HTGR Knowledge Base

HTR-2004: Conference on High Temperature Reactors

Proceedings of the Conference on High Temperature Reactors, Beijing, China, September, 22-24, 2004

International Atomic Energy Agency, Vienna (Austria), HTR-2004

Articles

Very High Temperature Reactor (VHTR)
Philippe Billot, CEA/DEN/DDIN Saclay, Gif sur Yvette, FRANCE; Dominique Barbier, CEA/DEN/Cadarache, Saint Paul Lez Durance, FRANCE

The European Programme of Development of HTR/VHTR Technology
Dominique Hittner, Framatome-ANP, Paris La Défense Cedex, FRANCE

Last Results From HTR-E Project "High Temperature Reactor Components and System"
E. Breuil, D. Besson, Novatome Framatome-ANP, Lyon Cedex, FRANCE

PBMR Project Status and The Way Ahead
Dieter Matzner, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA

MIT Modular Pebble Bed Reactor (MPBR)
Andrew C. Kadak, Ronald G. Ballinger, Institute of Technology, Massachusetts, USA

Present Status Of HTTR Project
N. Fujimoto, S.Fujikawa, H. Hayashi, T. Nakazawa, T. Iyoku and K. Kawasaki, Dept. of HTTR Project, Japan Atomic Energy Research Institute, Ibaraki, JAPAN

A private investor's initiative in HTR technology in The Netherlands
Aliki van Heek, F. Blom, S. Groot, NRG, Petten, THE NETHERLANDS; Benno Wiersma, R. Pahladsingh, Sunergy/Innoplan B.V., Rotterdam, THE NETHERLANDS; B. Boer, Delft University of Technology, Delft, THE NETHERLANDS

ANTARES: The HTR/VHTR project at Framatome ANP
Jean-Claude Gauthier, Michel Lecomte, Framatome ANP SAS; Gerd Brinkmann, Framatome ANP Gmbh; Bernie Copsey, Framatome ANP Inc.

Introduction of HTR-10 Development (STAGE II)
Yingsu Wang, Huaneng Energy and Communications Co. Ltd.

HTR and VHTR Fuel Irradiation Program In The OSIRIS Material Testing Reactor
Stéphane Bendotti, CEA Saclay, Gif-sur-Yvette Cedex, FRANCE; Mayeul Phélip, CEA Cadarache, St. Paul Lez Durance, FRANCE; Pierre Guillermier, FRAMATOME ANP Fuel Sector, Lyon Cedex , FRANCE

The AREVA HTR Fuel Cycle – An Overview of Technical Issues and Potential Industrial Solutions
Greneche, AREVA, FRANCE; William J. Szymczak, Framatome-ANP

The Atlas HTR Fuel Simulation Code Objectives, Description And First Results
Mayeul Phélip, Guy Degeneve, CEA Cadarache, St. Paul Lez Durance, FRANCE; Frédéric Michel, Michel Pelletier, CEA Cadarache, St Paul Lez Durance, FRANCE; Pierre Guillermier, FRAMATOME ANP Fuel Sector, Lyon Cedex , FRANCE

CEA And Areva R&D On HTR Fuel Fabrication & Presentation Of The Gaia Experimental Manufacturing Line
François Charollais, Sophie Fonquernie, Christophe Perrais, CEA Cadarache, St. Paul Lez Durance, FRANCE; Marc Perez, CEA Grenoble, Grenoble Cedex, FRANCE; François Cellier, AREVA Plant Sector, Lyon Cedex, FRANCE; Gérard Harbonnier, AREVA CERCA, Romans sur Isère Cedex, FRANCE

HTGR spent fuels processing: The CEA investigation program, Michel Masson
Michel Masson, Stéphane Grandjean, Jerôme Lacquement, Jean-Claude Thieblemont, Jacques Lacombe, CEA ValRho Research Center, FRANCE

European Programme On HTR Fuel Technology
Mayeul Phélip, and contributions from each HTR-F&F1 partner, CEA Cadarache, St. Paul Lez Durance, FRANCE

Microstructures of Silicon Carbide and Pyrocarbon Coatings for Fuel Particles for High Temperature Reactors (HTR)
D. Hélary, X. Bourrat, Laboratoire des Composites Thermostructuraux, Pessac, FRANCE; O. Dugne, G. Maveyraud, CEA, Pierrelatte, FRANCE; M. Perez, CEA, Grenoble Cedex, FRANCE; P. Guillermier, AREVA, Lyon Cedex, FRANCE

