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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
September 2024
Nuclear Technology
August 2024
Fusion Science and Technology
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
J-Ch. Sublet, D. E. Cullen, R. E. MacFarlane
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 293-297
Neutron Measurements | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9197
Articles are hosted by Taylor and Francis Online.
The results produced by a variety of currently available pointwise Monte Carlo neutron transport codes for the relatively simple problem of modeling a fast source of neutrons slowing down and thermalizing in water are compared. Initial comparisons showed rather large differences in the calculated flux: up to 80% differences. By working together to improve the results, iterations were done by (a) ensuring that all codes were using the same data, (b) improving the models used by the codes, and (c) correcting errors in the codes - no code is perfect. Even after a number of iterations, we still found differences, demonstrating that our Monte Carlo and supporting codes are far from perfect. In particular, we found that the often overlooked nuclear data-processing codes can be the weakest link in our systems of codes. The results presented here represent today's state of the art in the sense that all of the Monte Carlo codes are modern, widely available, and used codes. They all can use the most up-to-date nuclear data, and the results are recent; these are the results that current users of these codes should expect to obtain from them. As such, the accuracy and limitations of the codes presented here should serve as guidelines to code users in interpreting their results for similar problems. Results for the improved thermal scattering model now available, using advanced versions of NJOY-99.259, TRIPOLI-4.5, and MCNPX-2.6.f Beta, are presented. For comparisons among experimentally measured water cross sections and the unique JEFF-3.1 and ENDF/B-VII thermal scattering law, S(,) data are exemplified.