Current Status of Radiation Transport Tools for Proliferation and Terrorism Prevention   [open pdf - 125KB]

"We present the current status and future plans for the set of calculational tools and data bases developed and maintained at LLNL. The calculational tools include the Monte Carlo codes TART1) and COG2) as well as the deterministic code ARDRA3). In addition to these codes presently in use there is a major development effort for a new massively parallel transport code. An important part of the capability we're developing is a sophisticated user interface, based on a commercial 3-D modeling product, to improve the model development process. A major part of this user interface tool is being developed by Strela4) under the Nuclear Cities Initiative. Strela has developed a hub-and-spoke technology for code input interconversions (between COG, TART and MCNP) and will produce the plug-ins that extend the capabilities of the 3-D modeler for use as a radiation transport input generator. The major advantages of this approach are the built-in user interface for 3-D modeling and the ability to read a large variety of CAD-file [Computer-Aided Design] formats. In addition to supporting our current radiation transport codes and developing new capabilities we are working on some nuclear data needs for homeland security. These projects are carried out and the Lawrence Berkeley National Laboratory 88' cyclotron and at the Institute for Nuclear Research of the National Academy of Science of Ukraine under an STCU contract."

Report Number:
University of California Radiation Laboratory, UCRL-PROC-206614
Public Domain
Retrieved From:
Lawrence Livermore National Laboratory Library: https://library-ext.llnl.gov/
Media Type:
The Third Eurasian Conference Nuclear Science and Its Application. Tashkent, Uzbekistan. October 5-8, 2004
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