Nuclear Programmes and Nuclear Power Plants: Global Trends · CTU Prague UCT 2010 1 Nuclear Programmes and Nuclear Power Plants: Global Trends Radek Škoda Czech Technical University

CTU Prague UCT 2010 1

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



Why and which new NPPs

Around the world in 80 minutes + Reactor tenders

Nuclear education & networks



?

CTU Prague UCT 2010

CTU Prague UCT 2010

CTU Prague UCT 2010

CTU Prague UCT 2010

CTU Prague UCT 2010

CTU Prague UCT 2010

KERENA

CTU Prague UCT 2010


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 UCT 2010

CTU Prague UCT 2010

CTU Prague UCT 2010

CTU Prague UCT 2010


Pro-nuclear Central Europe1…

1-Except GREEN Austria all countries Pro-nuclear 2- Also three decommissioned NPPs

TEMELIN 34


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


RBMKGraphite moderator

Light water coolant

Boiling in channels

Low enrichment

Variable Pu vector



CANDUD2O moderator

D2O coolant

Fuel in channels

No enrichment

Variable Pu vector


CANDU


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


NPP Shippingport-1

68 MWe

USA Submarine

SSN-571Nautilus

PWR = submarine technology

Russian Submarine

NPP Novovoroněž-1

210 MWe

Remember: PWR in the world


Remember where the PWR comes from


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


MOTTO: Build and ship around…


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


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


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


WWER 440


NPP WWER 440 (V 230)


WWER 440 V-213


NPP WWER 440 (V 213)


WWER 440, reactor hall cross section


WWER 440 – primary circuit


WWER 440 – steam generator


WWER 440 – RPV cross section in 2 levels


WWER 440 – fuel pin and fuel assembly


WWER 440 Dukovany, Loviisa


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


WWER 1000 V320


Main parts:WWER 1000 reactor:


Mix: WWER1000 + Western technology

NPP Temelín

NPP Busehr


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)


Question: Which reactor is shown here?

•


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


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


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


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


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


Romania


Romania - Cernavoda


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 $$$


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

mailto:[email protected]

http://www.enen-assoc.org/


Contents

1. What is ENEN2. Achievements since 2003

3. Examples from CTU


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


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


Overview of ENEN Members


European and International cooperation


2. ENEN Achievements


SWITZERLANDSWITZERLAND

2-1. Master levelNew Master in Switzerland (in English)-1


2-1. Master levelNew Master in France (in English) -2

Scholarship available for non-European students.

FRANCEFRANCE


2-1. Master level2-1. Master level International Exchange Courses -1International Exchange Courses -1

Editions

2003

2004

2005

2006

2008


2-1. Master level2-1. Master level International Exchange Courses -1International Exchange Courses -1

21 days

6 ECTS


2-1. Master level2-1. Master level International Exchange Courses - 2International Exchange Courses - 2


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


2-2. PhD level2-2. PhD level Advanced CourseAdvanced Course -1 -1


2-3. For young professionals 2-3. For young professionals Training CoursesTraining Courses


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

http://www.neptuno-cs.de/


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


2-4. Knowledge Management2-4. Knowledge Management National network -1 National network -1

BELGIUMBELGIUM


UNITED KINGDOMUNITED KINGDOM

2-4. Knowledge Management2-4. Knowledge Management National network -2 National network -2

CTU PragueMay 13, 2009

Radek Skoda: CTU PragueUCT 2010

74

Nuclear education at CTU Prague

• Is focusing on experimental courses needed?

CTU Prague RS CTU PragueUCT 2010 75

Building a nuclear reactor…



76

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



77

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



78

Training reactor VR-1

www.ReactorVR1.eu



79

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 )



80



81

Nuclear fuel

Russian fuel IRT-4M

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



82

Nuclear fuel



83

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



84

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



85

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.)


Seeing is believing: CTU reactor


LWR & the void coefficient



88

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



89

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



90

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



91

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



92

NEW REACTOR CORE week 1: theory



93

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



94

NEW REACTOR CORE week 2:



95

NEW REACTOR CORE week 2



96




97




98

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”



99

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


THANK YOUFOR YOUR ATTENTION

[email protected]

Documents

Nuclear Programmes and Nuclear Power Plants: Global Trends · CTU Prague UCT 2010 1 Nuclear Programmes and Nuclear Power Plants: Global Trends Radek Škoda Czech Technical University