Technology Support for Long Term NP Deployment in Scope of ... IAEA NPTDS.pdf · in Scope of...

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

Outline• NPTDS Support to

Member States in Nuclear Reactor Technology Assessment for Near Term Deployment

• SMR• HTGR• WCRs• Non-Electric Applications

2

NPTDS Support to Member States in Nuclear Reactor Technology Assessment for Near Term Deployment

Stefano Monti – Section Head

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)

Energy 2016

1.1 B peopleno access to energy2.6 B people

rely on biomass1 B people

no health caredue to energy poverty

Energy Challenge

PopulationEnergy demandEnergy security

EnvironmentClimate change

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

SMR

Fast Reactors

WCR

GCR +

MSR

NEApp

Technology Development for Advanced Reactor Lines

NPTDS Sub-Programme Structure

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

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

11

https://aris.iaea.org/

Evolutionary, SMR and Innovative Reactors

https://aris.iaea.org/

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

NPTDS Support to Member States

SMR and HTGR Technologies

Frederik Reitsma Hadid Subki

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.

15

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

SMRs Estimated Timeline of Deployment

16

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

17

HTR-PM

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

18

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

20

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

21

HTGR focus areas : Support to MS

22

• 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

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

23

• 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

24


WCRs Technologies

Matthias Krause Tatjana Jevremovic

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

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

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

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%

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.

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)

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

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

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


Trieste, Italy

ICTP-NPTDS

7 2005 31 October – 11 November


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


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


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


Trieste, Italy

ICTP-NPTDS

6

2004

8 to 19 November


Trieste, Italy

ICTP-NPTDS

7

2005

31 October – 11 November


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


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


Daejeon, Korea


20

19

2015

22-27 November


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


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

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


Non-Electric Applications

Ibrahim Khamis

Rami El-Emam

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

Energy Market

Energy consumption by application

They world’s energy consumption for heat and transportation !

Non-Electric Applications & Nuclear Cogeneration

ValuesRoutes

Sustainability

Save Money

Save Energy

Save Environment

Source: OECD, Environmental Outlook Baseline, 2011

Nuclear Cogeneration for Climate Change Mitigation (1)

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)

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

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)

43

NPP: need water

– During construction (RO)

– During operation to substitute makeup water (Hybrid)

– Quality industrial water

– In case of accident (RO)

Nuclear Desalinationfrom Waste Heat

Improves overall efficiency

Improve economics

Use Off-Peak Power

Electric Power

Nuclear Desalination?

Synergies in Nuclear desalination are a catalyst

for sustainable development Aktau, 1961 Aktau, 1975

Nuclear Desalination:Sustainable Development

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

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

Tools & Toolkits on Non-Electric Applications and Nuclear Cogeneration

49

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

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

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.

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!

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