Univerzity a firmy

spolu na ceste

k inováciám

30. 01. 2017, Bratislava

Branislav Hatala

2

I graduated from the Faculty of Electrical Engineering

and Information Technology of the Slovak

University of Technology (1995).

I gained the academic degree PhD. Nuclear Power

Engineering at the Department of Nuclear Physics

and Technology at the same University (2008).

Since 1995 I have been working in Nuclear Safety

Division at VUJE, a. s.

I deal with the analysis of nuclear safety

and I am responsible for evaluating of licensing

documentation for NPP.

Gas Cooled Fast Reactors

3

1/1/1977 Foundation of the state-owned company Výskumný

ústav jadrových elektrární, š. p., Jaslovské Bohunice

(VUJE = NPP Research Institute) – scientific supervi-

sion of the commissioning of Czechoslovak NPPs

1/11/1994 Privatization and transformation into

the joint-stock company VÚJE Trnava, a. s.

orientation towards engineering and design activity,

complex provision of investment projects

15/8/2000 Transformation into the engineering company VÚJE

Trnava, a. s. – engineering, design and research

organization

increasing the scope of activities into the fields of

distribution networks, classical power industry and the

use of renewable resources

9/7/2004 Change of the commercial name of the company to

VUJE, a. s.

participation at the international research project

About VUJE company

History and characteristics

4

Activities of VUJE in the nuclear power industry

Decom-

missioning

Processing of

RAW,

development and

utilization of

manipulators

Termination

of operation

Disposal of fuel,

disposal of

process media

Project

Construction

proceeding, safety

documentation

and regulations,

project

management

Studies

Pre-project

analysis,

feasibility studies

Operation

Safety and reliabi-

lity of operation,

personnel

prepara-tion,

diagnostics

Construction

Physical and ener-

getic launching,

assessment of the

equipment

Activities of VUJE in the field of high-voltage networks

Project

Construction

proceeding, project

preparation and

management

Operation

Personnel prepara-

tion, diagnostics,

operation of power

stations Reconstruction

Modernization of

distribution plants,

replacement of

power lines

Construction

Performance and

coordination of

works, efficiency

evaluation, load

evaluation

Studies

Pre-project

analysis, feasibility

studies

6

Organization structure

0100 Department of General Director

0200 Division for Nuclear Safety

0300 Division for Diagnostic of Nuclear Power Components

0400 Division for Preparation of NPP Operation

0500 Division for Support of NPP Operation

0600 Division for NNP Personnel Training Centre

0700 Division for Radiation Safety, NPP Decommissioning and

Radwaste Management

0800 Division for Information Technologies

1000 Division for Economy

1200 Division for Support of Electric Grid Control and Operation

1700 Division for Preparation and Construction of New Nuclear

Power Installations

Výskumné projekty

• Zvyšovanie energetickej bezpečnosti SR

ITMS: 26220220077 (2010-2013)

VUJE, FEI STU, MTF STU

• Zvyšovanie energetickej bezpečnosti

a efektívnosti SR – BETA

ITMS2014+: 313011B759 (2017-2022)

VUJE, SjF STU, FEI STU, MTF STU, ÚMMS SAV

• Technická asistencia v oblasti jadrovej bezpečnosti

Financované UJD SR (2013-2016)

7

Výskumné projekty

• Ochrana obyvateľstva SR pred účinkami elektromagnetických polí

ITMS: 26220220145 (2011-2015)

VUJE, TUKE

• http://www.emp.vuje.sk

8

Výskumné projekty

• Zvyšovanie bezpečnosti

jadrovoenergetických zariadení

pri seizmickej udalosti

ITMS: 26220220171(2011-2015)

VUJE, SjF STU

• Rozšírenie platnosti výpočtových štandardov

pre návrh seizmicky odolných nádrží

naplnených kvapalinou,

z hľadiska bezpečnosti v JE

a iných priemyselných oblastiach,

APVV-15-0630, (2016-2018) zodpovedný riešiteľ: SjF STU

partner: VUJE, a. s.

9

Výskumné projekty - APVV

• Zabezpečenie elektromagnetickej kompatibility monitorovacích systémov

mimoriadnych prevádzkových stavov jadrovej elektrárne,

APVV-15-0062, (2016-2020) zodpovedný riešiteľ: FEI STU

partner: VUJE, a. s.