Behaviour of spent HTR fuel elements in aquatic phases of repository host rock formations
J. Fachinger, S. Holgerson, M. Titov, T. Podruhzina, Research Centre Jülich, Jülich, GERMANY; M. den Exter, Nuclear Research and Consultancy Group-NRG, Petten, THE NETHERLANDS; B. Grambow; C. Landesmann, Ecole de Mines de Nantes, Nantes Cedex, FRANCE

Advanced Coated Particle Fuel Options
J.M. Kendall, Global Virtual LLC, Prescott, Arizona, USA; R.E. Bullock, Sigma Science Inc. Albuquerque, New Mexico, USA

Current Capabilities of The Fuel Performance Modeling Code Parfume
G.K. Miller, J.T. Maki, D.L. Knudson, D.A. Petti, Idaho National Engineering and Environmental Laboratory, Idaho, USA

The Behavior of HTR-10 Fuel Under Irradiation
Tang Chunhe, Fu Xiaoming, Zhu Junguo, Institute of Nuclear Energy Technology, Beijing, CHINA; Konstantin N. Koshceev, Alexandre V. Kozlov, Institute of Nuclear Materials, Zarechny, RUSSIA; Oleg G. Karlov; Yu.G. Degaltsev, Vladimir I. Vasiliev, Russian Research Center “Kurchatov Institute” Moscow, RUSSIA

Irradiation of High Temperature Reactor Fuel Pebbles At VHTR Conditions In The HFR Petten
Michael A. Fütterer, Harald Lohner, Rainer Conrad, European Commission, Joint Research Center, Institute for Energy, Petten, THE NETHERLANDS; Klaas Bakker, Sander de Groot, Carla M. Sciolla, EC, Nuclear Research and Consultancy Group Petten, THE NETHERLANDS

Post-Irradiation Testing of HTR-Fuel Elements Under Accident Conditions. Part 2
Herbert Kostecka, John Ejton, Wim de Weerd, Enrique H. Toscano, EC, Joint Research Centre, European Institute for Transuranium, Karlsruhe, GERMANY

PBMR Nuclear Material Safeguards
Johan Slabber, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA

Pebble Fuel Advantages
Johan Slabber, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA

Novel Inert Matrix Fuel Kernels for Pu and Minor Actinide Incineration in High Temperature Reactors
J. Somers, A. Fernandez, Joint Research Centre, Institute for Transuranium Elements, Karlsruhe, GERMANY

TIMCOAT: An Integrated Fuel Performancemodel For Coated Particle Fuel
Jing Wang, Ronald G. Ballinger, Heather J. Maclean, Jane T. Diecker, Department of Nuclear Engineering, Massachusetts Inst. of Technoogy, Cambridge, USA

Fracture Mechanics Based Coated Particle Fuel Failure Models
Jing Wang, Ronald G. Ballinger, MIT Nuclear Engineering Dept., Cambridge, USA

Design Optimization and Analysis of Coated Particle Fuel Using Advanced Fuel Performance Modeling Techniques
Jing Wang, Ronald G. Ballinger, Jane T. Diecker, MIT Nuclear Engineering Dept., Cambridge, USA

Silver Ion Implantation and Annealing In Cvd Silicon Carbide: The Effect of Temperature on Silver Migration
Heather J. MacLean, Ronald G. Ballinger, MIT, Cambridge, USA

Modular Helium Reactor Fuel Cycle Concepts and Sustainability
Chris Ellis, Alan Baxter, Arkal Shenoy, General Atomics, San Diego, California, USA

Program of GT-MHR Fuel Development and Justification
N. Kodochigov, Yu. Sukharev, OKBM, RUSSIA; N. Ponomarev-Stepnoy, Yu. Degaltsev, RCC KI, RUSSIA; V. Novikov, I. Kadarmetov, V. Makarov, VNIINM, RUSSIA; V. Sulaberidze NIIAR, RUSSIA; A. Chernikov, SPA Lutch, RUSSIA; D. Mc Eachern, R. Noren, GA, USA

Physical Designs and Calculations For The First Full Power Operation of The 10MW High Temperature Gascooled Reactor-Test Module (HTR-10)
Jing Xingqing, Yang Yongwei, Institute of Nuclear Energy Technology, Beijing, CHINA

