Frederik ReitsmaVice-Chair of International Organizing Committee

Team Leader (SMR Technology Development)Nuclear Power Technology Development SectionInternational Atomic Energy Agency |

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HTR2021Organized in cooperation with the IAEA

IAEA support the HTR2021 conference:• It is the sole international conference focusing on high-temperature gas-cooled reactors and

process heat application technology• It provides a comprehensive networking and exchange forum for professionals in R&D and in

industry as well as for decision makers from governments, utilities, end-user industries and vendors.

• Offer to share proceedings on IAEA SharePoint site (like HTR2014 already available)Specific for Indonesia• Facilitate the exchange of information on HTR among various national stakeholders, from the

government, industry, regulatory body, industry and academia, allowing a first-hand account from the experts and HTR

• Showcase the IAEA TC activities supporting Indonesia and other Member States

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(Very) High Temperature Gas Cooled Reactors

VHTRs; HTRs; HTGRs

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• Characteristics• R&D areas• IAEA Activities • Flexible applications of HTGRs• Member State interest• IAEA TC support to Indonesia

High Temperature Gas Cooled Reactors is an advanced reactor system (part of GEN-IV) with the following main characteristics:• High temperatures (750-1000oC)• Use of coated particle fuel• Helium coolant • Graphite moderated• Small reactor units (~100 - 600 MWth)• To be deployed as multiple modules • Low power density (typically 3-6 W/cc compared to 60-100W/cc for LWRs) • Two basic design variations – Prismatic and pebble bed design

HTGRs Characteristics

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Prismatic (block-type) HTGRs

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1 mm

Spherical graphite fuel element with coated particles fuel

On-line / continuous fuel loading and circulation

Fuel loaded in cavity formed by graphite to form a pebble bed

Pebble type HTGRs

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• Higher (↑20-50%) efficiency in electricity generation than conventional nuclear plants due to higher coolant outlet temperatures

• Potential to participate in the complete energy market with cogeneration and high temperature process heat application

– Process steam for petro-chemical industry and future hydrogen production

– Market potential substantial and larger than the electricity market

– Allows flexibility of operation switching between electricity and process heat

• Significantly improved safety– Decay heat removal by natural means only, i.e. no meltdown

– No large release - radioactivity contained in coated particle fuel

– EPZ can be at the site boundary

• Position close to markets or heat users– Savings in transmission costs

• Can achieve higher fuel burnup (80-200 GWd/t)– Flexible fuel cycle and can burn plutonium very effectively

HTGRs - Benefits

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The low power density leads to large reactor pressure vessels (but site requirements not larger)• Forging capability can also set limit on RPV diameter and power

(e.g. ∅6.7 m < 350 MWth in South Korea) helium coolant has low density and thus requires high

pressurization helium coolant is non-condensable – so a traditional

containment cannot be used coated particle fuel costs are expected to be higher

HTGRs - Challenges

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Ceramic fuel retains radioactive materials up to and above 1800˚C

Coated particles stable to beyond maximum accident temperatures

Heat removed passively without primary coolant – all natural means

Fuel temperatures remain below design limits during loss-of-cooling events

Why so safe - No early or large FP release

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Ceramic fuel retains radioactive materials up to and above 1800˚C

Coated particles stable to beyond maximum accident temperatures

Heat removed passively without primary coolant – all natural means

Fuel temperatures remain below design limits during loss-of-cooling events

No early or large FP release

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“Safety Terrain” of Modular HTGRs

Modular HTGRs result in a safety terrain that is fundamentally much gentler and more forgiving:

Fuel failure mechanisms of CP fuel are decoupled and totally independent One coated particle failure cannot lead to the failure of a neighbouring CP, as it is driven by the maximum fuel temperature.

Failure also has no effect on the cool-ability of the fuel as a failure will not change the heat removal path.

CP failure will release miniscule amount of FPs -many CP will need to fail to be of any consequence.

Based on inherent and passive safety features, there is no cliff-edge effects or large releases even in extremely rare events far beyond the design basis.

