HTGR Knowledge Base

HTR-2002: Conference on High Temperature Reactors

Proceedings of the Conference on High Temperature Reactors, Petten, NL, April 22-24, 2002
Organized by HTR-TN in cooperation with the European Nucler Society (ENS) and the IAEA

International Atomic Energy Agency, Vienna (Austria), HTR-2002

Abstract

A lot of recent events show an increasing world-wide interest for High Temperature Reactors (HTR). In 1998, the first prototype HTR was started in Japan. In December 2000, there was a first criticality of the HTR10 prototype in China. The MTGHR project to build HTR reactors that burn plutonium is now more and more active, with collaborations between the US, Russia and other partners. A consortium of organizations from South-Africa, the UK and US, led by ESKOM is working very actively to build a new reactor in the near future.

In Europe, a network called HTR-TN has been created, so that collaborators can work on HTR technology. As there is an intense international collaboration in HTR projects, it was deemed necessary by the scientific community to establish a regular topical meeting dedicated to the subject.

This meeting, called HTR 2002, is intended to be the first of a series of annual meetings dedicated to this emergent technology.

view the full text of this conference report (format: PDF, size= 13463kB, 303 pages)

Articles

Chinese Point and Status
Y. Xu, INET, Tsinghua University, China

The GTHMR Project
A. Kiryushin, N. G. Kodochigov, OKB Mechanical Engineering, Russia

Key Differences in the Fabrication of U. S. and German TRISO-Coated Particle Fuel, and their Implications on Fuel Performance
D. A. Petti, J. Bongiorno, J. T. Maki and G. K. Miller, Idaho National Engineering and Environmental Laboratory, USA

Microspheres of UO2, THO2 and PUO2 for the High Temperature Reactor
E. Brandau, Brace GmbH, Germany

Development of an Integrated Performance Model for TRISO-Coated Gas Reactor Particle Fuel
G. K. Miller, D. A. Petti and J. T. Maki, Idaho National Engineering and Environmental Laboratory, USA

Prospective Studies of HTR Fuel Cycles Involving Plutonium
B. Bonin and D. Grenache, Cogema, F. Carré, d. Damian and J. Y. Doriath, CEA Direction de l Energie Nucléaire, France

Examination of the Potential for Diversion or Clandestine Dual Use of a Pebble-Bed reactor to produce Plutonium
A. Ougouag, W. K. Terry and H. D. Gougar, Idaho National Engineering and Environmental Laboratory, USA

Deep Burn Transmutation of Nuclear Waste
C. Rodriguez, A. Baxter and D. McEachern, General Atomics, Francesco Venneri, Los Alamos National Laboratory and General Atomics and D. Williams, Oak Ridge National Laboratory, USA

Analysis of the European Results on the HTTR’s Core Physics Benchmarks
X. Raepsaet, F. Damian, CEN Saclay, France, U. A. Ohlig, H. J. Brockmann, Research Centre Jülich, Germany, J. B. M. De Haas, NRG/Petten and E. M. Wallerboss, Interfaculty Reactor Institute, Delft, The Netherlands

Investigation of Criticality Parameters of High Temperature Reactors at the Kurchatov Institute’s ASTRA Critical Facility
N. E. Kukharkin, E. S. Glushkov, G. V. Kompaniets, V. A. Lobyntsev, D. N. Polyakov, O. N. Smirnov, Institute of Nuclear Reactors, RRC Kurchatov Institute, Russia

Matrix Formulation of Pebble Circulation in the PEBBED Code
H. D. Gougar, W. K. Terry and A. J. Ougouag, Idaho National Engineering and Environmental Laboratory, USA

Physics Studies for a Particle-Bed Gas Cooled Fast Reactor Core Design
T. A. Taiwo, M. Fatone, G. Palmiotti and R. N. Hill, Reactor Analysis and Engineering Division, Argonne National Laboratory, USA

An Evaluation of the Control Rod Modelling Approach used in VSOP by Comparing its Results to the Experiments Performed in the ASTRA Critical Facility
F. Reitsma, D. Naidoo and Z. Karriem, Radiation and Reactor Theory, NECSA, Pretoria, South Africa

Creation of the Equilibrium Core PBMR ORIGEN-S Cross Section Library
C. C. Stoker, F. Reitsma and Z. Karriem, Radiation and Reactor Theory, NECSA, Pretoria, South Africa

HTR Core Physics Analysis at NRG
J. C. Kuiper, J. B. M. de Haas and J. Oppe, Fuels, Actinides & Isotopes Department, NRG, The Netherlands

Three-Dimensional Numerical Simulation of Flow and Heat Transport in a High-Temperature Reactor
S. Becker and E. Laurien, Institute for Nuclear Technology & Energy Systems, Germany (IKE), University of Stuttgart, Germany

Decay heat removal by passive means in case of a block type HTR reactor core-CFD Analysis
A. Woaye-Hune and S. Ehster, FRAMATOME-ANP, France

Thermal Hydraulic Simulations on High Temperature Reactors
N. Tauveron, M. Elmo, O. Cioni, T. Chataing, CEA/Grenoble, France

Steady-State and Accident Analyses of PBMR with the Computer Code SPECTRA
M. M. Stempniewicz, NRG/Arnhem, The Netherlands

Design of a Physical Model of the PBMR with the Aid of Flownet
G. P. Greyvenstein and P. G. Rousseau, Department of Mechanical Engineering, Potchefstroom University, South Africa

Flow Distribution of Pebble Bed High Temperature Gas Cooled Reactors Using Large Eddy Simulation
Y.A Hassan and G. Gokhan Yesilut, Department of Nuclear Engineering, Texas A&M University, USA

GTHTR300 System Design Features and Performance
X. Yan, K. Kunitomi, T. Nakata and S. Shiozawa, Japan Atomic Energy research Institute, Japan