Flow Field Analysis of the Hot gas chamber of the 10 MW High Temperature Reactor
Jinhua Wang, Zhiyong Huang, Hanliang Bo, Shengyao Jiang, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Development and Validation of 3-D Multi-component Mixture Analysis Tool (GAMMA) for Air Ingress in HTGRs
Hong Sik Lim, Korea Atomic Energy Research Institute, Taejon, KOREA; Hee Cheon No, Korea Advanced Institute of Science and Technology, Taejon, KOREA

Dynamic Systems CFD Simulation Code For The Modeling of HTGR Power Plants
W.A. Landman, M-Tech Industrial, Potchefstroom, SOUTH AFRICA; G.P. Greyvenstein, School of Mechanical and Materials Engineering, Potchefstroom, SOUTH AFRICA

A Finite Volume-Based Network Method For The Prediction of Heat \Mass and Momentum Transfer In A Pebble Bed Reactor
G.P. Greyvenstein and H.J. van Antwerpen, Energy Systems Research, Potchefstroom, SOUTH AFRICA

Validation Of A Transient Thermal-Fluid Systems CFD Model For A Packed Bed High Temperature Gas-Cooled Nuclear Reactor
P.G. Rousseau, C.G. du Toit, Energy Systems Research, Potchefstroom, SOUTH AFRICA; W.A. Landman, M-Tech Industrial, Potchefstroom, SOUTH AFRICA

Thermal hydraulic 3D calculations on the core of a High Temperature Gas Cooled Reactor
O. Cioni, M. Marchand, G. Geffraye, F. Ducros, CEA-Grenoble, Grenoble Cedex, FRANCE

The Copernic/Cyclop Computer Tool: Pre-Conceptual Design of Generation 4 Nuclear Systems, David Haubensack
David Haubensack, Caroline Thévenot, Patrick Dumaz, CEN Cadarache, Saint Paul lez Durance, FRANCE

Analysis of HTR-10 First Criticality with Monte Carlo Code Tripoli-4.3
Hong Chang, Xingqing Jing, Yongwei Yang, Institute of Nuclear Energy and Technology, Beijing, CHINA; Xaxier Raepsaet, Frederic Damian, Yi-Kang Lee, CEA-Saclay, Gif-sur-Yvette Cedex, FRANCE; Oliver Köberl, CEA-Cadarache, Saint Paul lez Durance, FRANCE

Detailed Analysis Of Pebble-Bed HTR Proteus Experiments With The Monte Carlo Code Tripoli4
O. Köberl, CEA-Cadarache, Saint-Paul-Lez-Durance Cedex, FRANCE; R. Seiler, Paul Scherrer Institute, Villigen, SWITZERLAND

Determination Of A HTGR Radioactive Material Inventory
Christian Bourdeloie, CEA-Cadarache, Nuclear Technology Department, Saint-Paul-Lez-Durance Cedex, FRANCE; Pierre Marimbeau, CEA-Cadarache, Reactors Studies Department, Saint-Paul-Lez-Durance Cedex, FRANCE

Analysis Of The Turbine Deblading In A HTGR With The Cathare Code
M. Saez, N. Tauveron, T. Chataing, G. Geffraye, L. Briottet, N. Alborghetti, CEA/DEN Grenoble, FRANCE

PBMR Fuel Sphere Source Terms
C.C. Stoker, F. Reitsma, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA

The PBMR Steady State And Coupled Kinetics Core Thermal-Hydraulics Benchmark Test Problems
Frederik Reitsma, Gerhard Strydom, Reactor Analysis Group, PBMR (Pty) Ltd, SOUTH AFRICA; Han de Haas, D.F. da Cruz, Fuel, Actinides & Isotopes Group, NRG, THE NETHERLANDS; Kostadin Ivanov, Bismark Tyobeka, Nuclear Engineering Program, Penn State University, USA; Ramatsemela Mphahlele, Nuclear Engineering Program, Penn State University, USA and National Nuclear Regulator, Centurion, SOUTH AFRICA; Tom Downar, Volkan Seker, Nuclear Engineering Department, Purdue University, USA; Hans D. Gougar, Fission & Fusion Systems, INEEL, USA

Development and Validation of Fission Product Release Models and Software at PBMR
Jacobus Johannes van der Merwe, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA

Analysis of Effectiveness of Cavity Cooling System
Martin P. van Staden, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA

