STATUS OF INNOVATIVE FAST REACTOR DESIGNS AND CONCEPTS A Supplement to the IAEA Advanced Reactors Information System (ARIS) http://aris.iaea.org Nuclear Power Technology Development Section Division of Nuclear Power — Department of Nuclear Energy @ OCTOBER 2013 13-42471 PREFACE The important role of fast reactors and related fuel cycles for the long term sustainability of nuclear power has long been recognized. By the achievable breeding ratio and the multi- recycling of the fissile materials obtained from the spent fuel, fast reactors allow fully utilizing the energy potentiality of the natural resources (Uranium and Thorium), thus guarantying energy supply for thousands years and drastically enhancing the sustainability of nuclear power, especially in terms of resource preservation and management of high level and long-lived nuclear wastes. A successful large-scale deployment of fast reactors is reasonably achievable only if the research and technology developments create the conditions to accomplish the full potential of the fast neutron systems and related closed fuel cycles, and if the criteria of economic competitiveness, stringent safety requirements, sustainable development, and public acceptability are clearly satisfied. In this context, it is of paramount importance the understanding of different design options and related safety characteristics, based on past knowledge and experience, as well as on new scientific and technological research efforts. Since 1960 significant fast reactor development and deployment programmes have been pursued worldwide, bringing the knowledge on fast reactor and associated fuel cycle technologies to a high level of maturity. Furthermore, nowadays a new generation of fast reactors is being developed at national and international level in order to comply with higher standards of safety, sustainability, economics, physical protection and proliferation resistance. Member States, both those considering their first nuclear power plant and those with an existing nuclear power programme, are interested in information about innovative fast reactor designs and concepts, as well as new development trends. The International Atomic Energy Agency (IAEA), which has been accompanying and supporting the development of fast reactors and related fuel cycles for almost fifty years, plays a prominent role, representing for the interested Member States a major international forum for scientific and technical cooperation in this field. Furthermore the IAEA regularly publishes technical reports which provide comprehensive and detailed information on the different aspects of the fast neutron system science and technology. The objective of this booklet is to provide Member States with an overview of the status of innovative fast reactor designs and concepts that are currently under development. The report is intended as a supplementary booklet to the IAEA’s Advanced Reactor Information System (ARIS), which can be accessed at http://aris.iaea.org. It is also to be regarded as a complementary publication to the recently released Status of Fast Reactor Research and Technology Development (IAEA-TECDOC-1691). The IAEA officer responsible for this publication was S. Monti of the Division of Nuclear Power. CONTENTS INTRODUCTION ...................................................................................................................... 1 Background ....................................................................................................................... 1 Major Fast Reactor Options .............................................................................................. 2 Experience acquired with demonstration and prototype reactors operation ..................... 5 SODIUM-COOLED FAST REACTOR DESIGNS ................................................................ 11 CFR-600 (China Institute of Atomic Energy, China) ...................................... 13 ASTRID (CEA with its industrial partners EDF, AREVA NP, ALSTOM, BOUYGUES, COMEX NUCLEAIRE, TOSHIBA, JACOBS, ROLLS- ROYCE and ASTRIUM Europe, France) ........................................................ 15 FBR-1 & 2 (IGCAR, India) .............................................................................. 17 4S (Toshiba, Japan) .......................................................................................... 19 JSFR (JAEA, Japan) ......................................................................................... 21 PGSFR (KAERI, Rep. of Korea) ..................................................................... 23 BN-1200 (JSC “Afrikantov OKBM”, Russian Federation) ............................. 25 MBIR (NIKIET, Russian Federation) .............................................................. 27 PRISM (GE-Hitachi, USA) .............................................................................. 29 TWR-P (TerraPower, U.S.A.) .......................................................................... 31 HEAVY LIQUID METAL-COOLED FAST REACTOR DESIGNS .................................... 33 MYRRHA (SCK•CEN, Belgium) .................................................................... 35 CLEAR-I (INEST, China) ................................................................................ 37 ALFRED (Ansaldo Nucleare, Europe/Italy) .................................................... 39 ELFR (Ansaldo Nucleare, Europe/Italy) .......................................................... 41 PEACER (Seoul National University, Republic of Korea) ............................. 43 BREST-OD-300 (RDIPE, Russian Federation) ............................................... 45 SVBR-100 (AKME Engineering, Russian Federation) ................................... 47 ELECTRA (KTH, Sweden) ............................................................................. 49 G4M (Gen4 Energy Inc., USA) ....................................................................... 51 GAS-COOLED FAST REACTOR DESIGNS ........................................................................ 53 ALLEGRO (European Atomic Energy Community, Europe) ......................... 55 EM2 (General Atomics, USA) .......................................................................... 57 MOLTEN-SALT FAST REACTOR DESIGNS ...................................................................... 59 MSFR (CNRS, France) .................................................................................... 61 ACRONYMS ........................................................................................................................... 63 REFERENCES ......................................................................................................................... 65 INTRODUCTION Background The International Atomic Energy Agency (IAEA) devotes a number of its initiatives in support of the development and deployment of innovative fast reactors (FR) and the related closed fuel cycles, recognizing their importance in ensuring the long term sustainability of nuclear power. The objective of this booklet is to provide Member States, both those considering the initiation of nuclear power programmes and those already having practical experience in nuclear power, including the ones with an active FR programme, with a brief introduction to the IAEA's Advanced Reactor Information System (ARIS) by presenting a balanced and objective overview of the status of innovative FRs. The designs and concepts presented in the booklet were mostly derived from: a) the recently published Status of Fast Reactor Research and Technology Development (IAEA-TECDOC-1691), b) the proceedings (in preparation) of the International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), held in Paris on March 4-7 2013, c) presentations/consultations during the last meetings of the Technical Working Group on Fast Reactors (TWG-FR), and d) several interactions with the developers of the different FR concepts indicated by the respective Member States. The scope of the publication covers briefly the history of fast reactors, from the first experimental reactors and prototypes up to nuclear power plants that are currently under construction, for leading to present on-going initiatives on innovative fast reactor designs and concepts, followed by short but informative design descriptions. Fast reactors have the potential to enhance sustainability indices and correspond to cross- cutting prerequisites for large scale introduction of nuclear energy in the world’s energy mix, including economics, safety, natural resource utilization, reduction of waste, non-proliferation and public acceptance [1]. Fast neutron reactors differs from thermal reactors in the possibility to achieve the breeding ratio, meaning that during the operation they convert fertile material (Uranium-238) into fissile material (Plutonium-239) at a rate faster than they consume the fissile material by fission reactions. In the typical fast reactor fuel cycle, after irradiation, the reprocessing of the spent fuel allows extracting this fissile material which can be reused to produce fresh fuel. In this way, fast reactors allow fully exploiting the intrinsic energy potential also of the fertile Uranium, which represents the 99.3% of the natural resource, and thus to extract sixty-to-seventy times more energy from uranium than thermal reactors do. Furthermore, the physical characteristics of the fast neutron spectrum offer the possibility to burn more efficiently the long life transuranic wastes, reducing