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Technology Support for Long Term NP Deployment in Scope of Sustainability and Climate Change Mitigation
Nuclear Power Technology Development Section
INPRO Dialogue Forum on the Potential of Nuclear Energy to Support the Sustainable Development Goals, Including Climate Change Mitigation
IAEA Headquarters, Vienna. 6-8 June 2017
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Outline• NPTDS Support to
Member States in Nuclear Reactor Technology Assessment for Near Term Deployment
• SMR• HTGR• WCRs• Non-Electric Applications
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NPTDS Support to Member States in Nuclear Reactor Technology Assessment for Near Term Deployment
Stefano Monti – Section Head
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NPP in the World(as of 2 May 2017)
449 in operation 11% world electricity 30% low-carbon
60 under construction (2/3 in Asia)
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Energy 2016
1.1 B peopleno access to energy2.6 B people
rely on biomass1 B people
no health caredue to energy poverty
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Energy Challenge
PopulationEnergy demandEnergy security
EnvironmentClimate change
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Advanced Reactors and their Applications
CAREM-25, HTR-PM, KLT-405, RITM-200, AHWR, NuScale,
SMART, 4S, PRISM…
ABWR, ACR 1000, AP1000, APWR, Atmea-1, CANDU 6, EPR, ESBWR, VVER 1200,
CAP1400, APR1400, HPR1000…
LFR, GFR, SFR, SCWR, VHTR, MSR,
ADS
INNOVATIVE
SMRs
EVOLUTIONARY
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SMR
Fast Reactors
WCR
GCR +
MSR
NEApp
Technology Development for Advanced Reactor Lines
NPTDS Sub-Programme Structure
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Macro Areas for Each Reactor Line and Non-Electric Applications
Information Exchange
Modelling and Simulations
Development of Methodologies
Safety
Technology Support
Education and Training
Knowledge Preservation
Databases & Tool-kits
Assist MSs with national nuclear programmes; Support innovations in nuclear power deployment; Facilitate and assist international R&D collaborations
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NPTDS Support to Member States Exchange of information on all reactor technologies (LWR, HWR, FR, ADS, GCR,
SMR, Non-electric applications) TWGs Objective information to all Member States on reactor technology status and
development trends: Advanced Reactor Information System (ARIS) Reactor technology assessment and selection approaches for near-term
deployment embarking countries Technology Roadmap for SMRs and Advanced Reactor Deployments Collaborative researches (CRP, ICSP) for improving safety, reliability, analysis
methods and tools, availability and economy of advanced reactors Support to NS for development of safety standards for advanced reactors Education & Training: Workshops, Training Courses, Schools, IT tools Knowledge preservation PC-based simulators development, maintenance and distribution Toolkits for non-electrical applications and Sever Accident Management Cooperate with GIF, OECD/NEA and EC in the area of advanced reactors and
their applications
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https://aris.iaea.org/
Evolutionary, SMR and Innovative Reactors
https://aris.iaea.org/
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IAEA Technology Assessment• Nuclear Reactor Technology
Assessment for Near Term Deployment IAEA NE-Series Document # NP-T-1.10
• Formalized process • Owner exercise • ARIS database provides technical Design
Descriptions of advanced NPPs
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NPTDS Support to Member States
SMR and HTGR Technologies
Frederik Reitsma Hadid Subki
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News Update on SMRCountries Recent Milestone
Argentina CAREM25 is in advanced stage of construction. Aiming for fuel loading & start-up commissioning in 2019
Canada CNSC received request to perform design reviews for several SMR designs, mostly non-water cooled, including a molten salt reactor (MSR) design
China
• HTR-PM is in advanced stage of construction. Commissioning expected in 2018. • ACP100 undertook IAEA generic reactor safety review. CNNC plans to build ACP100
in Fujian Island.• China has 3 floating SMR designs (ACP100S, ACPR50S and CAP-F)
Indonesia BATAN performing a conceptual design on experimental HTGR (10 MWth) based on the design from NUKEM-Germany and ROSATOM
Korea, Republic of SMART (100 MWe) by KAERI certified in 2012. SMART undertakes a pre-project engineering in Saudi Arabia, for near-term construction of 2 units.
