Pitesti, Romania - Nuclear 2011/prezentari_sesiuni... · Nuclear 2011, May 25-27, Pitesti ROMANIA 4 INR Mission Scientific and technical national support for Cernavoda unit 1 and

Nuclear 2011, May 25-27, Pitesti ROMANIA 1

MINISTRY OF ECONOMY, TRADE and BUSSINESS ENVIRONMENT

RAAN – State Company for Nuclear Activities

Pitesti, Romania


INR Looking to the Future

RAAN – State Company for Nuclear Activities

Institute for Nuclear Research, Pitesti

Ilie TURCU, Constantin PAUNOIU, Marin CIOCANESCU

Institute for Nuclear Research – INR, Romania


Nuclear Power Programme

Cernavoda Candu unit 1 – commercial operation 1996

Cernavoda Candu unit 2 – commercial operation 2007

Cernavoda Candu unit 3 and 4 – under development

Spent fuel and radioactive waste safe repositories

Long term options: Advanced nuclear power reactors and fuel cycles; GEN IV

Second NPP – to be decided


INR Mission

Scientific and technical national support for Cernavoda unit 1 and unit 2 safe operation during plant lifetime.

Contribution to the international R&D effort to develop advanced NPP and Generation IV nuclear power reactors.

Education, training and knowledge management.

R&D infrastructure operation, maintenance and upgrading.

International Cooperation

Provide specific nuclear services, products and equipment for NPP

Support for non-power nuclear energy application (radioisotopes)


Scientific and technical support

throughout its life

Maintain and develop capabilities (R&D and expertise)

to solve operational and licensing issues during plant

lifetime.

Help ensure sustainability of NPP (nuclear safety, waste

management) and lifetime extension.

International obligations:

- Convention on Nuclear Safety (art. 11.2)

IAEA INSAG 16, Maintaining Knowledge, Training and

Infrastructure for Research and Development in Nuclear Safety

- EU Council Directive 71/2009 (art. 6.5, art. 7)



Technical areas, safety related

- Reactor physics

- Thermalhydraulics

- Nuclear fuel

- Fuel channel

- Materials

- Equipments and components

- Spent fuel and waste management

behavior during transient/abnormal/accident conditions

Accident analysis (deterministic and probabilistic)

Technical basis, standards, regulations



National Framework

- Regular R&D programs

- Cernavoda NPP R&D Agreement

- Technical assistance for COG R&D

- AECL R&D Agreement

- COG R&D programs

Nuclear 2011, May 25-27, Pitesti ROMANIA

Research and Development Regular Programs

Nuclear Power

Nuclear Safety

Fuel Channel

Nuclear Fuel

Fuel Handling

Radwaste Management

Radioprotection

Steam Generator

Systems & Equipment

Chemistry of Circuits

Instrumentation & Control

Ageing, PLIM

Other Programs

TRIGA Reactor

Radioisotopes

Applications of Nuclear Techniques

Heavy Water

Support for International Cooperation

Advanced reactors and fuel cycles

8


99


Nuclear Safety

Reactor Physics Analysis

Reactor Physics Computer Methods and Codes Development

Development of experimental methods for reactor physics

Thermo-hydraulic Analysis

Plant behavior during severe accident conditions

Nuclear Safety Analysis for NPP

PSA for Cernavoda NPP, research reactors

Safety Assessment for Radioactive Wastes Repositories



Fuel Channel Program

DHC and fracture

Irradiation behavior and deformation

Corrosion and hydrogen pick-up

Methods and equipment for measurement of hydrogen content in P/T material

Methods and equipment for post-irradiation examination of pressure tubes

10



Nuclear Fuel Program

Development and validation of computer codes describing fuel behavior in normal operating conditions

Design of SEU / RU advanced fuel bundle

Manufacturing technologies for advanced fuel bundle

TRIGA irradiation tests and out-of-pile tests

Fuel behaviour during accident conditions (LOCA and RIA)

11



Fuel Handling Program

Qualification of Fuelling Machine (F/M) head testing facility

Computer system for F/M head testing

Software for checking NPP fuel handling programs

Technologies for testing of F/M head

Technical assistance for operation and maintenance of Cernavoda NPP fuel handling system

12



Radioactive Waste Management Program

Technologies for treatment of liquid and gaseous wastes generated by Cernavoda NPP

