IAEA Meetings » CN 226 » Presentations
MONDAY, 15 JUNE 2015
09:30 - 10:30 Opening Session
  F. Rayment
Conference President
Director, Fuel Cycle Solutions
National Nuclear Laboratory, UK
Opening Remarks
Y. Amano
IAEA Director General
Opening Remarks
W. Magwood
Director General
OECD Nuclear Energy Agency (NEA)
A Holistic View of the Nuclear Fuel Cycle
Opening Remarks
10:30 - 17:30 SESSION 1: Spent Fuel Management Strategies
  Chairpersons:
D. Fox, UK
S. Kahook Jordan
Nuclear Power and the Fuel Cycle Options for Jordan
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T. Saegusa, Japan
Potential Interface Issues in Spent Fuel Management
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D. Hambley, UK
Lessons Learned from a Review of International Approaches to Spent Fuel Management
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H. Zaccai, WNA
Successful Strategy Development in Used Fuel Management – An Industry Perspective
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C. Devron, France
Sustainable Cycle Solutions
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K. Agarwal, India
The Management of Spent Fuel from PHWRs in India – An Integrated Approach
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S. Lee, Korea, Republic of
Study of the Multilateral Management of Spent Fuel According to Korea’s Power Supply Plant
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J. Fernandez Lopez, Spain
Spanish Strategy for the Management of Spent Nuclear Fuel – ATC Project
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A. Khaperskaya, Russian Federation
Spent Nuclear Fuel Management System in the Russian Federation
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C. Eckerberg, Sweden
Deep Geological Disposal of Spent Fuel in Sweden
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S. Caruso, Switzerland
Spent Nuclear Fuel Management in Switzerland: Perspective for Final Disposal
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E.J. Bonano, USA
Managing Spent Nuclear Fuel from Generation to Final Disposal: Integration of the Back End of the Nuclear Fuel Cycle
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Posters
I.Kuzman, Russian Federation
Performance Assessment of Fuel Assemblies Removed from Shut Down RBMK Reactor Cores
A. Newman, Nuclear Threat Initiative
Developing Regional Spent Fuel Strategies
M. Afifi, Egypt
Egyptian Proposed Strategy of Spent Fuel Management from Nuclear Power Reactors
N. Chapman, Switzerland
Developing a Spent Fuel Strategy for a Newcomer Nuclear Power Country
Posters Summary
MONDAY, 15 JUNE 2015
17:30-18:00 SESSION 2: Status and Challenges in an Integrated Approach
  CHAIRPERSONS:
B. Droste, Germany
M. Chiguer, France
P. Swift, USA
How Spent Nuclear Fuel Management Options Might Affect Geologic Disposal
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J. Gerža, Czech Republic
History and Current Status of Spent Fuel Management at Dukovany Nuclear Power Plant
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P. Maaranen, Finland
Enlargement of the Olkiluoto Spent Fuel Interim Storage
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H. Völzke, Germany
Long Term Storage of Spent Nuclear Fuel and HLW in Dual Purpose Casks Towards Disposal – Challenges and Perspectives
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T. Ishikawa, Japan
Design and Construction Work Experience of Interim Storage Facility for Spent Fuels
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S. Kirilov, Russian Federation
Status and Prospect of Spent Nuclear Fuel Reprocessing at Mayak Plant
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V. Vo Van, France
Safe Solutions for Transport and Dry Storage of Defective Fuel Rods
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S. Perepelkin, Russian Federation
Russian Experience and Proposals on Management of Non – Conforming Spent Nuclear Fuel of RBMK Reactors
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G. Ashworth, UK
Retrieval of Damaged Fuel from Wet and Dry Storage Using Innovative Remote Handling Techniques
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Y. Kumano, IAEA
DPC Safety Case Development
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B. Droste, Germany
Ageing Mechanisms Influence on Transport Safety of Dual Purpose Casks for Spent Nuclear Fuel
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C. McCombie, Switzerland
Regional Cooperation on Spent Fuel Management: Status and Prospects in Europe, Arab Regions and Asia
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B. Bonnardel-Azzarelli, WNTI
Industry Experience on Back End Transport
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S. Laârouchi Engstroem, Sweden
Licensing of the Swedish Deep Geological Disposal of Spent Fuel
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J. Andersson, Sweden / Finland
Challenges in Developing the Basic Design of the KBS-3 System into a Qualified and Industrially Viable Operation
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Posters
S. Kim, Korea, Republic of
The Status of Spent Fuel Management and the Process of Building Public Opinion in Korea
S. Squasoni, USA
Linking Nuclear Security to Spent Fuel Management
Posters Summary
TUESDAY, 16 JUNE 2015
09:00-18:00 SESSION 3: Safety Aspects of Spent Fuel Management
 