Saudi Arabia • K.A.CARE performs a PPE with KAERI to prepare a construction of 2 units of SMART• An MOU between K.A.CARE and CNNC on HTGR development/deployment in KSA
Russian Federation
• Akademik Lomonosov floating NPP with 2 modules of KLT40S is in advanced stage of construction. Aiming for commissioning in 2019.
• AKME Engineering will develop a deployment plan for SVBR100, a eutectic lead bismuth cooled, fast reactor.
United Kingdom• Rolls Royce has started design activities on SMR; many organizations in the UK work on
SMR design, manufacturing and supply chain preparation• Identified potential sites for future deployment of SMR
United States of America
• NuScale (600 MWe from 12 modules) submitted for NRC design review in January 2017. Aiming for deployment in Idaho Falls.
• TVA submitted early site permit for Clinch River site, design is still open.
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https://en.wikipedia.org/wiki/File:Flag_of_Argentina.svghttps://en.wikipedia.org/wiki/File:Flag_of_Canada.svghttps://en.wikipedia.org/wiki/File:Flag_of_the_People's_Republic_of_China.svghttps://en.wikipedia.org/wiki/File:Flag_of_Indonesia.svghttps://en.wikipedia.org/wiki/File:Flag_of_South_Korea.svghttps://en.wikipedia.org/wiki/File:Flag_of_Saudi_Arabia.svghttps://en.wikipedia.org/wiki/File:Flag_of_Russia.svghttps://en.wikipedia.org/wiki/File:Flag_of_the_United_Kingdom.svghttps://en.wikipedia.org/wiki/File:Flag_of_the_United_States.svg
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SMRs Estimated Timeline of Deployment
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SMRs Under Construction for short term deployment – the front runners …
Country ReactorModel
Output(MWe)
Designer Number of units
Site, Plant ID, and unit #
CommercialStart
Argentina CAREM-25 27 CNEA 1 Near the Atucha-2 site 2019
China HTR-PM 250 Tsinghua Univ./Harbin
2 mods,1 turbine
Shidaowan unit-1 2018
RussianFederation
KLT-40S(ship-borne)
70 OKBMAfrikantov
2modules
Akademik Lomonosov 2019
CAREM-25 KLT-40S
Page 17 of 37
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HTR-PM
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Other developments of SMRs
• Canada– 4 SMR designs submitted for pre-licensing vendor design review with
the Canadian Nuclear Safety Commission (CNSC)– Aimed for deployment in remote areas– 2 x HTGRs (U-battery, UltraSafe), Terrestrial Energy integral molten
salt reactor design concept; LeadCold Reactor Inc. SEALER design concept
• United Kingdom– "ambitious" nuclear research and development program proposed– SMRs identified as a focus area to develop and to maximize the
opportunities for UK industry• Not a complete list…
– Many small startup companies developing a range of SMRs across many member states
– (about 50 SMR designs already captured in the IAEA booklet)• Many newcomer countries interested
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Development status - HTGRs
• HTR-PM construction of a commercial demonstration plantmodular 2 x 250MWth; operation in 2018; dummy fuel loadedShidao Bay, Shandong province, China
• Commercial 600MWe NPP under developmentfeasibility review passes for 2 NPPs at Ruijin city, Jiangxi province construction expected to start in 2018may be first approved inland NPP site
Past Experience | Current test reactors
• Wealth of past experience
• test reactors in Japan and China
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Higher (↑20-50%) efficiency in electricity generation than conventional nuclear plants
Potential to participate in the complete energy market
High temperatures (750-1000oC)
Use of coated particle fuel
Helium coolant; Graphite moderated
Small reactor units (~100 - 650 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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Significantly improved safety potential:
Coated particle fuel contain almost all fission products for the expected operating and postulated accident temperatures in a modular HTGR.
