Basic Studies in the Field of High-Temperature Engineering.

360 Pages·6.283 MB·English

by  OECD

Nuclear Science
Basic Studies in the Field of
High-temperature Engineering
Second Information Exchange Meeting
Paris, France
10-12 October 2001
Co-organised by the
Japan Atomic Energy Research Institute (JAERI)
NUCLEAR ENERGY AGENCY
ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT
ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT
Pursuant to Article 1 of the Convention signed in Paris on 14th December 1960, and which came into force on
30th September 1961, the Organisation for Economic Co-operation and Development (OECD) shall promote policies
designed:
− to achieve the highest sustainable economic growth and employment and a rising standard of living in
Member countries, while maintaining financial stability, and thus to contribute to the development of the
world economy;
− to contribute to sound economic expansion in Member as well as non-member countries in the process of
economic development; and
− to contribute to the expansion of world trade on a multilateral, non-discriminatory basis in accordance with
international obligations.
The original Member countries of the OECD are Austria, Belgium, Canada, Denmark, France, Germany, Greece,
Iceland, Ireland, Italy, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey, the United
Kingdom and the United States. The following countries became Members subsequently through accession at the dates
indicated hereafter: Japan (28th April 1964), Finland (28th January 1969), Australia (7th June 1971), New Zealand (29th
May 1973), Mexico (18th May 1994), the Czech Republic (21st December 1995), Hungary (7th May 1996), Poland (22nd
November 1996) and the Republic of Korea (12th December 1996). The Commission of the European Communities takes
part in the work of the OECD (Article 13 of the OECD Convention).
NUCLEAR ENERGY AGENCY
The OECD Nuclear Energy Agency (NEA) was established on 1st February 1958 under the name of the OEEC
European Nuclear Energy Agency. It received its present designation on 20th April 1972, when Japan became its first
non-European full Member. NEA membership today consists of 27 OECD Member countries: Australia, Austria, Belgium,
Canada, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Luxembourg,
Mexico, the Netherlands, Norway, Portugal, Republic of Korea, Spain, Sweden, Switzerland, Turkey, the United Kingdom
and the United States. The Commission of the European Communities also takes part in the work of the Agency.
The mission of the NEA is:
− to assist its Member countries in maintaining and further developing, through international co-operation, the
scientific, technological and legal bases required for a safe, environmentally friendly and economical use of
nuclear energy for peaceful purposes, as well as
− to provide authoritative assessments and to forge common understandings on key issues, as input to
government decisions on nuclear energy policy and to broader OECD policy analyses in areas such as energy
and sustainable development.
Specific areas of competence of the NEA include safety and regulation of nuclear activities, radioactive waste
management, radiological protection, nuclear science, economic and technical analyses of the nuclear fuel cycle, nuclear law
and liability, and public information. The NEA Data Bank provides nuclear data and computer program services for
participating countries.
In these and related tasks, the NEA works in close collaboration with the International Atomic Energy Agency in
Vienna, with which it has a Co-operation Agreement, as well as with other international organisations in the nuclear field.
© OECD 2002
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FOREWORD
In the field of basic research on materials pertinent to high-temperature and neutron irradiation
tests, great international interest exists concerning the study of irradiation effects, notably on advanced
ceramic and metallic materials and on the development of in-core instrumentation.
For this reason, the Nuclear Science Committee (NSC) of the OECD Nuclear Energy Agency
(NEA), along with the Japan Atomic Energy Research Institute (JAERI), organised the Second
Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering.
The meeting was held in Paris on 10-12 October 2001, and attended by 43 participants from eight
countries and two international organisations. A total of 28 papers were presented, including 26 orally,
dealing with recent progress in the following research domains:
• overviews of high-temperature engineering research in each country and organisation;
• improvement in material properties by high-temperature irradiation;
• development of in-core material characterisation methods and irradiation facilities;
• basic studies on the behaviour of irradiated graphite/carbon and ceramic materials including
their composites under both operation and storage conditions;
• basic studies on high-temperature, gas-cooled reactor (HTGR) fuel fabrication and performance.
The final session was dedicated to discussing possible co-operative works to be undertaken within
the framework of the OECD/NEA Nuclear Science Committee. It was recommended that a further
information exchange meeting, dealing with possible international collaboration as well as some of the
topics addressed here, should be planned to be held in Oarai, Japan in 2003.
