengcao Li, Zhen Hu, Hong Li, Jianzhu Cao.

Tsinghua Univ., China

4-4

HTR2014-41340

Transient analysis of nuclear graphite oxidation for high temperature gas cooled reactor. 

Xu Wei, Shi Lei, Zheng Yanhua.

INET, China

4-5

HTR2014-41341

Surface Chemical Properties of Nuclear Carbon Materials after Nitrogen Adsorption and Ion Implantation. 

Xiaoyu GUO, Zhengcao LI, Zhen HU, Hong LI, Jianzhu CAO. 

Tsinghua Univ., China

4-5

HTR2014-41342

Temperature programmed desorption (TPD) studies on nuclear carbon materials charged with hydrogen at elevated temperatures. 

Zhengcao Li, Mingyang Li, Zhen Hu, Hong Li, Jianzhu Cao.

Tsinghua Univ., China

4-5

HTR2014-41361

Ten years of high temperature materials research at PSI - an overview paper. 

Manuel A. Pouchon, Jiachao Chen.

PSI, Switzerland

4-2

HTR2014-41376

Investigation of Creep Rupture Properties in Air and He Environments of Alloy 617 at 800. 

Woo-Gon Kim, I.M.W. Ekaputra,Jae-Young Park, Min-Hwan Kim, Yong-Wan Kim.

KAERI, Korea

4-2

HTR2014-41425

Aspects of nuclear process heat application of very high temperature reactors (VHTR)

W.T. Jansing, K. Kugeler

FZJ, Germany

plenary session

4

HTR2014-41450

Relationship between the Toyo Tanso Group and HTR-PM. 

GuoBin Zhan, Takashi Konishi.

TOYO TANSO, Japan

4-5

TRACK 5  Reactor Physics Analysis

ID

Paper Title

Paper Authors

Session

HTR2014-51106

The IAEA Coordinated Research Program on HTGR Uncertainty Analysis: Phase I Status and Initial Results. 

Frederik Reitsma, Gerhard Strydom, Friederike Bostelmann, Kostadin Ivanov.

IAEA

5-1

HTR2014-51126

Characteristic Behaviour of Pebble Bed High Temperature Gas-cooled Reactors during Water Ingress Events. 

Samukelisiwe N. Khoza, Dawid E. Serfontein, Frederik Reitsma. 

North-West Univ., South Africa

5-2

HTR2014-51133

Methodology of the On-line Follow Simulation of Pebble-bed High-temperature Reactors.

XIA Bing, LI Fu, WEI Chunlin, ZHENG Yanhua, CHEN Fubing, ZHANG Jian, GUO Jiong.

INET, China

 

HTR2014-51157

Study of the Effect of Burnable Poison Particles Applying in a Pebble Bed HTR. 

Wei Chunlin, Zhao Jing, Zhang Jian, Xia Bing. 

INET, China

5-3

HTR2014-51163

Introduction of HTR-PM Operation and Fuel Management System.

Liu Fucheng, Luo Yong, Gao Qiang.

Shidao Bay, China

 

HTR2014-51181

Calculation of the Fission Product Release for the HTR-10 based on its Operation History. 

A. Xhonneux, C. Druska, S. Struth, H.-J. Allelein. 

FZJ, Germany

5-2

HTR2014-51207

Research on Benchmark Calculation and Analysis of HTR-10 with RMC code. 

Wanlin Li, Ganglin Yu, Chunlin Wei. 

Tsinghua Univ., China

5-1

HTR2014-51209

Development of a new nuclide generation and depletion code using a topological solver based on graph theory. 

S. Kasselmann, S. Scholthaus, C. Rössel, H.-J. Allelein. 

FZJ, Germany

5-1

HTR2014-51253

ON THE EVALUATION OF PEBBLE BEAD REACTOR CRITICAL EXPERIMENTS USING THE PEBBED CODE. 

Hans D. Gougar, R. Sonat Sen. 

INL, USA

5-3

HTR2014-51272

A Conceptual Study on a Supercritical CO2-cooled Micro Modular Reactor. 

Hwanyeal Yu, Donny Hartanto, Yonghee Kim. 

KAIST, Korea

5-3

HTR2014-51276

Improvement of Discontinuity Factor for Strong Absorber Region. 

Guo Jiong, Li Fu, Hao Chen, Zhang Han, Zhou Xiafeng, Fan kai, Wang lidong, Lu Jianan. 