The failure mechanisms are decoupled and totally independent.
One coated particle failure cannot lead to the failure of a neighbouring CP, as it is only driven by the maximum fuel temperature (and a statistical process)
A failure also has no effect on the cool-ability of the fuel as a failure will not change the heat removal path.
Core design and operating parameters ensure large margins
No credible events can lead to early large release - No core melt of an all ceramic core
Decay heat removal by natural means only – can lose all the coolant and external cooling (station blackout)
Most transients are slow (develop over hours and days) and no operator actions are needed
Special attention needed to limit water ingress and to mitigate massive air ingress
Safety of HTGR technology
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HTGR focus areas : Support to MS
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• CRPs• HTGR Reactor Physics, Thermal-Hydraulics
and Depletion Uncertainty Analysis• Modular High Temperature Gas Cooled
Reactor Safety Design• HTGR Application for Sustainable Extraction
and Mineral Product development Processes – with NEFW-NFCM
• Example of Planned Publications• TECDOC: Improving the Understanding of
Irradiation-Creep Behaviour in Nuclear Graphite Part 1: Models and Mechanisms
• TECDOC: Graphite Oxidation in Modular HTGR
• TECDOC: Performance of German mixed Th-U and UO TRISO Fuels
Information Exchange:- TWG-GCR- Nuclear Graphite Knowledge Base- Technology Needs for Increased Operating and Accident Temperatures
Further development of HTGR training and educational simulator
specification- Training workshop- Draft specification
(unfunded)
TC support:- Indonesia experimental power reactor (BATAN and BABETEN)- KA CARE (Saudi Arabia) on HTGR Technology
Portals / DB:Support to ARIS,
HTGR knowledgebase and Nuclear Graphite
Knowledge Base
Technology Development for
HTGRs
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Agency support related to HTGR technology – Indonesia project
• Supported by TCAP• Indonesia did a Technical assessment including HTGRs as one of the
options studied using IAEA NE-Series Document # NP-T-1.10• Expert missions to Indonesia
– Support Indonesia BATAN on HTGRs / the experimental power reactor
• Evaluate the Research and Development Project on HTGRs• HTR technology, fuel, safety, software• RDE 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
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• Newcomer countries are expressing interest in SMRs (including that with advanced reactor technology for near term deployment)
• Main reasons (and risks) were discussed:– Better fit to their needs– Newcomers want to participate in the development of the technology– Cogeneration market– Enhanced safety characteristics– No proven track record or commercial offerings
• Division of Nuclear Power supports newcomer countries that express interest in SMRs– Use of all the mechanisms available (technical meetings, CRPs)– Member state specific needs are addressed through TC projects and
missions
Summary
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NPTDS Support to Member States
WCRs Technologies
Matthias Krause Tatjana Jevremovic
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WCR Technology Development Team Core Business
HWRs
SCWRsSevere
Accidents
RTA
E & TSimulators
LWRs
Assist MSs with national nuclear programmes; Support innovations in nuclear power deployment; Facilitate and assist international R&D collaborations.
