h. h. over on behalf of h. weisshaeupl jrc information day in romania on 11th may 2006 nuclear...
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H. H. Over on behalf of H. Weisshaeupl
JRC Information Day in Romania on 11th May 2006
Nuclear Safety Research at the JRC/IE
JRC Information Day in Romania on 11th May 2006 page 2
High Flux Reactor
Multi-purpose research reactor tank-in-pool, light water cooled/moderated,
45 MW irradiation at:
reactor core, reflector region, poolside horizontal beam tubes,
gamma irradiation facilities, hot cells labs (NRG)
The Programmes At the service of medicine
o Radio-Isotopes productiono Boron Neutron Capture Therapy (BNCT)
At the service of reactor technologyo Nuclear Safety (study of ageing materials)o Waste (study of transmutation and thorium cycle)o New reactors for the future (HTR, Fusion reactors, etc.)
At the service of research and industryo Neutron diffraction applications in materials scienceo Neutron radiography, gamma irradiation, activation analysis, etc
JRC Information Day in Romania on 11th May 2006 page 3
ACCIDENT PREVENTION:Integrity of the Reactor Coolant System
ACCIDENT PREVENTION:Integrity of the Reactor Coolant System
ACCIDENT MITIGATION:Integrity of the Confinement System
ACCIDENT MITIGATION:Integrity of the Confinement System
with investigation on: material’s degradation(irradiation, corrosion, thermal fatigue) in-service inspection structural integrity preventive maintenance
with investigation on: material’s degradation(irradiation, corrosion, thermal fatigue) in-service inspection structural integrity preventive maintenance
with investigation on: accident analysis(test interpretation, code validation) - ‘severe accidents’ accident management system interaction
with investigation on: accident analysis(test interpretation, code validation) - ‘severe accidents’ accident management system interaction
Horizontal activities: probabilistic & risk assessment methodologies data management & dissemination training
Horizontal activities: probabilistic & risk assessment methodologies data management & dissemination training
Nuclear Safety at IE
JRC Information Day in Romania on 11th May 2006 page 4
Scope:
• Mark 10 years of achievements in the European Networks (1993-2003)
• Learn from the best scientific and technical achievements
• Look at new R&D challenges in FP6 and beyond
• Round table (industry, universities, R&D providers,DG-RTD, DG-TREN)
• Establish possibilities and structure for future network actions
10 years of networking at Petten
JRC Information Day in Romania on 11th May 2006 page 5
European Networks
EUROPEAN NETWORKS for a common understanding and harmonisation on key issues in nuclear reactor safety
strong Integration element with hands-on research in key competence areas and reference laboratories
Key words: Sharing/exchange of knowledge Training & Education Benchmark-Exercises and Workshops Support to Harmonisation
General Deliverables: Contribution to Best practices / Guidelines Contribution to Code & Standards Contribution to harmonized conclusions on safety assessment methodologies and
procedures (Web-based) Platform for virtual dissemination and learning specific reports on emerging issues on demand
JRC Information Day in Romania on 11th May 2006 page 6
Ageing Materials Evaluation and Studies
Study RPV materials and other (internals) on irradiation embrittlement and thermal ageing
non-destructive ageing monitoring techniques annealing and re-irradiation studies
AMES has taken major initiatives, including: Kick-Off of the European Plant Life Assessment Forum
(EPLAF) at Minatom 1999 key role in defining the new Tacis/Phare projects on
irradiation embrittlement
20 participating organisations
AMESAMESAGEING MATERIALS EVALUATION AND STUDIES
JRC Information Day in Romania on 11th May 2006 page 7
European Network on Inspection Qualification
Assessment and qualification of Non Destructive Testing systems
Inspection qualification schemes harmonisation of codes and standards risk-informed inspection
The ENIQ-led European Non-Destructive Evaluation Forum (ENDEF) has elaborated a strategy on measures to improve in-service inspection in VVER and RBMK reactors
64 participating organisations
ENIQEuropean Network for Inspection Qualification
JRC Information Day in Romania on 11th May 2006 page 8
Network for Evaluating Steel Components
NESC I Spinning Cylinder NESC II MPA Pressurized Thermal Shock NESC IIIDissimilar Weld NESC IV Multi-axial loading (ORNL Beam) Thermal Loading
25 organisations
NESCNESCNetwork for Evaluating Steel Components
Validation of entire structural integrity process through large-scale testing
NESC INESC I