INET, China

5-2

HTR2014-51291

Advancements in reactor physics modelling methodology of Monte Carlo Burnup Code MCB dedicated to higher simulation fidelity of HTR cores. 

Jerzy Cetnar. 

AGH Univ. of Science and Technology, Poland

5-1

HTR2014-51380

ON POWER REFUELING MANAGEMENT OF HTR-PM.

Sun Furui, Luo Yong, Gao Qiang.

Shidao Bay, China

 

HTR2014-51384

The influence of thorium on the temperature reactivity coefficient in a 400 MWth pebble bed high temperature plutonium incinerating reactor. 

Guy A. Richards, Dawid E. Serfontein. 

North-West Univ., South Africa

5-3

HTR2014-51403

Neutronics Analysis of A 100 kWe Pebble Bed Space Reactor Concept. 

Zeguang LI, Lei SHI, Zuoyi ZHANG. 

INET, China

5-3

TRACK 6  Thermal-Hydraulics and Coupled Code Analyses

ID

Paper Title

Paper Authors

Session

HTR2014-60148

Separate Effect Experiment on Density Gradient Driven Flow in VHTR Small Break Air Ingress Accident. 

Jae Soon Kim, Jin-Seok Hwang, Eung Soo Kim. 

Seoul National Univ., Korea

6-8

HTR2014-60231

First Results for Fluid Dynamics, Neutronics and Fission Product Behaviour in HTR applying the HTR Code Package (HCP) Prototype. 

H.-J. Allelein, S. Kasselmann, A. Xhonneux, D. Lambertz. 

FZJ, Germany

6-1

HTR2014-61107

Separate Effects Tests to Determine the Pressure Drop over Packed Beds in the PBMR HPTU Test Facility. 

CG du Toit, PG Rousseau.

North-West Univ., South Africa

6-2

HTR2014-61112

Nodal Method for Solving Temperature Equations of High Temperature Reactor. 

Zhihong Deng, Yuliang Sun, Fu Li, Rizwan-uddin.

Huaneng Group, China

6-1

HTR2014-61130

Predictions of the Bypass Flows in the HTR-PM Reactor Core. 

Sun Jun, Chen Zhipeng, Zheng Yanhua, Shi Lei, Li Fu. 

INET, China

6-6

HTR2014-61132

Reactivity accident analysis during running-in phase and equilibrium core of a High Temperature Gas-cooled Reactor. 

Zheng Yanhua, Xia Bing, Shi Lei, Chen Fubing.

INET, China

6-4

HTR2014-61144

Discussion on Design Transients of Pebble-bed High Temperature Gas-cooled Reactor.

Wang YanLi Fu, Zheng Yanhua. 

INET, China

6-4

HTR2014-61155

Study on the Break Accidents of the HTR-PM Primary Loop. 

Lang Minggang, Sun Ximing, Zheng Yanhua.

INET, China

6-4

HTR2014-61172

Modelling and Transient Studies of a Liquid-Salt-Cooled Pebble Bedded Reactor (LSPBR). 

Hao Haoran, Frank Wols, Jan Leen Kloosterman.

INET, China

6-4

HTR2014-61184

Efficient Simultaneous Solution of Multi-physics Multi-scale Coupled Nonlinear System in HTR Based on Nonlinear Elimination Method. 

Han Zhang, Fu Li, Jiong Guo, Xiafeng Zhou, Kai Fan.

INET, China

6-1

HTR2014-61185

The Thermohydraulics and Dynamics Study of the HTR-10 High Temperature Helium Experimental Loop.

Chen Yang, Chao Fang, Jianzhu Cao. 

INET, China

6-7

HTR2014-61188

Chemical Mechanism of Graphite Dust Migration in the Primary Loop of HTGR. 

Bo Yuan, Huaqiang Yin. 

INET, China

6-5

HTR2014-61192

The Helium Test Facility (HTL) – Description and Operational Experiences. 

Zuoyi Zhang, Mingde Yang, HanLiang Bo, Riqiang Duan, Hongye Zhu. 

INET, China

6-7

HTR2014-61206

Effect of Crossflow on Hot Spot Fuel Temperature in Prismatic VHTR. 

Sung Nam Lee, Nam-il Tak, Min Hwan Kim, Jae Man Noh, Goon-Cherl Park. 