Characterization of site foreseen for LLW / ILW disposal

Safety assessment of LLW / ILW final repository

Technologies for treatment and conditioning of INR hot cell radwastes

13



Chemistry of Cernavoda NPP Circuits

Corrosion of PHTS structural materials in normal and abnormal operating conditions

Decontamination techniques

Water chemistry and transport of corrosion products

Corrosion of structural materials from secondary circuit

14



Systems and Equipment Program

Contributions to the development and implementation of a Plant Life Management Program for Cernavoda NPP

Improved design and manufacturing of Failed Fuel Location System

Computerized data acquisition systems for surveillance of Cernavoda NPP reactor core components

Design and manufacturing of a new Gross Activity Monitor for surveillance of reactor activity in Cernavoda NPP

15



Instrumentation and Control

Integrated radiation monitoring system

Fixed area monitors

Radiation detectors

Ageing mechanisms

16



Canadian Co-operation

Collaboration with AECL - CANADA, started in 1999 under the Memorandum of Understanding for cooperation in the research and development of nuclear energy and technology between Romania and Canada, is foreseeing joint research activities in the fields of:

– CANDU nuclear fuel;

– Nuclear safety;

– Nuclear Power Plant life management

Projects with AECL– Power cycling condition for Candu fuel in C9 capsule of TRIGA reactor;

– Fatigue test for Zircaloy - 4 sheaths;

– Transfer, implementation and validation of computer codes for nuclear safety analysis and design.

COG Projects – Cernavoda technical assistance for COG R&D programs (Fuel channel, Plant chemistry, Safety and

licensing, Radioprotection, Computer programs;

– Developing Irradiated Testing Facilities at ICN Pitesti ; to develop the capability to test irradiated material in the hot cells at ICN Pitesti. Types of tests to be develop cover DHC testing and associated with material (PT) surveillance.


A number of 336 COG documents were analyzed by the

ICN Technical Team during the 2008 – 2010 under five COG

R&D Programs:

Fuel Channels (5)

Safety & Licensing (4)

Health, Safety and Environment (7)

Chemistry, Materials & Components (8)

Industry Standard Toolset (17)

18

Scientific and Technical Support

Technical Assistance for COG R&D Programs

COG R&D contract:

Developing Irradiated Testing Facilities at ICN Pitesti


Contribution to advanced reactors and fuel cycles

Generation IV nuclear power reactors

LFR: Lead fast reactors

Participation in ELSY, LEADER, ADRIANA

Involvement in ALFRED

Governmental approval (February 2011)

for:

proposal to host ALFRED

INR to represent Romania in the future consortium

Reporting to Prime Minister the status every 6 months

19


LEADER: Lead-cooled European Advanced DEmonstration Reactor

Objectives:

- to design a scaled demonstrator fully representative of the industrial size reactor

- to evaluate safety aspects and perform a preliminary safety analysis

- to minimise the cost of the demonstrator to define the main suitable

- to use components/technologies already available in the short term to be able to

proceed in the near future to a detailed design followed by the construction phase

INR participation: 40 person*months: WP2 (Core Design); WP4 (instrumentation and

Control); WP1 (Reference Design Objectives and Specification)





Education, training and knowledge management

INR Staff

Researchers 117 185

PhD 31 33

PhD students 27 28

MSc students 51 37

Nuclear Scientists/Engineers 237 244

Technical staff 296 277

Administration and Services 125 137

Total 658 658

0%

5%

10%

15%

20%

25%

30%

35%

40%

45%

Nuclear

Scientists/Engineers

Technical staff Administration and

Services

Mar-07

Nov-07

Breakdown by qualification

0

20

40

60

80

100

120

140

160

180

200

Researchers PhD PhD students MSc students

mar.07

Nov-07



Estimated for next 10 years

23

Total number of

nuclear

experts/researc

hers* in 2010

Approximate age span of nuclear experts in

2010

Need for new (to replace

the retired experts + for

new nuclear projects)

within:

276

Below 35: Between

35-45:

Between

45-55

Above 55 1 year 5 years 10

years

49 (18%) 59 (21%) 100

(36%)

68 (25%) 22+10 29+100 38+100

Need for abour 300 more experts during the next 10 years



University cooperation and training

24

- Pitesti University- Bucharest Politechnical University

- Students diploma disertations- Masters- PHD- Students fellowships

- Hosting IAEA fellowships- IAEA Knowledge Management projects

- Implementation of INR Knowledge management strategy


Large Irradiation Facility: 14 MW TRIGA Steady State Reactor and Pulse Reactor, Irradiation devices