HTR-N Reactor Physics and Fuel Cycle Studiies
J.C. Kuijper, J.B.M. de Haas, J. Oppe, NRG, Petten, THE NETHERLANDS; X. Raepsaet, F. Damian, F. Dolci, CEA, Saclay-Cadarache FRANCE; W. von Lensa, U. Ohlig, H.-J. Ruetten, H. Brockmann, Forschungszentrum Jülich, Jülich, GERMANY; W. Bernnat, Universität Stuttgart, IKE, Stuttgart, GERMANY; J.L. Kloosterman, Delft University of Technology, Delft, THE NETHERLANDS; N. Cerullo, G. Lomonaco, Universita di Pisa, Pisa, ITALY; A. Negrini, Ansaldo Energia S.p.A., Genova, ITALY; J. Magill, European Commision, JRC-ITU, Karlsruhe, GERMANY; R. Seiler, Paul Scherrer Institute, Villigen, SWITZERLAND

Coupling of Neutronics and Thermal-Hydraulics Codes For The Simulation of Transients of Pebble Bed HTR Reactors
T. Rademer, W. Bernnat, G. Lohnert, Institute of Nuclear Technology and Energy Systems (IKE), Stuttgart, GERMANY

Comparison of Fuel Loading Pattern In HTR-PM
Fu Li, Xingqing Jing, Institute of Nuclear and New Energy Technology, Beijing, CHINA

The Application of Compact Heat Exchangerin 10MW Nuclear Power Conversion System
Yu Cheng, Jinling Li, Jie Wang, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA

GTMHR Code
V.A. Bolnov, V.S. Vostokov, V.S. Gorbunov, V.V. Shashkov, OKBM, Nizhny Novgorod, RUSSIA

Provision of the Possibility to Increase Helium Temperature at the core Outlet of GT-MHR-Type Reactor to the Level of 1000 centigrade
V.N. Afanasev, N.G. Kodochigov, N.G. Kuzavkov, S.F. Shepelev, OKBM, Nizhny Novgorod, RUSSIA

Development and Calculation of Neutronic Benchmark Models For The GT-MHR Type Reactor Cells
V. Boyarinov, E. Glushkov, V. Davidenko, P. Fomichenko, V. Tsibulsky, RRC Kurchatov Institute, Moscow, RUSSIA; E. Marova, Yu. Sukharev, OKBM, Nizhny Novgorod, RUSSIA; E. Mitenkova, N. Novikov, IBRAE, Moscow, RUSSIA

Verification and Validation of The HTGR Systems CFD Code Flownex
Jan P. van Ravenswaay, Johann T. Labuschagne, M-Tech Industrial (Pty) Ltd, SOUTH AFRICA; Gideon P. Greyvenstein, Willem M.K. van Niekerk, School of Mechanical and Materials Engineering, Potchefstroom, SOUTH AFRICA

Study on The Thermodynamic Cycle of HTR-10GT
Zhiyong Huang, Jie Wang, Jinling Li, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Concept of Pebble Bed Based HTGR With Fast Pebble Discharge System
Jianling Dong, Suyuan Yu, INET, Beijing, CHINA

Design and Experiments of The Active Magnetic Bearing System For The HTR-10
Lei Shi, Lei Zhao, Guojun Yang, Huidong Gu, Xingzhong Diao, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Design Features of Gas Turbine Power Conversion System for HTR-10GT
Jie Wang, Zhiyong Huang, Shutang Zhu, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA

The Monitoring System of The PCU For The 10MW High Temperature Gas-Cooled Reactor
Zhjengang Shi, Meisheng Zha, Hong Peng, Lei Shi, Lei Zhao, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Using Transfer Function Method To Study The Dynamic Circulation Characteristics of HTR-10GT
Shutang Zhu, Jie Wang, Zhioyong Huang, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Comparison of Two Models for a Pebble Bed Modular Reactor Core Coupled to a Brayton Cycle
Ayelet Walter, Alexander Schulz, Günter Lohnert, Intitute of Nuclear Technology and Energy Systems (IKE), Stuttgart, GERMANY

Evaluating The PBMR Main Power System Turbo Machines With The Aid Of Sensitivity and Monte Carlo Analyses
Erik van der Linde, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA

Design of Pebble-Bed Reactors Using Genetic Algorithms
Hans D. Gougar, William K. Terry, Abderrafi M. Ougouag, Idaho National Engineering and Environmental Laboratory, Idaho, USA; Kostadin N. Ivanov, The Pennsylvania State University, Dept. of Mechanical and Nuclear Engineering, PA, USA