Information Exchange
Modelling and
Simulations
Safety
Development of
Methodologies
Technology Support
Education and Training
Knowledge Preservation
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WCR Activities in 2016 • Technical Meetings on
Phenomenology and Technologies Relevant to In-Vessel Melt Retention and Ex-Vessel Corium Cooling” in Shanghai, China
Heat Transfer, Thermal-Hydraulics and System Design for SCWRs, UK Materials and Chemistry for SCWRs
• Data Bases ARIS THERPRO
• Training Courses on: Science and Technology of SCWRs Understanding Technology and Physics of WCRs (RoK, Mexico and
Tunisia) Reactor Technology Assessment (Kenya) Use of CFD in NPP Design, SJTU, Shanghai, China
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WCR Activities in 2017 • Coordinated Research Projects (CRPs) – 3 ongoing and 2 new
1. Computational Fluid Dynamics Codes for Design (2012-2018)2. Prediction of Axial and Radial Creep in Pressure Tubes (2013-2017)3. Thermal Hydraulics of SCWRs (2014-2018)4. Probabilistic Safety Analysis [Benchmark] for Multi-unit, Multi-type NPP Sites (2017-2020)5. Methodology for Developing Pipe Failure Rates for Advanced Water-cooled Reactors (2017-
2020)• International Collaborative Standard Problems (ICSPs)
1. Numerical Benchmark Database for PHWR Transients (2016-2019)• Technical Meetings on
New Concepts in Innovative Water Cooled Reactor Technology, 13 – 17 March Developing a Systematic Education and Training Approach Using Personal Computer Based
Simulators for Nuclear Power Programmes, 15 – 19 May Workshop on Advances in Understanding the Progression of Severe Accidents in BWRs, 17 –
21 July Severe Accidents Modelling and Simulations, 9 – 12 October
• Consultancy Meetings Two meetings to develop proposals for two new CRPs: Presentation Effective Utilization of THERPRO Data Base, 22 – 23 February
• Data Bases ARIS THERPRO
• Training Courses on: Understanding Physics and Technology of WCRs through Simulators: 6 new courses Reactor Technology Assessment (forthcoming Ghana) Use of CFD in NPP Design, XJTU, China
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CRPs on Water Cooled Reactor Technologies
Recently Completed
CurrentlyOn-Going Planned
SCWR Heat Transfer Behaviour and Code Testing
PHWR Radial Pressure Tube Creep PredictionUse of CFD Computer Codes for NPP Design
SCWR Thermal-Hydraulics Phenomena
MUPSA Benchmark
METHODOLOGY FOR DEVELOPING PIPE FAILURE RATES FOR ADVANCED WATER-COOLED REACTORS
Fictitious PSA ModelCombined (Internal Events, Internal Flooding and Fire) CDF (= 4.82E-5) Distribution by Initiator
Loss of Offsite Power 1%
Medium or Large Break LOCA 2%
Small-Break LOCA 4%
Station Blackout 5%
Loss of Offsite Power - Train A or B 1%
Loss of Support System (CCW, IA, HVAC) 1%
Loss of ESF Train 7%
Loss of DC Power 0%
Loss of Condensate, Feedwater or Condenser
Vacuum 2%Internal Flooding - Aux. Bldg. Service Water Piping System
Breach 29%
Internal Flooding - Aux. Bldg. Fire Protection Water Piping
System Breach 11%
Interfacing Systems LOCA 19%
Fire 9%
ATWS 1%
Turbine Trip 3%
Steam Generator Tube Rupture 1%
Reactor Trip ("Uncomplicated") 6%
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CRP on Understanding and Prediction of Thermal-Hydraulics Phenomena Relevant to SCWRs
(2014-2018)
2nd RCM, Mumbai, India, 23-27 November 2015
• Title: “Understanding and Prediction of Thermal-Hydraulics Phenomena Relevant to SCWRs”, 2014-2018.
• Overall objective:– To improve the understanding of T/H phenomena and prediction accuracy of
T/H parameters related to SCWRs; and– To benchmark numerical toolsets for SCWR T/H analyses.
• 12 Participating Institutes from 10 Member States and OECD/NEA hosting the database for the CRP; and
• The 2nd RCM held at BARC, India, November 2015.
The 3rd RCM to be held in Madison, USA, June 2017.