NESC IVNESC IV
BenchmarksVVER IssuesHTR IssuesTrainingDisseminationHarmonisation
hot
cold
mixing area
JRC Information Day in Romania on 11th May 2006 page 9
Network on Neutron Techniques Standardization for Structural Integrity
39 organisations To employ neutron based testing methods for gaining improved
understanding on residual stresses and material degradation To harmonise the corresponding experimental methodologies Technical tasks:
pilot study on residual stress analysis with neutron diffraction, X-ray diffraction, computational analysis
study on stress relief heat treatment for novel repair welding methods study on thermal ageing effects based on Small Angle Neutron Scattering
JRC Information Day in Romania on 11th May 2006 page 10
IASCC issues in LWR
PWR + BWR:Baffle/former bolts
support pinsrod cluster control assemblies tip
Core shroudtop guide and core plate
PWR + BWR:Baffle/former bolts
support pinsrod cluster control assemblies tip
Core shroudtop guide and core plate
AMALIA test facility (Ageing of Materials under Load and and Irradiation-Assisted
stress-corrosion cracking)
AMALIA test facility (Ageing of Materials under Load and and Irradiation-Assisted
stress-corrosion cracking)
Studies on stress corrosion cracking in NPP: autoclave with pneumatic loading device and a water chemistry preparation loop for fracture toughness testing, equipped with a device for bending tests of mini and standard Charpy-size specimens
JRC Information Day in Romania on 11th May 2006 page 11
Experimental Facilities (outside HFR)
Implantation of simulated defects in components
Fracture testing of steels
Impact testing and degradation monitoring lab
Thermal fatigue rig for pipe test pieces
Microstructural analysis
Ultrasound measurements for detection of defects
JRC Information Day in Romania on 11th May 2006 page 12
JRC-IE has adopted a new integrated
approach to its R&D for safety of ageing
nuclear plant, bringing together the established
European networks with new groups in
SAFELIFE
The way into FP 6projects related to structural integrity
JRC Information Day in Romania on 11th May 2006 page 13
Analysis and Management of Nuclear Accidents
SEVERE ACCIDENTSto integrate the knowledge on severe accident phenomenology into common databases and reference analytical computer tools and to support conclusions for accident management measures
SA research results in a better understanding and evaluation of this very unlikely event - risks connected reduced
DESIGN BASIS ACCIDENTS (DBA)(limited effort)to support the transfer of knowledge, data and tools in some key issues of VVER-DBA safety based on JRC previous programs and expertise
LOBI test facility
JRC Information Day in Romania on 11th May 2006 page 14
PHEBUS-FP (integral in-pile tests) European dissemination networks on:
= Core degradation and fission product release= Circuit and containment aerosol behaviour= Containment chemistry
Over 30 participating organisations (incl. USA, Canada, Japan, S-Korea)
test interpretation, code validation and bench-marking, dissemination of the
results: for improving accident mitigation
Networks on Severe Accident Research
Cadarache / F
JRC Information Day in Romania on 11th May 2006 page 15
The PHEBUS FP Test Matrix
Contributions from JRC:Defining the test matrix / pre-test calculations for test
planning / review and quality assurance of the Test Reports / contribution&coordination of the Dissemination Reports /
Deputy Program Manager / promoting European participation (Dissemination Work-Shops) / etc.
Contributions from JRC:Defining the test matrix / pre-test calculations for test
planning / review and quality assurance of the Test Reports / contribution&coordination of the Dissemination Reports /
Deputy Program Manager / promoting European participation (Dissemination Work-Shops) / etc.
JRC Information Day in Romania on 11th May 2006 page 16
Potential hydrogen explosion within a NPP containment as consequence of a SA
REACFLOW: 3D reactive gas flow code for turbulent combustion, deflagration and detonation of highly reactive gas mixtures in large, complex enclosures
Full scale simulation of the containment of a PWR:
Without two external walls
Non-nuclear application
JRC Information Day in Romania on 11th May 2006 page 17
Hydrogen Explosion in a Tunnel
Following a release of H2 from a bus tank at 350 bar
- pressure distribution on a temperature iso surface of 350 K
Following a release of H2 from a bus tank at 350 bar
- pressure distribution on a temperature iso surface of 350 K
JRC Information Day in Romania on 11th May 2006 page 18
Probabilistic and Risk Assessment Methodologies & Reliability and
Availability aspects
P1
P2
etc.