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R&D Areas for HTGRs

High Temperature Gas cooled Reactors

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Extensive operating experience

Mature technology ready for commercial deployment (in next decade) for temperatures up to ~850 oC

Past Experience | Current test reactors

Wealth of know-how available

SMR designs take all lessons learned into account

Needs to preserve and transfer this knowledge

R&D areas

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• Well established technology up to reactor outlet of 850 – 950 0C• Many times the development work is done to re-establish the technology

(such as coated particle fuel)• R&D needs mainly focused on VHTR applications…• GIF work areas (as example)

– Materials (advanced), Components and Supply Chain– Fuel, (advanced) Fuel Cycle, and Waste Minimization– Design, System Integration– Cost Reduction Approaches– Safety Demonstration and Licensing– Coupling to Cogeneration Applications– Energy System Integration

HTGR Research and Technology IAEA Identified Development areas

• Fuel / coated particle fuel performance• Materials

– Graphite– High temperature metals (for future higher

temperatures• Software developments / Code V&V• Safety requirements (for modular HTGRs)• Co-generation, applications and economy• Experimental facilities for V&V and licensing

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HTGR coated particle fuel• Advances in High Temperature Gas

Cooled Reactor Fuel Technology• Excellent performance of modern fuel• US NGNP program extends envelope

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Key Technologies• Fuel

– Good quality and mass production well established and now well understood

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Graphite and high temperature metals• Development of Material Properties and Design

Rules and ASME Codification• Historical grades are no longer available, new

ones must be qualified• IAEA International Graphite Knowledge Base• CRP on the “Treatment of irradiation graphite to

meet disposal acceptance criteria”• CRP on Improved Understanding of the

Irradiation Creep Behaviour of Nuclear Graphite • High Temperature Alloy 617

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Software development, Benchmarks, V&V• Evaluation of high temperature gas cooled reactor performance:

Benchmark analysis related to initial testing of the HTTR and HTR-10 (TECDOC 1382)

• Benchmark analysis related to the PBMR-400, PBMM, GT-MHR, HTR-10 and the ASTRA critical facility (IAEA-TECDOC-1694)

• Research on the Uncertainties in Analysis (cross sections, manufacturing, methods, etc) – TECDOC under development

• Others efforts include Proteus, ASTRA, SANA, NACOK • High Temperature Test Facility at Oregon State University

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IAEA to release HTR Software

• The HCP code system from Research Centre Julich was made available to IAEA for free distribution to all interested member States:– VSOP99/11 (ready for distribution soon)– STACY (to be distributed after user manual is updated)– HCP (need further development)

• Will be released as part of the IAEA Open-source Nuclear Code for Reactor Analysis (ONCORE) initiative – Information how to access, download, contribute to the OPEN SOURCE further

development will be made available soon:– https://nucleus.iaea.org/sites/oncore/SitePages/Home.aspx– https://nucleus.iaea.org/sites/oncore/htgr-codes/SitePages/Home.aspx– Will require some expert support group and developers to develop HCP further

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Safety requirements (for modular HTGRs)• A need as all current IAEA safety requirements is LWR based

– Harmonised interpretation of existing requirements– May need additional requirements / new approach

• So, develop comprehensive safety design criteria that take HTGR-specific characteristics into account

• provide a high level of assurance that modular HTGRs are consistently designed, constructed, and operated

• takes advantage of these inherent / intrinsic safety properties• The CRP is important to the HTGR community to show the safety

advantage of the HTGR to nuclear experts in the other fields.• TECDOC under development• Further actions taken by NS department on applicability of IAEA

requirements to SMRs / HTGRs – TECDOC related to Design SSR-2/1– New initiative looking at many NS requirements and guides

• SMR regulators forum• Actions by many regulators (US, Canada, UK etc)

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Co-generation• Need designs and system analysis• Provide an additional income stream• Economic feasibility

• User requirements• Safety and licensing• Clients and financing

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• Allows flexibility of operation switching between electricity and process heat• Niche market for high temperature reactors (does not compete with existing

