EUROSAFE Forum 2013

43353
EUROSAFE Forum 2013 on Safe Disposal of Nuclear Waste.

The EUROSAFE Forum 2013 on Safe Disposal of Nuclear Waste, took place on 4th and 5th November 2013 in Cologne, Germany. The event was fairly well attended with over 350 participants from 28 countries according to EUROSAFE. In general, the Forum an interesting two days which proved to be extremely useful, both in content and attendees, setting some good proactive approaches and methods, to challenges in Radioactive waste management environment.

Introduction – Frank-Peter Weiß, Scientific and Technical Director of GRS

1.1 French safety policy regarding radioactive waste disposal
Pierre-Franck Chevet (ASN, France)
ASN considers that long term management of radioactive waste is a nuclear safety concern, considering that clearance of radioactive waste is not acceptable and requires traceability of waste produced by areas of nuclear facilities where these waste may be activated or contaminated.
Presentation

1.2 An implementer’s view on site selection – recent technical and societal experience in Switzerland
Piet Zuidema (Nagra, Switzerland)
Swiss waste management concept – Stepwise approach – Site selection (Rules) – Safety & technical feasibility – Nice analogy on the river principle (page 27)
Presentation

1.3 View of a local stakeholder on repository siting
Harri Hiitiö (Eurajoki, Finland)
Presentation

1.4 Methodological approaches to safe waste disposal in rock salt formations
Klaus Fischer-Appelt (GRS, Germany)
Stepwise and criteria-based site selection procedure is stipulated by law, in this context, preliminary long-term safety analyses are an essential element for the stepwise assessment of the results of above-ground andunderground explorations in a site selection procedure.
Presentation

Seminar 1 – Nuclear Installation Safety Assessment

1.5 Severe accident analyses for shutdown modes and spent fuel pools to support PSA level 2 activities
T. Steinrötter et al. (GRS)
On the field of Level 2 PSA, two projects are being performed to study the plant behaviour during shutdown modes and inside spent fuel pools of PWR and BWR under severe accident conditions.
Noting PSA Framework
LEVEL 1 PSA – The assessment of plant failures leading to core damage and the determination of core damage frequency (CDF).
LEVEL 2 PSA – The assessment of containment response leading, together with the results of Level 1 analysis, to the determination of release magnitudes and frequencies.
LEVEL 3 PSA – The assessment of off-site consequences leading, together with the results of Level 2 analysis, to estimates of risk to the public.
Paper / Presentation

1.6 Spent fuel pool risk analysis for the Dukovany NPP
S. Hustak, M. Jaros, J. Kubicek (ÚJV)
PSA for Dukovany NPP – PSA Scope, level 1 & 2
Paper / Presentation

1.7 Fire risk analysis method for nuclear installations
Y. Ormières, J. Lacoue (IRSN)
A position on the management of fire safety analysis in nuclear installations by specifying:– the fire risk analysis process – the demonstrative elements expected in terms of nuclear safety
Paper / Presentation

1.8 Application of fire PSA in case of modifications for post-operational shutdown states
M. Röwekamp, M. Türschmann, S. Babst (GRS)
The status of Hazard analysis & Fire PSA in Germany – German PSA Guideline and its technical document on PSA methods require PSA for NPP safety reviews – Since 2005, this also covers detailed probabilistic analyses for the following (internal and external) hazards: Internal fire – flooding – Aircraft crash – Explosion pressure (blast) wave – External flooding – Earthquake. – For these hazards, specifications and methodological approaches are provided in the German PSA Guidelines.
Paper / Presentation

1.9 Severe accident mitigation strategy for the generation II PWRs in France – some outcomes of the on-going periodic safety review of the French 1300 MWe PWR series
P. Chevrier, G. Cénérino, N. Rahni, M. Dubreuil, Y. Guigueno, E. Raimond, J.M. Bonnet (IRSN)
Periodic Safety Reviews (PSRs) every 10 years for the whole series considered – EDF has produced a severe accident safety standard for 1300 MWe reactors including the safety requirements
Paper / Presentation

Nuclear Installation Safety Research

1.10 Analyses in regulatory practice
F. Blömeling, P. Pandazis (TÜV NORD SysTec), A. Schaffrath (GRS)
Paper / Presentation

1.11 Challenge of PWR new core design simulation: a focus on uncertainties due to nuclear data and reflector modelling
Y. Perin, A. Aures (GRS), V. Salino (IRSN)
Paper / Presentation

1.12 Multi-scale approach and advanced fuel modelling for enhanced safety
F. Ribeiro (IRSN), G. Khvostov (PSI)
Paper / Presentation

1.13 Structure-mechanical and thermal hydraulic aspects of the behaviour of crack-like leaks in piping
K. Heckmann, H. Grebner, G.-P. Moner, G. Lerchl, J. Sievers (GRS)
Paper / Presentation

1.14 Multi-physics modelling in the frame of the DRACCAR code development and its application to spent-fuel pool draining accidents
G. Guillard, F. Jacq, O. De Luze (IRSN)
Paper / Presentation