CHAIRPERSONS:
F. Besnus, France
D. Wolff, Germany

I. Le Bars, France
Safety and Technological Aspects of Spent Fuel Management
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J. Heinonen, Finland
Regulatory Experiences from Implementation of Spent Nuclear Fuel Disposal Programme from Site Selection to Construction of Disposal Facility – the Finnish Case
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A. Hagros, Finland
Development of Long Term Safety Requirements for an Alternative Design Variant (KBS-3H) for Spent Fuel Disposal
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I. Reiche, Germany
Transport Aspects of Spent Fuel Management
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V. Chrapciak, Slovak Republic
Spent Fuel Transport Container C-30
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J. Vaclav, Slovak Republic
Thermal Field Modeling of Spent Fuel Transport Container C-30
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M. Bailey, USA
Activities of the OECD/NEA/CSNI WG on Fuel Cycle Safety in Spent Fuel and High Level Waste Management
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K. Doğan, Turkey
Consequences of Long Term Black Out Accident on Spent Fuel Pool for VVER-1200
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WEDNESDAY, 17 JUNE 2015
09:00-12:00 SESSION 3 (cont'd): Safety Aspects of Spent Fuel Management
  CHAIRPERSONS:
F. Besnus, France
D. Wolff, Germany

T. Ihara, Japan
Spent Fuel Storage at Fukushima Daiichi Nuclear Power Plant
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J. Palmes, Germany
Interim Storage of Spent fuel in Germany - History, State and Prospects
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D. Racimor, France
Lessons Learned from a Periodic Safety Review, Applied to the Design of New Nuclear Fuel Cycle Facilities
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K. Linnenman, Germany
Aspects of Spent Fuel Behaviour Assessment for Transport Packages
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K. Shirai, Japan
Evaluation of Sealing Performance of Metal Gasket used in Dual Purpose Metal Cask Subjected to an Aircraft Engine Missile
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D. Garrido Quevedo, Spain
Fabrication Thermal Test Methodology for a Safe Cask Thermal Performance
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Posters
K. Tiyapun, Thailand
MNCP Model for Research Reactor (TRR-1/M1) Fuel Storage Rack Criticality Analysis
M. Ibrahim, Egypt
Criticality Safety and Burnup Credit Analysis for MOX Fuel
D. Lee, Korea, Republic of
Major Consideration in Safety Assessment for Interim Spent Fuel Storage Facility in Korea
S. Skilarrov, Russian Federation
Potential of Active Neutron Interrogation to Control Fissile Materials in “Closed” Fuel Cycle
S. Lee, Korea, Republic of
Safety Tests of Spent Fuel Storage Systems in Korea
A. Kirkin, Russian Federation
Implementation of Guidance for an Integrated Transport and Storage Safety Case for Dual Purpose Casks for Spent Nuclear Fuel in Russian Regulatory Documents
S.Jones, USA
Value of Expedited Transfer of Fuel From At-Reactor Wet Storage
Posters Summary
13:00-16:30 SESSION 4: Ageing Management Programmes
 