LWRs fleet)• Huge potential to be realised

IAEA Activities on HTGRs

IAEA ARIS database include SMR designs

Advanced Reactors Information System Submissions made by vendors / design organizations, often small startup companies

11 SMR design updated in ARIS in JULY 2020 24

Updating IAEA SMR Booklet 2020 and ARIS

• The booklet contains information provided by vendors and designers on their SMRs

• Main Features

Design description and main features of 72 SMR designs being updated (we had 56 in 2018)

Also requested information on fuel cycle, decommissioning and final disposal (for the first time)

SMRs are categorized in types based on coolant type/neutron spectrum: Land Based WCRs Marine Based WCRs HTGRs Fast Reactors MSRs Micro reactors Test reactors (to be included with the types above as

applicable)

MANY designs not included / not submitted and thus not included in IAEA reporting

Content to be finalized this week Printing date 3 September

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2020 Edition

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HTR-PM SC-HTGR GTHTR300 PBMR-400 Xe-100

Design Status:Finalizing construction in Shidao Bay for operation by 2021

Design Status:Conceptual Design

Design Status:Pre-Licensing; Basic Design Completed

Design Status:Preliminary Design Completed, Test Facilities Demonstration

Design Status:Basic design developmentLicensing activities to start 2021

• INET Tsinghua University, China

• Modular pebble-Bed HTGR

• 250 MWt / 210 MWe x 2 modules

• Forced Circulation• Core Outlet Temp: 750oC• Enrichment: 8.5%• Refuel interval: Online

refuelling

• Framatome Inc ,United States, France

• Prismatic-bloc HTGR• 625 MWt / 272 MWe per

module• Forced convection• Core Outlet Temp: 750oC• Enrichment: <14.5% avg,

18.5% max• Refuel interval: ½ core

replaced every 18 months

• JAEA, Japan• Prismatic HTGR• 600 MWt / 100~300 MWe• Core Outlet Temp: 850-

950oC• Enrichment: <14%• Refuel interval: 48 months• Multiple applications• Use the HTTR Test

reactor to demonstrate key technologies and H2 production

• PBMR SOC, Ltd, South Africa

• Pebble-Bed HTGR• Forced Circulation• 400 MWt / 165 MWe per

module• Core Outlet Temp: 900oC• Enrichment: 9.5%• Refuel interval: Online

refuelling• Design in Care and

Maintenance

• X-Energy, United States of America

• Modular Pebble-Bed HTGR

• Forced Circulation• 200 MWt / 82 MWe • Core Outlet Temp: 750oC• Enrichment: <15.5%• Refuel interval: Online

refuelling• Aim to start construction

~2025

HTGR-type SMRs (Examples)

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HTR-PM Status

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Pressure Vessel Installation

Construction started Dec 2012

Site as in 2019: Civil construction completed

• Steam generator

2012/12/09：FCD 2015/06/30：Civil Engineering of Reactor plant 2016/03/20：1st RPV installed 2016/09：2nd RPV installed 2017/06: 1st ceramic internals installed 2018/06: 2nd ceramic internals installed 2019/01: 1st SG hoisted in place 2019/07: 2nd SG hoisted in place 2020/07: Commissioning started

Images Courtesy of INET, Tsinghua University, China

Operation expected in 2021 !

2017.6, graphite pebbles, ceramic internals finished

MoveluX MMR eVinci

Design Status:Conceptual design

Design Status:Preliminary Design, under vendor design review with the Canadian CNSCLicense to prepare site 2020

Design Status:Conceptual Design

• Toshiba, Japan• Fast Reactor• 10 MWt / 3-4 MWe• Natural circulation• Core Outlet Temp: 680-685oC• Enrichment: <4.8-5%• Refuel interval: Continuous

• USNC, USA• HTGR / micro-reactor / nuclear battery• 15 MWt / 5 MWe• Core Outlet Temp: 630oC• Enrichment: <9-12%• Refuel interval: N/A

• Westinghouse, United States of America• Heat Pipe cooled• 7-12 MWt / 2-3.5 MWe per module• Core Outlet Temp: 800oC• Enrichment: 5-19.75%• Refuel interval: 36+ months

Microreactors (Examples)

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• The Canadian Nuclear Safety Commission (CNSC) has received the first licence application for a small modular reactor.

