Role of HTGR in Japan and Japans HTGR Technology 18 th September - PowerPoint PPT Presentation

Side Event of 63rd IAEA GC organized by JAEA, 18 th September 2019, Vienna Austria Role of HTGR in Japan and Japanʼs HTGR Technology 18 th September 2019 Kazuhiko Kunitomi Sector of Fast Reactor and Advanced Reactor Research and Development Japan Atomic Energy Agency (JAEA)

Role of HTGR in Japan -Greenhouse gas emissions & reduction goals- Plan for global warming countermeasures (Cabinet decision on May 13, 2016) Mid-term target: 26.0% reduction by FY2030 compared to FY2013 • Long-term goal: 80% reduction by 2050 • Breakdown of GHG emission (2016) GHG emission in Japan (Final report of FY2017) Role of HTGR Ref. ： Website of Ministry of Environment, Japan • The emission reduction in FY2017 : 8.4% compared to FY2013 • HTGR producing hydrogen for nuclear steel • To achieve the goal, making and fuel cell vehicle  Reduction by additional 18% by 2030 • HTGR producing steam for conventional  Reduction by additional 72% by 2050 industries • HTGR for absorbing renewable power variation Use of HTGR for not only power generation but also for the other fields 2

History and status of HTTR Proposal for prototype commercial system Specification Conformity review on the new Long term high temperature operation 2014 regulatory requirements start Establishment of toward resumption of operation Purpose fundamental <Integrity of fuel coating> Start of loss of technologies 950oC, forced cooling test  Establishment of HTGR technologies 50days 2010  Establishment of heat application technologies 950ºC/50 days operation First in the 2007 850ºC/30 days operation world Reactor Building Reactor outlet coolant 2004 temperature 950ºC Safety demonstration test 2002 (control rod drawing test) Reactor outlet coolant 2001 temperature 850ºC (30MWt) 1998 First criticality Intermediate Heat Exchanger (IHX) 1997 Construction 〜 1991 Construction of reactor 1990 R/B of 88 Kr : 4 orders of magnitude Application and permission  Reactor Pressure 〜 Vessel 1989 of construction less than the operational limit Pressurized Water Concentric Hot Gas 1988 Cooler Duct Detail design 〜 1985 Specification of HTTR H T T R ● Reactor thermal power ･･30MW Research and development 1984 ● Reactor coolant ･････････････ Helium gas Basic design 〜 1981 ● Reactor inlet/outlet coolant temperature Fuels・Materials Reactor physics Thermal hydraulics ･･････････ 395ºC / 850ºC, 950ºC 1980 System integrity ● Reactor material ･･････ Graphite 〜 design 1974 ● Fuel ･･････････････ UO 2 coated particle fuel ● Uranium enrichment ･･･ 3% ~10% (average 6%) 1973 Conceptual design 〜 Research and 1969 development Very High Temperature Helium Engineering In-pile helium loop (OGL-1) Experimental multi-purpose Very Reactor Critical assembly 3 Demonstration Loop and design High Temperature Reactor (VHTR) (VHTRC) (HENDEL)

HTGR technologies developed in HTTR Project Japan`s HTGR technologies are front runner in the world. Fuel (Nuclear Fuel Industry) Experiences of HTTR design, construction, operation Ceramics coating layer (MHI, Toshiba/IHI, Hitachi, Fuji retains fission products Electric, KHI, etc.) inside the coated fuel particle at extreme low A lot of technical data of HTTR has been Coated fuel particle leak level. accumulated. Optimum design of commercial HTGR may be Fuel compact conducted using Japan`s technologies alone. Ceramics coating is stable for long-term. High temperature resistant metal, (3 times higher burnup than LWR) Hastelloy XR (Mitsubishi Material) Graphite, IG-110 (Toyo Tanso) Hastelloy XR is applicable Intermediate at 950  C as nuclear World highest quality graphite heat exchanger structural material. (isotropic, high density) →Adoption by HTR-PM (IHX) Graphite core component in HTTR IHX（Toshiba/IHI) can deliver hot helium gas at 950  C to outside of the reactor pressure vessel. High strength, high thermal conductivity, irradiation resistance 4 p.4

