Microsoft word - call_for_papers2008.doc

2008 International Congress on Advances in
Nuclear Power Plants (ICAPP '08)
Embedded International Topical Meeting / 2008 ANS Annual Meeting June 8-12, 2008 • Anaheim, CA, USA
Sponsored by ANS, AESJ, ENS, KNS, SFEN, and SNE In collaboration with IAEA, OECD NEA, BNES, BNS, CNS, CNS, FNS, KTG, NSR, SNS and SNS CALL FOR PAPERS Abstracts Due: October 15, 2007
The City of Anaheim is one of the nation's premier municipalities and California's 10th most populous city.
Centrally located in Orange County of Southern California between Los Angeles and San Diego, Anaheim is
best known for its professional sports and the Anaheim Resort district. The Anaheim Resort district offers an
abundance of hotels, dining, shopping and theme park fun, all linked by a modern visitor transportation system.
Hundreds of picturesque palm trees line the boulevards of the resort area, which encompasses: Anaheim
Convention Center and Disneyland.
Within easy reach of four major airports, Orange County boasts 42 miles of breathtaking coastline, 34 unique
cities, views of the nearby mountains to the east, and ideal year-round weather filled with sunny days and an
average temperature of 70 degrees.
About the Meeting
Following the highly successful ICAPP 2007 meeting held in Nice-France, the 2008 International Congress on
Advances in Nuclear Power Plants will bring together international experts of the nuclear industry involved in
the operation, development, building, regulation and research related to Nuclear Power Plants.
The program will cover the full spectrum of Nuclear Power Plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. The program is expected to cover lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design and reliability. This congress will have full-length technical papers, which will be peer reviewed and published on a CDROM, available at the meeting. Papers of archival quality will be recommended for publication in special issues of the Nuclear Science & Engineering and Nuclear Technology Journals. All authors will be expected to present their papers in English at the congress. About 20 minutes will be allotted for each paper. At least one author is required to register for the congress and present their paper.
Abstract Submission
Paper Deadlines
By October 15, 2007 authors should submit a one-page 500
word abstract (text only) with name, affiliation, address, phone, or
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
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),
modeling 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
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: Space Nuclear Power and Propulsion, 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.
13. Plant Licensing Issues (New)
Reactor licensing and rulemaking, advanced reactor design certifications, combined license applications and review,
multinational design evaluation, risk informed decision making and regulation, generic safety issues, fire protection,
emergency preparedness, nuclear plant security, construction inspection, environmental models for dose
assessment, spent fuel storage and transportation, reactor inspection and assessment, emerging
electrical/mechanical/materials issues.

Honorary Chairs
5. Plant Safety Assessment and Regulatory
Nam Dinh (Royal Institute of Tech-Sweden) General Chairs
Amir Shahkarami (Exelon Nuclear-USA) Jean Claude Gauthier (AREVA-France) 6. Thermal Hydraulics Analysis and Testing
TBA (Hitachi-Japan) *
Shripad Revankar (Purdue Univ-USA) Cesare Frepoli (Westinghouse-USA) Genevieve Geffraye (CEA-France) Nusret Aksan (PSI-Switzerland) Technical Program Chairs
Akira Ohnuki (JAEA-Japan) *
Kune Y. Suh (Seoul National Univ-Korea) 7. Fuel Cycle and Waste Management
Steering Committee
Dominique Grenèche (AREVA NC-France) Samim Anghaie (Univ of Florida-USA) Chan Oh Park (KNFC-Korea) *
Toshikazu Takeda (Univ of Osaka-Japan) *
Richard F. Wright (Westinghouse-USA) Bertrand Vieillard-Baron (SFEN-France) 8. Materials and Structural Issues
Travis W. Knight (Univ of South Carolina-USA) Ram Srinivasan (Energy Solutions-USA) Track Leaders
1. Water-Cooled Reactor Programs and Issues
Kunihiro Itoh (Nuclear Development Corp- Philippe Lauret (AREVA NP-France) 9. Nuclear Energy and Sustainability
Richard Swinburn (Rolls-Royce-UK) Ken Schultz (General Atomics-USA) 2. High Temperature Gas Cooled Reactors
10. Near Term Deployment
Richard F. Wright (Westinghouse-USA) Michael Fütterer (JRC Petten-The Netherlands) 11. Reactor Physics and Analysis
Bojan Petrovic (Westinghouse-USA) 3. LMFR & Longer Term Reactor Programs
Christine Poinot-Salanon (CEA-France) Youichiro Shimazu (Hokkaido Univ-Japan) Jean-Pol Serpantié (AREVA NP-France) Tadashi Yoshida (Musashi Institute of Dubravko Pevec (Univ of Zagreb-Croatia) 12. Innovative and Space Reactor Systems
4. Operation, Performance & Reliability
Shannon Bragg-Sitton (NASA MSFC-USA) Management
Elliott Flick (Exelon Nuclear-USA) Norbert Frischauf (QASAR-Austria) 13. Plant Licensing Issues


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