The Impact of Design on the Decay Heat Removal Capabilities of a modular Pebble Bed HTR
Nader Ben Said, Michael Buck, Wolfgang Bernnat, Günter Lohnert, Institute of Nuclear Technology and Energy Systems, Stuttgart, GERMANY

The Interim Fuel Storage Facility of The PBMR
W.F. Fuls, ISTN and PhD Student, University of North-West; C. Viljoen, CFD Engineer, PBMR; C. Stoker, Neutronics Specialist, PBMR; C. Koch, Metallurgical Engineer, ISTN; E.H. Mathews, PhD Study Promoter, University of North-West

Advanced Modularity Design for The MIT Pebble Bed Reactor
Andrew C. Kadak, Marc. V. Berte (Graduate Student), Dept. of Nuclear Engineering, Massachusetts Institute of Technology, USA

Design of Chinese Modular High-Temperature Gas-Cooled Reactor HTR-PM
Zuoyi Zhang, Zongxin Wu, Yuanhui Xu, Yuliang Sun, Fu Li, Institue of Nuclear and New Energy Technology, Beijing, CHINA

Dynamics Analysis of Very Flexible Rotor
Yang Xu, Lei Zhao, Suyuan Yu, Institute of Nuclear Energy Technology, Beijing, CHINA

Impact Analysis of The Catcher Bearing For The Magnetic Suspending Rotor In HTR10-GT Project
Li Wan, Yang Xu, Guojun Yang, Lei Zhao, Xinxin Wu, Institute of Nuclear Energy Technology, Beijing, CHINA

GTHTR300C For Hydrogen Cogeneration, Kazuhiko KUNITOMI
Kazuhiko Kunitomi, Xing Yan, Shusaku Shiozawa, Nozomu Fujimoto, Dept. of Advanced Nuclear Heat Technology, JAERI, Ibaraki-ken, JAPAN

Calculation-Information Code "GT-MHR Analyzer"
N.G. Kodochigov, A.V. Vasyaev, V.V, Bankrutenko, V.F. Golovko, L.E. Kuznetsov, I.V. Dmitrieva, E.A. Zvyagin, M.E. Ganin, OKBM, Nizhny Novgorod, RUSSIA

Influence Of Htgr Parameters On The Configuration And Characteristics Of Power Conversion Unit With Direct Gas-Turbine Cycle
N.G. Kodochigov, A.V. Vasyaev, V.F. Golovko, N.G. Kuzavkov, I.V. Dmitrieva, OKBM, Nizhny Novgorod, RUSSIA

Power Conversion Unit With Direct Gas-Turbine Cycle For Electric Power Generation As A Part Of GT-MHR Reactor Plant
V.I. Kostin, N.G. Kodochigov, A.V. Vasyaev, V.F. Golovko, OKBM, Nizhny Novgorod, RUSSIA

Investigation of Full Electromagnetic Suspension For Turbomachine Rotor
V.I. Kostin, N.G. Kodochigov, V.V. Drumov, V.S. Vostokov, I.V. Drumov, S.E. Belov, A.V. Khodykin, OKBM, Nizhny Novgorod, RUSSIA

Investigation of Influence of Integral Component In Proportional Integral Differential Regulator Of Electromagnetic Bearing Control System On Stability and Dynamics Of GT-MHR Turbomachine
F.M. Mitenkov, V.S. Vostokov, V.S. Gorbunov, V.V. Drumov, A.V. Khodykin, OKBM, Nizhny Novgorod, RUSSIA

Rotation Investigations Of Rotor On Electromagnetic Suspension. Calculation And Methods
F.M. Mitenkov, N.G. Kodochigov, V.S. Vostokov, V.S. Gorbunov, V.V. Drumov, E.F. Sabaev, A.V. Khodykin, OKBM, Nizhny Novgorod, RUSSIA

Comparison of Horizontal and Vertical Layout of The Rotor on Electromagnetic Suspension
V.S. Vostokov, N.G. Kodochigov V.S. Gorbunov, A.V. Khodykin, OKBM, Nizhny Novgorod, RUSSIA

Design And Analysis Under Conditions Of Limited Space By 3D Means
M.K. Vladimirsky, A.V. Vasyaev, OKBM, Nizhny Novgorod, RUSSIA