Chairpersons:
J. Kessler, USA
T. Saegusa, Japan

Y. Liu, USA
Managing Ageing Effects on Dry Cask Storage Systems for Extended Long
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Catherine Shelton, Vanessa Vo Van, Justo Garcia, France
Ageing Management Solutions to Ensure Safety of Extended Dry Fuel Storage
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Michele Sampson, USA
Renewing Dry Spent Fuel Storage Certificates of Compliance and Specific Licenses
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J. Kishimoto, Japan
Demonstration Test Programme for Long Term Dry Storage of Pressurised Water Reactor Spent Fuel
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K. Sorenson, USA
The High Burnup Confirmatory Data Project
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M. Jaunich, Germany
Performance of Elastomer Seals in Transport and Storage Casks
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J. Kishimoto, Japan
Mechanical Properties of Aluminium Alloys for Transport and Storage Cask
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J. Scaglione, USA
A Unified Spent Nuclear Fuel Database and Analysis System
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J. Kessler, USA
The CRP on Demonstrating Performance of Spent Fuel and Related Storage System Components during very Long Term Storage (CRP TI 3014)
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Posters
Oberländer, Norway
Al-Clad Metallic Uranium Legacy Fuel after 50 Years in Underground Dry Storage: Spent Fuel Ageing Management
R. Versaci, Argentina
Ageing Management of Spent Nuclear Fuel Facilities
Posters Summary
16:30-17:50 SESSION 5: Storage Options in Support of an Integrated Approach (Industry)
  Chairpersons:
C. Ganguly, India
S. R. Smith, USA
J. García, France
AREVA Operational Experience in Interim Dry Storage
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T. Makarchuk, Russian Federation
Experience for Cask Technology of Spent Nuclear Fuel Management
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R. Springman, USA
Multi-Purpose Canisters for Long Term Storage
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W. Woodward, USA
Underground Interim Storage of Spent Nuclear Fuel HI – Storm UMAX
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Kent S. Cole, USA
Spent Fuel Dry Storage: Challenges and Lessons Learned From Recent Project Experience at Shutdown Nuclear Plants in the U.S.
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THURSDAY, 18 JUNE 2015
09:00-10:30 SESSION 5 (Cont'd): Storage Options in Support of an Integrated Approach (Industry)
  Chairpersons:
C. Ganguly, India
S. R. Smith, USA

P. Hallington, UK
50 years of the Magnox Reprocessing Plant at Sellafield Site United Kingdom (50 not out)
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R. Kellar, USA
Spent Fuel Storage Integration in the US Planning for Storage and Transportation
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R. Stoll, USA
Development of an Execution Strategy Analysis (ESA) Capability and Tool for Storage of Used Nuclear Fuel (UNF)
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J. Carter, USA
Design Concepts and Options for Consolidated Interim Storage in the United States
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Posters
M. Mazzuccato, EU
Dry Storage of Irradiated Nuclear Material in Dual Purpose Cask at the JRC-Ispra Site
P. Bennett, Norway
Progress towards a Solution for Intermediate Storage of Spent Nuclear Fuel in Norway
H. Luna Dávila, Argentina
First Experience in Basic Design of a Dry Storage Facility for Spent Fuel in Argentina
K. Whitmore, USA
Strategy for the Determination of an Appropriate On-Site Dry Fuel Storage System and for Optimizing the Location of the Facility

Posters Summary

11:00-15:15 SESSION 6: Impact of the Front End of the Nuclear Fuel Cycle on the Back End
 

Chairpersons:
A. Bychkov, Russian Federation
J.P. Carreton, France

A. Bychkov, Russian Federation
Introduction on INPRO
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M.S. Yim, Korea
Republic of Influence of Fuel Design and Reactor Operation on Spent Fuel Management
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M. Chiguer, France
How Innovative Approaches and Technologies throughout the Fuel Cycle are Supporting Nuclear Power Plant Operations while Anticipating Future Back End Challenges
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G. Spykman, Germany
Specific Aspects of High Burnup or Mixed Oxide Fuel Rods During Dry Storage
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Y. Fedorov, Russia
Multiple Recycle of Remix Fuel Based on Reprocessed U and Pu Mixture in Thermal Reactor
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J. García de la Infanta Bello, Spain
On the Impact of the Fuel Assembly Design Evolution in Spent Fuel Management
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Y. Kovbasenko, Ukraine
Comparative Analysis of Isotope Composition of VVER-1000 WESTINGHOUSE and TVEL Spent Fuel
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V. Ivanov, Russian Federation
Closed Nuclear Fuel Cycle with Fast Reactors and Dense Fuel
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A. Shadrin, Russian Federation
Reprocessing of BREST Reactor Mixed Nitride Spent Nuclear Fuel
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Posters
L. Rodríguez-García, Cuba
Thorium Cycles in a Very High Temperature Hybrid System
M. Nader, Egypt
Design Strategies for Direct Recycling of ACR-700 Spent Fuel