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CRP on Computational Fluid Dynamics Codes for Design (2013-2018)
• Objectives:– Assess the capabilities of CFD to address various specific design aspects through validation
benchmarks– Assess the current capabilities of advanced CFD tools to contribute to the technology advance in
NPP design– Identify and document the gaps in the technology and the state-of-the-art of CFD in respect to
being considered an essential ingredient in the design process of advanced nuclear reactors• Participants:
– 14 Institutes participating from 11 Member States• Outcomes:
– Summary Review document (document maturity of CFD in addressing design issues for NPPs)– Informal Benchmark Specifications “White Papers”– Final CRP TECDOCs (summarize benchmark results)– CFD Training Course (1st course in Shanghai, Aug 29- Sept 2 2016; 2nd in planning stage)
• Meetings:– 1st RCM July 2013, 2nd RCM February 2015, 3rd RCM October 2016 in RoKorea,
4th in VIC 2017 Oct 7-10• Future Plans
– Document Status of CFD in NPP Design (NES) and 2 Benchmark Reports (TECDOCs)– Possibility of a Phase 2 CRP if sufficient interest in more CFD benchmarks, e.g. ABWR Lower
Plenum Temperature Distribution (discuss on Friday in LWR group)
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New CRP on Probabilistic Safety Analysis (PSA) for Multi-Unit, Multi-Reactor Sites
• At many nuclear sites world-wide, several NPPs, either of the same or of different types, designs, or age, are co-located on a single site.
• Regulations generally recognize the potential for multiunit accidents, PSA of NPPs have mainly focused on estimating the risk arising from damage to a single NPP.
• Safety assessments based on deterministic and probabilistic approaches in which the risk at a site with multiple reactors can be represented by summing up the risks of individual units.
• simplified approach with several limitations ignores complex interactions during a severe
event impacting a multiunit site.
Fukushima accident lesson learned: Need to improve PSA methodologies when applied to multi-unit, multi-reactor-type nuclear sites.
Several methods have are being explored around the world to extend or “translate” per-unit PSA results to multi-unit site PSA results, such as core damage and large release frequencies.
This CRP will bring together experts from LWR and PHWR MSs to benchmark their practices, compare assumptions and results and recommend improvements to the "Framework and Process for Multi-unit Site PSA" (parallel NSNI Activity).
Example – Atucha, Argentina:• 2 unique PHWRs operating• 1 SMR under construction• 1 CANDU planned• 1 PWR possible
One NPP site with five different reactor types
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New CRP on METHODOLOGY FOR DEVELOPING PIPE FAILURE RATES FOR
ADVANCED WATER-COOLED REACTORS• Objectives:
– Increase the knowledge and understanding of the methodology in MSs on how to predict pipe failure rates for advanced WCRs that utilize the current state-of-knowledge regarding the five decades of extensive and well documented operating experience data on piping system components in operating WCRs
– Provide specific guidelines in consideration to the effect of new materials on piping reliability including the prediction of aging factor effects
– Develop common set of benchmarks
• 1st CM:– February 27 – March 2, 2017– 4 MSs and OECD participants developed a detailed proposal for
launching the CRP in 2018
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Human Capacity Building: Active Learning with Education and Training Courses Using PC Based Basic SimulatorsUnderstanding Physics and Technology of WCRs/FRs/HTGRs
No. Year Dates Title Location Funding Organization
1 1999 November 22-26
Workshop on Reactor Simulator Development Vienna, Austria
NPTDS
2 2000 16-27 October Workshop on the Application and Development of Advanced Nuclear Reactor Simulators for Educational Purposes
Trieste, Italy
NPTDS
3 2001 29 October to 9 November
Workshop on Advanced Nuclear Simulation Trieste, Italy
ICTP-NPTDS
4 2002 14 - 25 October Workshop on Advanced Nuclear Power Plant Simulation
Trieste, Italy
ICTP-NPTDS
5 2003 27 October – 7 November
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
6 2004 8 to 19 November
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
7 2005 31 October – 11 November
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
8 2006 3-7 July Workshop on NPP Simulators for Education Bucharest, Romania
TC Project ROM9026
9 2007 29 October - 9 November
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
10 2009 12 - 23 October Workshop on NPP Simulators for Education Trieste, Italy
ICTP-NPTDS
11 2011 3 - 14 October Workshop on Enhancing Nuclear Engineering through the Use of the IAEA PC-based Nuclear Power Plant Simulators
Milano, Italy
NPTDS
12 2012 3-4 October Present paper at European Nuclear Power Plant Simulation Forum 2012
Barcelona, Spain
NPDTS
