石油与天然气工程及钻采工程

 
会议名称(英文)：  2014 Water Reactor Fuel Performance Meeting 
所属学科：  电力,热工学,核科学技术应用 
开始日期：  2014-09-14 
结束日期：  2014-09-17 
所在国家：  日本 
所在城市：  日本 
具体地点：  Sendai, Japan 
主办单位：  Atomic Energy Society of Japan (AESJ) 

E-MAIL：  WRFPM2014@aesj.or.jp 
 
会议网站：  http://web.apollon.nta.co.jp/WRFPM2014/ 
会议背景介绍：      European, American and Asian  country  Nuclear  Societies  have jointly organized the  Reactor FuelPerformance Meetings annually on a tri-annual rotational basis. AESJ, KNS and CNS have organized the WRFPM in Kyoto (2005), Seoul (2008) and  Chengdu (2011). Following the successful  LWR Fuel Performance Meeting 2013 in Charlotte, WRFPM 2014 will take place 14 – 17 September 2014, Sendai, Japan.
    The WRFPM2014 Program Committee is calling for both oral and poster presentations in the following special program and tracks. Papers describing theoretical, analytical, methodological, empirical, and application research on fuel performance under various conditions in water-cooled reactors are welcomed.
    In the WRFPM 2014, the Program Committee features the special program considering the accident in the  Fukushima-Daiichi NPP. Progress status and future challenges towards the decommissioning of Fukushima Daiichi NPP Units 1-4 will be presented in the plenary session preceding the special program.
征文范围及要求：  Track 1: Fuel Performance, Reliability and
Operational Experience
- Fuel operating experience, reliability and performance
- High burnup fuels
- Waterside corrosion and hydriding
- Water chemistry and corrosion counter-measures
- MOX fuel performance
- Pool-side and hot cell examinations
- Irradiation experience in test reactors
- Fuel assembly distortion
- Mixed core operation
- Re-use after transportation/storage
Track 2: Advances and Innovation in Nuclear Fuel Technology
- Advances in fuel design, processing and manufacturing
- Improved fuel pellet and cladding alloy development
- New fuel concepts and new material development such as accident tolerant fuel
- Improvements in MOX fuel design and manufacturing
- Innovative fuel concepts and new fuel designs for next generation reactors
Track 3: Transient and Accidents Related Issues
- Transient fuel behavior and criteria (RIA, LOCA, ATWS, power ramps …)
- Fuel safety-related issues
- Pellet-cladding interaction (PCMI/PCI/SCC)
- Transient fission gas release
- Cladding bursting, pellet fragmentation/relocation/dispersal during transient events
- Small and large scale fuel testing facilities
- Fuel behavior under extended loss of cooling, re-criticality
Track4: Fuel Cycle, Interim Storage and Transportation
- Fuel characterization and performance for transportation and interim/long-term storage
- Criticality in back end processes
- Fuel behavior in dry containers, wet storage ponds and during transportation
- Fuel design optimization for recycle and disposal Track 5: Science and Fundamental Aspects
- Irradiation effects and micro-/nano-structural evolution in fuel and cladding materials
- Physical properties
- Modeling of fuel behavior under normal operation, transient, accident and back-end conditions
- Multiscale modeling
- Multi-physics coupling
- Modeling of water chemistry and corrosion
- Statistical analysis and numerical treatment of uncertainty