Control System of NPP with GT-MHR Power Unit
A.V. Vasyaev, V.F. Golovko, A.B. Pobedonostsev, V.S. Gorbunov, V.V. Drumov, OKBM, Nizhny Novgorod, RUSSIA

Simulator Development For GT-MHR Reactor Plant Designing
V.A. Bolnov, E.V. Bogdanova, V.S. Vostokov, V.S. Gorbunov, OKBM, Nizhny Novgorod, RUSSIA

Discussion About Several Key Problems To Develop Helium Gas Turbo Compressor System of HTR-10GT
Limin Xu, Harbin Marine Boiler and Turbine Research Institute, Harbin, CHINA

The Full Perfornance Test For The Safety Valves of HTR-10
Xinxin Wu, Jianling Dong, Rizhu Li, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Design of The HTR-10 Helium Circulator With The Active Magnetic Bearings
Xingzhong Diao, Lei Zhao, Huizhong Zhou Meisheng Zha, Jie Wang, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Study on the helium cooling of high-speed generator for HTR-10GT
Shahed Fazluddin, Kobus Smit, Johan Slabber, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA

Housing Vibration Control of A Large Rotor Suspended By Magnetic Bearings
Kai Zhang, Hongbin Zhao, Department of Engineering Physics, Tsinghua University, Beijing, CHINA; Lei Zhao, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Redundancy Design and Reliability Analysis of AMB System
Gu Huidong, Zhao Hongbin, Department of Engineering Physics, Tsinghua University, Beijing, CHINA; Lei Zhao, Lei Shi, Xingzhong Diao, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA

The use of Compact Heat Exchangers technologies for the HTRs recuperator application per proper design
Patrice Tochon, Frank Pra, CEA GREThE, Grenoble Cedex, FRANCE; Christian Mauget, Novatome Framatome-ANP, Lyon Cedex, FRANCE

Fatigue Analysis of Steam Generator In HTR-10
Xiaotian Li, Shuyuan He, Institute of Nuclear and New Energy Technology, Beijing, CHINA

The Feasibility Study on PCPV In Modular HTR
Shuyuan He, Xinxin Wu, Jisheng Wang, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Results From EU 5Th Framework HTR Projects HTR-M & HTR-M1
D.E. Buckthorpe,NNC Ltd, Knutsford, UNITED KINGDOM plus contributions from the HTR-M & M1 partners

Studies on Mechanical Behavior of Mod 9CR-1MO Steel
Marie Therese Cabrillat, CEA/DEN/Cadarache, Saint Paul lez Durance, Cedex, FRANCE; Magali Reytier, Maxime Sauzay, Michel Mottot, Jean Louis Seran, Philippe Billot, CEA/DEN/Saclay, Gif sur Yvette, FRANCE; Bernard Riou, Framatome-ANP, Lyon Cedex, FRANCE; Vincent Gaffard, Ecole des Mines de Paris, Evry Cedex, FRANCE

Application of A Leak Before Break Procedure To A HTGR CROSS-DUCT
Yves Lejeail, Marie-Thérèse Cabrillat, Cécile Krakowiak, CEA Cadarache, Saint Paul lez Durance Cedex, FRANCE

Metallic And Graphite Materials For Out-Of-Core and In-Core Components of The VHTR: First Results Of The CEA R&D Program
J.L. Séran, P. Billot, J.P. Bonal, L. Gosmain, CEA/DEN/Saclay, Gif sur Yvette, FRANCE; H. Burlet, R. Couturier, CEA/DRT/Grenoble, Grenoble Cedex, FRANCE; J.C. Robin, CEA/DEN/Cadarache, Saint Paul lez Durance, Cedex, FRANCE; B. Riou, Framatome-ANP/Novatome, Lyon Cedex, FRANCE

Issues in Reactor Pressure Vessel materials
B. Riou, C. Escaravage, Framatome-ANP, Lyon Cedex, FRANCE; D. Hittner, Framatome-ANP, Paris La Défense Cedex, FRANCE; D. Pierron, Framatome ANP, Saint Marcel, FRANCE

Theoretical Analysis On The Tribological Properties Of HTGR-10 Graphite
Xuanyu Sheng, Suyuan Yu, , Institute of Nuclear and New Energy Technology, Beijing, CHINA

