Ref. Number
Paper Title
Corresponding Author
Paper
Presentation
A00000113
GAS COOLED REACTORS R&D STRATEGY IN FRANCE
Frank Carre
Download
A00000117
RAPHAEL, a European Project for the development of HTR/VHTR technology for industrial process heat supply and cogeneration
Dominique HITTNER
A00000150
Outlines of the French R&D Program for the development of High and Very High Temperature Reactor
Philippe Billot
B00000024
Irradiation testing of matrix graphite for spherical HTR-10 fuel elements
Chunhe Tang
B00000031
FUELBASE: a thermodynamic database for advanced fuels
Christine Gueneau
B00000035
Irradiation Results of AVR Fuel Pebbles at Increased Temperature and Burn-Up in the HFR Petten
Michael Futterer
B00000055
Selection criteria for chosing carbonaceous matrix for HTR block type design
Virginie Basini
B00000066
Structure and Mechanical Properties of Pyrolytic Carbon Produced by Fluidized Bed Chemical Vapor Deposition
Ping Xiao
B00000070
Establishment of the Technology to Manufacture Uranium Dioxide Kernels for PBMR Fuel
Anneleen Müller
B00000075
HIGH-TEMPERATURE REACTOR FUEL TECHNOLOGY IN THE RAPHAEL EUROPEAN PROJECT
Mayeul PHELIP
B00000077
Commissioning experience with both the Laboratory Coater and the initial full size Coater at the PBMR Fuel Laboratories.
John Barry
B00000081
Nondestructive Measurement of the Coating Thickness in the Simulated TRISO-coated Fuel Particle for the HTGR
Woong-Ki Kim
B00000085
Microscopic thermal characterization of HTR particle layers
Virginie Bassini
B00000086
LATEST ACHIEVEMENTS OF CEA & AREVA NP ON HTR FUEL FABRICATION
Charollais Francois
B00000087
KINETIC STUDY OF THE UO2/C INTERACTION BY HIGH TEMPERATURE MASS SPECTROMETRY
Gosse Stephane
B00000098
Fabrication of Plutonium Based Coated Particle Fuel at the Institute for Transuranium Elements
Joseph Somers
B00000099
Quality Control of High Temperature Reactors (HTR) compacts via X-Ray Tomography
Julien BANCHET
B00000125
Porosity Evaluation of Pyrolytic Carbon in TRISO-coated Fuel Particles by the Depth-sensing Indentation Method
Ji Yeon PARK
B00000127
Development of HTGR coated particle fuel technology in Korea
Young-Woo LEE
B00000162
HTR Specific Waste Characterisation Programme
Pascal BROS
B00000170
Characteristics of Different Fuel Cycles in a PBMR-400 for Burning Reactor – or Weapons Grade Plutonium
Eben Mulder
B00000176
Current Status of Development of Coated Particle Performance Code GOLT
Igor Golubev
B00000177
COATED FUEL PARTICLES WITH ZIRCONIUM CARBIDE COATING
Albert Chernikov
B00000200
Characterisation of nuclear waste for the PBMR Fuel Plant
Zola Hlatshwayo
B00000212
BURN-UP DETERMINATION OF HIGH TEMPERATURE REACTOR SPHERICAL FUEL ELEMENTS BY GAMMA SPECTROMETRY
Daniel Freis
B00000227
Fragmentation of Coated Particle Fuel Using Welding Techniques
B00000281
manufacture of high corrosion resistant fuel spheres (FS) for high temperature pebble bed modular reactors (pbmr)
Karl-Heinz Grosse
B00000282
Rotary cascade retort furnace for the manufacture of htr fuel element kernels
C00000023
Verification and Validation of the CFD model of the PBMR Reactor
Jaap Hoffmann
C00000044
Active control to avoid surge development in the case of a pipe rupture in a direct cycle HTGR
Geffraye Genevieve
C00000048
Design modelling tool for fuel blocs management and application to Uranium and Plutonium cores
Jean-Christophe KLEIN
C00000050
A SCENARIO FOR THE DEPLOYMENT OF HTRs TYPE GTMHR USING REACTOR-GRADE PLUTONIUM
LIONEL BOUCHER
C00000053
