Current Status and Future Challenges of Innovative Reactors Development in Japan

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1 Innovation for Cool Earth Forum 2017, Tokyo, Japan, October 4-5, 2017 Current Status and Future Challenges of Innovative Reactors Development in Japan 5 October, 2017 Yutaka Sagayama Assistant to the President Japan Atomic Energy Agency Chair Emeritus of GIF

2 Policy on Innovative Reactors Development in Japan Generation IV 4 th Strategic Energy Plan (2014) Generation II Commercial power Reactors Mihama1 PWR, etc. Generation III Advanced LWRs Kashiwazaki Kariwa ABWR, etc Revolutionary Designs Generation IV International Forum (GIF) Sodium-cooled FR (SFR) Monju Joyo Very High Temperature Reactor (VHTR) HTTR Electricity generation as a baseload power source as a low carbon and quasi-domestic energy source Reducing the volume and radiotoxicity of radioactive wastes JSFR Multi-purpose use such as hydrogen production and electricity generation HTGR IFR JSFR: Japanese Sodium-cooled Fast Reactor IFR: Integral Fast Reactor HTGR: High-Temperature Gas-cooled Reactor 1

3 Feasibility Study on Commercialized FR Cycle Systems (FS) ( JFY ) Based on the comprehensive evaluation in FS, the combination system of sodium-cooled FR (SFR) with MOX fuel, advanced aqueous reprocessing and simplified pelletizing fuel fabrication was selected as the most promising concept for commercialization. Main R&D investment is being focused on this concept aiming at cost reduction and safety enhancement. the combination system of sodium-cooled FR (SFR) with Metallic fuel, pyroprocessing and injection casting fuel fabrication was selected as the complementary concept for commercialization. In order to respond flexibly to various future needs such as uranium supply and demand tightening, R&D is being conducted focusing on the core fuel. 2

4 Japanese Sodium-cooled Fast Reactor (JSFR) -Advanced Loop-type SFR- 1,500 MWe large-scale sodium cooled FBR with MOX fuel, Innovative technologies for enhancement of reactor core safety, high economic competitiveness and countermeasures against specific issues of sodium Innovative technologies to reduce plant materials and the reactor building volume (1) Shortening of piping with high chromium steel Secondary pump SG Prevention of sodium chemical reactions (8) Double-wall piping (9) High reliable SG with double-wall tube (2) Two-loop cooling system (3) Integrated Pump-IHX Component (10) Inspection and repair technology under sodium (4) Compact reactor vessel (5) Fuel handling system (6) S&C structure building (CV) Integrated IHX with primary Pump Enhancement of safety (11) Passive reactor shutdown system and decay heat removal by natural circulation (7) ODS cladding to achieve high burn-up with an elevated temperature Reactor Vessel (12) Re-criticality free core (13) 3D seismic isolation technology 3

5 SFR Development in Japan (JFY: April to March) Earthquake and 1F accident FaCT Phase-I (FaCT Phase-II) Safety Enhancement Maintenance & Repair Enhancement SDC Improvement of plant systems SDG Strategy Roadmap FaCT phase-i: Evaluation on innovative technologies for a commercial JSFR FaCT phase-ii (suspended due to the 1F accident): Demonstration of innovative technologies and conceptual design of the demonstration JSFR After the 1F accident, design study on safety enhancement was initiated. Activities related with SDC/SDG are ongoing since Strategy Roadmap on FR development is under formulation. 4

6 International Cooperation on FR Cycle in Japan Bilateral or Trilateral Cooperation Sharing resources of R&D: Cost Human Knowledge Infrastructure International Cooperation International contribution: Common technical issues Safety design criteria Data base Infrastructure Others Global communication accelerates R&D on FR cycle! Researchers and Developers in: U.S.A France Kazakhstan Russia Civil Nuclear Energy R&D WG (CNWG) Cooperation ASTRID Cooperation EAGLE Project Waste Management Japan IAEA OECD/NEA Korea China India Others.. 5

7 Safety Design Standards (SDC/SDG) 5 GIF leads to build safety design standards (safety design criteria (SDC) / guidelines (SDG)) toward the safety enhancement of SFR in the world. GIF and non GIF countries (e.g. India) intend to reflect them in their safety regulations and safety design. De facto standard SDC/SDG With the aim of establishing the globally standardized safety design concepts, the SDC has already been completed and the SDG is under construction. Review is in progress among regulatory bodies/technical support organizations of GIF countries and international organizations (IAEA, OCED/NEA/CNRA, etc.) <Hierarchy of Safety Standards> Safety Fundamentals SDC SDG Safety Requirements Design Guides of the Reactor Coolant System and Associated Systems in Nuclear Power Plants Domestic Codes and Standards Targets of Global Standards 6