Status of regulatory review on HTTR Additional Major discussion item Regulatory review condition Regulatory review results countermeasures Design seismic Raised from 350gal to 973gal ground motion Some of safety systems, components and No large-scale reinforcement due to the Earthquake Not required Re-evaluation of structures (SSCs) were classified from S to B degradation of the SSCs. seismic design based on results of safety demonstration tests. classification Core heat removal: S class to B class  Reactor internal structure: S class to B class.  Assumption of tsunami height for evaluation︓ Tsunami does not reach the site because siting Tsunami evaluation Not required 17.8m from sea level location is 36.5 meters high from the sea level. All SSCs needed to be protected are  Design basis tornado wind speed: 100 m/s  Evaluation of integrity of SSCs installed inside the reactor building Fire proof belt was against natural phenomena such Thickness of descent pyroclastic material by  Fire proof belt necessary around reactor required.  as tornado, volcano, etc. volcano: 50 cm building.  Amount of burnable materials in the reactor Cable protection Burnable materials in and around the reactor Fire building is limited. against fire was building was additionally evaluated.  Cables necessary to be protected against fire required. Decay heat is removable from the core without Reliability of power supply Emergency power supply failure was evaluated. Only portable electricity. power generator Postulated BDBAs for monitoring No core melt occurs in all BDBAs. Beyond design basis accident DBA + failure of reactor scram   during accident is Intentional aircraft crash does not damage (BDBA) DBA + failure of heat removal from the core   required. SSCs in the reactor building . DBA + failure of containment vessel  Intentional aircraft crash  New regulation standard was issued on 18 December, 2013, according to which application was submitted to NRA on 26 5 November, 2014 HTTR is expected to restart without significant additional reinforcement due to its own high-level inherent safety features

Target schedule towards HTTR restart FY2014 FY2015 FY2016 FY2017 FY2018 FY2019~ Evaluation of natural phenomena Re-evaluation of seismic design classification Seismic evaluation Documentation of verification results, including evaluation of BDBA Evaluation by NRA Restart Application Nov. 26 6

HTGR-H 2 system technology development IS process To successfully license  2045〜 H 2 production facility and operate the worldʼs HTTR Thermal decomposition of water requires heat above first HTGR gas turbine  Commercial power generation and 4000 o C . hydrogen production IS process decomposes water with heat of ca. 900 o C Planned  use plant using chemical reactions of iodine (I) and sulfur (S). To establish safety  ・I and S circulate in the process. ⇒ No harmful waste design criteria for ・HTGR heat is used. ⇒ No CO 2 emission coupling chemical plant such as hydrogen Technology transfer production plant to Helium gas High-temp. nuclear reactor to private sectors H 2 O 2 400 o C 900 o C To complete the turbine power  heat system technology generation required for construction of the first 1/2O 2 H 2 demonstration plant H 2 SO 4 + + 2HI 〜2035 SO 2 + H 2 O I 2 H 2 production rate was HTTR-GT/H 2 test 2HI + H 2 SO 4 intentionally adjusted to I S reduce risk of clogging Production of H 2 and O 2 [m 3 ] SO 2 I 2 + SO 2 + 2H 2 O pipe caused by I 2 ・ Establishment of safety design + solidification. I 2 standard for integrating heat H 2 O application systems with reactor Water H 2 O Ceramic (SiC) H 2 production test facility Present (0.1 m 3 /h) Glass • lined Verification of integrity of total steel components and stability of Industrial material hydrogen production pipe Filter maintenance • component test Development of strength H 2 SO 4 Corrosion- HI decomposer Bunsen reactor evaluation methodology for decomposer resistant Fluoro-plastic lined steel Ni-base alloy ceramic components ・ Integrity of components / operation Time [h] Ceramic (SiC) lining • (<500 o C) (<100 o C) (<900 o C) Plant operation control system H 2 (integrated val.) vessel O 2 (integrated val.) stability Development of key components in the IS Plant maintenance techniques (fluoro- Operations for 3 sections integration was • ・ Plant operation control system process environment plastic, Membrane technologies to successfully carried out 7 glass) improve thermal efficiency (corrosion resistance, heat resistance) (30 L/h for 150 h).