• Zvýšenie účinnosti prenosu elektrickej energie v PS SR,

APVV-15-0464, (2016-2020) zodpovedný riešiteľ: UNIZA

partner: VUJE, a. s.

• Vývoj softvérovej platformy pre výpočtové stanovovanie a optimalizáciu nákladov

vyraďovania jadrových zariadení z prevádzky na báze medzinárodného štandardu

ISDC pre zaistenie bezpečného a efektívneho vyraďovania,

APVV-15-0558, (2016-2018) zodpovedný riešiteľ: VUJE, a. s.

partner: FEI STU

10

List of EU projects

• THERAMIN - Thermal treatment for radioactive waste minimisation

and hazard reduction

H2020 (06/2017 – 05/2020)

• VINCO - Visegrad Initiative for Nuclear Cooperation

H2020 (09/2015 – 08/2018)

• ESSANUF - European Supply of SAfe NUclear Fuel

H2020 (09/2015 – 10/2017)

• CONCERT - European Concerted Programme on Radiation Protection Research

H2020 (06/2015 – 05/2020)

• PREPARE - Innovative integrative tools and platforms to be prepared for radiological

emergencies and post-accident response in Europe

FP7 (02/2013 – 01/2016)

• ESNII PLUS - Preparing ESNII for HORIZON 2020

FP7 (09/2013 – 08/2017)

11

List of EU projects

• CESAM - Code for European Severe Accident Management

FP7 (04/2013 – 03/2017)

• ASAMPSA_E - Advanced Safety Assessment: Extended PSA

FP7 (07/2013 – 12/2016)

• NUCL-EU - Reinforcing the networking of FP7 National Contact Points and third

country contacts in the Euratom Fission programme

FP7 (10/2009 – 12/2013)

• NERIS-TP - Towards a self sustaining European Technology Platform (NERIS-

TP) on Preparedness for Nuclear and Radiological Emergency Response and

Recovery

FP7 (02/2011 – 01/2014)

• SARGEN_IV - Proposal for a harmonized European methodology for the safety

assessment of innovative reactors with fast neutron spectrum planned to be built

in Europe

FP7 (01/2012 – 12/2013)

12

List of EU projects

• NC2I-R - Nuclear Cogeneration Industrial Initiative - Research and Development

Coordination

FP7 (10/2013 – 09/2015)

• CATO - CATO - CBRN crisis management: Architecture, Technologies and

Operational Procedures

FP7 (01/2012 – 12/2014)

• ALLIANCE - Preparation of ALLegro - Implementing Advanced Nuclear Fuel

Cycle in Central Europe

FP7 (10/2012 – 09/2015)

• SARNET2 - Severe Accident Research Network of Excellence

FP7 (04/2009 – 03/2013)

13

14

Nuclear Power in the World

15

Nuclear Power in the World

Nuclear power plants produce low-carbon electricity

at stable and competitive costs.

Further development of nuclear technology is needed

to meet future energy demand.

The first commercial nuclear power stations started

operation in the 1950s.

There are over 437 commercial nuclear power reactors

operable in 31 countries.

They provide over 11% of the world's electricity.

About 70 more reactors are under construction

in 16 countries.

16

Share of sources on electricity

production in the year 2015 and 2016

List of NPP units

Slovak Republic

Name Reactor Type Put in to

Operation

Note

1 NPP Bohunice V1 Unit 1 VVER440/230 December, 1978 Shutdown December 2006

2 NPP Bohunice V1 Unit2 VVER440/230 March, 1980 Shutdown December 2008

3 NPP Bohunice V2 Unit3 VVER440/213 August, 1984 Modernization + Power Up-rate

Electric output 500 MW

4 NPP Bohunice V2 Unit4 VVER440/213 August, 1985 Modernization + Power Up-rate 107%

Electric output 500 MW

5 NPP Mochovce Unit 1 VVER440/213 Jul 1998 Power Up-rate 107%

Electric output 470 MW

6 NPP Mochovce Unit 2 VVER440/213 December, 1999 Power Up-rate 107%

Electric output 470 MW

7 NPP Mochovce Unit 3 VVER440/213 Under

Construction

Project Finalization + licensing

8 NPP Mochovce Unit 4 VVER440/213 Under

Construction

Project Finalization + licensing

18

Nuclear Power in the World

On December 20, 1951,

at the Experimental Breeder Reactor EBR-I

in Arco, Idaho, USA,

for the first time electricity

was produced by nuclear energy.