• The application from Global First Power (GFP), with support from Ontario Power Generation and Ultra Safe Nuclear Corporation (USNC), supports a proposal to deploy a Micro Modular Reactor plant at Chalk River in Ontario.

– in response to an invitation issued in April 2018 by Canadian Nuclear Laboratories (CNL) to SMR project proponents for the construction and operation of an SMR demonstration unit at a CNL-managed site.

• The MMR is a 15 MW (thermal), 5 MW (electrical) high-temperature gas reactor– the reactor uses fuel in prismatic graphite blocks– TRISO coated particle fuel encased within a fully dense silicon carbide matrix

• MMR technology would serve as a model for future off-grid SMR deployment in Canada, to provide low-carbon energy and heat to remote industry and northern communities

First Canadian SMR license application submitted

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HTGRs – Coordinated Research ProjectsCompleted 2014 CRP on Improving the Understanding of Irradiation-Creep Behaviour in Nuclear Graphite: 2x TECDOCS under preparation

• Part 1: Models and Mechanisms• Part 2: Recent Developments

To determine the uncertainty in HTGR calculations at all stages of coupled reactor physics, thermal-hydraulics and depletion calculations- Completed 2019

HTGRs applications for energy neutral sustainable comprehensive extraction and mineral products development –completed 2019

CRP on HTGR Uncertainty in Analysis

Use process heatExtract U/Th with products i.e. cleaner fertilizerU / Th content and extraction studies

CRP I1026 on Modular High Temperature Gas cooled Reactor Safety Design – Completed 2019

IAEA LWR requirements include operation,

management, events, equip qual., personnel safety, etc. with greater detail in breadth

and depth at the level of existing LWRsCommon Safety

Design Criteria

Approach 2Modify LWRApproach 1

IAEA SRS No. 54

New CRP: Technologies to enhance the competitiveness and early deployment of SMRs and HTRs

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• The Coordinated Research Project will study technologies related to reactor design and innovative power conversion of SMRs and HTRs to enhance the competitiveness and possibilities for deployment

• This includes aspects such as reactor core and NPP designs for novel applications

• .CRP-I3 2231 Technologies to Enhance the Competitiveness and Early Deployment of SMRs & HTRs (Q2/2021 – 2024);

• Provides a forum for R&D with the objective to facilitate MS with the formulation of innovative solutions to make SMRs / HTRs more attractive viable option to diverse markets

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FLEXIBLE APPLICATIONS

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SMR Designs Based on Core Exit Temperature

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Electricity Generation

Process Heat

Desalinated Water Replace Aging Fossil PlantsIntegrated with Renewables

A viable option to contribute to Climate Change Mitigation

Image courtesy of KAERI and K.A.CARE

Viable Applications of SMRs / HTRs

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Role of SMRs in Climate ChangeSMR Renewables Hybrid Energy System to Reduce GHG

Emission

Reactor Core

Electricity Production

Energy Storage Modules

Alternative Application

Modules

Alternative Application

Modules

Alternative Application

Modules

Alternative Application

Modules

Energy Storage Modules

Energy Storage Modules

Modules:• Electricity production• Process heat

• Petro-chemical industry• Desalination plant• Oil and gas reforming• Hydrogen production• Ammonia production• District heating / cooling• Waste reforming

• Energy storage• Load follow capabilities

• Switch between applications

TECDOC:Options to Enhance Energy Supply Security using Hybrid Energy Systems based on SMR; being finalised in 2020

Example of load follow with renewables

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Coupling examples

Member State Specific Activities IAEA support to Indonesiathrough the Technical Cooperation Department

