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
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.
R. E. Maerker, F. J. Muckenthaler, R. L. Childs
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 275-297
Shielding | doi.org/10.13182/NT74-A31409
Articles are hosted by Taylor and Francis Online.
An experiment concerning deep neutron penetration in sodium was performed, and experimental results were obtained which provide a basis for verification of the accuracy of sodium cross sections to be used in transport calculations. The experiment was conducted at the Tower Shielding Facility of Oak Ridge National Laboratory and included measurements of both the neutron fluence and the neutron spectra through a large diameter sample of sodium up to 15 ft thick. Calculated results for the experiment were also compared with the experimental measurements. These results were obtained using the multigroup Monte Carlo code, MORSE, and a two-dimensional discrete ordinates code, DOT-III. One-hundred group data sets were developed from both a preliminary and the final version of the ENDF/III set (MAT-1156) for sodium for use in the calculations. Comparisons of the calculations with experiment indicate that (a) the preliminary version is slightly superior to the final version and (b) using the preliminary set, the total neutron leakage above thermal energies penetrating through 15 ft of sodium agrees to within ∼15%; and the absolute spectra penetrating through 12.5 ft of sodium, when integrated over the energy range of the measurement, agrees to within 20%. Using the final set, the corresponding comparisons are 30% and 60%.