KAERI, Korea

6-6

HTR2014-61238

Examination of rapid depressurization phenomena modeling problems in VHTR following sudden DLOFC event. 

Izabela Gutowska, Brian G. Woods. 

Warsaw Tech. Univ., Poland

6-4

HTR2014-61244

RANS simulation of the thermal mixing in HTTF LP during normal operation conditions – High Temperature Test Facility at Oregon State University. 

Malwina J. Gradecka, Brian Woods. 

Warsaw Tech. Univ., Poland

6-2

HTR2014-61245

Development of a Coupled Multi-Physics Code System for Pebble Bed Reactor Core Modeling. 

Heikki Suikkanen, Ville Rintala, Riitta Kyrki-Rajamäki. 

Lappeenranta Univ. of Technology, Finland

6-1

HTR2014-61248

Experiment Study of Fuel Element Motion in HTR-PM Conveying Pipelines. 

WANG Xin, ZHANG Haiquan, NIE Junfeng, LI Hongke, LIU Jiguo, HE ayada. 

INET, China

6-9

HTR2014-61259

The X-Ray Pebble Recirculation Experiment (X-PREX): Facility Description, Preliminary Discrete Element Method Simulation Validation Studies, and Future Test Program. 

Michael R. Laufer, Jeffrey E. Bickel, Grant C. Buster, David L. Krumwiede, Per F. Peterson. 

Univ. of California, Berkeley, USA

6-9

HTR2014-61270

Preliminary Economic Evaluation Comparison of Hydrogen Production using G4ECONS and HEEP Code. 

Tae-hoon Lee, Ki-young Lee, Young-joon Shin. 

KAERI, Korea

6-5

HTR2014-61285

Nodal Expansion Method for Multi-dimensional Steady Convection-Diffusion Equation. 

ZHOU Xiafeng, LI Fu, GUO Jiong, HAO Chen, ZHANG Han, FAN Kai, WANG Lidong, LU Jianan. 

INET, China

6-1

HTR2014-61286

Thermodynamics Properties of Binary Gas Mixtures for Brayton Space Nuclear Power System. 

Ersheng YOU, Lei SHI, Zuoyi ZHANG. 

INET, China

6-6

HTR2014-61288

Analysis of Dust and Fission Products in PBMR Turbine. 

M.M. Stempniewicz, D. Wessels. 

NRG Arnhem, Netherlands

6-5

HTR2014-61289

Sorption Coefficients for Iodine, Silver, and Cesium on Dust Particles. 

M.M. Stempniewicz, P. Goede. 

NRG Arnhem, Netherlands

6-5

HTR2014-61302

Numerical Simulation of Two-branch Hot Gas Mixing at Reactor Outlet of HTR-PM. 

Hao Pengfei, Zhou Yangping, Li Fu, Shi Lei, He Heng. 

Tsinghua Univ., China

6-2

HTR2014-61303

Simulation of Thermal-hydraulic Process in Reactor of HTR-PM. 

ZHOU Kefeng, ZHOU Yangping, SUI Zhe, MA Yuanle. 

Ministry of Environment Protection, China

6-3

HTR2014-61322

Verification of two-temperature method for heat transfer process within a pebble fuel. 

Dali Yu, Minjun Peng. 

Harbin Engineering Univ., China

6-3

HTR2014-61328

Experimental Study of the Twin Turbulent Water Jets Using Laser Doppler Anemometry for Validating Numerical Models. 

Huhu Wang, Saya Lee, Yassin A. Hassan, Arthur E. Ruggles. 

Texas A&M Univ., USA

6-6

HTR2014-61348

Numerical Analysis on Control Method of Natural Circulation by Injection of Helium Gas.

Tetsuaki Takeda, Hirofumi Hatori,Shumpei Funatani. 

Univ. of Yamanashi, Japan

6-8

HTR2014-61353

Study on Heat Transfer Characteristics of One Side Heated Vertical Channel Applied as Vessel Cooling System. 

Shinji Kuriyama, Tetsuaki Takeda, Shumpei Funatani. 

Univ. of Yamanashi, Japan

6-3

HTR2014-61354

Study on the Effect of One-dimensional Natural Circulation on the Mixing Process of Two Component Gases in a Vertical Fluid Layer. 

Shumpei Funatani, Tetsuaki Takeda. 