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Status and major accomplishment on HTGRs

Countries RArgentinaecent Milestone

Canada• First Canadian SMR licence application submitted: Global First Power (GFP), with support from Ontario Power Generation and

Ultra Safe Nuclear Corporation (USNC), to deploy a Micro Modular Reactor plant at Chalk River in Ontario• U-battery; STARCORE

China • HTR-PM is in advanced stage of construction. Commercial operation expected in 2021 • HTR-PM600 design under development and several sites under consideration

United Kingdom • Government support for Advanced (non-water-cooled SMRS)• Recent allocation to U-Battery

United States of America• X-Energy development continues and engagement with licensing planned in 2021 . • New non-water cooled licensing approach developed and approved (including for HTGRs)• Some finding of activities (TRISO fuel, HALEU, etc.)

Indonesia

• Through an open-bidding, an experimental 10 MW(th) HTR-type SMR was selected in March 2015 for a basic design work aiming for a deployment in mid 2020s

• Site: R&D Complex in Serpong where a 30 MW(th) research reactor in operation - BAPETEN, the regulatory body has issued a site license

• Expert missions related to HTGRs since 2013

Jordan • Part of the Feasibility Studies on SMR deployment identified possible designs (including at least two HTGRs)• Two exert missions in 2019 focussed on HTGRs

Poland • HTGR for process heat application to be implemented in parallel to large LWRs• 10 MW(th) experimental HTGR at NCBJ proposed possibly with EU cooperation

Saudi Arabia • An MOU between K.A.CARE and CNNC on HTGR development/deployment in KSA

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• Industrial Heat Market in Poland– 13 largest chemical plants need 6500 MW of heat at T=400-550°C – Construction of experimental reactor of ~10 MWth in Swierk– Target to construct the first commercial reactor of 150-300 MWth (165

MWth was determined to be optimum size for Poland)– Huge potential: Foresee 10, 100, 1000 reactors for Poland, Europe

and the world …

HTGRs and Poland

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• Decreasing dependence on fossil fuel import. HTGR is the only practical alternative to replace fossil fuels for industrial heat production. With expected growth of CO2 tax and low discount rate, the cost of the steam from HTGR could be comparable to that from gas, while having more secure availability and more predictable prices.

• Decreasing sensitivity of economy to environmental regulations. Industry dependent on fossil fuels might become less competitive in case of stronger environmental regulations (CO2 tax, emission limits, etc.). HTGR being a zero emission technology is immune to that.

• Boost for economy growth based on high added value. HTGR deployment is a large, innovative project, opening a new branch of economy, leading to high-tech reindustrialization and creating more attractive jobs.

• Synergy with multi-GW LWR program. Increasing scientific and industrial potential, upgrading the regulatory framework, developing human resources and creating a supply chain, will be beneficial for both HTGR and LWR projects.

• Large export potential. Very high safety level, favorable output parameters (>500°C) and relatively small size makes HTGR a very attractive export product.

• Most of those benefits are valid for other countries. You are invited to cooperate.* From 2017 IAEA GC Side Event – Poland Ministry of Energy

Benefits from HTGR deployment for economy & society in Poland*

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INDONESIATC-Mission 2013

• INS2015/04; 2-6 September 2013• To Evaluate the Research and Development

Project for the Development of a High Temperature Gas-Cooled Reactor Design– support efforts to produce a conceptual design

of a High Temperature Gas-Cooled Reactor• Possible need for two needs to deploy two

separate nuclear power technologies (programs): – (1) nuclear electricity for regions with existing

grids; – (2) nuclear electricity/heat co-generation for

regions not yet with sufficient grids• discussions on the experimental power

reactor

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IAEA support: DDG-NE visit and CM -2014

• Consultancy meeting was held in parallel by two IAEA technical experts.• Discussion on strategy, technology selection, integrated work plan,

practical approach for engineering design, best approach for international cooperation, project organization and master planning.