Event Tree Network
Initiating event failure
probability logice.g.
pipe break
Initiating event
failure probability
OUTPUT:Radioactivity release
probabilities
X fails Y fails
Fault Tree Model
JRC Information Day in Romania on 11th May 2006 page 19
Methodological Developments Reliability of passive safety systems
to develop new methods how to quantitatively assess reliability on passive safety systems in the lack of statistical failure data
PSA for Aging reactors to cross-compare existing approaches in Europe and USA for including aging from
active and passive components in PSA
PSA Quality Guide to develop an international Guidance on how to verify quality level of a PSA study
(together with IAEA)
PSA and RI-ISI (together with ENIQ) to develop a Guidance on how to make best use of available PSA results for RI-ISI
application
Quantification of uncertainty and sensitivity analysis Comparative Energy Risk Assessment
to enable consistent and fair cross-comparisons of different energy systems in terms of risk and sustainability
Previous Benchmark exercise on Expert Judgement Techniques in PSA Level2 Benchmark exercise on Safety Evaluation of Computer Based Systems
JRC Information Day in Romania on 11th May 2006 page 20
Mapping nuclear safety related practices and methods as used in the Enlarged EU to provide all interested parties with status of top level safety documents
and risk informed approaches
Knowledge Dissemination
http://www.energyrisks.jrc.nl
JRC Information Day in Romania on 11th May 2006 page 21
Safety of new Reactor Designs
Safety analyses and comparisons of a range of new reactor designs Material and fuel issues related to HTRs
participation in: Generation IV (GIF) INPRO (IAEA) OECD/NEA
MICANET“strategy for R&Dkeeping the optionfor nuclear fissionenergy open”
Co-ordination of the High Temperature Reactor Technology Network (HTR-TN)with technical support via irradiations of fuel, graphite and structural materials
Schematic of the capsule used for irradiation exposures on HTR fuel pebbles in the Petten HFR
JRC Information Day in Romania on 11th May 2006 page 22
New Reactor Designs(VHTR, GFR, LFR, SCWR, SFR)
Main activities: Irradiations (HFR)
HFR-EU1, HFR-EU1bis, HFR-EU2, PBMRwith: fabrication, commissioning, analysis, …
Out-of-pile tests (GIF related) (De-)Carburization tests for HTR components
High T material tests
Tests at supercritical water conditions
Corrosion tests (H2 production processes)
Analytical work Neutronic/Thermal-hydraulic safety studies & design
Proposals for System safety improvements
HTR fuel database
JRC Information Day in Romania on 11th May 2006 page 23
Casks for high level nuclear waste
design principles for high level waste packages: acceptance criteria associated for their structural integrity and functioning against loads that may occur under transport, storage, handling and the long-term deposition
JRC Information Day in Romania on 11th May 2006 page 24
SAFECASK: CASKS FOR HIGH-LEVEL RADIOACTIVE WASTE
Waste packages constitute an important part in management of radioactive waste to ensure that there is no release of hazardous radioactive nuclides.
The objective of SAFE-CASK is to develop design and assessment methods for nuclear waste packages and to provide scientific support to policy DG’s in this area.
Transport Casks Short times Cask primary barrier Design against accident
scenarios (dynamic loads, fire etc)
Geological Disposal Casks Very long functioning (100 000 years) Cask constitute first barrier in multi-
barrier system Design account for very long processes
(including climate change)
Intermediate and Long-term Storage Casks in near- or sub-surface facilities
Intermediate times (50-500 years) Cask primary or secondary barrier Design against accident scenarios Waste retrievable
Decay of waste radiotoxicity with time, reduced need for monitoring
JRC Information Day in Romania on 11th May 2006 page 25
On-line Data Information Network – ODIN (https://odin.jrc.nl)
ODIN architecture
ODIN Web Portal on Petten Server
secure connection <-> fire-wall <-> access control <-> integrated user management
Engineering DBs
Mat-DB, Gasket-DB, HTR-Fuel-DB
Document Management DB
DoMa
Relational Database Management System (ORACLE)
Open Interfaces toEuropean competence sites:
Webservice between Mat-DB and FIT-IT life-time prediction at Fraunhofer IKM, Freiburg
Mat-DB web application at FZ Jülich
HFR-Fuel-DB data exchange with CEA Caderache
Nuclear DBs
SENUF-DB, NuCoC-DB, DARES-DB
Investments for hard- & software ~ 1 MEuro
JRC Information Day in Romania on 11th May 2006 page 27
NUCLEAR REACTOR SAFETY
Accident analysis Accident management
System interaction
Ageing of materialInspection qualificationPreventive maintenance
Structural integrity
Probabilistic & risk assessment Reliability
Uncertainty quantification
PreservationDisseminationOn-line service
Technical/scientificSupport:
Design SafetyOn-Site Assistance
DisseminationRegulators, Waste,...
Generation IV
INPRO
MICANET
HFR applications
TACIS/PHARE Accident Prevention Accident Mitigation Innovative Reactors
PSA & Risk Methodologies
Data & Information Management
Training & Education Benchmark Exercises & Work-Shops
Best Practices / Guidelines / Code&Standards
Western & Russian type NPPs European Harmonisation