GCFR Design Optimization for passive safety
Marek Stempniewicz
C00000059
Analysis of Dust Transport, Deposition, and Resuspension for HTR/PBMR Reactor Systems using SPECTRA
C00000069
Reactor Pressure Vessel Temperature Analysis of Candidate Very High Temperature Reactor Designs
Hans Gougar
C00000072
TINTE ANALYSIS OF PBMR REACTIVITY INSERTION TRANSIENTS
UGUR EMRE SIKIK
C00000074
The stability of Xenon-induced spatial power oscillations in the 400 MW PBMR reactor
Gerhard Strydom
C00000084
Application of SPECTRA on PBMR V704 Design
C00000089
Sensitivity Studies of Air Ingress Accidents in Modular HTGRs
Syd Ball
C00000094
DOSE RATE ANALYSIS FOR THE DESIGN PROCESS OF THE PBMR CORE CONDITIONING SYSTEM
Zukile Zibi
C00000095
GETTER – A Model for Fission Product Release from Spherical HTR Fuel Elements
Jeetesh Keshaw
C00000109
Status of the IAEA Coordinated Research Project on HTGR Core Physics and Thermal-Hydraulic Benchmarks (CRP-5)
Mabrouk Methnani
C00000128
Modified Point Kinetics Analysis of some HTR Transients
Osman Kemal Kadiroglu
C00000130
Heat transfer correlation limitations at the pebble bed reflector interface
Jean Van der Merwe
C00000131
A CONCEPTUAL STUDY OF THE RETENTION OF FISSION PRODUCTS FROM A DELAYED RELEASE IN THE PBMR BUILDING
Martin Sage
C00000134
Burnup and transient analysis of a HTR-400 design loaded with PuO2 fuel
Aliki van Heek
C00000147
Radiation Transport from the Bottom of the Reactor Core to the Bottom of the Reactor Pressure Vessel of the PBMR.
Oscar Zamonsky
C00000149
CALCULATION ASPECTS OF DETAILED RADIATION HEAT TRANSFER
Herman van Antwerpen
C00000155
COMPARISON OF VSOP AND MCNP RESULTS OF PBMR EQUILIBRIUM CORE MODELS
Sonat Sen
C00000157
A STOCHASTIC METHOD TO SIMULATE THE RELOADING OF PEBBLES AFTER A FULL-CORE UNLOAD
C00000169
VERIFICATION AND VALIDATION OF FLOWNEX NUCLEAR
Kobus Van der Merwe
C00000173
Features of calculation of temperature reactivity coefficient in the GT-MHR reactor
Yuri Sukharev
C00000174
Development of core dynamics analysis of coolant flow reduction tests of HTTR
Testuaki TAKEDA
C00000180
PEBBLES: A Computer Code for Modeling Packing, Flow and re-Circulation of Pebbles in a Pebble Bed Reactor
Abderrafi Ougouag
C00000188
Development of a Method for Neutronics Treatment of Non-Multiplying Zones in Pebble Bed Reactors
C00000190
THE THERMAL HYDRAULIC MODEL FOR THE PBMR PLANT TRAINING SIMULATOR
Trevor Dudley
C00000192
THE REACTOR CORE NEUTRONIC MODEL FOR THE PBMR PLANT TRAINING SIMULATOR
C00000196
Development of a fast 3D thermal-hydraulic tool for design and safety studies for HTRs
Kamal Hossain
C00000201
Blind Benchmark Predictions of NACOK Air Ingress Tests
Mary-Anne Brudieu
C00000210
PLANT DYNAMICS AND CONTROLLABILITY OF INDIRECT CYCLE HTR
yoshio shimakawa
C00000211
HTR PLANT DYNAMICS ANALYSES WITH MANTA AND ASURA CODES
dominique PETIT
C00000221
Modelling Heat and Fluid Flow through Packed Beds - A Density Based Vertex-Centered Methodology
Arnaud Malan
C00000222
Fundamental Derivation of Continuum Thermodynamic Governing Energy Equations and Order of Magnitude Estimates
C00000228
Validation of the CATHARE code against experimental data from Brayton cycle plants
Bentivoglio Fabrice
C00000253
DEVELOPMENT OF THE ANALYTIC NODAL METHOD IN CYLINDRICAL GEOMETRY FOR PBMR APPLICATION
Rian Prinsloo
D00000033
THE USAGE OF DYNAMIC SIMULATION FOR THE DEVELOPMENT OF ACTIVE MAGNETIC BEARINGS FOR THE GT-MHR-TYPE REACTOR
Frank Worlitz
D00000051
Design and optimization of a multistage turbine for a helium cooled reactor.