• Several key findings:– Clarify type of contract taking into account for long-term utilization– Identify experiments to be conducted– Clarify long term plan and priority, including subsequent units

• Future assistance from IAEA including through Technical Cooperation

• In a letter (29 Jan 2014) sent by the chairman of BATAN to the DDG-NE the RDE project was announced IAEA support was asked

• Visit by Mr A. Bychkov, DDG-NE to meet the Chairman of BATAN., Jakarta, 20-22 August 2014.

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TC missions – 2015• WORKSHOP OF HTGR TECHNOLOGY AND SAFETY,

APRIL 13-17, 2015– IAEA Expert Mission to provide Technical Assistance on

Pebble Bed HTGR Design Knowledge sharing of the for German HTGR Program

– Topics presented and discussed included: Design and Licensing process; Codes and standards; Design assessment and approval; Independent safety assessment; Document / SAR preparation and chapters; Safety analysis case studies and Management systems.

– The expert mission was successful in providing Indonesia with detailed knowledge and shared experiences on the HTGR Technology and Safety with specific focus on the experience in the German programme and the HTR-Module experiences.

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‾ Hands-on training on Software Packages used for core design and system safety analysis

‾ Focus on VSOP94 and FLOWNEX: enable participants to experience first-hand the pitfalls, typical errors and reasons for best practises in setting up simulation models.

HTGR training coursesIAEA Course on High Temperature Gas Cooled Reactor Technology

• Regular Budget Activity but the course was hosted by BATAN, 19 – 23 October 2015, Serpong, Indonesia

• attended by more than 40 participants from 17 IAEA member states

Proved to be very useful for both experts and new-comers to the HTGR technology

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TC Missions 2016• Expert Mission INS2016/01/01; 5 – 9 September 2016 • HTGR Fuel Engineering,

– Coated Particle Fuel Experience base (Experience, Failure mechanism,

– Specifications, Irradiation, Safety testing, PIE, Analysis methods)– Design and performance requirements (pebble and prismatic

considerations, performance requirements)– Fuel Qualification Program (fabrication, test programs, experiences)– HTR Fuel Cycle Concept (alternative cycles, thorium)– Fluidized bed PB-CVD Triso Coated Particle Production (Theory,

material and process)• Essential aspect of coated particle evaluation and the HTGR

safety case

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TC Missions BATAN on TRISO Fuel and PSAR- 2016• Expert Mission INS2016/02/01: 19-23 September

2016• HTR fuel kernel fabrication (Training and trouble-

shooting of process)– I. EXPERIENCE BASE AND ITS RELATED THEORY:

• A. Troubleshooting, discussion and follow up of the existing sol-gel precipitation column system and AWD system.

• B. Troubleshooting discussion and follow up of thermal treatment (Calcination, reduction, sintering).

• C. Troubleshooting discussion and follow up of supporting facility: VAC, Health physics equipment, media & energy supply.

– II. SUPERVISION AND PRACTICAL OF UO2 KERNEL PREPARATION USING SURROGATE MATERIAL:

• A. Sol preparation and its experimental parameters.• B. Spherical Liquids droplet formation and its experimental

parameters.• C. AWD Process and its experimental parameters.• D. Thermal treatment (calcination, reduction, sintering) and its

experimental parameters.• Included practical instructions, safety practices and

recommendations on equipment upgrades

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• INS2016/03/01: BATAN: 21 November –2 December 2016

• Expert Mission on Review of the Experimental Power Reactor (EPR) Concept Design and Preliminary Safety Analysis Reports

– The purpose is to review and discuss the concept design and safety documentation of the RDE.

– 1st Week: Individual and team review on the design and safety of RDE conceptual design.

– 2nd Week: completing a summary of the review and discuss the result to BATAN's engineers; write a summary report with findings and recommendations

• Supported by team of 4 experts and IAEA TO

– Experts from Japan, South Africa, UK, The Netherlands.