Univ. of Yamanashi, Japan

6-8

HTR2014-61375

Numerical Study on the Helium Flow Characteristics for Steam Generator Subsystem of HTR. 

Jung Hoon Ha, Jin Ki Ham, Min-Hwan Ki, Won Jae Lee. 

Hyundai Heavy Industries, Korea

6-7

HTR2014-61414

Supercritical Steam Generator Design in Modular High-Temperature Gas-Cooled Reactor. 

ZHANG Zhen, YANG Xing-tuan, JU Huai-ming.

INET, China

6-7

HTR2014-61423

Evaluation of Effective thermal conductivity models on VHTR fuel block by CFD analysis. 

Dong-Ho Shin, Hyoung-Kyu Cho, Nam-Il Tak, Goon-Cherl Park.

Seoul National Univ., Korea

6-3

HTR2014-61426

Numerical Simulation of Flow Patterns of Fuel Spheres in Pebble Bed Reactors. 

Sun Ximing, Li Fu.

INET, China

6-9

HTR2014-61430

Experimental Observations of Natural Circulation Flow in the NSTF at Steady-State Conditions.

Darius D. Lisowski, Mitch T. Farmer. 

ANL, USA

6-8

HTR2014-61438

Thermal Hydraulic Analysis of RPV Support Cooling System for HTGR.

Qi Min, Xinxin Wu, Xiaowei Li, Li Zhang, Shuyan He.

INET, China

6-7

TRACK 7  Development, Design and Engineering

ID

Paper Title

Paper Authors

Session

HTR2014-71098

NUCLEAR BURNING WAVE MODULAR FAST REACTOR CONCEPT. 

N.G. Kodochigov, Yu.P. Sukharev. 

OKBM, Russia

7-2

HTR2014-71099

NEUTRONIC ASPECTS OF NUCLEAR BURNING WAVE MODULAR FAST REACTOR CONCEPT SUBSTANTIATION. 

N.G. Kodochigov, Yu.P. Sukharev. 

OKBM, Russia

7-2

HTR2014-71114

Development and Reliability Analysis of HTR-PM Reactor Protection System. 

Duo Li, Chao Guo, Huasheng Xiong. 

INET, China

7-3

HTR2014-71116

Software Unit Testing during the Development of Digital Reactor Protection System of HTR-PM. 

Chao Guo, Huasheng Xiong, Duo Li, Shuqiao Zhou, Jianghai Li.

INET, China

7-3

HTR2014-71131

Modeling and Simulation of the Multi-module High Temperature Gas-cooled Reactor. 

Liu Dan, Sun Jun, Sui Zhe, Xu Xiaolin, Ma Yuanle, Sun Yuliang.  INET, China

7-1

HTR2014-71138

Digital Distributed Control System Design: Control Policy for Shared Objects in HTR-PM. 

Shuqiao ZHOU, Xiaojin HUANG.

INET, China

7-6

HTR2014-71141

Study on cryogenic adsorption capability of trace nitrogen and methane by activated carbon for coolant helium purification. 

Hua Chang, Zong-Xin Wu.

INET, China

7-5

HTR2014-71146

Digital Information Platform Design of Fuel Element Engineering For High Temperature Gas-cooled Reactor. 

Du Yuwei.

China Nuclear Power Engineering, China

7-4

HTR2014-71164

Modeling and Application of Pneumatic Conveying for Spherical Fuel Element in Pebble-Bed Modular High-Temperature Gas-Cooled Reactor. 

ZHOU Shuyong, WANG Junsan, Wang Yuding, CAI Ruizhong, Zhang Xuan, Cao Jianting.

CNPSC, China

7-4

HTR2014-71165

The HTR-PM Plant Full Scope Training Simulator.

WANG Jun-san, WANG Yu-ding, ZHOU Shu-yong, CAI Rui-zhong,CAO Jian-ting.

China Nuclear Power Simulation Technology, China.

plenary session 3

HTR2014-71176

Evaluation, Comparison and Optimization of the Compact Recuperator for the High Temperature Gas-Cooled Reactor (HTGR) Helium Turbine System. 

Hao Haoran, Yang Xiaoyong, Wang Jie, Ye Ping, Yu Xiaoli, Zhao Gang.

INET, China

7-5

HTR2014-71190

Research and Measure of Tritium and Carbon-14 in HTR-10. 

Pi Yue, Cao Jianzhu, Xie Feng.

