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
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Aug 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
October 2024
Nuclear Technology
Fusion Science and Technology
August 2024
Latest News
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
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.