• The safety analysis report (SAR) of Reaktor Daya Eksperimental (RDE) was reviewed – it includes detailed information on the design and its safety features. (20 chapters)

TC activities - 2016

• INS9026: BAPETEN (Extra-budgetary funds)• Expert Mission on Modular HTGR Safety Philosophy, Safety Requirements and Evaluation. 12-16 December

2016– Modular HTGR safety philosophy, safety requirements and evaluation; HTGR Accident Analysis; Tools and software; V&V;

DBA and analysis; Licensing approach and licensing challenges• Expert mission on Modular HTGR coated particle fuel safety and supporting analysis. 5-9 December 2016

– Modular HTGR coated particle fuel safety; Coated Particle Fuel Experience base (Experience, Failure mechanism, Specifications, Irradiation, Safety testing, PIE, Analysis methods); Design and performance requirements; - Fuel Qualification Program (fabrication, test programs, experiences); Operational and Safety analysis to determine fuel conditions in NO and accidents; HCP code system and tools; Analysis of fuel performance and fission product release (software codes and application); Spent fuel and waste;

• Scientific fellowships:– 10 personnel from BAPETEN to visit GRS in Germany– Subject areas: Regulatory overview, codes and standards, source term, atmospheric dispersion and dose assessment, I&C,

Accident analysis, definition of DBA• The availability of substantial extra-budgetary funds allow the implementation of an extensive

programme to enhance the human resource capacity at the regulator

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TC activities – 2017: RDE review• Expert Mission on Review of the Experimental Power Reactor Updated Design

and Safety Analysis Report: Review of Start of Basic Engineering Work• (INS2016 - EVT1703146) 16-20 October 2017

– Assessment of the Engineering Work performed as part of the Basic Design Phase – Core Graphite Structural Design and Modelling – Overview of the Physics and Safety Analyses

• Supported by team of 4 experts and IAEA TO– Experts from China, South Africa, UK, The Netherlands.

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• INS9027 BAPETEN– Expert Mission for Safety Classification, Quality,

Codes and Standards of SSCs for HTGRs; 9 - 13 October 2017;

– Expert Mission for Safety assessment of HTGRs using HCP and related software; 11 – 15 December 2017

TC activities – 2018 - 2020• INS9027 BAPETEN

– SV to KAERI to receive training on Gamma+, DeCart2d, and CAPP codes for HTGR safety analysis.

– SV to National Nuclear Safety Administration (NNSA), INET and HTR10, Beijing, China.

• INS2016 : Expert mission on Technology development for BATAN HTR fuel development programme (27 August until 7 September 2018)

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• INS/1/028: BATAN– Expert Mission to review the

Detailed Design and Main Component of Reaktor Daya Eksperimental, a pebble bed high temperature reactor; 25 February –1 March 2019

• INS9027 BAPETEN – TC Expert Mission to Support

BAPETEN to Establish a PIRT (Phenomena Identification and Ranking Table) to Facilitate Regulatory Review and Assessment of HTGRs; 24 – 27 June 2019 2020: SMR deployment refocus

Other support

• International Conference on Nuclear Energy Technologies and Sciences

• ICoNETS 2015, Denpasar – Bali, Indonesia; 15 – 16 October 2015

• ICoNETS 2017, Makassar, Indonesia; 12 October 2017• Symposium of Emerging Nuclear Technology and Engineering

Novelty (SENTEN 2018) 4-5 July 2018, Palembang, Indonesia • IAEA Presented: Research and Development on High

Temperature Gas-Cooled Reactors /SMRs:IAEA support to Embarking Countries

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Activities 2020 .. and beyond• INS 2017

– Activities to be redefined (R&D for HTGRs) – Added SMR deployment focus

• INS 9027– Outstanding activities of value was identified– No implementation due to Covid-19

• 10th International Conference on High Temperature Reactor Technology (HTR2021) in Yogyakarta, Indonesia, June 2021 in cooperation with the IAEA

• INGSM meeting – 2022 (Graphite)

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Thank you!For inquiries on SMR and HTGRs , please contact:

Mr Hadid Subki

IAEA Nuclear Power Technology Development Section

M.Subki@iaea.org