The Eighth International Topical Meeting on
Nuclear Applications and Utilization of Accelerators

The Next Generation of Accelerator Applications

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Conference Scope

The Eighth International Topical Meeting on Nuclear Applications and Utilization of Accelerators (AccApp'07) is the eighth in a series of international meetings of the American Nuclear Society's Accelerator Applications Division.  Venues for the previous conferences include:
 
  • AccApp05 - Venice, Italy
  • AccApp03 - San Diego, California
  • AccApp01 - Reno, Nevada
  • AccApp00 - Washington, D.C.
  • AccApp99 - Long Beach, California
  • AccApp98, Gatlinburg, Tennessee
  • AccApp97, Albuquerque, New Mexico
 
AccApp'07 is the first conference of the AccApp series to be organized in Idaho.  The conference will be held on the Idaho State University campus, providing a unique opportunity to experience glimpses of the historic Old West and tour the internationally renowned Idaho Accelerator Center.  The Conference will occur July 30th to August 2nd, 2007.
 
The AccApp'07 conference is an international forum for discussing new results in accelerator application technology as it relates to present accelerator research and to future accelerator applications.  The AccApp'07 subject areas include:
 
 
High-power Accelerator Operations:
  • Operational Experience
  • Beam Interface Issues
  • Instrumentation & Controls
  • Shielding
  • Remote Handling
  • Health Physics & Dosimetry
  • Waste Management
Systems Engineering & Integration:

  • Accelerator Driven System (ADS) Simulations
  • ADS Experiments
  • Design Optimizations
  • Reliability Analysis
  • Cost Estimating & Economics
  • University Systems & Programs
Applications:

  • Spallation Neutron Sources
  • Industrial Applications
  • Accelerator Mass Spectrometry
  • Medical Imaging and Therapy
  • Nuclear Waste Transmutation
  • Energy Production
  • Environmental Applications
  • Food Safety
  • Free Electron Lasers
  • Portable Accelerators
  • Radioisotope Production
  • Inspection Technology for Explosives and Fissile Materials
  • Radiation Damage and Biological Effects
  • Imaging and Advances in Detectors
Other:

  • Neutronics Calculations
  • Codes and Models for Beam Transport and Experiment Validation
  • Nuclear Data
  • Photonuclear Cross Sections
  • Safety and Source Term
  • Subcritical Assembly Design
  • Transmutation Fuels
  • Separations Technologies
  • Target Engineering
  • Materials for Accelerator Applications
  • Long-lived Fission Product Transmutation
  • Accelerator-driven University Neutron Sources
  • Positron Annihilation Spectroscopy