Overview Of Graphite Treatment Processes In High Temperature Reactors
Fabienne Delage, CEA Cadarache Fuel Study Dept., Saint Paul lez Durance, FRANCE; Christian Latge, Pascal Thouvenot, CEA Cadarache Nuclear Technology Dept., Saint Paul lez Durance, FRANCE

Data For Computing Radiation Induced Damage In HTR Fuel Matrices
A.M. Ougouag , C.A. Wemple, Idaho National Engineering and Environmental Laboratory, Idaho, USA

A Flexible Rotor In HTR-10 Passing Through The First Bending Critical Speed 24,000 RPM
Huidong Gu, Hongbin Zhao, Department of Engineering Physics, Tsinghua University, Beijing, CHINA; Lei Zhao, Lei Shi, Xingzhong Diao, Suyuan Yu, , Institute of Nuclear and New Energy Technology, Beijing, CHINA

Preliminary Scheme Design and Analysis of Catcher Bearing for HTR-10GT
Guojun Yang, Li Wan, Lei Zhao, Suyuan Yu, , Institute of Nuclear and New Energy Technology, Beijing, CHINA

Fracture Behaviour Of Nuclear Graphite
Andrew Hodgkins, James Marrow, Paul Mummery, Laurent Babout, Manchester Materials Science Centre, Manchester, UNITED KINGDOM; Barry Marsden, Alex Fok, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM

The Use Of X-Ray Microtomography To Determine Relationships Between Microstructure and Mechanical Behaviour of Nuclear Graphite
Laurent Babout, Andrew Hodgkins, Richard Dewhurst, T.James Marrow, Paul M. Mummery, School of Materials, University of Manchester, Manchester, UNITED KINGDOM; Alex Fok, Barry Marsden, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM

The Relationship Between Strength and Modulus In Nuclear Graphite
S.L. Fok, Barry Marsden, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM; T.James Marrow, Paul M. Mummery, Manchester Materials Science Centre, University of Manchester, Manchester, UNITED KINGDOM

Stress Wave Propagation Following Primary Cracking In Cylindrical Specimens of Brittle Materials
Wei-jing He, Shi-ping Yao, Siu-lun Fok, J.D. Jackson, J.R. Wright, Nuclear Graphite Research Group, Manchester, UNITED KINGDOM

The Effect of Softening on The Predicted Strength of Brittle Materials Using a Continuum Damage Mechanics Failure Model
Li Shi, Haiyan Li, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA; S.L. Fok, B.J. Marsden, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM

An Experimental Study on The Porosity Networks In Nuclear Graphite
S.L. Fok, B.J. Marsden, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM; Libin Sun, Institute of Nuclear and New Energy Technology, Beijing, CHINA; James Marrow, Andrew Hodgkins, Manchester Materials Science Centre, Manchester, UNITED KINGDOM

Development Of Shaft Gas Seal
V.M. Rogozhin, V.B. Zinoviev, OKBM, Nizhny Novgorod, RUSSIA

Materials Used For The Main Elements of Hightemperature Elements Of HTGR Turbocompressor
N.G. Kodochigov, A.A. Romantsov, S.A. Dolgov, OKBM, Nizhny Novgorod, RUSSIA

The Mode Design Of The Rotor In Active Magnetic Bearing
Hongwei Li, Yang Xu, Lei Zhao, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA

HTGR Helium Turbine Conceptual Design By Genetic/Gradient Optimization
Guojun Yang, Suyuan Yu, Long Yang, Zhiyong Huang, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Vertical Turbogenerator With Helium Cooling
Ya.B. Danilevich, E.Yu. Anishev, N.S. Delfontsev, V.I. Kostin

Analysis of Reactivity Induced Accidents for HTR-10
Serhat Kose, Ihsan Kilic, Technology Dept. Turkish Atomic Energy Authority, Ankara, TURKEY

Thermal Response of a High Temperature Reactor during Passive Cooldown under Pressurized and Depressurized Conditions
Hamidul Haque, Wolfgang Feltes, Gerd Brinkmann, Framatome-ANP, Erlangen, GERMANY

On The Use Of Point Kinetics For High-Temperature Gas-Cooled Reactor Transient Analysis
Mabrouk Methnani, International Atomic Energy Agency, Vienna, AUSTRIA

Leak-Before-Break Analysis Of The HTR-10's Hot-Gas Duct Vessel
Zhengming Zhang, Shuyuan He, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Dose Rate Effects of Ion-Irradiated Isotropic Nuclear Graphite
Se-Hwan Chi, Gen-Chan Kim, Jong-Hwa Chang, HTGR Project, KAERI, Daejeon, KOREA