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TABLE OF CONTENTS
Foreword............................................................................................................................................ 3
Executive Summary............................................................................................................................ 9
OPENING SESSION....................................................................................................................... 11
C. Kessler
Welcome Address..................................................................................................... 13
S. Ishino
Opening Address...................................................................................................... 15
SESSION I Overviews of High-temperature Engineering Research in Each
Country and Organisation..................................................................................... 17
Chair: W. von Lensa
J. Martín-Bermejo, M. Hugon, G. Van Goethem
Research Activities on High-temperature Gas-cooled Reactors (HTRs)
in the 5th EURATOM RTD Framework Programme................................................ 19
J. Kendall, M. Methnani
Update on IAEA High-temperature Gas-cooled Reactor Activities......................... 31
Y. Sudo, T. Hoshiya, M. Ishihara, T. Shibata, S. Ishino,
T. Terai, T. Oku, Y. Motohashi, S. Tagawa, Y. Katsumura,
M. Yamawaki, T. Shikama, C. Mori, H. Itoh, S. Shiozawa
Present Status of the Innovative Basic Research on High-temperature
Engineering using the HTTR.................................................................................... 39
J.C. Kuijper, A.I. van Heek, J.B.M. de Haas,
R. Conrad, M. Burghartz, J.L. Kloosterman
Present Status in the Netherlands of Research Relevant to High
Temperature Gas-cooled Reactor Design................................................................. 51
D. Hittner, F. Carré, J. Roualt
Current Status of High-temperature Engineering Research in France...................... 69
K. Kugeler, P-W. Phlippen, M. Kugeler, H. Hohn
Overview of High-temperature Reactor Engineering and Research......................... 77
A.J. Wickham, I.M. Coe, P.J. Bramah, T.J. Abram
The Contribution of UK Organisations in the Development of New
High-temperature Reactors....................................................................................... 91
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SESSION II Improvement in Material Properties by High-temperature Irradiation........... 101
Chairs: T. Shikama, B. Marsden
H. Kurishita
Improvement in Ductility of Refractory Metals by Neutron Irradiation.................. 103
M. Ishihara, T. Shibata, S. Baba, T. Hoshiya,
C. Wan, Y. Motohashi
Effects of Superplastic Deformation on Thermal and Mechanical
Properties of 3Y-TZP Ceramics (Review)................................................................ 113
C.H. Wu
Development of an Innovative Carbon-based Ceramic Material:
Application in High-temperature, Neutron and Hydrogen Environment................. 125
T. Nitawaki, Y. Kato
A Carbon Dioxide Partial Condensation Cycle for
High-temperature Reactors....................................................................................... 133
SESSION III Development of In-core Material Characterisation Methods
and Irradiation Facility.......................................................................................... 143
Chairs: C. Vitanza, M. Yamawaki
T. Shibata, T. Kikuchi, S. Miyamoto, K. Ogura, Y. Ishigaki
Development of the I-I Type Irradiation Equipment for the HTTR......................... 145
T. Shikama, M. Narui, T. Kakuta, M. Ishitsuka,
K. Hayashi, T. Sagawa, T. Hoshiya
Application of Optical Diagnostics in High-temperature
Gas-cooled Systems.................................................................................................. 153
C. Mori, A. Uritani, T. Kakuta, M. Katagiri, T. Shikama,
M. Nakazawa, T. Iguchi, J. Kawarabayashi, I. Kimura,
H. Kobayashi, S. Hayashi
Measurement Method of In-core Neutron and Gamma-ray
Distributions with Scintillator Optical Fibre Detector and
Self-powered Detector.............................................................................................. 161
C. Vitanza
Development of In-core Test Capabilities for Material Characterisation................. 167
G-N. Luo, T. Terai, M. Yamawaki, K. Yamaguchi
Application of Work Function Measuring Technique to Monitoring/
Characterisation of Material Surfaces under Irradiation........................................... 177
M. Narui, T. Shikama, M. Yamasaki, H. Matsui
Development of High-temperature Irradiation Techniques
Utilising the Japan Materials Testing Reactor.......................................................... 191
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SESSION IV Basic Studies on Behaviour of Irradiated Graphite/Carbon and
Ceramic Materials Including their Composites under both Operation
and Storage Conditions.......................................................................................... 201
Chairs: B. McEnaney, A. Wickham
D. Buckthorpe, R. Couturier, B. van der Schaaf, B. Riou,