China Nuclear Power Engineering, China

7-5

HTR2014-71237

DESIGN OF THE HTR-PM SPENT FUEL STORAGE FACILITY. 

WANG Jinhua, ZHANG Zuoyi, WU Bin, LI Yue.

INET, China

7-8

HTR2014-71239

The Design of the Radioactive Graphite Dust Experimental System in the Primary Circuit of HTR-PM. 

Feng Xie, Yongnan Liang, Yue Pi, Hong Li, Jingyuan Qu.

INET, China

7-4

HTR2014-71240

The Design and Development of the Radiation Monitoring System for the Primary Circuit of HTR-PM. 

Feng Xie, Yongnan Liang, Jiang Zhu, Jianzhu Cao, Jiejuan Tong.

INET, China

7-3

HTR2014-71279

Analysis the Response Function of the HTR Ex-core Neutron Detectors in Different Core Status. 

FAN Kai, LI Fu, ZHOU Xuhua.

INET, China

7-1

HTR2014-71287

Research status on hydrodynamics and particle motion behavior of absorber sphere pneumatic conveying system in HTR-PM. 

Tianjin Li, He Zhang, Zhiyong Huang, Weiwei Qi, Hanliang Bo.

INET, China

7-8

HTR2014-71307

Coordinated Control Design for the HTR-PM Plant: From Theoretic Analysis to Simulation Verification. 

Zhe Dong, Xiaojin Huang.

INET, China

7-1

HTR2014-71312

Initial Start-Up and Testing of the Fort St. Vrain HTGR - Lessons Learned which May Be Useful for the HTR-PM.

H.L. Brey.

USA

plenary session 2

HTR2014-71317

Control room conceptual design of nuclear power plant with multiple modular high temperature gas-cooled reactors. 

Jia Qianqian, QuRonghong, Zhang Liangju.

INET, China

7-1

HTR2014-71326

Transient Analysis of a Gas-cooled Fast Reactor for Single Control Assembly Withdrawal. 

Hangbok Choi.

General Atomic, USA

7-1

HTR2014-71338

Research on Fault Diagnosis of HTR-PM Based on Multilevel Flow Model. 

Yong Zhang, Yangping Zhou.

INET, China

7-3

HTR2014-71346

AREVA Modular Steam Cycle – High Temperature Gas-Cooled Reactor Development Progress. 

L. Lommers, F. Shahrokhi, J. Mayer, F. Southworth.

AREVA, USA

7-2

HTR2014-71351

Seismic Study of TMSR Graphite Core Structure. 

Derek Tsang, Chao Chao Huang.  Shanghai Institute of Applied Physics, China

7-7

HTR2014-71369

Two-branch Gas Experiments on Thermal Mixing of HTR-PM Reactor Outlet. 

Zhou Yangping, Hao Pengefei, Li Fu, Shi Lei, He Heng.

INET, China

7-5

HTR2014-71378

The Design of High Reliability Magnetic Bearing Systems for Helium Cooled Reactor Machinery. 

N. Davies, R. Gao, Z. Guo, R. Jayawant, R. Leung, R. Shultz, M. Swann.  Waukesha Magnetic Bearings, USA

7-9

HTR2014-71379

Nonlinear finite element analysis of a test on the mechanical mechanism of the half-steel-concrete composite beam in HTR-PM. 

SUN Feng, PAN Rong. 

Ministry of Environment Protection, China

7-7

HTR2014-71390

SHIDAOWAN HTR EX-CORE NEUTRON FLUX MONITORING SYSTEMS. 

Clark J. Artaud.  Thermo Fisher Scientific (China), USA

7-8

HTR2014-71392

Concept of a Prestressed Cast Iron Pressure Vessel for a Modular High Temperature Reactor. 

Wolfgang Steinwarz, Dieter Bounin.  Siempelkamp Nukleartechnik GmbH, Germany

7-9

HTR2014-71402

Reliability Analysis on the Speed Measurement Redundant System of AMB Based on Markov Process. 

Zhou Yan, Shi Zhengang, Mo Ni, Yang Guojun.

INET, China

7-9

HTR2014-71421

The cross-flow mixing analysis of quasi-static pebble flow in pebble bed reactor. 

Xiang Fang, Zhiyong Liu, Yanfei Sun, Xingtuan Yang, Shengyao Jiang.

INET, China

7-4

HTR2014-71422

Introduction to the Chinese HTR-PM heat transfer test facility. 

