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Nuclear Programmes and Nuclear Power Plants: Global Trends
Radek Škoda
Czech Technical University in Prague
University of Cape Town, May 2010
page
Based on materials from CTU, Skoda, Areva, B.Barre, ENEN, WNU
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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
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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)
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Pro-nuclear Central Europe1…
1-Except GREEN Austria all countries Pro-nuclear 2- Also three decommissioned NPPs
TEMELIN 34
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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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RBMKGraphite moderator
Light water coolant
Boiling in channels
Low enrichment
Variable Pu vector
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CANDUD2O 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
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NPP Shippingport-1
68 MWe
USA Submarine
SSN-571Nautilus
PWR = submarine technology
Russian Submarine
NPP Novovoroněž-1
210 MWe
Remember: PWR in the world
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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 featuresCore: 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
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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
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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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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
2 x 10004 x 440
WWER 440 x WWER 1000 comparison
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WWER 1000 V320
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Main parts:WWER 1000 reactor:
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Mix: WWER1000 + Western technology
NPP Temelín
NPP Busehr
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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 >60 MWd/kgU
Future/currently built WWER1000: A-92 = WWER1000 V392 (Belene)
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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 Net MWe First power Ann. closure
Bohunice 3 V2 V-213 408 1984 2025
Bohunice 4 V2 V-213 408 1985 2025
Mochovce 1V-213 436 1998
Mochovce 2V-213 436 1999
Total (4) 1688 MWe
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Czech RepublicReactors Model 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
Total (6) 3686 MWe
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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
Total (4) 1826 MWe
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Bulgaria
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 1906 MWe
Belene
Kozloduy
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Romania
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Romania - Cernavoda
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Central Europe – outlookvarious successful nuclear programs
•EU forced closure of 7 reactors
•Shortage of capacity
•Many new nuclear builds on the way•Many new NPPs considered x $$$
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ANSWER: KS150 from A1 npp
•
NUCLEAR EDUCATION
Radek SkodaENEN Board member
European Nuclear Education Network AssociationCEA-Centre de Saclay
INSTN Bldg 395F-91191 Gif-sur-Yvette, FRANCE
Tel +33 1 69 08 34 21 and +33 1 69 08 97 57Fax +33 1 6908 9950
Email [email protected] http://www.enen-assoc.org
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Contents
1. What is ENEN2. Achievements since 2003
3. Examples from CTU
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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”.
STARTING POINT -2
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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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SWITZERLANDSWITZERLAND
2-1. Master levelNew Master in Switzerland (in English)-1
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2-1. Master levelNew Master in France (in English) -2
Scholarship available for non-European students.
FRANCEFRANCE
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2-1. Master level2-1. Master level International Exchange Courses -1International Exchange Courses -1
Editions
2003
2004
2005
2006
2008
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2-1. Master level2-1. Master level International Exchange Courses -1International Exchange Courses -1
21 days
6 ECTS
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2-1. Master level2-1. Master level International Exchange Courses - 2International Exchange Courses - 2
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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
2-1. Master levelEuropean MSc in Nuclear Engineering
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2-2. PhD level2-2. PhD level Advanced CourseAdvanced Course -1 -1
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2-3. For young professionals 2-3. For young professionals Training CoursesTraining Courses
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2-4. Knowledge Management2-4. Knowledge Management ENEN Website and Database
ENEN WebsiteENEN Website http://www.enen-assoc.orghttp://www.enen-assoc.org NEPTUNO DatabaseNEPTUNO Database (Aug 2004-) (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
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2-4. Knowledge Management ENEN 2-4. Knowledge Management ENEN publicationpublication
• First text book published under ENEN as a deliverable of ENEN II project– 18 chapters, 670
pages includingexercises and solutions
– mainly for students, young professionals and researchers
• CD-ROM including multimedia presentations for the general public
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2-4. Knowledge Management2-4. Knowledge Management National network -1 National network -1
BELGIUMBELGIUM
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UNITED KINGDOMUNITED KINGDOM
2-4. Knowledge Management2-4. Knowledge Management National network -2 National network -2
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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
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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
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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
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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
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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
• Application for the basic critical experiment approval
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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
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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