Sensitivity Studies of Modular High-Temperature Gas-Cooled Reactor (MHTGR) Postulated Accidents
Sydney Ball, Oak Ridge National Laboratory, Oak Ridge, USA

Advanced High-Temperature Reactor (AHTR) Loss-Of-Forced-Circulation Accidents
Sydney Ball, Charles Forsberg, Nuclear Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, USA

The PBMR Containment System
Albert Koster, Derek Lee, PBMR, Centurion, SOUTH AFRICA

Safety Classification and Defence In Depth For HTRS
Albert Koster, David Nicholls, PBMR, Centurion, SOUTH AFRICA

Mcnp Simulations And Measurements For The Validation Of The PBMR Burnup Measurement System At Necsa
Zainuddin Karriem, Wessel J. Strydom, Necsa, Pretoria, SOUTH AFRICA; Johan H. Venter, PBMR, Centurion, SOUTH AFRICA

Radioactive Waste Arising from HTR
J. Fachinger, H. Brücher, W. von Lensa, Institute for Safety Research and Reactor Technology, Forschungszentrum Jülich, Jülich, GERMANY; J.M. Turner, A. Nuttall, NNC Limited, Knutsford, UNITED KINGDOM; C. Bourdeloie, CEA Saclay, Gif sur Yvette, FRANCE; G. Brinkmann, Framatome-DE KWU NGES3, Erlangen, GERMANY

Air Ingress Benchmarking with Computational Fluid Dynamics Analysis
Andrew C. Kadak, Tieliang Zhai (Graduate Student), Department of Nuclear Engineering, MIT Massachusetts, Massachusetts, USA

From Field to Factory - Taking Advantage of Shop Manufacturing for the Pebble Bed Modular Reactor
Edward Wallace, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA; Regis Matzie, Westinghouse Electric Company LLC, USA; Roger Heider, Sargent and Lundy, LLC, USA; John Maddalena, Imhotep Consulting, CC, SOUTH AFRICA

Tribology In High Temperature Helium: First Phase of The CEA Helium Technology Program
Lionel Cachon, Serge Albaladejo, Pascal Taraud, Alain Berjon, Commissariat a l’energie Atomique Centre de Cadarache, Saint Paul lez Durance, FRANCE

PBMR Existing And Future R&D Test Facilities
Dieter Matzner, PBMR, Centurion, SOUTH AFRICA

Pebble Flow Experiments For Pebble Bed Reactors
Andrew C. Kadak, Department of Nuclear Engineering, Massachusetts Institute of Technology; Martin Z. Bazant, Department of Mathematics, Massachusetts Institute of Technology

Safety Demonstration Tests On HTR-10
Shouyin Hu, Ruipian Wang, Zuying Gao, Institute of Nuclear Energy Technology, Tsinghua University, Beijing, CHINA

Power Operation Commissioning Tests Of HTR-10
Shouyin Hu, Ruipian, Wang, Institute of Nuclear Energy Technology, Tsinghua University, Beijing, CHINA

Results of Experimental Investigations on Sliding Seal Mock-up for GT-MHR RP Turbomachine
N.G. Kodichigov, S.E. Belov, V.I. Fomichev, A.I. Maxyanin, I.B. Orlov, M.N. Borokov, OKBM, Nizhny Novgorod, RUSSIA

Experimental Investigation For The Optimization Of Powerful Turbine Plants Gas Coolers Heat Exchange Surface Ribbing
O.A. Bikh, B.M. Kamashev, N.G. Kodochigov, A.E. Komarov, A.E. Krasilschikov, N.G. Kusavkov, A.V. Malkov, V.M. Rulev, V.A. Sobolev, OKBM, Nizhny Novgorod, RUSSIA

Experimental Investigation Of High-Temperature High-Performance Recuperator
O.A. Bikh, V.M. Golovko, I.V. Dmitrieva, B.M. Kamashev, A.E. Krasilschikov, A.V. Malkov, V.M. Rulev, OKBM, Nizhny Novgorod, RUSSIA

Design And Experiment Investigations of Compact Recuperators For Reactor Plants With Gas-Turbine Cycle
O.A. Bikh, V.F. Golovko, I.V. Dmitrieva, N.G. Kuzakov, L.K. Nikanorov