H. H. Over on behalf of H. Weisshaeupl JRC Information Day in Romania on 11th May 2006 Nuclear Safety Research at the JRC/IE.

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


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


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


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


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


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


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


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


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


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-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


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


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


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.


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


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


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


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


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


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


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


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


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


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



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

H. H. Over on behalf of H. Weisshaeupl JRC Information Day in Romania on 11th May 2006 Nuclear Safety Research at the JRC/IE.

Documents

accident management

structural integrity

reactor core

nuclear safety research

demand slide

petten slide

jrcie slide

training nuclear safety