M. Baryshnikov, Russian Federation

Posters Summary
15:45-18:00 SESSION 7: Research and Development Required to Deliver an Integrated Approach
  Chairpersons:
K. Shirai, Japan
B. Hanson, USA
  B. Boullis, France
The French Nuclear Fuel Cycle: Current Status and Possible Future Solutions
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  F. Takats, Hungary
The IAEA CRP BEFAST and SPAR – 34 Years of Experience with the Storage of Spent Fuel and Facility Components
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  J. Desquines, France
Influence of Decaying Stress and Temperature on Radial Hydride PPT in Zr 4 Claddings
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  T. Hirose, Japan
Fuel Rod Mechanical Behaviour Under Dynamic Load Condition on High Burnup Spent Fuel of BWR and Pressurized Water Reactor
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  A. Smaizys, Lithuania
Evaluation of Radiation Characteristics of Spent RBMK-1500 Nuclear Fuel Storage Casks During Very Long Term Storage
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  M. Wataru, Japan
CRIEPI’s Studies on the SCC of the Canister for Spent Nuclear Fuel
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FRIDAY, 19 JUNE 2015
09:00-11:00 SESSION 7 (Cont'd): Research and Development Required to Deliver an Integrated Approach
  Chairpersons:
K. Shirai, Japan
B. Hanson, USA
  J. Kyffin, UK
Technological Development to Support a Change in United Kingdom’s Strategy for Management of Spent AGR Oxide Fuel
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  M. Gotoh, Japan
Development of SCC Resistant Canisters For Spent Fuel Storage and Transport
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  S. Salzstein, USA
Investigations of SCC on Spent Fuel Dry Canisters Used for Long Term Storage
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  M. Lloret, Spain
Hydride Effect on Cladding Behaviour for Spent Fuel Storage and Transport Conditions
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  K. Sorenson, USA
An Integrated Approach to Closing the Technical Data Gap for High Burnup Spent Fuel Performance during Normal Conditions of Transcript (NCT)
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  Posters
  S. Alyokhina, Ukraine
Safety of the Dry Spent Nuclear Fuel Storage in Ukraine: Scientific Approach and Results
  J. Cha, Korea, Republic of
Preliminary Thermal Margin Comparison Between a Simple Spent Fuel Model and a Complex Spent Fuel Model for a Dry Storage Cask
  H. Yagihashi, Japan
Study on Temperature Estimation Method of PWR Spent Fuel Cladding in Dry Storage
  I. Bosneaga, Rep. of Moldova
Huge Non-Spent Potential of “Spent Fuel”- the Ways of its Utilization
  H. Issard, France
Technologies for Integrated Safety Management Regarding Gas Generation in Spent Fuel Dry Storage Systems or Transport Systems, Wet or Dry
  P. Finocchiaro, Italy
Low Cost Gamma and Neutron Radiation Sensors for Real Time Cask Monitoring
  K. Christodoulides, UK
A Novel Approach for Monitoring Highly Active Wastes
  M. Pordomingo, Spain
Gamma Neutron Dynamic Scanner
  Posters Summary
11:15-12:00 CLOSING SESSION
 

Conference President
F. Rayment, UK
Conference Summary

D. Flory, IAEA, Deputy Director General Department of Nuclear Safety and Security
Closing remarks
M. Chudakov, IAEA, Deputy Director General Department of Nuclear Energy
Closing remarks
 
 
 
 
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