High Temperature Gas Cooled Reactors

Transcription

1 High Temperature Gas Cooled Reactors Frederik Reitsma Gas-Cooled Reactors Technology Nuclear Power Technology Development Section Division of Nuclear Power Department of Nuclear Energy 11th GIF-IAEA Interface Meeting IAEA Headquarters, Vienna February th GIF-IAEA Interface International Atomic Energy Agency 1

2 Technology Development for HTGRs Objectives Foster international exchange of information related to advances in GCR technology Provide a forum for the collaboration of R&D efforts related to GCR technology Support Member States by providing an understanding of state-of-the-art GCR technology Focus on modular HTGRs Activities High Fidelity Analysis Tools, Benchmarking and Uncertainty Analysis Technology Development for HTGRs High temperature Performance of coated particle fuel and high temperature materials Plan and organize Consultancy and Technical Meetings Manage Coordinated Research Projects (CRPs) Make contributions to the Advanced Reactor Information System (ARIS) and the SMR booklet Coordinate efforts with other sections and International Organizations; manage Technical Working Groups (TWGs) for Gas Cooled reactors to help develop future project activities Process heat applications / cogeneration / thermal extraction of minerals Support to ARIS, HTGR knowledgebase and Nuclear Graphite Knowledge Base 11th GIF-IAEA Interface 2

3 IAEA activities supporting these areas through Member State activities The HTGR Technology pillars TM CRP TC Nuclear Power Technology Development Gas Cooled Reactors Expert missions Knowledge Training 11th GIF-IAEA Interface 3

4 Cooperative Research Projects (CRPs) Improved Understanding of the Irradiation Creep Behaviour of Nuclear Graphite ( ) HTGR Reactor Physics, Thermal-Hydraulics and Depletion Uncertainty Analysis ( ) Modular High Temperature Gas Cooled Reactor Safety Design ( ) Uranium/Thorium Fuelled High temperature Gas Cooled Reactor Application for Energy Neutral and Sustainable Comprehensive Extraction and Mineral Product development Processes (2015 ongoing) 11th GIF-IAEA Interface 4

5 I. CRP on Graphite Irradiation Creep Behaviour Background: The graphite core components are, in addition to normal mechanical loads, subjected to additional stresses due to neutron irradiation induced dimensional change and thermal gradients Stresses in the graphite core are relaxed by irradiation induced creep This delays the onset of damaging cracks... UK AGRs continue in operation only because of the presence of creep... For future HTR deployment: it is important to be able to confidently predict the irradiation induced creep strain in a component as a function of dose, temperature, and stress. The behaviour of graphite structures, reflector and fuel components thus need to be evaluated as part of operational and accident safety cases 11th GIF-IAEA Interface 5

6 I. CRP on Graphite Irradiation Creep Behaviour Some outcomes: Major reviews of irradiation-damage mechanisms at all scales undertaken New data on effects of neutron irradiation on crystal structure revealed by X ray diffraction studies of irradiated graphite; Existing creep models reviewed; Creep database established Participation The seven MS participating: United States of America; United Kingdom; The Netherlands; China; Japan; South Korea; Ukraine Two IAEA TECDOC publications are planned as the final outcome of these activities. The titles are: Improving the Understanding of Irradiation-Creep Behaviour in Nuclear Graphite Part 1: Models and Mechanisms: Ready to be sent for publication Part 2: Recent Developments: Still under preparation 11th GIF-IAEA Interface 6

7 II. Uncertainty in design and safety analysis Determine the uncertainty in HTGR calculations at all stages of coupled reactor physics, thermal-hydraulics and depletion calculations Use well defined test cases to propagate uncertainties Develop a methodology but also quantify the most important uncertainties in HTGR design and safety analysis 10 organizations 7 member states Closely follow the OECD LWR Uncertainty Benchmark 3 rd RCM was hosted by INL, USA from 9-12 May th RCM scheduled for May 2017 in Vienna 11th GIF-IAEA Interface 7

8 Multiplication Factor Uncertainty Results (With Double heterogeneity modelled as explicit regular lattice) Case/Model TSUNAMI/KENO-VI lattice % k/k ± σ Exercise I-1a Fresh CZP Exercise I-1a Fresh HFP Exercise I-2a (Av burnup) CZP Exercise I-2a (Av burnup) HFP Exercise I-2b (+ high burnup) CZP Exercise I-2b (+ high burnup) HFP Exercise I-2c (+ Fresh) CZP Exercise I-2c (+ Fresh) HFP Exercise I-2d (+ reflector) CZP Exercise I-2d (+ reflector) HFP Uncertainties increase with temperature and burnup 11th GIF-IAEA Interface 8

