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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Roberto Orsi
Nuclear Science and Engineering | Volume 150 | Number 3 | July 2005 | Pages 368-373
Computer Code Abstract | doi.org/10.13182/NSE05-A2524
Articles are hosted by Taylor and Francis Online.
BOT3P consists of a set of standard FORTRAN-77 language programs developed at the ENEA-Bologna Nuclear Data Centre. BOT3P Version 1.0 was originally conceived to give the users of the DORT and TORT deterministic transport codes some useful diagnostic tools to prepare and check their input data files. BOT3P Version 3.0 introduced some important additions in the input geometrical model description and extended the possibility to produce the geometrical, material distribution, and fixed neutron source data to the deterministic transport codes TWODANT, THREEDANT, and PARTISN, and in the case of X-Y-Z mesh grids, a geometrical input to the MCNP Monte Carlo transport code, starting from the same input to BOT3P.BOT3P Version 4.0 extends the modeling capabilities of previous BOT3P versions, reduces CPU times, and facilitates the debugging of the computer code input. Version 4.0 also produces the geometrical entries for the sensitivity code SUSD3D, for both Cartesian and cylindrical geometries, and stores the fine-mesh arrays and the material zone map in a binary file, the contents of which can be visualized by the graphics modules of BOT3P. This new feature makes interfacing to any deterministic and Monte Carlo transport code easy and might open new promising application fields to this package.BOT3P was developed on a DIGITAL UNIX ALPHA 500/333 workstation and successfully used in some complex neutron shielding and criticality benchmarks. It was also tested on Red Hat Linux 7.1 and is designed to run on most UNIX platforms. All BOT3P versions are publicly available from the Organization for Economic Cooperation and Development/Nuclear Energy Agency Data Bank.
