Nuclear Programmes and Nuclear Power Plants: Global Trends

Radek Škoda Czech Technical University in Prague

University of Cape Town, May 2010

Based on materials from CTU, Skoda, Areva, B.Barre, ENEN, WNU page

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Nuclear Programmes and Nuclear Power Plants: Global Trends Why and which new NPPs

Around the world in 80 minutes + Reactor tenders

Nuclear education & networks

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Nuclear Programmes and Nuclear Power Plants: Global Trends

? CTU Prague

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KERENA

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Building new NPPs Countries with vendors that did not interrupt building NPPs: • South Korea, Russia, Japan All other vendors had a „pause“ in production. Largest markets now in ASIA (India+China) CTU Prague

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Pro-nuclear Central Europe … 1

TEMELIN 34

1-Except GREEN Austria all countries Pro-nuclear

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2- Also three decommissioned NPPs

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CE Reactor technology • RBMK – Lithuania, and former USSR • CANDU – Romania, and many others • WWER – Czech R., Slovakia, Hungary, Bulgaria, Finland (East Germany), and many others •

PWR – Slovenia, and many others

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RBMK Graphite moderator Light water coolant Boiling in channels Low enrichment Variable Pu vector

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CANDU D2O moderator D2O coolant Fuel in channels No enrichment Variable Pu vector

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CANDU

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WWER(VVER) reactor = Soviet PWR • Thermal nuclear reactors • Pressurized Light Water used as moderator • Pressurized Light Water used as coolant

• Steam generator used to produce steam CTU Prague

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Remember: PWR in the world

USA Submarine

Russian Submarine

SSN-571Nautilus

PWR = submarine technology

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NPP Shippingport-1

NPP Novovoroněž-1

68 MWe

210 MWe

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Remember where the PWR comes from

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WWER reactor history • First demoplants: PWR at Shippingport at USA: 1957 • WWER-210 at USSR: 1964

• In USSR focused on RBMK reactors (LWGR) at that time, “eastern” PWR development initially in Eastern Germany !!

• 7 year technology gap

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MOTTO: Build and ship around…

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WWER reactor history • Railroads were the limiting factor => “slender&high” R.P.V. => small core => higher enrichment • Horizontal steam generators => large volume => initially no containment/confinement • Faster development in fewer steps => robust and conservative approach

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WWER typical features Core: triangular lattice => hexagonal fuel assemblies fuel assembly with grid 12.6mm; small core size => higher enrichment Small RPV diameter => neutron damage on RPV 156 mm water for WWER440 (V-230), 263 mm for WWER1000 (V-320) between fuel and RPV => “high” RPV (esp. for WWER440) Primary circuit: more loops (6 for WWER440)=>more water horizontal steam generators=>less sediments Safety: WWER440 (V-230): LOCA: 32mm diameter, weak ECCS From WWER440(V-213): LOCA: full rupture, standard ECCS CTU Prague

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WWER typical features WWER 440: very efficient control rods -different design than in other PWR - effort of being robust and simple - large worth, quick scram -”long” RPV, a lot of water… -unusual burnout of fuel attached to the control rod -safety studies: control rod ejection is more dramatic than in PWR WWER 1000: standard approach to control rods, like PWR CTU Prague

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WWER 440

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NPP WWER 440 (V 230)

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WWER 440 V-213

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NPP WWER 440 (V 213)

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WWER 440, reactor hall cross section

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WWER 440 – primary circuit

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WWER 440 – steam generator

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WWER 440 – RPV cross section in 2 levels

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WWER 440 – fuel pin and fuel assembly

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WWER 440 Dukovany, Loviisa

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WWER 440 x WWER 1000 comparison 2 x 1000

4 x 440

Reactor type

VVER 440 (V 213)

VVER 1000 (V320)

Thermal power

1375 MW

3000 MW

RPV diameter

3.56 m

4.5 m

RPV height

11.8 m

10.9 m

# of fuel assemblies

312

163

Fuel load

42 t

92 t

Moderator/coolant

H2O

H2O

RPV pressure

12.25 MPa

15.7 MPa

Coolant temperature

267 °C - 297 °C

290 °C - 320 °C

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WWER 1000 V320

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WWER 1000 reactor:

Main parts:

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Mix: WWER1000 + Western technology

NPP Temelín

NPP Busehr

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Future/currently built WWER1000: A-92 = WWER1000 V392 (Belene)

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Primary circuit:

 

Number of loops

4

Coolant pressure

15.7 MPa

Core inlet temperature

291°C

Core outlet temperature

321°C

FA number

163

# of control rods

121

Maximum FA burn-up UCT 2010

>60 MWd/kgU 44

Question: Which reactor is shown here?