8 Application of IFR Concept Objectives: examine the potential of the IFR(Integral Fast Reactor) technology to reduce the volume of radioactive waste and the level of hazard (radiotoxicity) through the burning of transuranium (TRU) elements. Example: treat the fuel debris generated in conjunction with the TEPCO Fukushima Daiichi Nuclear Power Station Accident. The concept of IFR consists of reprocessing the fuel debris, fabricating TRU fuel, burning it in a small MF-SFR and recycling the spent fuel by reprocessing Amount of heavy metals (HM), such as uranium, presented in the fuel debris: Approximately 250 tons including about 1.9 tons of TRU elements. Inner 内側炉心燃料集合体 core fuel assemblies (24 体 ) (24) Outer 外側炉心燃料集合体 core fuel assemblies (24 体 ) (24) Control 制御棒 (7 体 rods ) (7) GEM (gas expansion modules) (2) GEM( ガス膨張式モジュール )(2 体 ) Features Neutron 中性子反射体 reflector An MF-SFR with inherent safety Shielding 遮へい体 features (reactor output: 190MWt) Application of a metallic fuel pyroprocessing method that makes Core configuration debris processing possible. 7

9 Debris Processing Scheme and TRU Reductions The 1.9 tons of TRU presented in the debris will be reduced to a total of 1.2 tons in 25 years after the launch of the IFR including that remaining in the reactor and that existing in the spent fuel. [ I ] Debris Metal Reprocessing/ conversion Fuel fabrication Initial loading fuel [ II ] Debris Metal conversion New fuel IFR Spent fuel (small metalfueled reactor) Concept diagram of debris processing scheme [ III ] Reprocessing/ Fuel fabrication New fuel IFR Spent fuel (small metalfueled reactor) 8

10 Recent Developments of JAEA s activities for HTGR Objective: Contributes further to the advancement and diversity of nuclear utilization such as power generation and hydrogen production Task: Research and Development of an HTGR with high level of safety and economy HTTR (1) Reactor technology 30 MWt and 950 o C prismatic core advanced test reactor (Operation started in 1998) Technology of fuel, graphite, superalloy and experience of operation, and maintenance. Safety evaluation by NRA is underway. (2) Gas turbine and H 2 technology He compressor Hydrogen facility R&D of gas turbine technologies such as high-efficiency helium compressor and shaft seal In October 2016, 31 hours of hydrogen production with the rate 0.02m 3 /h was achieved. GTHTR300 (3) Innovative HTGR design GTHTR300 for electricity generation GTHTR300C for cogeneration and nuclear/renewable energy hybrid system Clean Burn HTGR for surplus plutonium burning Establishment of safety design philosophy HTTR (4) HTTR-GT/H2 test H 2 facility Helium Gas turbine Connection of a helium gas turbine and hydrogen production system with the HTTR. Basic design for the HTTR-GT/H 2 test completed. 9

11 Outline of HTTR (High Temperature engineering Test Reactor) The only helium gas-cooled graphite-moderated reactor in Japan Rated thermal power: 30 MW Maximum reactor outlet coolant temperature: 950 History Nov First criticality Dec Operation at reactor outlet coolant temp. 850 Apr Operation at reactor outlet coolant temp. 950 Mar Long term (50-day ) high-temperature (950 ) operation Dec Loss of forced cooling test from 30% rated power Nov Submission of the application to confirm conformity to Site new regulation standards to Nuclear Regulation Authority : Oarai Research and Development Center core Fuel Activities for HTGR development in Japan MEXT established an Industry-Academia-Government forum for HTGR in Discussion on a strategy for HTGR development and deployment internationally started at the working group in August Liberal Democratic Party established HTGR development supporting group in

12 Conclusion Japan is developing innovative reactors that will play a key role as a future energy source for power supply focusing on the SFR and also studying their various usages. Discussion about the fast reactor development in the future is being carried out mainly by the Government. Based on the discussion, Strategic Roadmap (tentative) which identifies development tasks for the next 10 years will be formulated in For various usages of innovative reactor systems, the IFR with metal fuel developed for the reduction of radiotoxicity of wastes and the HTGR with high-temperature heat for hydrogen production are also being studied. Since enormous resources are required and development risks are involved in the development for a single country, the utilization of international cooperation is very important for reducing resources and risks. 11

13 Thank You for Your Attention! 12

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