IAEA-TECDOC-1496 Thermophysical properties database of materials for light water reactors and heavy water reactors Final report of a coordinated research project 1999–2005 June 2006 IAEA-TECDOC-1496 Thermophysical properties database of materials for light water reactors and heavy water reactors Final report of a coordinated research project 1999–2005 June 2006 The originating Section of this publication in the IAEA was: Nuclear Power Technology Development Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria THERMOPHYSICAL PROPERTIES DATABASE OF MATERIALS FOR LIGHT WATER REACTORS AND HEAVY WATER REACTORS IAEA, VIENNA, 2006 IAEA-TECDOC-1496 ISBN 92–0–104706–1 ISSN 1011–4289 © IAEA, 2006 Printed by the IAEA in Austria June 2006 FOREWORD The IAEA Coordinated Research Project (CRP) on the Establishment of a Thermo-physical Properties Database for Light Water Reactors (LWRs) and Heavy Water Reactors (HWRs) started in 1999. It was included in the IAEA’s Nuclear Power Programme following endorsement in 1997 by the IAEA’s Technical Working Groups on Advanced Technologies for LWRs and HWRs (the TWG-LWR and the TWG-HWR). Furthermore, the TWG on Fuel Performance and Technology (TWG-FPT) also expressed its support. This CRP was conducted as a joint task within the IAEA’s project on technology development for LWRs and HWRs in its nuclear power programme. Improving the technology for nuclear reactors through better computer codes and more accurate materials property data can contribute to improved economics of future plants by helping to remove the need for large design margins, which are currently used to account for limitations of data and methods. Accurate representations of thermo-physical properties under relevant temperature and neutron fluence conditions are necessary for evaluating reactor performance under normal operation and accident conditions. The objective of this CRP was to collect and systematize a thermo-physical properties database for light and heavy water reactor materials under normal operating, transient and accident conditions and to foster the exchange of non-proprietary information on thermo-physical properties of LWR and HWR materials. An internationally available, peer reviewed database of properties at normal and severe accident conditions has been established on the Internet. This report is intended to serve as a useful source of information on thermo-physical properties data for water cooled reactor analyses. The properties data have been initially stored in the THERSYST data system at the University of Stuttgart, Germany, which was subsequently developed into an internationally available Internet database named THERPRO at Hanyang University, Republic of Korea. Appreciation is expressed to the institutes participating in the CRP. In particular, appreciation is expressed to P.M. Mathew, Atomic Energy of Canada Ltd, for serving as chairman of the CRP and to J.K. Fink who has been working closely with the IAEA during the past several years as a consultant from Argonne National Laboratory on the planning and conduct of this CRP. The IAEA is particularly grateful to the Government of the Republic of Korea for extra-budgetary funds to prepare and maintain the Internet database. The IAEA staff members responsible for this publication were Y.-E. Kim, J.-W. Park and J. Cleveland of the Division of Nuclear Power. EDITORIAL NOTE The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA. CONTENTS 1.INTRODUCTION ..............................................................................................................................1 2. OBJECTIVE AND SCOPE ...........................................................................................................3 3. ACTIVITIES AND CONTRIBUTIONS OF PARTICIPATING INSTITUTES ..........................4 3.1. Atomic Energy of Canada Limited......................................................................................4 3.2. Nuclear Power Institute, China............................................................................................4 3.3. University of West Bohemia, Czech Republic ....................................................................4 3.4. CEA Cadarache, France.......................................................................................................4 3.5. Bhabha Atomic Research Centre, India...............................................................................4 3.6. Seoul National University, Republic of Korea ....................................................................5 3.7. Hanyang University, Republic of Korea..............................................................................5 3.8. Institute for High Energy Densities, Russian Federation.....................................................5 3.9. Institute of Physics and Power Engineering, Russian Federation........................................5 3.10. J.K. Fink (Argonne National Laboratory, USA)..................................................................5 4. PROCEDURE FOR ASSESSMENT AND PEER REVIEW........................................................6 4.1. Assessment guidelines .........................................................................................................6 4.1.1. Collect data...........................................................................................................6 4.1.2. Convert to ITS-90 temperature scale....................................................................6 4.1.3. Review data for consistency, reliability, and systematic errors............................7 4.1.4. Review all available equations from other assessments.......................................7 4.1.5. Statistical analysis of all data ...............................................................................7 4.1.6. Error analysis and uncertainties............................................................................8 4.1.7. Submit assessment for peer review ......................................................................8 4.2. Temperature conversion ......................................................................................................9 4.2.1. Comparison between ITS-27 and IPTS-48...........................................................9 4.2.2. Comparison between IPTS-48 and IPTS-68 ......................................................10 4.2.3. Comparison between IPTS-68 and ITS-90.........................................................14 4.2.4. Conversion of the thermo-physical property values to the new temperature scale ITS-90....................................................................................19 4.2.5. Graphic representation of temperature differences and derivatives ...................20 4.2.6. General recommendations..................................................................................21 5. SUMMARY OF DATA USED IN ASSESSMENT....................................................................23 6. THERMO-PHYSICAL PROPERTIES OF MATERIALS..........................................................25 6.1. Fuel materials.....................................................................................................................25 6.1.1. Uranium dioxide (UO2) ......................................................................................25 6.1.2. Thermal conductivity of irradiated UO2...........................................................143 6.1.3. Thermal properties of (U, Gd)O2......................................................................152 6.1.4. ThO2 , (Th1-y1Uy) O2 and (Th1-yPuy) O2 properties........................................... 182 6.2. Cladding and pressure tube materials ..............................................................................225 6.2.1. Zircaloy ............................................................................................................225 6.2.2. Thermal conductivity of Zr-1%Nb...................................................................289 6.2.3. Thermal conductivity of Zr-2.5%Nb................................................................293 6.3. Absorber materials and their oxides ................................................................................296 6.3.1. Hafnium............................................................................................................296 6.3.2. Hafnium dioxide...............................................................................................307 6.4. Structural materials..........................................................................................................314 6.4.1. Russian steels ...................................................................................................314 6.4.2. Thermal conductivity of alloy 600 and 800 .....................................................324 6.5. Zirconium ........................................................................................................................328 6.5.1. Enthalpy and heat capacity...............................................................................328