Daniela Diaconu, Mirela Nitoi, Adrieana Paraschiv, Ilie Turcu, Marin Constantin, Mihai Cojan, Alexandru Toma

1
INSTITUTE FOR NUCLEAR RESEARCH PITESTI
INR participation in European research programs
achievements and expectations
Daniela Diaconu, Mirela Nitoi, Adrieana
Paraschiv, Ilie Turcu, Marin Constantin, Mihai
Cojan, Alexandru Toma
2
Summary

• contribution to the ongoing FP 6 projects and
  main achievements
• SARNET, COWAM2 and HOTLAB
• participation in the new accepted FP6 projects
• NULIFE, CIP, MRTI3, ELSY
• cooperation activities with JRC
• expectations

3
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
Web portal and digital catalogue on devices and
services (WP 1) Current status and future needs
(WP 2)
Information and data regarding the
Post-Irradiation Examination Laboratory
capabilities and competences
Romanian hot cells will be part of the European
network
4
SARNET
NoE in Nuclear Reactors Severe Accidents
ASTEC code development (WP 2, WP 3, WP 4) PSA
Level 2 (WP 5) Severe Accident Phenomena
-Experiments (WP14)

• ASTEC Adaptation to CANDU type reactors -
  preparing models and new modules for code
  extension to CANDU (e.g. core degradation models)
• validation of the calculation models against
  experiments for physical Model Assessment
• benchmarks with other codes on plant
  applications for CANDU NPP
• comparison and integration of PSA Level 2
  methodologies improvement of the event tree
  methodology using dynamic reliability techniques
• Source Term-effect of air ingress, oxidation of
  the fuel pellets

5
COWAM 2
Community waste management Improving the
governance of nuclear waste management and
disposal in Europe
Implementing Local Democracy and Participatory
Assessment Methods (WP 1) Integration (WP 5)

• Study of the impact of radioactive waste
  information on the young people
• National Stakeholders Group
• National Insights in radioactive waste management

• awareness of each stakeholder on their role in
  the decision making process
• open the dialog between the most important
  stakeholders in RWM
• educational program for young generation in
  order to be better prepared for future decision
  making process

6
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

Inception and facilitation (WP 1) Integration
(WP 3)

• to guide the discussions of National Stakeholder
  Group regarding of their experience in the field
  of RWM governance
• to prepare the Prospective Case Study, i.e. the
  assessment of the local and national situation
• to discuss and validate draft guidelines
  developed to give global advice on the
  implementation and improvement of governance
  approaches to radioactive waste management with
  NSG

7
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

Mapping of partner RTD expertise and
competences Lifetime evaluation Sefety, risk
information and reliability

• Provide the INR expertise and competences in
  application of ageing management in CANDU 6
  PLiM/PLEX programs
• Provide advice on/develop the lifetime evaluation
  tools used by the INR
• Provide benchmarking of specific lifetime
  evaluation tools (experimental analytical
  procedures, evaluation criteria...)
• Review the practical applicability of various
  probabilistic methods for structural reliability
  assessment, ageing and residual life of NPP
  components, and identify RD needs in this area
• Assess the limitations of structural component
  modelling in PSA and their importance for
  risk-informed decision making

8
MTRI3

• Materials Testing Reactors Innovations
  strengthening the European experimental potential
  in materials and nuclear fuel testing

Networking activities Best practices in
measurements (NA4) Joint Research
Activities Mechanical testing instruments (JRA
2) Instrumentation for safety tests(JRA 4)
Transnational access

• to define measurement technologies
• to assess the information regarding the selected
  practices
• to elaborate the final recommendations
• to develop sample holders for the mechanical
  behaviour studies in LWR and HTR and for stress
  corrosion studies for LWR chemical environments
• to develop instrumentation for nuclear safety
  testing for future experimental programs
• INR will have access to the material testing
  reactors of the consortium

9
ELSY
Generation IV Reactors- European Lead System to
develop a lead-cooled fast reactor concept until
2009

• Core Design including fuel pin, fuel assembly,
  neutronic and thermo-hydraulic core behavior,
  impact of homogeneously diluted minor actinides
  on the performance of the reference MOX core- WP2

• preliminary neutronic and shielding design
• (core design and shielding properties of the lead
  used as coolant)

10
JRC APSA Network
Incorporating Ageing Effects into Probabilistic
Safety Assessment (APSA) - operating under the
JRC FP-6 Institutional Work Program Analysis
and Management of Nuclear Accidents by Sector of
Probabilistic Risk and Availability Assessment of
Energy Systems, IE, Petten

• Evaluation of available methods and approaches on
  incorporation of ageing effects into PSA
• Identification of necessary information on ageing
  issues to be addressed in PSA tools for specific
  PSA applications
• Demonstrations of the impact of different levels
  of ageing information included in a PSA model on
  the overall PSA results
• Discussion of reliability models and data to be
  used for modeling of ageing effects in PSA
  models
• Development and revision of Report on APSA in
  Risk Informed Applications

to develop and operate a network of interested
partners (operators, industry, research, academia
and consultants) on the topic of incorporating
ageing effects into PSA and use of APSA
applications.
11
Radioprotection
Harmonisation of techniques and methodologies for
measuring the radioactivity in environment -
operating under the JRC FP-6 Institutional Work
Program Measurement of the radioactivity in
environment by ITU Karlsruhe

• Creation of a network of nuclear environmental
  safeguards in CC and AC countries and initiation
  of an "enlarged" European Research Area for
  Measurement of Radioactivity in the Environment
• Development of protocols (guidelines) for
  harmonised procedures for measuring radioactivity
  in different ecosystems
• Exchange of knowledge and expertise between the
  participants
• Development of a database of validated analytical
  procedures accessible to all.

• Activities
• Several actions in the project
• meetings and workshops
• sampling campaign,
• intercomparison run

12
TRANSURANUS (1)

• Feasibility study for the application of
  TRANSURANUS to CANDU fuel - in the framework of
  the EU Enlargement and integration activities,
  INR ITU Karlsruhe collaboration

• Content
• Test coupling of DCHAINV code to TRANSURANUS
  (FUMEX-II)
• Provide clad surface temperature calculation
• Assess nominal CANDU cases of FUMEX-II
• Assess various AECL tests

• to verify the Volatile Fission Products Release
  model implemented in the DCHAIN5V code on a large
  experimental data from the IFPE Database, in the
  framework of the IAEA CRP - FUMEX II Exercise
• to simulate a CANDU fuel experiment using models
  already present in code, selected as much as
  adequately to the constructive features and
  operating conditions corresponding to this type
  of fuel

13
TRANSURANUS (2)
TRANSURANUS - a computer programme for the
thermal and mechanical analysis of fuel rods in
nuclear reactors DCHAIN5V - a programme
dedicated to the fission products behaviour
analysis during irradiation

• TRANSURANUS and DCHAIN5V represent a powerful
  tool for nuclear fuel behavior analysis during
  operation in nuclear plants

TRANSURANUS code may be improved in order to be
used in CANDU fuel analyses
14
Expectations (1)

• To extend our participation in the European
  Research Programs
• - number of projects
• - contribution to the project
• To enhance our participation in the Nuclear
  Safety Research and to contribute to the Nuclear
  Safety Standards harmonization
• To open new research topics
• - Radioactive Waste Disposal
• - Nuclear Knowledge Management including
  learning, teaching, training and preservation
  
• - Radioprotection
• To take part in the Generation IV research

15
Expectations (2)

• Common data base of information, expertise and
  equipment
• Integration of our nuclear facilities for
  research and education
• INR integration in the European Research Area

Thank you !