On June 26, 1954,

at Obninsk, Russia,

the nuclear power plant APS-1

with a net electrical output of 5 MW

was connected to the power grid.

19

Evolution of Nuclear Energy Systems

20

Sustainability–1 Generation IV nuclear energy

systems will provide sustainable energy

generation that meets clean air objectives and

promotes long-term availability of systems and

effective fuel utilization for worldwide energy

production.

Sustainability–2 Generation IV nuclear energy

systems will minimize and manage their nuclear

waste and notably reduce the long-term

stewardship burden, thereby improving protection

for the public health and the environment.

Economics–1 Generation IV nuclear energy systems

will have a clear life-cycle cost advantage over

other energy sources.

Economics–2 Generation IV nuclear energy systems

will have a level of financial risk comparable to

other energy projects.

Goals for Generation IV Nuclear Energy Systems

21

Safety and Reliability–1 Generation IV nuclear

energy systems operations will excel in safety and

reliability.

Safety and Reliability–2 Generation IV nuclear

energy systems will have a very low likelihood and

degree of reactor core damage.

Safety and Reliability–3 Generation IV nuclear

energy systems will eliminate the need for offsite

emergency response.

Proliferation Resistance and Physical Protection

Generation IV nuclear energy systems will

increase the assurance that they are a very

unattractive and the least desirable route for

diversion or theft of weapons-usable materials,

and provide increased physical protection against

acts of terrorism.

Goals for Generation IV Nuclear Energy Systems

22

Generation IV technologies

• gas-cooled fast reactor (GFR);

• lead-cooled fast reactor (LFR);

• sodium-cooled fast reactor (SFR)

• molten salt reactor (MSR);

• supercritical-water-cooled reactor (SCWR);

• very-high-temperature reactor (VHTR).

“Power industry

based on thermal neutron reactors

is a preparation

for a future power industry

to be based on fast breeder reactors

capable to utilize a major share

of uranium-238.

23

Conventional Light Water Reactors

extract less than 1% of the energy in the uranium mined from the earth.

In a fast breeder reactor there is fertile material (uranium-238)

in the core and in the blanket around the core.

The core consists of a mixture of plutonium oxide and uranium oxide.

Fission takes place chiefly in the reactor core, while the conversion of uranium-238

to plutonium-239 through capture of excess neutrons occurs in both areas of

the reactor.

General principles of Fast Breeder Reactors

24

Closed fuel cycle

25

26

Gas cooled fast reactors (GFR) represent one of the three European candidate fast reactor types.

Allegro Gas Fast Reactor (GFR)

Potential Site: Jaslovské Bohunice Slovakia

Astrid Advanced Sodium Technical Reactor for Industrial Demonstration

Sodium Fast Reactor (SFR)

Site: Marcoule France

Alfred Advanced Lead Fast Reactor European Demonstrator

Led Fast Reactor (LFR)

Potential Site: Mioveni, Romania

General objectives

27

• Sodium cooled fast reactors are the shortest route to fast reactors deployment, but the sodium coolant has some undesirable features:

- Chemical incompatibility with air and water

- Liquid metal reactors have a strong positive void coefficient of reactivity

- Avoiding sodium boiling places a restriction on achievable core outlet temperature.

• Gas cooled fast reactors do not suffer from any of the above:

- chemically inert, - very stable nucleus, - void coefficient is small (but still positive), - single phase coolant eliminates boiling - optically transparent.

• But …

- Gaseous coolants have little thermal inertia => rapid heat-up of the core following loss of forced cooling;

• Motivation is two-fold: enhanced safety and improved performance

Gas-Cooled Fast Reactor System Why have gas cooled fast reactors ?

28

The GFR system features a fast-spectrum helium-cooled reactor.

