ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.
