July 1, 2005 ANL-SMFR-1 Small Modular Fast Reactor Design Description Joint Effort by Argonne National Laboratory (ANL) Commissariat a l’Energie Atomique (CEA) and Japan Nuclear Cycle Development Institute (JNC) Project Leaders Y. I. Chang and C. Grandy, ANL P. Lo Pinto, CEA M. Konomura, JNC Technical Contributors ANL: J. Cahalan, F. Dunn, M. Farmer, S. Kamal, L. Krajtl, A. Moisseytsev, Y. Momozaki, J. Sienicki, Y. Park, Y. Tang, C. Reed, C. Tzanos, S. Wiedmeyer, and W. Yang CEA: P. Allegre, J. Astegiano, F. Baque, L. Cachon, M. S. Chenaud, J-L Courouau, Ph. Dufour, J. C. Klein, C. Latge, C. Thevenot, and F. Varaine JNC: M. Ando, Y. Chikazawa, M. Nagamura, Y. Okano, Y. Sakamoto, K. Sugino, and H. Yamano ii TABLE OF CONTENTS ABSTRACT……………………………………………………………………………………. vii I. INTRODUCTION……….................................................................................................……..1 II. OVERALL PLANT DESCRIPTION…… .......................................................................…….4 III. REACTOR MODULE AND SUPPORT STRUCTURES …………………………………...9 A. Reactor Module Arrangement...............................................................................……..9 B. Reactor Vessel.......................................................................................................……..9 C. Guard Vessel ......................................................................................................……14 D. Reactor Vessel Enclosure......................................................................................……14 E. Core Support Structure..........................................................................................……14 F. Core Barrel Assembly…………………………………………………………………15 G. Top Support Structure…………...........................................................................……16 H. Reactor Containment Boundary………………………………………………………16 I. Integrity of Primary Coolant Boundary.................................................................……16 J. In-Service Inspection …………………………....................................................……18 K. Seismic Isolation System ......................................................................................……23 References………………………………………………………………………………..27 IV. REACTOR CORE………...............................................................................................……28 A. Core Configuration ...............................................................................................……28 B. Assembly Design Description ........................................................................……30 C. Core Performance Characteristics ........................................................................……33 D. Reactivity Control Requirements ........................................................................……40 References………………………………………………………………………………..47 V. PRIMARY HEAT TRANSPORT SYSTEM....................................................................……48 A. Primary Sodium Pumps ........................................................................................……48 B. Primary Piping……...............................................................................................……49 C. Core Barrel and Redan Assembly .........................................................................……51 D. Intermediate Heat Exchanger……........................................................................……51 VI. INTERMEDIATE HEAT TRANSPORT SYSTEM.......................................................……59 A. Intermediate Sodium Pump……….......................................................................……59 B. Intermediate Piping……………… .......................................................................……59 C. Sodium-CO2 Heat Exchanger…………................................................................……59 D. Auxiliary Sodium System……….. .......................................................................……63 iii TABLE OF CONTENTS (Contd.) VII. SUPERCRITICAL CO2 BRAYTON CYCLE POWER CONVERSION SYSTEM…….64 A. Supercritical CO2 Brayton Cycle Arrangement…………………………………….64 B. Turbine Generator .................................................................................................….70 C. Compressors..........................................................................................................….71 D. Recuperator ...........................................................................................................….71 E. Inventory Control System......................................................................................….73 F. Coolers and Heat Rejection System ......................................................................….77 G. Carbon Dioxide Release Mitigation System.........................................................….78 References………………………………………………………………………………79 VIII. SHUTDOWN HEAT REMOVAL SYSTEM...............................................................…..80 IX. FUEL HANDLING STRATEGY………… ...................................................................…..86 X. OTHER REACTOR PLANT EQUIPMENT....................................................................…..88 A. Reactor Vessel Heating System ............................................................................…..88 B. Shield and Thimble Cooling System.....................................................................…..88 C. Emergency and Backup Systems ..........................................................................…..89 XI. INSTRUMENTATION AND CONTROL SYSTEM.....................................................…..90 A. Plant Control System ..........................................................................................…..90 B. Plant Protection System ……………………………………………………………..90 C. Flux Monitoring System .......................................................................................…..90 D. Cover Gas Radiation Monitoring System .............................................................…..91 E. Delayed Neutron Detection System ......................................................................…..91 F. Process Instrumentation System ........................................................................…..91 XII. BUILDINGS AND STRUCTURES……………… ......................................................…..92 A. Reactor Building ...................................................................................…..92 B. Brayton Cycle Building ......................................................................…..96 C. Control Room and Personnel Building ................................................................…..97 D. Radwaste/Maintenance Building ........................................................................…..97 E. Security Building ..................................................................................................…..97 F. Emergency Generator Building………………………………………………………98 G. Balance of Plant Service Building…………………………………………………...98 H. Lift Station and Waste Treatment Plant Building……………………………………98 XIII. COMMISSIONING AND DECOMMISSIONING .....................................................…..99 iv TABLE OF CONTENTS (Contd.) LIST OF ACRONYMS ............................................................................................................101 APPENDIX A. OVERALL SMFR DESIGN REQUIREMENTS...........................................103 1. Base Requirements....................................................................................................103 2. Technical Requirements............................................................................................104 APPENDIX B. TECHNICAL RATIONALE FOR METAL FUEL........................................107 1. Steady-State Irradiation Performance.......................................................................107 2. Off-Normal Performance Characteristics .................................................................110 3. Inherent Passive Safety.............................................................................................112 4. Fuel Cycle Implications ........................................................................................... 114 APPENDIX C. SAFETY ANALYSES ....................................................................................116 1. Introduction and Summary .......................................................................................116 2. Analysis Scope..........................................................................................................118 3. Analysis Methods and Input Data.............................................................................119 4. Analysis Results........................................................................................................131 References.....................................................................................................................139 APPENDIX D. THERMAL-HYDRAULIC ANALYSES.......................................................140 APPENDIX E. ADVANCED DESIGN CONCEPT................................................................159 1. Advanced Loop Concept...........................................................................................159 2. Advanced Pool-Loop Concept..................................................................................171 References.....................................................................................................................177 APPENDIX F. SCALE-UP POTENTIAL ...............................................................................178