9 Isotopic contributions to uncertainty Neighbouring pebbles with ~98,000 MWd/te Covariance matrix contributions to uncertainty in eigenvalue Nuclide reaction % k/k ± σ Exercise I-2a (average burnup) HFP Pu nubar Pu nubar ± U n,gamma 238 U n,gamma 0. ± U nubar 235 U nubar ± Xe n,gamma 135 Xe n,gamma ± Pu fission Pu n,gamma ± Exercise I-2b (+ high burnup) HFP Pu nubar Pu nubar ± U n,gamma 238 U n,gamma ± Pu fission Pu fission ± Pu fission Pu n,gamma ± Pu n,gamma Pu n,gamma ± Burnup effect: Uncertainties increase Pu uncertainties more important 135 Xe(n,γ) and graphite capture or elastic scattering 11th GIF-IAEA Interface 9

10 III. Modular High Temperature Gas-cooled Reactor Safety Design CRP on Modular High Temperature Gas Cooled Reactors Safety Design To develop a process for establishing Safety Design Criteria at the plant and major Structure, System, and Component (SSC) level for modular HTGRs. To Implement the process for representative modular designs; To establish the Safety Design Criteria for the representative designs, with associated technical background, so as to provide the technical information for the future separate activities of the development of IAEA Safety Standards for HTGRs with the cooperation of the department of Nuclear Safety and Security of IAEA. Implementation started December 2014 Good support for the CRP 10 participating organizations from 9 member states: China, Germany, Indonesia, Kazakhstan, Korea (Republic of), Japan, UK, Ukraine, USA 1st RCM took place 9-12 June nd RCM took place June rd RCM scheduled for June 2017 Planned outcomes: NE series report: Modular High Temperature Gas-cooled Reactor Safety Design Criteria TECDOC: Modular High Temperature Gascooled Reactor Safety Design Methodology and Implementation Examples 11th GIF-IAEA Interface 10

11 IV. HTGRs applications for energy neutral sustainable comprehensive extraction and mineral products development A future more sustainable option to perform comprehensive extraction of resources / minerals by using thermal processing also do U/Th extraction as by product Techno-economic investigations on the use of HTGRs as heat/electricity supplier for minerals and uranium/thorium recovery from unconventional resources; phosphate rock using the thermal process during phosphate fertilizer production; copper and gold ores during copper and gold mining/extraction; rare earth elements mining; Create a platform for experts in various areas to exchange knowledge and ideas: Resources and products Mineral processing High Temperature Reactors 1 st RCM took place in Nov nd RCM scheduled for 3-6 July 2017 Need more contributions to the thermal process modelling and coupling to the HTR and mineral process plant 11th GIF-IAEA Interface 11

12 Meetings and Activities Technical Working Group Gas Cooled Reactors Training course Tecdoc drafted / planned Re-evaluation of maximum temperatures Technical Cooperation (TC) support 11th GIF-IAEA Interface 12

13 Technical Working Group - GCRs GCR-TWG: Members: China, France, Germany, Indonesia, Japan, Korea (Rep. of), Netherlands, Russian Federation, South Africa, Switzerland, Turkey, Ukraine, United Kingdom, United States of America OECD/NEA, European Commission Gen-IV Forum. New interest from Poland and Singapore Focus mostly on HTGRs Advisory role on major development areas and IAEA activities Meet every 24 months Next meeting scheduled Q4 of 2017 Previous scheduled date of March 2017 not possible 11th GIF-IAEA Interface 13

14 HTGR training courses IAEA Course on High Temperature Gas Cooled Reactor Technology under development as part of a long term plan and knowledge preservation Course hosted by INET October 2012, Beijing, China The course was attended by 35 participants from 10 IAEA Member States Course hosted by BATAN, 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 11th GIF-IAEA Interface 14

15 NPTDS HTGR Activities Re-evaluation of maximum temperatures Series of Technical Meetings to re-evaluate the maximum operating and accident conditions of fuel and structural materials for High Temperature Reactors (HTRs): To enhance and evaluate the safety characteristics of modular HTGRs in the light of the Fukushima Daiichi Accident Technical Meeting on Re-evaluation of Maximum Operating Temperatures and Accident Conditions for High Temperature Reactor (HTR) Fuel and Structural Materials, Jan 2015 Technical Meeting on High-Temperature Qualification of High Temperature Gas Cooled Reactor Materials, Jun 2014 Technical Meeting on the Safety of High Temperature Gas Cooled Reactors in the Light of the Fukushima Daiichi Accident, 8-11 Apr 2014 Technical Meeting on Re-evaluation of Maximum Operating Temperatures and Accident Conditions for High Temperature Reactor (HTR) Fuel and Structural Materials, Jun 2013 Technical Meeting on Re-evaluation of Maximum Operating Temperatures and Accident Conditions for High Temperature Reactor (HTR) Fuel and Structural Materials, Jul 2012 TECDOC under preparation: Reevaluation of Maximum Operating Temperatures and Accident Conditions for High Temperature Reactor (HTR) Fuel and Structural Materials 11th GIF-IAEA Interface 15