The high outlet temperature of the helium coolant makes it possible to deliver electricity, hydrogen, or process heat with high conversion efficiency.

Through the combination of a fast-neutron spectrum and full recycle of actinides, GFRs minimize the production of long-lived radioactive waste isotopes.

The GFR’s fast spectrum also makes it possible to utilize available fissile and fertile materials (including depleted uranium from enrichment plants) two orders of magnitude more efficiently than thermal spectrum gas reactors with once-through fuel cycles.

Gas-Cooled Fast Reactor System

29

A technology demonstration as a first gas-cooled fast reactor

ALLEGRO GFR 2400

ALLEGRO Project

30

A technology demonstration as a first gas-cooled fast reactor

ALLEGRO Project

ALLEGRO

GFR 2400

31

A technology demonstration as a first gas-cooled fast reactor

ALLEGRO Project

ALLEGRO

32

Fuel 87

Diverse Shutdown Devices (DSD) 4

Control and Shutdown Devices (CSD) 6

Reflector

Schield

Main characteristic of the ALLEGRO core

MOX Core Ceramic Core

Core power 75 MWth

Coolant pressure 7 MPa

Primary mass flow rate 53 kg/s 36 kg/s

Core inlet temperature 260 °C 400 °C

Core outlet temperature 560 °C 850 °C

The reactor shall be operated with two different cores:

The starting MOX core will serve to test the

operation of the gas cooled fast reactor

with well established fuel.

The second core using the ceramic fuel

will serve for testing the new fuel design.

33

The ultimate objectives of ALLEGRO:

1. Demonstration of the GFR gen-4 concept,

(alternative technology to the reactor cooled by molten sodium)

-demonstration of the technological feasibility, helium cooling and high

temperature core,

- demonstration of the breeding capacity,

- demonstration of the ability of transmutation of actinides.

2. Demonstration of heat production at industrial and economic conditions.

As a one of fast reactor would produce heat about 850°C, which will be able to

chemically produce hydrogen.

High temperature heat could be used also for technological purposes.

General objectives

Cooperation

in the European Union

V4G4 Center of Excellence

VUJE, a. s.

UJV Řež, a. s.

Hungarian Academy of Sciences

Centre for Energy Research

National Centre for Nuclear Research Poland

CEA signed as associated member on March 15th 2017

Allegro Project – Preparatory Phase

will be carried out by the V4G4 Centre of Excellence

36

V4G4 Centre of Excellence Interest Association of Legal Entities

V4G4 Centre of Excellence

was introduced to the public at

the Hungarian Academy of

Sciences on July 18, 2013.

Memorandum on Cooperation in the Framework of the International Research Centre MBIR

State Corporation ROSATOM and V4G4 Centre of Excellence

signed the Memorandum of Understanding

on participation in partnership

“International Research

Centre on the Basis of Multi-Purpose Research Reactor (MBIR)”.

Signing of the Agreement

took place in the course

of the International Conference

on Fast Reactors

and Related Fuel Cycles (FR-17),

started in Yekaterinburg on June 26th. .

EUROPEAN PROJECTS on GFR

2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020

ALLIANCE ALLEGRO

GoFastR GFR GCFR GFR

VINCO ALLEGRO+HTR

GCFR - The Gas Cooled Fast Reactor Project (FP7) - research project

March 2005 - February 2009

GoFastR - European Gas Cooled Fast Reactor (FP7) - research project

March 2010 - February 2013

ALLIANCE - ALLegro Implementing Advanced Nuclear Fuel Cycle (FP7)

coordination and support action

Non-research activities in support of the implementation

of the Strategic Research Agenda of Sustainable Nuclear Energy Technology Platform

and safety of nuclear systems October 2012 - September 2015

VINCO - Visegrad Initiative for Nuclear Cooperation (Horizon 2020)

coordination and support action

capacity building activities aiming at strengthening the coordinating

role of the “V4G4 Centre of Excellence”