Seminar 2 – Radioactive Waste, Decommissioning & Dismantling

2.1 A TSO research programme on the safety of geological disposal and its necessary evolution along the development of a national industrial project
J.-D. Barnichon (IRSN)
Paper/Presentation

2.2 Radioactive waste management in the Russian nuclear development strategy: a view of the Kurchatov Institute
A. Gagarinsky (Kurchatov Institute)
Paper/Presentation

2.3 The IAEA activities and international projects on the safety of radioactive waste disposal
G. Bruno, Y. Kumano, K. Moeller (IAEA)
Paper/Presentation

2.4 Results of the SITEX project – ETSON coordination of the TSO expertise and research on waste management at European level
C. Serres (IRSN), V. Havlova (ÚJV)
Defining the conditions and means (TOR and road map) for establishing a coordinated European (and possibly international) workforce ensuring a sustainable capability to provide a technical and independent expertise in the field of radwaste management safety and radiological protection.
Paper/Presentation

2.5 Large-scale in-situ demonstration of engineered barrier systems in a salt repository
R. Mauke (BfS), H.-J. Herbert (GRS)
Closure concept and sealing measures of the low- and intermediate-level radioactive waste disposal facility Morsleben (ERAM)
Paper/Presentation

2.6 Microbial processes in a clay repository
P. de Canniere (FANC), A. Meleshyn (GRS)
Paper/Presentation

2.7 Safety issues in construction of facilities for the long-term storage of radioactive waste at the Vektor Site, Chernobyl, Ukraine.
O. Tokarevsky, Z. Alekseeva, S. Kondratiev (SSTC-NRS), N. Rybalka (SNRIU)
Paper/Presentation

2.8 Safety assessment of near surface disposal facilities in Russia
A. Guskov (SEC-NRS)
Paper/Presentation

2.9 Licensing documentation and licensing process for dismantling and decontamination (D&D) projects in Lithuania.
E. Uspuras, S. Rimkevicius, E. Babilas (LEI)
Licensing process applied to authorized activities under separate dismantling and decontamination (D&D) projects at Ignalina NPP.
Paper/Presentation

2.10 Selection and evaluation of decontamination and dismantling techniques for the decommissioning of large NPP components
B. Brendebach (GRS), E. Babilas (LEI)
Paper/Presentation

Seminar 3 – Radiation Protection, Environment & Emergency Preparedness

3.1 Regional radiological surveys: another tool for environmental monitoring in France
C. Antonelli (IRSN)
Paper/Presentation

3.2 Development and application of models for the safety analysis of repositories with regard to the clearance of radioactive materials for landfill.
A. Artmann, D. Weiss, R. Roloff, H. Seher, P.-J. Larue (GRS)
Paper/Presentation

3.3 Scenarios of radiological impacts in the long-term safety analysis of radioactive waste disposal at the Vektor Site located in the Chernobyl exclusion zone
N. Rybalka, O. Mykolaichuk (SNRIU), Z. Alekseeva, S. Kondratiev, E. Nikolaev (SSTC-NRS)
Paper/Presentation

3.4 Radiological aspects and behaviour of spent fuel considering long-term interim storage
F. Rowold, B. Gmal, K. Hummelsheim, S. Kessen (GRS)
Paper/Presentation

3.5 Potential cancer risk associated to CT scans: state of the art of epidemiological studies
M.-O. Bernier et al. (IRSN)
Paper/Presentation

Seminar 4 – Security of Nuclear Installations & Materials

4.1 The European Nuclear Security Regulators Association (ENSRA) organisation
R. Dresselaers (FANC)
Paper/Presentation

4.2 IAEA activities on security of nuclear installations and materials
C. Torres Vidal (IAEA)
Presentation

4.3 The assessment of the physical protection system of a nuclear facility based on the security study and the crisis management process
E. Gosset (IRSN)
Presentation

4.4 Implementation of computer security at nuclear facilities in Germany
A. Lochthofen (GRS)
Paper/Presentation

4.5 Enhancement of the physical protection of waste storage – A step to sustain the nuclear security regime in Ukraine
I. Kuzmyak, V. Kravtsov (SSTC-NRS), V. Kushka (SNRIU)
Paper/Presentation

ETSON Awards

Experimental Investigation and Numerical Analyses of Reinforced Concrete Structures Subjected to External Missile Impact
C. Heckötter (GRS), A. Vepsä (VTT)
Paper – WINNER of the ETSON AWARD
Selection and evaluation of decontamination and dismantling techniques for decommissioning of large NPPs components
E. Babilas (LEI), B. Brendebach (GRS)
Paper

CEMTEX Project – CEMent Temperature EXperiment: Physico-chemical evolution of concrete at high temperature in a high-level radioactive waste repository in deep clay formation
A. Dauzères, P. Lalan (IRSN), T. M. Tang, T. van de Velde (Bel V)
Paper

Assessing the risk related to the spent fuel pool and interactions with the reactor core for WWER type reactors
O. Dybach (SSTC), S. Khiznyak (SEC NRS), J. Kubicek (NRI Rez)
Paper

Challenge of PWR new core design simulation: a focus on uncertainties due to nuclear data and reflector modelling
Y. Perin, A. Aures (GRS), V. Salino (IRSN)
Paper