Thermophysical Properties of Materials for Water Cooled Reactors
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XA9744411 IAEA-TECDOC-949 Thermophysical properties of materials for water cooled reactors June 1997 ¥DL 2 8 fe 2 Q The IAEA does not normally maintain stocks of reports in this series. However, microfiche copies of these reports can be obtained from IN IS Clearinghouse International Atomic Energy Agency Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna, Austria Orders should be accompanied by prepayment of Austrian Schillings 100,- in the form of a cheque or in the form of IAEA microfiche service coupons which may be ordered separately from the IN IS Clearinghouse. IAEA-TECDOC-949 Thermophysical properties of materials for water cooled reactors WJ INTERNATIONAL ATOMIC ENERGY AGENCY /A\ June 1997 The originating Section of this publication in the IAEA was: Nuclear Power Technology Development Section International Atomic Energy Agency Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna, Austria THERMOPHYSICAL PROPERTIES OF MATERIALS FOR WATER COOLED REACTORS IAEA, VIENNA, 1997 IAEA-TECDOC-949 ISSN 1011-4289 ©IAEA, 1997 Printed by the IAEA in Austria June 1997 FOREWORD The IAEA Co-ordinated Research Programme (CRP) to establish a thermophysical properties data base for light and heavy water reactor materials was organized within the framework of the IAEA's International Working Group on Advanced Technologies for Water Cooled Reactors. The work within the CRP started in 1990. The objective of the CRP was to collect and systematize a thenmophysical properties data base for light and heavy water reactor materials under normal operating, transient and accident conditions. The important thermophysical properties include thermal conductivity, thermal diffusivity, specific heat capacity, enthalpy, thermal expansion and others. These properties as well as the oxidation of zirconium-based alloys, the thermophysical characteristics of high temperature concrete-core melt interaction and the mechanical properties of construction materials are presented in this report. The thermophysical properties of a broad spectrum of reactor and construction materials, such as fuel cladding, absorber, structural materials, concretes, light and heavy water and gases, are presented over a wide range of temperature. Experimental methods and the test facilities used for the thermophysical property measurements are described in supplements. It is hoped that this report will serve as a useful source of thermophysical properties data for water cooled reactor analyses. The properties data are maintained on the THERSYST system at the University of Stuttgart, Germany and are internationally available. The IAEA staff members responsible for this activity were V. Krett and J. Cleveland of the Nuclear Power Technology Development Section, Division of Nuclear Power and the Fuel Cycle. EDITORIAL NOTE In preparing this publication for press, staff of the IAEA have made up the pages from the original manuscripts). The views expressed do not necessarily reflect those of the governments of the nominating Member States or of the nominating organizations. Throughout the text names of Member States are retained as they were when the text was compiled. 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 7 2. OBJECTIVE AND SCOPE OF THE CO-ORDINATED RESEARCH PROGRAMME 8 3. ACTIVITIES AND CONTRIBUTIONS OF PARTICIPATING INSTITUTIONS 9 3.1. Activities of participating institutions 9 3.2. Contributions of participating institutions to the CRP 10 4. THERMOPHYSICAL PROPERTIES OF SOLID MATERIALS 13 4.1. Fuel materials 16 4.1.1. Uranium 16 4.1.2. Uranium-aluminium alloys 28 4.1.3. Uranium dioxide 33 4.1.4. UO2-PuO2 mixture 50 4.1.5. UO2-Gd2O3 mixture 61 4.2. Cladding materials 67 4.2.1. Zirconium based alloys 67 4.2.2. Oxidation properties of zirconium based alloys 85 4.2.3. Ni-Cr-based alloys 100 4.2.4. Zirconium dioxide 106 4.3. Absorber materials 118 4.3.1. Boron carbide 118 4.3.2. Silver-indium-cadmium alloy 128 4.4. Structural materials 132 4.4.1. Austenitic stainless steel 132 4.4.2. Martensitic stainless steel 141 4.5. Concretes, including erosion in concrete-core melt interaction 147 4.5.1. Introduction 147 4.5.2. Refractory concrete properties 147 4.5.3. Investigation of melt-concrete interaction thermophysics 150 4.5.4. Conclusions 151 5. THERMOPHYSICAL PROPERTIES OF LIGHT AND HEAVY WATER 159 5.1. Introduction 159 5.2. Literature survey 159 5.3. Evolution of IAPS formulations 159 5.4. Thermodynamic properties of heavy water 161 5.5. Thermal conductivity of heavy water 