Hot Cells

Out-of-Pile High Pressure Loops

Laboratories for Testing / Investigation of Materials

Radioactive Waste Treatment / Conditioning Facility

Fuelling Machine (F/M) Heads Testing Rig

Workshop s for manufacturing of irradiation devices and fuel element instrumentation

R&D infrastructure operation, maintenance and upgrading

Main R&D Facilities at INR


R&D infrastructure operation, maintenance and upgrading

TRIGA Reactor Program

Upgrading and extending existing infrastructure

Irradiation devices

Laboratory equipments

Radioactive waste management station

Education and training center facilities

26



R&D Agreements and technical cooperation

AECL - Canada

CEA – France

ITU- Germany

KAERI- Korea

IRSN-France

JSI – Slovenia

SCK-CEN – Belgie

Ansaldo Nucleare- Italy, ENEA-Italy

LANL – Los Alamos National Laboratory

ORNL- Oak Ridge National Laboratory

ANL- Argonne National Laboratory

BNL – Brookhaven National Laboratory

SNL - Sandia National Laboratory

IAEA, EU, CANDU Owners Group, US DOE

Expected: NEA/OECD



EU R&D Framework Programs

FP5 EURATOM:

PHEBEN 2, Validating Severe Accident Codes Against Phebus FP for Plant Applications - integral codes for LWR and guidelines for optimum code use for the various applications (2002 – 2005)

FP6EURATOM:

SARNET, NoE in Nuclear Reactors Severe Accidents

COWAM2, Community waste management: Improving the governance of nuclear waste management and disposal in Europe

HOTLAB: European Hot Laboratories Research Capacities and Needs - to set up a hot laboratories network in support of the nuclear energy safety optimization and long-term management of radioactive waste

NULIFE, NOE on Nuclear Plant Life Prediction - framework for continuing professional development of its personnel via targeted internal training, exchange of best practices and where appropriate mobility/exchanges

CIP, COWAM in Practice - to assist local communities directly with their engagement on their particular siting programmes - and to capture the learning from that experience and to prepare EU-level guidance for the implementation and improvement of inclusive radioactive waste management approaches

MTR+I3, Materials Testing Reactors Innovations – strengthening the European experimental potential in materials and nuclear fuel testing

ELSY, Generation IV Reactors- European Lead System – to develop a lead-cooled fast reactor concept


2929


EU R&D Framework Programs

FP7 EURATOM participation:

CARBOWASTE, Waste management, Graphite

LEADER, Generation IV Reactors- European Lead System – to develop a lead-

cooled fast reactor concept

SARNET-II, NoE in Nuclear Reactors Severe Accidents

ADRIANA, Infrastructure for Generation 4 reactors

STYLE, Materials Investigations for NPP (non-pressure vessels components)

MATTER, Advanced materials for generation 4

During the period 2003-2010: 15 EU FP projects

29

FP7 EURATOM Call 2011: partner in 4 proposals

Expected an enhanced involvement for remaining FP7 and future FP8


3030


EU research area

SNETP

IGD-TP

EERA

APSA (JRC IE Petten)

Expected:

ENEN

ETSON

30


3131


IAEARegular Projects with INR as the main recipient:

- Development and testing of locally made fuel elements

- Building Nuclear Safety capabilities

- Development of the Cernavoda Probabilistic Safety Evaluation Studies

- Plant commissioning requirements and training

- Radiological protection

- Licensing of test facilities for CANDU 600 fuelling machine

- Full conversion of TRIGA 14-Mw Core from HEU to LEU

Regional projects

Training courses, scientific visits, expert missions, etc.

Ex: RER/9/076 Strengthening Safety and Reliability of Nuclear Fuel and Materials in Nuclear Power Plants: Upgrading the Hot Cells at INR Pitesti and development of the CANDU spent fuel examination technologies.

Others co-operation forms:

Research contracts

INR contribution to the IAEA activities (development of standards, experts)

31


1, Campului Street

115400 Mioveni, Arges

POB 78, Pitesti

ROMANIA

Tel: (+40) 248 213400

Fax: (+40) 248 262449

email: [email protected]

Web: http://www.nuclear.ro

INSTITUTE FOR NUCLEAR RESEARCHPitesti, ROMANIA

Documents

Pitesti, Romania - Nuclear 2011/prezentari_sesiuni... · Nuclear 2011, May 25-27, Pitesti ROMANIA 4 INR Mission Scientific and technical national support for Cernavoda unit 1 and