Design of a Power Conversion System for an Indirect Cycle, Helium Cooled Pebble Bed Reactor System
C. Wang, R. G. Ballinger and P. W. Stahle, Department of Nuclear Engineering, Massachusetts Institute of Technology, USA

Thermodynamic assessment of plant efficiencies for HTR power conversion
W. Fröhling, H. M. Unger, Research Centre Jülich, Germany and Y. Dong, Institute of Nuclear Energy Technology, Tsinghua University, China

ACACIA-Indirect: A Small Scale Nuclear Plant for New Markets
D. F. Da Cruz, J. B. M. de Haas and A. I. Van Heek, NRG/Petten, The Netherlands

Burn-up Dependent Core Neutronic Analysis for PBMR
Y. Cecen, U. Colak and O. K. Kadiroglu, Department of Nuclear Engineering, Hacettepe University, Turkey

Operating Experience with the Dragon High Temperature Reactor Experiment
R. A. Simon, DRAGON Operation Branch/EC (retired), Belgium and P. D. Capp, DRAGON Operations Branch/UKAEA (retired), United Kingdom

The relation between irradiation induced dimensional change and the coefficient of thermal expansion: A new look
G. Hall, B. J. Marsden, A. Fok and J. Smart, Nuclear Graphite Technology Group, University of Manchester, United Kingdom

Studies on Air Ingress for Pebble Bed Reactors
R. L. Moore, C. H. Oh, B. J. Merrill and D. A. Petti, Idaho National Engineering and Environmental Laboratory, USA

Nuclear Emergency Planning and Preparedness for the HTR-10
J. Qu and Z. Wu, Institute of Nuclear Energy Technology, Tsinghua University, China

HTR-E Project: High Temperature Components and Systems
E. Beruil, FRAMATOME-ANP, France and R. Exner, Borsig Energy GmbH, Germany

The measurement of burn-up level in HTR-10
L. Zhengpei, I. Wenfeng, H. Song and L. Fu, Institute of Nuclear Energy Technology, Tsinghua University, China

Overview of LEI investigations on heat transfer and flow structure in gas- cooled packed beds of spheres and channels
J. Vilemas, E. Uspurus, S. Rimkevicius, A. Kaliatka, P. Pabarcius, Lithuanian Energy Institute, Lithuania

A High Temperature Reactor for Ship Propulsion
P. Lobet, R. Seigel, Ecole de Application Militaries de l Energie Atomique, France and A. C. Thompson, R. J. Beadnell and P. A. Beeley, HMS Sultan, Nuclear Department, United Kingdom

The Numerical Determination of the Variation in the Porosity of Pebble-Bed Core
C. du Toit, School for Mechanical and Materials Engineering, Potchefstroom University, South Africa

Analysis of Operational Transients in a Fluidized Bed Nuclear Reactor
A. Agung, D. Lathouwers, T. H. J. J. van der Hagen, H. van Dam, Interfaculty Research Institute, Delft University of Technology, The Netherlands and C. C. Pain, C. R. E. Oliviera, A. J. H. Goddard, Department of Earth Science and Engineering, Imperial College of Science, Technology and Medicine, United Kingdom

Conceptual design of a passive, inherently safe emergency shutdown rod for High Temperature Reactor applications
A. M. Ougouag, W. K. Terry and R. R. Schultz, Idaho National Engineering and Environmental Laboratory, USA

An In-Depth Study on Oscillation Peculiarities by Step-Input of Reactivity and Frequency of Helium Fan’s Transducer of 10 MW High Temperature Gas-Cooled Reactor and its Control Strategy
X. Huang, Institute of Nuclear Energy Technology, Tsinghua University, China

Stress and Seismic Calculation of HTR-10 SG Accident Discharge System
J. Gong, J. Fu and S. Yu, Institute of Nuclear Energy Technology, Tsinghua University, China

Modelling of the HTTR in Flownet
P. Rousseau and G. P. Greyvenstein, School of Mechanical & Materials Engineering, Faculty of Engineering, Potchefstroom University, South Africa

EC-Funded Project (HTR-L) for the Definition of a European Safety Approach for HTR’s
S. Ehster, FRAMATOME-ANP, France, M. T. Dominguez, Empresarios Agrupados Internacional SA, I. Coe, NNC Ltd., United Kingdom, G. Brinkmann, FRAMATOME-ANP GmbH, Germany, W. von Lensa, Research Centre Jülich, Germany, W. van der Mheen, Nuclear Research and Consultancy Group, The Netherlands, C. Allessandroni, Ansaldo Nucleare, Italy and J. Pirson, Tractebel Energy Engineering, Belgium

Graphite Materials Testing in the ATR for Lifetime management of Magnox Reactors
S. B. Grover, Idaho National Engineering and Environmental Laboratory, USA and M. P. Metcalfe, British Nuclear Fuels plc, Research and Technology, Berkeley Centre, United Kingdom

Energy Storage and Release Calculations for HTR-10 Reactor
U. Colak, H. Dikmen and U. E. Sikik, Nuclear Energy Department, Hacettepe University, Turkey

The Behaviour of Fission Products in the HTGR Fuel Irradiated in the IVV-2M Reactor
K. N. Koscheyev, Sverdlovsk Branch of R&D Institute of Power Engineering, Zarechny and A. S. Chernikov, RPA Lutch, Russia

Thermodynamic Analysis of PBMR Plant
S. Sen and O. K. Kadiroglu, Nuclear Energy Department, Hacettepe University, Turkey

Mathematical Model and Computer Code for Coated Particles Performance at normal operating conditions
I. Golubev, I. Kadarmetov, V. Makarov, All-Russian Research Institute of Inorganic Materials (VNIINM), Moscow