Rene Van den Braembussche
D00000052
Commissioning and Operation experience and safety experiment at HTR-10
Shouyin Hu
D00000056
EVALUATION OF ALTERNATE POWER CONVERSION UNIT DESIGNS FOR THE GT-MHR
Chandrakant Baxi
D00000067
A new ordered bed modular reactor concept
Jiafu Tian
D00000078
Thermal Assessment and Second Law Analysis of Indirect Brayton Power Cycles for High-Temperature Gas-Cooled Nuclear Reactors
Luis E. HERRANZ
D00000091
HPC: Loop for helium purification
Christian POLETIKO
D00000112
In Reactor Pressure Vessel Measurements for the PBMR DPP.
Gordon Procter
D00000121
Loading and unloading scheme of the ordered bed modular reactor
D00000167
Advanced High Temperature Concepts for Pressure-Tube Reactors, including Co-Generation and Sustainability
Romney Duffey
D00000189
THE FUEL HANDLING STORAGE SYSTEM (FHSS) MODEL FOR THE PBMR PLANT TRAINING SIMULATOR
D00000193
THE PBMR PLANT TRAINING SIMULATOR
E00000027
Technological Loops for H.T. Heat Exchangers Development
BERJON ALAIN
E00000038
Thermal and irradiation creep of advanced high temperature materials
Wolfgang Hoffelner
E00000060
Corrosion studies of the PBMR spent fuel tank material – aiming for 80 years life on carbon steel
Wim Fuls
E00000090
SiC encapsulation of (V)HTR components and waste by laser beam joining of ceramics
Juergen Knorr
E00000093
Evaluation of the Gamma-Irradiation Effects on the IG-110 Nuclear Graphite by Raman Spectroscopy, XRD and Hardness Measurement
Se-Hwan Chi
E00000100
Compact Heat Exchangers technologies for the recuperator application in a HTR with a direct cycle
Franck Pra
E00000101
Material degradation in high temperature, the AREVA-NP corrosion loop
Damien KACZOROWSKI
E00000102
Mechanical properties of extreme surface layer of Ni base alloys. in HTR environment.
E00000104
Development of an appropriate surveillance program for the reactor pressure vessel of an HTGR.
Kobus Smit
E00000106
Processing and characterization of β-SiC for GFR core components
Jean-Louis Seran
E00000107
Possibilities for the microstructural modelling of the irradiation properties of graphites for future High Temperature Reactors
Barry Marsden
E00000111
RAPHAEL Project: Materials development for the VHTR – results from HTR-M & HTR-M1 projects plus future RAPHAEL programme
Derek Buckthorpe
E00000114
RAPHAEL IP Project, VHTR component developments
Eric Breuil
E00000116
Development of 9-12Cr martensitic steels for future nuclear systems
Jean-Louis Séran
E00000132
Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR
Rainer Moormann
E00000143
High temperature corrosion of two structural nickel base alloys in the primary coolant helium of a VHTR
Celine CABET
E00000206
Modeling the Multiaxial Strength of Nuclear Graphite
Timothy Burchell