13 2013 4 - 15 November Course on Physics and Technology of Water Cooled Reactors through the Use of PC-Based Simulators
Madrid, Spain
In cooperation
14 2013 03-07 June Interregional Course on Fundamentals of Pressurized Water Reactors with PC-Based Simulators
Daejeon, Korea
TC Inter-regional
27
15 2014 15-19 December Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Bangi, MALAYSIA
TC Funded 24
16 2015 16-28 February Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
Trieste, Italy
ICTP-NPTDS 35/ 118
17 2015 4-8 May Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Santiago, CHILE
TC Funded 15
18 2015 1-5 June Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Daejeon, Korea
In cooperation with KAERI
20
19 2015 22-27 November
Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Amman, Jordan
TC Funded 16
20 2015 7-18 December Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
TAMU, Texas
TC Funded 28
21 2016 May 23- June 3 Physics and Technology of PWRs with PC-based Simulators
Daejeon, Korea
In cooperation with KAERI
18
22 2016 11-15 July Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Tunis, Tunisia
In cooperation with AAEA
14
23 2016 24-28 October Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Ocoyoacac, Mexico
TC Funded
24 Pilot Training on WCR Technology and Severe Accidents Salt Lake City, USA Okayama University funded 13
25 IAEA/KAERI Regional Training Course on WCRs Technologies and Passive Systems: Competence Based Approach with PC-Based Basic Principle Simulators
KAERI, RoK TC and KAERI funded
26 Advanced WCRs: Physics, Technology, Passive Safety, and Basic Principle Simulators
Islamabad, Pakistan
TC and Pakistan supported
27 IAEA/VINATOM National Training Course on PWRs Technologies and Passive Systems: Competence Based Approach with PC-Based Basic Principle Simulators
Hanoi, Viet Nam
TC and VINATOM supported
28 Technology and Physics of WCRs and SMRs with PC based Simulators KAERI for Saudi Arabia
TC and Saudi Arabia supported
29 Understanding Technology and Physics of WCRs with the Use of PC based Simulators
ICTPItaly
ICTP, TC and NPTDS supported
2016
2017
No.
Year
Dates
Title
Location
Funding Organization
1
1999
November 22-26
Workshop on Reactor Simulator Development
Vienna, Austria
NPTDS
2
2000
16-27 October
Workshop on the Application and Development of Advanced Nuclear Reactor Simulators for Educational Purposes
Trieste, Italy
NPTDS
3
2001
29 October to 9 November
Workshop on Advanced Nuclear Simulation
Trieste, Italy
ICTP-NPTDS
4
2002
14 - 25 October
Workshop on Advanced Nuclear Power Plant Simulation
Trieste, Italy
ICTP-NPTDS
5
2003
27 October – 7 November
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
6
2004
8 to 19 November
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
7
2005
31 October – 11 November
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
8
2006
3-7 July
Workshop on NPP Simulators for Education
Bucharest, Romania
TC Project ROM9026
9
2007
29 October - 9 November
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
10
2009
12 - 23 October
Workshop on NPP Simulators for Education
Trieste, Italy
ICTP-NPTDS
11
2011
3 - 14 October
Workshop on Enhancing Nuclear Engineering through the Use of the IAEA PC-based Nuclear Power Plant Simulators
Milano, Italy
NPTDS
12
2012
3-4 October
Present paper at European Nuclear Power Plant Simulation Forum 2012
Barcelona, Spain
NPDTS
13
2013
4 - 15 November
Course on Physics and Technology of Water Cooled Reactors through the Use of PC-Based Simulators
Madrid, Spain
In cooperation
14
2013
03-07 June
Interregional Course on Fundamentals of Pressurized Water Reactors with PC-Based Simulators
Daejeon, Korea
TC Inter-regional
27
15
2014
15-19 December
Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Bangi, MALAYSIA
TC Funded
24
16
2015
16-28 February
Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
Trieste, Italy
ICTP-NPTDS
35/
118
17
2015
4-8 May
Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Santiago, CHILE
TC Funded
15
18
2015
1-5 June
Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Daejeon, Korea
In cooperation with KAERI
20
19
2015
22-27 November
Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Amman, Jordan
TC Funded
16
20
2015
7-18 December
Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
TAMU, Texas
TC Funded
28
21
2016
May 23- June 3
Physics and Technology of PWRs with PC-based Simulators
Daejeon, Korea
In cooperation with KAERI
18
22
2016
11-15 July
Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Tunis, Tunisia
In cooperation with AAEA
14
23
2016
24-28 October
Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Ocoyoacac, Mexico
TC Funded
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TRAINING COURSESREACTOR TECHNOLOGY
ASSESSMENTA formal process of specifying key factors,based on country-specific protocols, assigning relative importance to each, and quantitatively evaluating each designin a consistent manner using reliable and comparable data, e.g. from ARIS andfrom vendors.