•

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CE Country programs • • • • • • •

Slovak – tender + already building Czech – tender evaluation Hungarian – thinking of a tender Bulgarian - building Romanian - building Other players thinking of new builds …and Austria complaining as usual

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Slovakia

Reactors

Model

First power

Ann. closure

Bohunice 3 V2

V-213

408

1984

2025

Bohunice 4 V2

V-213

408

1985

2025

V-213

436

1998

V-213

436

1999

Mochovce 1 Mochovce 2 Total (4)

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Net MWe

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1688 MWe

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Czech Republic Reactors

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Net MWe

First power

Dukovany 1

V-213

428

1985

Dukovany 2

V-213

428

1986

Dukovany 3

V-213

470

1986

Dukovany 4

V-213

434

1987

Temelin 1

V-320

963

2000

Temelin 2

V-320

963

2003

 

3686 MWe

Total (6)

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Model

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Hungary

Reactors

Model

Net MWe

First power

Paks 1

VVER440/V-213

472

1982

Paks 2

VVER440/V-213

441

1984

Paks 3

VVER440/V-213

433

1986

Paks 4

VVER440/V-213

480

1987

 

1826 MWe

Total (4)

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Bulgaria

Belene Kozloduy

Reactors

Model

Type

Net MWe

First power

Commercial operation

close

Kozloduy 5

V-320

PWR

953

1987

9/88

 

Kozloduy 6

V-320

PWR

953

1991

12/93

Total operating

 

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1906 MWe

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Romania

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Romania - Cernavoda

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Central Europe – outlook various successful nuclear programs

•EU forced closure of 7 reactors •Shortage of capacity •Many new nuclear builds on the way •Many new NPPs considered x $$$ CTU Prague

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ANSWER: KS150 from A1 npp

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NUCLEAR EDUCATION Radek Skoda ENEN Board member European Nuclear Education Network Association CEA-Centre de Saclay INSTN Bldg 395 F-91191 Gif-sur-Yvette, FRANCE Tel +33 1 69 08 34 21 and +33 1 69 08 97 57 Fax +33 1 6908 9950 Email [email protected] Web http://www.enen-assoc.org

Contents

1. What is ENEN 2. Achievements since 2003

3. Examples from CTU

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STARTING POINT -2 A study conducted by OECD/NEA – July 2000 “Although

the number of nuclear scientists and

technologists may appear to be sufficient today in some countries, there are indicators that future expertise is at risk. In most countries, there are now fewer comprehensive, high quality nuclear technology programmes at universities than before. The ability of universities to attract top quality students, meet future staffing requirements of the nuclear industry, and conduct leading-edge research is becoming seriously compromised”.

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What is ENEN The European Nuclear Education Network Association A non-profit organization established in September 2003 under the French law of 1901  For the continuity of achievements through the past Euratom-EC projects on nuclear E&T  Headquarter is located near Paris, CEA Centre in Saclay, France 

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Overview of ENEN Members

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European and International cooperation

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2. ENEN Achievements

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2-1. Master level New Master in Switzerland (in English)-1 SWITZERLAND

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2-1. Master level New Master in France (in English) -2 FRANCE

Scholarship available for non-European CTU Prague

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2-1. Master level International Exchange Courses -1 Editions 2003 2004 2005 2006 2008

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2-1. Master level International Exchange Courses -1 21 days 6 ECTS

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2-1. Master level International Exchange Courses - 2

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2-1. Master level European MSc in Nuclear Engineering 



    CTU Prague

Established under the European Commission – EURATOM 5th FP ENEN project and 6th FP NEPTUNO project Common reference curricula and mutual recognition among ENEN members Promotes and facilitates mobility of students and teachers Definition and assessment of ENEN international exchange courses Implemented since 2005 “ENEN Certificate” recognised among ENEN Members UCT 2010

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2-2. PhD level Advanced Course -1

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2-3. For young professionals Training Courses

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2-4. Knowledge Management ENEN Website and Database  



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ENEN Website http://www.enen-assoc.org NEPTUNO Database (Aug 2004-) http://www.neptuno-cs.de/ E&T courses by ENEN Members A new ENEN Database (to be opened in autumn 2009) - E&T courses - Master program - PhD topics - Opportunities (scholarship, fellowship, internship, job opportunities) provided by ENEN Members and Partners UCT 2010

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2-4. Knowledge Management ENEN publication • First text book published under ENEN as a deliverable of ENEN II project – 18 chapters, 670 pages including exercises and solutions – mainly for students, young professionals and researchers • CD-ROM including multimedia presentations for the general public UCT 2010 CTU Prague

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2-4. Knowledge Management National network -1 BELGIUM

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2-4. Knowledge Management National network -2 UNITED KINGDOM

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Nuclear education at CTU Prague • Is focusing on experimental courses needed?