163 5.6. Viscosity of heavy water 164 5.7. Saturation properties of heavy water 164 5.8. Results and discussions 164 6. THERMOPHYSICAL PROPERTIES OF GASES 169 6.1. The properties of hydrogen 169 6.2. The properties of helium 171 6.3. The properties of krypton 173 6.4. The properties of xenon 175 6.5. The properties of mixtures of inert gases 178 7. CONCLUSIONS 186 SUPPLEMENTS 187 51 Oxidation kinetics of the zirconium based alloys 187 52 Concrete-core melt interaction investigation 197 53 Thermal conductivity of U-Al alloy and UO2 201 54 Mechanical properties of steels 218 55 THERSYST data base 223 56 TPSYS - Thermophysical properties data base for reactor materials 226 57 Thermophysical properties of uranium (experimental data) 233 58 Thermophysical properties of light water and steam 243 59 IAPS formulations for themophysical properties of light water and steam 262 ABBREVIATIONS 277 CONTRIBUTORS TO DRAFTING AND REVIEW 279 1. INTRODUCTION The Co-ordinated Research Programme (CRP) on "Thermophysical Properties Data Base for Light and Heavy Water Reactor Materials" was organized in the framework of the IAEA's International Working Group on Advanced Technologies for Water Cooled Reactors (IWGATWR). This IWG serves as a forum for exchange of information on national programmes, provides advice to the IAEA on international cooperative activities in advanced technologies in water cooled reactors, and supports the conduct of these activities. Institutes which have participated in this CRP are: Institute of Atomic Energy, Beijing, China Nuclear Research Institute, Rez, Czech Republic University of Stuttgart, Stuttgart, Germany Bhabha Atomic Research Centre, Mumbai, India High Energy Density Research Centre, Russian Academy of Science, Moscow, Russian Federation Institute of Physics and Power Engineering, Obninsk, Russian Federation Boris Kidric Institute of Nuclear Sciences, Yugoslavia (through 1991). The report developed by the CRP has been independently reviewed in a collaborative effort between the IAEA and the US DOE's International Nuclear Safety Center at Argonne National Laboratory (ANL), and between the IAEA and the Atomic Energy of Canada, Ltd. (AECL). These independent technical reviews have been carried out to ascertain that there are no inconsistencies in related parameters and that the presented properties are consistent with accepted data. Furthermore, additional data have been provided to the CRP by ANL and by AECL. The data base on reactor materials presented in this report, except for the data base for light and heavy water, is incorporated into the existing THERSYST data base system established at Stuttgart University in Germany. This database is described in Supplement S5. This data base can be obtained through a special request addressed to the Stuttgart University. The description of the Chinese data base TPSYS is presented in Supplement S6. Regarding future nuclear power, a key conclusion of the IAEA Symposium on Advanced Nuclear Power Systems (Republic of Korea, October 1993) was that advanced water cooled reactors currently undergoing development and design review will, in the short and medium term, be the main contributor to any revival of nuclear power. While the early development of nuclear power was conducted to a large extent on a national basis, the cooperation demonstrated by institutes contributing to establishment of this thermophysical properties data base is an example of the increased level of international cooperation in reactor technology. 2. PURPOSE, OBJECTIVES AND SCOPE OF THE CO-ORDINATED RESEARCH PROGRAMME The objective of the CRP has been to collect and systematize a thermophysical properties data base for light and heavy water reactor materials under normal operating, transient and accident conditions. The materials properties considered include those needed for light and heavy water reactor operational and safety assessments. The materials have been grouped within the following categories: nuclear fuels, cladding materials, absorber materials, structural materials, coolants, gases. The thermophysical properties included in the database are: thermal conductivity, thermal diffusivity, specific heat, enthalpy, heat of melting, coefficient of thermal expansion (linear for solids, volume coefficient for fluids), emittance, density (and porosity, as a parameter defining sintered materials), equation of state. The data on thermal conductivity, thermal diffusivity, coefficient of thermal expansion, and emittance of solid materials were collected from room temperature to their melting points. The specific heat, enthalpy,