Recently conducted in:• Kenya (2016)• Mexico, Kazakhstan (2015)• Algeria, Bangladesh, Korea (2014)In planning:• Ghana
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NPTDS Support to Member States
Non-Electric Applications
Ibrahim Khamis
Rami El-Emam
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Cont
ents Introduction on Energy MarketIntroduction on Nuclear Cogeneration: Routes
Values Sustainability Climate Change
Nuclear Desalination
Nuclear District Heating
Nuclear Hydrogen ProductionTools & ToolkitsActivities on Non-Electric Applications & CogenerationSummary
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Energy Market
Energy consumption by application
They world’s energy consumption for heat and transportation !
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Non-Electric Applications & Nuclear Cogeneration
ValuesRoutes
Sustainability
Save Money
Save Energy
Save Environment
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Source: OECD, Environmental Outlook Baseline, 2011
Nuclear Cogeneration for Climate Change Mitigation (1)
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Current Status:
Total Number of Operating Reactors today is 449 reactor
with total net electrical capacity of 392,116 MWe
This is equivalent to annual reduction of 1 - 2 Million tonnes of CO2 emissions
Based on the type of fossil fuel would be used to cover this thermal demand
Assume: ~ 25% recovery of waste heat
Nuclear Cogeneration for Climate Change Mitigation (2)
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The need of Desalination?
50% Gulf region
17% N. America
10% Asia
8% N. Africa
7% Europe
1% Australia Regi
ons f
or g
row
ing
inte
rest
in d
esal
inat
ion
Water Stress by 2040
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The nexus of Desalination & Nuclear Power Plants
Desalination: need energy
– Waste heat (recovery using MED)
– Low quality steam (MED or MSF, or RO)
– Off-peak power (elect. For RO)
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NPP: need water
– During construction (RO)
– During operation to substitute makeup water (Hybrid)
– Quality industrial water
– In case of accident (RO)
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Nuclear Desalinationfrom Waste Heat
Improves overall efficiency
Improve economics
Use Off-Peak Power
Electric Power
Nuclear Desalination?
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Synergies in Nuclear desalination are a catalyst
for sustainable development Aktau, 1961 Aktau, 1975
Nuclear Desalination:Sustainable Development
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Nuclear District Heating
• Over 500 reactor years of operation
• The recovery of nuclear heat from present NPP is technically feasible• The primary heat transport line can be designed with low thermal losses even for
long distances, Recent developments in piping insulation allows transfer of heat for100 km with only ∼ 2% heat loss of the transported power
• Heat recovery enhances plant efficiency, provides a high energetic gain (+70%)
• The recovered heat is economically competitive
Environment !
in Paris: avoid ∼ 1.7 Million tons of CO2/year
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Nuclear Hydrogen Production
For Current nuclear reactors: Low-temperature electrolysis, Off-peak power or intermittent
Future nuclear reactors: High-temperature electrolysis Thermochemical cycles hybrid thermochemical cycles
Promising Technologies
Sustainability & Carbon footprint
Replacement of CO2 emitting fossil fuels
Saving of resources by 30-40%
Securing energy supply by reducing dependency on foreign oil uncertainties
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Tools & Toolkits on Non-Electric Applications and Nuclear Cogeneration
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DEEP can be used forperformance and costevaluation of various powerand seawater desalinationcogeneration configurations.
