ICAPP 2007 2007 International Congress on Advances in Nuclear Power Plants “The Nuclear Renaissance at Work” May 13-18, 2007 • Nice Acropolis, France
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Step 1: Online Submission of Abstracts due by September 30, 2006 
Authors should submit a one-page 500 word abstract (text only) with name, affiliation, address, phone, fax and email information to icapp2007.papers@sfen.fr . Please Indicate Track Number. Track descriptions shown below. Click here for a list of technical sessions.

Step 2a: Online Submission of Draft Papers due by January 15, 2007
Once abstracts have been accepted, authors may then upload their full-length draft papers for review. Please send copies of both a PDF and Word file of your draft to (email: icapp2007.papers@sfen.fr or upload DRAFT PAPERS HERE). Please name your draft files according to your paper number (7001-draft.pdf, 7001-draft.doc). Instructions for preparation of full-length papers are noted in the following four pages entitled: “Guidelines for Proceedings Manuscript Preparation”. Template is also available in MS Word. 

<New> Step 2b: Online Submission of Final Abstracts due by January 15, 2007

ICAPP 2007 will publish a BOOK OF ABSTRACTS available at the Meeting. Please send copies of both a PDF and Word file of your Final (formatted) Abstract to (email: icapp2007.papers@sfen.fr or upload Final Abstracts HERE). Please name your final abstract files according to your paper number (7001-abstract.pdf, 7001-abstract.doc). Template for final abstract is also available in MS Word. 

Step 3a: Online Submission of Final Papers due by February 28, 2007
Once draft papers are reviewed and approved, authors may then send their final papers for CD-Rom Publication to (email: icapp2007.papers@sfen.fr or upload FINAL PAPERS HERE). Again, please submit both a PDF and Word file. Please name your final paper files according to your paper number (7001-final.pdf, 7001-final.doc). Hard copies of papers are no longer required.

Note that SFEN will not edit or proof read your final paper. 

Please DO NOT put page numbers on your final paper.

 

Step 3b: Submission of signed copyright/speaker documents due by February 28, 2007

1. Water-Cooled Reactor Programs and Issues 
Evolutionary designs, innovative, passive, light and heavy water cooled reactors; issues related to meeting near term utility needs; design issues; business, economical cost challenges; infrastructure limitations and improved construction techniques including modularization.

 

2. High Temperature Gas Cooled Reactors
Design and development issues, components and materials, safety, reliability, economics, demonstration plants and environmental issues, fuel design and reliability, power conversion technology, impact of non electricity applications on reactor design; advanced thermal and fast reactors.

 

3. LMFR & Longer Term Reactor Programs (new)
Reactor technology with enhanced fuel cycle features for improved resource utilization, waste characteristics, and power conversion capabilities. Potential reactor designs with longer development times such as super critical water reactors and liquid fuel reactors, Gen IV, INPRO, EUR and other programs.

 

4. Operation, Performance & Reliability Management
Training, O&M costs, life cycle management, risk based maintenance, operational experiences, performance and reliability improvements, outage optimization, human factors, plant staffing, outage reduction features, major component reliability, repair and replacement, in-service inspection, and codes & standards.

 

5. Plant Safety Assessment and Regulatory Issues
Transient and accident performance including LOCA and non-LOCA, severe accident analysis, impact of risk informed changes, accident management; Advances in regulatory issues for operating and future plants, life assessment and management of aging, degradation and damage extension lessons from plant operations, probabilistic safety assessment and reliability engineering, new methodologies for plant safety analysis.

 

6. Thermal Hydraulics Analysis and Testing 
Phenomena identification and ranking, computer code scaling applicability and uncertainty, containment thermal hydraulics, component and integral system tests, improved code development and qualification, single and two phase flow; advanced computational thermal hydraulic methods. 

 

7. Fuel Cycle and Waste Management 
TRU separation processes, fuel and target design for transmutation, transmutation performances, scenarios for P&T deployment, review of national programs on P&T, impact of P&T on waste minimization, advanced reprocessing processes and technologies (Purex, Coex, Urex, Pyro, …), nuclear material recycling technologies (MIMAS, Vibropack, …), modelling of processes, back end fuel cycle options, uranium and plutonium management issues, waste conditioning storage and disposal, thorium cycle, fully integrated fuel cycle and symbiotic nuclear power systems, Accelerator Driven Systems (ADS).

 

8. Materials and Structural Issues
Fuel, core, reactor pressure vessel and internals structures: advanced materials issues, environmental effects and fracture mechanics - Concrete and steel containments design and analysis - Design and monitoring for seismic, dynamic and extreme accidents - Irradiation issues, materials and structural mechanics issues, codes and standards for new generation plants.

 

9. Nuclear Energy and Sustainability
Environmental impact of nuclear and alternative systems, spent fuel dispositions and transmutation systems, application of advanced designs to non-power applications such as the production of hydrogen, sea water desalination, heating and other co-generation applications.

 

10. Near Term Deployment Context Issues (new)
Includes general issues not directly related to plants designs but connected to various issues linked to the near-term deployment of new Nuclear Power Plants, such as international licensing convergence of designs, electrical grid concerns, environmental and sitting issues, macro economical & financing, education and training, technological infrastructure, public acceptance, non proliferation...

 

11. Reactor Physics and Analysis
Advances in nuclear field are strongly linked with computer code capabilities for reactor physics. Various aspects are concerned: nuclear data, lattice calculation, deterministic and Monte-Carlo approaches, core calculation, multi physics coupling. Progresses achieved in this domain contribute to the improvement of core performances (for existing reactors and next generation ones: GEN IV). The current topics of interest include new fuel management, new fuels, new reactor cores (for example pebbled bed reactors).

 

12. Innovative and Space Reactor Systems
Other Advanced reactor concepts:
1. Space Nuclear Power and Propulsion
2. Planet Surface Nuclear Power Systems
and other innovative systems with intended design features such as fail proof safety and security, proliferation resistant, small power reactors, modular deployable reactors, long life once burn core and other applications that are not primarily emphasized by conventional power reactor systems.