H. Rantala, R. Moormann, F. Alonso, B-C. Friedrich
Investigation of High-temperature Reactor (HTR) Materials................................... 203
W.R. Taylor, M.D. Warner, G.B. Neighbour, B. McEnaney, S.E. Clift
Radially Keyed Graphite Moderator Cores: An Investigation
into the Stability of Finite Element Models.............................................................. 215
M. Ishihara, T. Shibata, T. Takahashi, S. Baba, T. Hoshiya
Understanding of Mechanical Properties of Graphite on the
Basis of Mesoscopic Microstructure (Review)......................................................... 225
R. Moormann, H-K. Hinssen
Advanced Graphite Oxidation Models..................................................................... 243
B.J. Marsden, S.D. Preston
Irradiation Creep in Graphite – A Review................................................................ 255
G.B. Neighbour, P.J. Hacker
An Analysis of Irradiation Creep in Nuclear Graphites............................................ 269
B. McEnaney, A.J. Wickham, M. Dubourg
Planning for Disposal of Irradiated Graphite: Issues for the New
Generation of HTRs.................................................................................................. 281
P.J. Hacker, B. McEnaney, A.J. Wickham, G. Haag
Status of IAEA International Database on Irradiated Graphite
Properties with Respect to HTR Engineering Issues................................................ 293
SESSION V Basic Studies on HTGR Fuel Fabrication and Performance.............................. 305
Chairs: J. Kuijper, R. Moormann
L. Thomé, A. Gentils, F. Garrido, J. Jagielski
Evidence of Dramatic Fission Product Release from Irradiated
Nuclear Ceramics...................................................................................................... 307
A. Chernikov, V. Eremeev, V. Ivanov
Method of Reactor Tests of HTGR Fuel Elements at an Impulse Loading.............. 315
D. Petti, G. Miller, J. Maki, D. Varacalle, J. Buongiorno
Gas Reactor TRISO-coated Particle Fuel Modelling Activities
at the Idaho National Engineering and Environmental Laboratory.......................... 323
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Session Summaries........................................................................................................................... 339
Chair: Y. Sudo
Recommendations.............................................................................................................................. 349
List of Participants.............................................................................................................................. 351
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EXECUTIVE SUMMARY
Co-organised by the OECD Nuclear Energy Agency and Japan Atomic Energy Research Institute,
the Second Information Exchange Meeting on Basic Studies in the Field of High-temperature
Engineering was a great success. It was held in Paris on 10-12 October, 2001, and its main topics
were:
• The exchange of information with regard to the latest activities for studying high-temperature
irradiation-induced damage/effects in advanced materials and fuels.
• The discussion of the possibility of co-operative studies in the field of high-temperature
engineering using the HTTR and other research reactors for irradiation research programmes
in the framework of international co-operation organised by the OECD/NEA/NSC.
• The development of a framework of possible international co-operative activities concerning
topics of interest.
• The proposal/recommendation of possible co-operative works to be undertaken within a
framework or under the auspices of the OECD/NEA/NSC.
Forty-three participants gathered together from eight countries and two international organisations.
Twenty-eight papers were submitted, of which 26 were oral presentations dealing with recent progress
and national/international programmes in the field of high-temperature engineering. The papers were
presented in five sessions as follows:
• Session I: Overviews of high-temperature engineering research in each country and
organisation (six papers).
• Session II: Improvement in material properties by high-temperature irradiation(four papers).
• Session III: Development of in-core material characterisation methods and irradiation facilities
(six papers).
• Session IV: Basic studies on the behaviour of irradiated graphite/carbon and ceramic materials
including their composites under both operation and storage conditions(eight papers).
• Session V: Basic studies on HTGR fuel fabrication and performance(two papers).
In Session I, the current status of high-temperature engineering research in the EC, Japan, the
Netherlands, France, Germany and the United Kingdom were summarised.
In Session II, examples of improvement in material properties through high-temperature
irradiation, the effects of superplastic deformation on thermal and mechanical properties of 3Y-TZP
ceramics and the development of an innovative carbon-based ceramic material and carbon dioxide
partial condensation cycle were presented.
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