LEADER 04254nam 22004933 450 001 9911006769503321 005 20230802010011.0 010 $a1-5231-3009-1 010 $a1-283-98861-5 035 $a(CKB)2550000001006204 035 $a(MiAaPQ)EBC5266215 035 $a(Au-PeEL)EBL5266215 035 $a(CaONFJC)MIL430111 035 $a(OCoLC)1027169092 035 $a(Exl-AI)5266215 035 $a(EXLCZ)992550000001006204 100 $a20210901d2012 uy 0 101 0 $aeng 135 $aurcnu|||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aLiquid Metal Coolants for Fast Reactors (Reactors Cooled by Sodium, Lead and Lead-bismuth Eutectic) 205 $a1st ed. 210 1$aLanham :$cInternational Atomic Energy Agency,$d2012. 210 4$dİ2012. 215 $a1 online resource (95 pages) 311 08$a92-0-131810-3 327 $aCover -- FOREWORD -- CONTENTS -- 1. INTRODUCTION -- 1.1. BACKGROUND -- 1.2. SCOPE AND OBJECTIVES -- 1.3. STRUCTURE -- 2. SHORT HISTORY OF NUCLEAR POWER DEVELOPMENT -- 3. PHYSICAL AND CHEMICAL PROPERTIES OF COOLANTS (SODIUM, LEAD AND LEAD-BISMUTH ALLOY) -- 3.1. LIQUID METAL DEVELOPMENT (SHORT HISTORY) -- 3.2. PHYSICAL PROPERTIES -- 3.3. CHEMICAL PROPERTIES -- 4. COMPARISON OF DIFFERENT SODIUM AND LEAD COOLANT TECHNOLOGIES -- 4.1. BACKGROUND -- 4.2. SODIUM TECHNOLOGY -- 4.3. LEAD AND LEAD-BISMUTH TECHNOLOGY -- 4.4. CONCLUSION -- 5. THERMOHYDRAULICS OF REACTOR CORE -- 5.1. HYDRODYNAMICS -- 5.2. HEAT TRANSFER -- 5.3. CONCLUSIONS -- 6. COOLANT RADIOACTIVITY -- 6.1. SODIUM RADIOACTIVITY -- 6.2. LEAD AND LEAD-BISMUTH RADIOACTIVITY -- 6.3. CONCLUSIONS -- 7. LIQUID METAL COOLED FAST REACTOR TECHNOLOGY DEVELOPMENT -- 7.1. INTRODUCTION -- 7.2. OBJECTIVES AND CHALLENGES FOR THE DEVELOPMENT OF ADVANCED LIQUID METAL COOLED FAST REACTOR -- 7.3. FEATURES OF LIQUID METAL COOLED FAST REACTORS -- 7.4. CONCLUSION -- 8. MODULAR LEAD-BISMUTH COOLED SMALL SIZE FAST REACTORS -- 8.1. INTRODUCTION -- 8.2. EXPERIENCE AND OPPORTUNITY TO USE LEAD-BISMUTH EUTECTIC ALLOY AS A FAST REACTORS' COOLANT -- 8.3. BRIEF DESCRIPTION OF EXPERIENCE WITH LEAD-BISMUTH EUTECTIC APPLICATIONS -- 8.4. REACTOR INSTALLATION SVBR-75/100 -- 8.5. BASIC CONCEPTS OF THE NUCLEAR POWER PLANT BASED ON SVBR-75/100 -- 8.6. CONCLUSIONS -- 9. LIQUID LEAD COOLED FAST REACTORS -- 9.1. THE LEAD COOLED FAST REACTOR CONCEPT -- 9.2. NUCLEAR FUEL CYCLE CONCEPT -- 9.3. BREST CONCEPT -- 9.4. BREST-1200 -- REFERENCES -- ABBREVIATIONS -- CONTRIBUTORS TO DRAFTING AND REVIEW. 330 $aThe choice of the coolant is one of the main technical issues concerning fast reactors design, since it determines design approach as well as safety, technical and economic characteristics of the system. This publication provides a comprehensive summary of the status of the liquid metal coolant technology development for fast reactors, with regard to basic data and main technological challenges. It starts with historical remarks on the nuclear power development, provides a complete survey of physical and chemical properties of liquid metals and discusses the coolant quality control and thermal-hydraulics studies for both sodium and lead alloys systems. Other chapters elaborate on radioactivity of coolants and describe past experiences as well as current projects. Finally, design objectives, main research and technology development challenges of innovative fast reactor concepts, currently under investigation in Russia, having sodium, lead-bismuth eutectic, and lead as coolant, as well as the status of the respective research and development activities are summarized. 517 $aLiquid Metal Coolants for Fast Reactors 606 $aFast reactors$7Generated by AI 606 $aLiquid metal cooled reactors$7Generated by AI 615 0$aFast reactors 615 0$aLiquid metal cooled reactors 700 $aAuthor)$b IAEA (Corporate$01823353 701 $aEditor)$b IAEA (Corporate$01823354 801 0$bMiAaPQ 801 1$bMiAaPQ 801 2$bMiAaPQ 906 $aBOOK 912 $a9911006769503321 996 $aLiquid Metal Coolants for Fast Reactors (Reactors Cooled by Sodium, Lead and Lead-bismuth Eutectic)$94389953 997 $aUNINA