and supporting its member organizations September 2015 - August 2018

39

Beginning of the project - 9. September 2014

End of the project - 31. December 2015

Project „ALLEGRO Research Centre“ in Slovakia

Contract between

40

Partneri

Slovenská akadémia vied

Ústav materiálov a mechaniky strojov

Ústav anorganickej chémie

Fyzikálny ústav

Elektrotechnický ústav

Slovenská technická univerzita v Bratislave

Elektrotechnická Fakulta

Strojnícka Fakulta

Operačný program OP Výskum a vývoj

Spolufinancovaný z ERDF

Prioritná os Podpora výskumu a vývoja

Opatrenie 2.2. Prenos poznatkov a technológií získaných výskumom

a vývojom do praxe

Výskumné centrum ALLEGRO

41

1. Vybudovanie a sprevádzkovanie Výskumného centra ALLEGRO

Vybudovanie špecializovaných pracovísk a laboratórií,

priestorov pre zamestnancov a technologický transfer.

2. Aplikovaný výskum a vývoj v oblasti nových materiálov a technológií

Realizácia špičkového výskumu a vývoja v oblasti nových materiálov a technológií,

príprava prototypov, ich testovanie a diagnostika

Adaptácia a validácia výpočtových programov v neutronike a termohydraulike reaktora

Výskum materiálov pre reaktor ALLEGRO

Výskum zariadení pre reaktor ALLEGRO

Výskum a overenie metodík na meranie radiačnej situácie terénu

Diagnostické systémy reaktora ALLEGRO

Nedeštruktívne a deštruktívne testovanie a hodnotenie materiálov

3. Vytvorenie platformy pre technologický transfer

Vytvorenie kontaktného bodu pre styk s podnikateľským sektorom v rámci

Kancelárie pre transfer technológií (KTT),

vytvorenie inkubátora, identifikácia spin-off

a program na podporu technologického transferu a mobilizáciu inovácii.

Výskumné centrum ALLEGRO

42

V rámci Výskumného centra ALLEGRO SAV je vybudovaných 6 laboratórií:

• Laboratórium deštruktívneho a nedeštruktívneho skúšania materiálov

• Laboratórium mikroštruktúrnych analýz materiálov

• Laboratórium keramických komponentov

• Laboratórium experimentálnej héliovej slučky

• Laboratórium AFM

• Laboratórium jadrových reakcií

Výskumné centrum ALLEGRO

43

Experimentálna Héliová slučka

Slovenská technická univerzita v

Bratislave

Strojnícka Fakulta

Helium temperature at the GFR output 400ºC to 520 ºC

Helium temperature at the GFR input 150 ºC to 250 ºC

Helium operational pressure 3 MPa to 7 MPa

Installed input power of the GFR 500 kW

Designed heat power of the DHR 220 kW

Výskumné centrum ALLEGRO

Výskumné projekty

x

44

Helium Loop

Seismic Shaker

Výskumné projekty

x

45

Helium Loop

Výskumné projekty – APVV

výzva VV 2017 • Tvorba korekčných koeficientov a koeficientov vplyvu pre EX-CORE detektory v

reaktore VVER - KOEFCORE zodpovedný riešiteľ: FEI STU

partner: VUJE, a. s.

• Inovácia edukačného procesu v oblasti havarijnej pripravenosti pre účely krízového

manažmentu vo verejnej správe – EDUCATIONIS zodpovedný riešiteľ: APZ

partner: VUJE, a. s.

• Metodika na stanovenie stupňa znečistenia izolátorov vonkajších vedení s využitím

dostupných údajov o znečisťujúcich látkach v ovzduší – POLINS zodpovedný riešiteľ: SHMU

partner: VUJE, a. s.

• "Analýza nízkofrekvenčných elektromagnetických polí a ich vybraných biologických

účinkov v husto obývaných územiach SR – SAFEfields zodpovedný riešiteľ: JLF UK

partner: VUJE, a. s.

46

Výskumné projekty – APVV

výzva VV 2017

• Validácia termohydraulických

výpočtových nástrojov

pre vysokoteplotné aplikácie - DELTA zodpovedný riešiteľ: SjF STU

partner: VUJE, a. s.

47

Vedecko-technický tím roka 2017

48

49

VUJE, a. s.

Okružná 5

918 64 Trnava

Slovak Republic

www.vuje.sk

Branislav.Hatala@vuje.sk

VUJE, a. s. Okružná 5, 918 64 Trnava

Thank you

for your attention