DE-TOP models the steam powercycle (Rankine cycle) of differentwater cooled reactors or fossilplants, and coupling with othernon-electrical applications.
HEEP is to Evaluates the economics of the most promising processes for hydrogen production TOOLKITS
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Ongoing CRP on Application of advanced low temperature desalination systems to support NPPs and non-electric applications (2012-2017)
IAEA Project on Non-Electric Applications
CRP on Assessing Technical and Economic Aspects of Nuclear Hydrogen Production for Near-Term Deployment (starts 2018)
Coordinated Research Programs CRP
Technical Meetings TM
Technical Meeting to Examine the Techno-Economics of and Opportunities for Non-Electric Applications of Small and Medium-Sized or Modular Reactors, Vienna, 29-31 May.
Technical Meeting to Examine the Role of Nuclear Hydrogen Production in the Context ofthe Hydrogen Economy, Vienna, 17–19 July 2017
6th TM of the Technical Working Group on Nuclear Desalination (TWG-ND), 13-15November 2017(closed to TWG-ND members)
Technical Meeting on the Responsibilities of Users and Vendors in Nuclear DesalinationProjects, VIC, 20-22 Nov
Activities on Non-Electric Applications
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Summary
A great opportunity for non-electric applications using nuclear power exists in the heat and transportation market.
Nuclear Cogeneration provide many incentives for better NPP economics, environment, and electrical grids.
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Thank you!
Time for questions and discussions!
Technology Support for Long Term NP Deployment in Scope of Sustainability and Climate Change Mitigation OutlineNPTDS Support to Member States in Nuclear Reactor Technology Assessment for Near Term Deployment NPP in the World�(as of 2 May 2017)Slide Number 5Energy 2016Energy ChallengeSlide Number 8NPTDS Sub-Programme StructureMacro Areas for Each Reactor Line and Non-Electric ApplicationsNPTDS Support to Member StatesEvolutionary, SMR and Innovative ReactorsIAEA Technology AssessmentNPTDS Support to Member States� �SMR and HTGR TechnologiesNews Update on SMRSMRs Estimated Timeline of DeploymentSMRs Under Construction for short term deployment – the front runners …Other developments of SMRsDevelopment status - HTGRsHTGRs CharacteristicsSlide Number 21HTGR focus areas : Support to MSAgency support related to HTGR technology – Indonesia projectSummary NPTDS Support to Member States� �WCRs TechnologiesWCR Technology Development Team Core BusinessWCR Activities in 2016 WCR Activities in 2017 Slide Number 29CRP on Understanding and Prediction of Thermal-Hydraulics Phenomena Relevant to SCWRs (2014-2018)CRP on Computational Fluid Dynamics Codes for Design �(2013-2018)New CRP on Probabilistic Safety Analysis (PSA) for Multi-Unit, Multi-Reactor SitesNew CRP on METHODOLOGY FOR DEVELOPING PIPE FAILURE RATES FOR�ADVANCED WATER-COOLED REACTORSHuman Capacity Building: Active Learning with Education and Training Courses Using PC Based Basic Simulators�Understanding Physics and Technology of WCRs/FRs/HTGRsTRAINING COURSES�REACTOR TECHNOLOGY ASSESSMENTNPTDS Support to Member States� �Non-Electric ApplicationsContents�Energy MarketNon-Electric Applications �& Nuclear CogenerationSlide Number 40Slide Number 41The need of Desalination?The nexus of Desalination & Nuclear Power PlantsNuclear Desalination �from Waste HeatSlide Number 45Slide Number 47Slide Number 48Tools & Toolkits on Non-Electric Applications and Nuclear CogenerationOngoing CRP on Application of advanced low temperature desalination systems to support NPPs and non-electric applications (2012-2017)Slide Number 51Thank you!