16 TC support (HTGR technology) Technical support on request by member states Example of expert missions to Indonesia Support Indonesia BATAN on HTGRs / the experimental power reactor Evaluate the Research and Development Project on HTGRs HTR technology and safety - German experience Software modelling HTR fuel engineering Concept design review Support Indonesia BAPETEN on HTGR licensing preparations Modular HTGR coated particle fuel and supporting analysis for fuel performance Modular HTGR Safety Philosophy, Safety Requirements and Evaluation Scientific fellowships 11th GIF-IAEA Interface 16

17 HTGR related portals or database 11th GIF-IAEA Interface 17

18 Objective and Reliable Source of Information: ARIS Database 11th GIF-IAEA Interface 18

19 Newest HTGR designs information Update of booklet Advances in Small Modular Reactor Technology Developments was published in August HTGR designs included 11th GIF-IAEA Interface 19

20 IAEA Nuclear Graphite Knowledge Base to support the preservation and sharing of expert knowledge and experience, across the international Graphite Community. 11th GIF-IAEA Interface 20

21 Nuclear Graphite KB seek to learn from the behaviour of existing graphites how new graphites will behave and how existing graphites will perform at fluences we have not yet reached The knowledge base contains two levels of knowledge: General information on the subject of Nuclear Graphite Specialist knowledge, secured for members of the international project All data captured in Microsoft Excel (>34,000 lines) Links provided to source documents and QA evaluation Taxonomy under development and testing of automated tools The Nucleus Sharepoint site is hosted and maintained by IAEA The 17th International Nuclear Graphite Specialists Meeting was hosted by IAEA (5 8 September 2016), Vienna, Austria All records of the INGSM conferences (since 2000) are available on the KB site 11th GIF-IAEA Interface 21

22 PC Based Basic Principle Simulators No HTGR simulator available Initial specification for a HTGR simulator has been developed Extra-budgetary funds will be required for implementation Important to demonstrate the advanced safety characteristics Simulator Name Type Developer Funded by Standard 2-Loop PWR 2-Loop Large PWR Advanced PWR WWER-1000 Standard BWR Advanced BWR Conventional Pressurized Heavy Water Reactor (PHWR) A generic two-loop PWR with inverted U-bend steam generators and dry containment similar to existing Westinghouse, Framatome or KWU designs. Represents Korea s 1000 MWe Optimized PWR Largely based on Westinghouse AP- 600 PWR with passive safety systems WWER-1000 reactor is a vesseltype Light Water Reactor where chemically purified water with boric acid serves as coolant and moderator. A typical 1300 MWe BWR with internal recirculation pumps similar to ABWR plant Represents GE s ESBWR with passive safety features Represents a 700 MWe class CANDU-6 reactor Micro-Simulation Technology of USA KAERI Cassiopeia Technologies Inc. (CTI) of Canada Moscow Engineering and Physics Institute in Russia Cassiopeia Technologies Inc. (CTI) of Canada Cassiopeia Technologies Inc. (CTI) of Canada Cassiopeia Technologies Inc. (CTI) of Canada Advanced PHWR Represents the ACR-700 system Cassiopeia Technologies Inc. (CTI) of Canada Micro-Physics Simulator (Lite) Core Physics Simulator (Part Task) Nuclear Engineering Ltd. (NEL)- Japan IAEA Korea IAEA Russia IAEA IAEA IAEA IAEA NEL Japan ipwr Small Modular Reactor (SMR) TECNATOM- Spain IAEA 2017 PWRsim Pressurized water reactor KSU Sweden KSU 2017 BWRsim Boiling Water Reactor KSU Sweden KSU th GIF-IAEA Interface 22

23 Concluding remark The IAEA support member states interested in HTGRs in many areas: Information exchange Cooperative research projects Meetings on topics of common interest Knowledge preservation Technical cooperation expert missions Publications Training 11th GIF-IAEA Interface 23

24 Concluding remarks... GIF-IAEA interface / opportunities to cooperate Important to coordinate (and not duplicate) activities with other international organizations Already good examples with OECD NEA prismatic benchmarking and uncertainty studies Stakeholders are different but the IAEA HTGR community and the GEN-IV VHTR system members represents a substantial overlap Areas of common interest that could be explored Safety (to be discussed separately) Computational methods, V&V, Uncertainty studies Economical analysis Knowledge preservation (graphite database, other) Training and course material 11th GIF-IAEA Interface 24

25 Thank you! Frederik Reitsma Gas-Cooled Reactors Technology Nuclear Power Technology Development Section 11th GIF-IAEA Interface 25