Zhiyong Liu, Cheng Ren, Yanfei Sun, Xingtuan Yang, Shengyao Jiang.

INET, China

7-4

HTR2014-71428

System Design of a Supercritical CO2 cooled Micro Modular Reactor. 

Seong Gu Kim, Seongkuk Cho, Hwanyeal Yu, Yonghee Kim, Yong Hoon Jeong, Jeong Ik Lee.

KAIST, Korea

7-2

HTR2014-71433

Applications and Prospects of Modularization Technology in HTR Project Starting from Primary Loop Cavity Construction. 

Guokang Yang, Jing Chen, Wen Huang, Lizhi Lin, Yunlun Sun, Yan Chen, Jiaxin Mao, Yougang wang, Jinwen Wang, Mingfeng Lin, Mingshan Yang.

Chinergy, China.

7-6

HTR2014-71434

Research and tests of Steel-concrete-steel sandwich composite shear wall in reactor containment of HTR-PM. 

Yunlun Sun, Wen Huang, Ran Zhang, Pei Zhang, Chunyu Tian.

Chinergy, China.

7-6

HTR2014-71435

Experimental and numerical study of granular flow characteristics of absorber sphere pneumatic conveying process. 

He Zhang, Tianjin Li, Weiwei Qi, Zhiyong Huang, Hanliang Bo.

INET, China

7-5

HTR2014-71437

The Application of Integrated Design System for HTR-PM Design. 

Qi Shi, Xiaojing Kang.

Chinergy, China

7-8

TRACK 8  Safety and Licensing

ID

Paper Title

Paper Authors

Session

HTR2014-81096

Is Tritium an Issue for High Temperature Reactors? 

Michael A. Fütterer, Elio D'Agata, Xavier Raepsaet. 

JRC, Netherlands

8-1

HTR2014-81105

Working Towards Unified Safety Design Criteria for Modular High Temperature Gas-cooled Reactor Safety Design.

Frederik Reitsma, Fred Silady, Kazuhiko Kunitomi.

IAEA

plenary session 2

HTR2014-81150

Safety Design Approach for the Development of Safety Requirements for Design of Commercial HTGR. 

Hirofumi Ohashi, Hiroyuki Sato, Shigeaki Nakagawa, Yukio Tachibana, Tetsuo Nishihara, Xing Yan, Nariaki Sakaba, Kazuhiko Kunitomi.

JAEA, Japan

8-1

HTR2014-81197

Flood control construction of Shidao Bay nuclear power plant and safety analysis for hypothetical accident of HTR-PM.

Chen Yongrong, Zhang Keke, Zhu Li.

Shidao Bay, China

 

HTR2014-81246

Experimental Research Needs for Safety Analysis on High Temperature Gas Reactor Plant. 

LIU Yusheng, TANG Jilin, WEN Lijing, ZHANG Chunming, ZHANG Pan.

Ministry of Environment Protection, China

8-2

HTR2014-81282

Comparative Study on the Method of Uncertainty Analysis in the Maximum Fuel Temperature of HTR-PM. 

Hao Chen, Li Fu, Zheng Yanhua.

INET, China

8-2

HTR2014-81296

Phenomena Identification and Ranking Tables Related to the HTR-PM Accident Analysis. 

Fubing CHEN, Yanhua ZHENG, Lei SHI, Fu LI, Yujie DONG, Zuoyi ZHANG.  INET, China

8-2

HTR2014-81332

Plant Operation Station for HTR-PM Low Power and Shutdown Operation Probabilistic Safety Analysis. 

Liu Tao, Tong Jiejuan.

INET, China

8-2

HTR2014-81358

HTR -PM Safety requirement and Licensing experience.

LI Fu, ZHANG Zuoyi, DONG Yujie, WU Zongxin, SUN Yuliang.

INET, China

plenary session 2

HTR2014-81367

Perspectives on Understanding and Verifying the Safety Terrain of Modular High Temperature Gas-Cooled Reactors. 

Donald E. Carlson.

NRC, USA

8-1

HTR2014-81408

Radiation Level and Occupational Exposure during the Helium Circulator Maintenance Of The 10 MW High Temperature Gas-cooled Reactor-test Module (HTR-10). 

Sheng FANG, Hong LI, Zaizhe YIN, Chengxiang GUO.

INET, China

8-1