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Building a nuclear reactor…

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Nuclear education at CTU • Czech Technical University & nuclear reactor • Basic VR1 reactor characteristics • Reactor utilization • Standard reactor experiments • Designing a new reactor core: 2 week course • Organisation of the course • Conclusions CTU Prague

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Faculty of Nuclear Sciences and Physical Engineering CTU in Prague • Unique faculty - Technical University type with deep focus to physics and mathematics (like natural sciences universities) – Department of Nuclear Reactors – Department of Dosimetry and Ionizing Radiation – Department of Nuclear Chemistry – Centre for Radiochemistry

• Base for new nuclear engineering scholars and R&D experts

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Training reactor VR-1

www.ReactorVR1.eu CTU Prague

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Basic characteristics of reactor • • • • • • • • •

Operating - since 1990 Reactor type - pool type Power - 1 kWth (5kWth) Moderator - light water Coolant - light water Cooling - natural convection Fuel elements - IRT-4M enr. 19.7% Neutron flux - 2 - 3.109 /cm2.s neutron source- Am-Be (1.1x107/s )

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Nuclear fuel

Russian fuel IRT-4M

Reactor was converted from HEU to LEU fuel in October 2005 within RERTR program

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Nuclear fuel

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Experimental equipment • • • • • • • • • • •

Two horizontal experimental channels (radial and tangential) Vertical experimental channels (diameter 12, 25, 32, 56 and 90 mm) DOJICKA - instrumentation for delayed neutrons detection BUBLINKY - instrumentation for simulation of bubbly boiling – void coefficient studies HOPIK - instrumentation for reactor dynamics studies POSTA - instrumentation for irradiation of small samples (rabbit system for NAA) DRAT – instrumentation for measurement of neutron flux distribution with wires CAMPBELL - instrumentation for neutron flux measurement by Campbell technique Modules for ADS studies Neutron, alpha, beta and gamma detectors MSA and SCA analysators

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Reactor utilization • Education and training – University students - 250 students/year

• Training of NPP specialists – 2-3 courses /year

• R&D with respect to reactor parameters – limited use, potential for extension

• Information and promotional activities – 1000 -1500 high school students / year CTU Prague

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Standard reactor experiments • • • • • • • • • • • • •

Properties of neutron detectors study Study of delayed neutrons parameters Measurements of reactivity (SJ, RD, positive period, Greenspan, reactivity-meter) Control rod calibration (inverse counting, RD) Critical experiment (approach to critical state) Measurement of neutron flux density (thermal and fast - wires, foils, ionizing chambers, Campbell technique) Study of nuclear reactor dynamics Study of void coefficient of reactivity Simulation of the selected operating statuses of the power reactor of the WWER type Study of subcritical multiplying assembly Determination of the effect of various materials on the reactivity NAA in different environmental studies Reactor start-up and operation,… (> 20 exp.)

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Seeing is believing: CTU reactor

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LWR & the void coefficient

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3 Standard experiments levels • I Demonstration level – demonstration without active student’s work – for non-nuclear engineering students at Bc. and M.Sc. level • II Basic level – active work of the students ( and evaluation) – for nuclear engineering students at Bc. and M.Sc. level – for non-nuclear engineering students at Ph.D. level • III Advanced level – active work of the students (calculation, measurement and evaluation) – deep study of phenomena in various conditions, methods… – for nuclear engineering students at Ph.D. level – thesis at M.Sc. and Ph.D. level

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Advanced level courses

• Standard experiments at advanced level: – Example: Study of delayed neutrons in different power levels, time and samples (enriched uranium, uranium ore…), comparison with theory

• Annual projects, diploma and dissertation theses in Bc. M.Sc. and Ph.D. levels • Student’s research work • Training course for reactor operators

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BUILDING A NEW REACTOR CORE • NEW REACTOR CORE: Basic critical experiment – Idea of a new core – Design of new active core and its calculations – Application for the basic critical experiment approval by Regulatory body – Disassembly of the old core – Assembly of new core – Evaluation of experiments – Final report for Regulatory body CTU Prague

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NEW REACTOR CORE: week 1: theory • High level of nuclear theory required: reading & quiz • Already loads core configurations approved by the regulator – used as patterns for students to choose • MCNP calculations done on Linux clusters CTU Prague

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NEW REACTOR CORE week 1: theory

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NEW REACTOR CORE: week 2: basic criticality experiment – Disassembly of the “old” existing core – Assembly of the new core – Reaching criticality – Rod calibration – Evaluation of experiments CTU Prague

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NEW REACTOR CORE week 2:

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NEW REACTOR CORE week 2

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NEW REACTOR CORE week 2

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NEW REACTOR CORE week 2

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NEW REACTOR CORE course • For CTU students done in 1 semester – lots of time for overhead, slippage, regulatory deadlines • For international students done in a 2 week module: condensed approach = “pre-approved cores”

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NEW REACTOR CORE course • Synergies: – reactor physics – both theoretical and experimental – numerical methods – detection techniques – Nuclear safety – legislation – security – radiation protection • Demanding for the staff: – Not the same starting level of all participants: pre-course reading – Close supervision of all students: small student/teacher ratio: limit – Time pressure: weekends reserved for slippage CTU Prague

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THANK YOU FOR YOUR ATTENTION [email protected]

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