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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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!
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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.
L. E. Hansen, E. D. Clayton, R. C. Lloyd, S. R. Bierman, R. D. Johnson
Nuclear Technology | Volume 6 | Number 4 | April 1969 | Pages 371-380
Technical Papers and Note | doi.org/10.13182/NT69-A28347
Articles are hosted by Taylor and Francis Online.
To predict the critical parameters of plutonium fueled systems one must establish the accuracy of the computational methods to be employed and the accuracy and applicability of the available critical experiment data with which the calculations are to be compared. The accuracy of a multigroup diffusion theory code, HFN, and a multigroup transport theory code, DTF-IV, was examined by analyzing recent plutonium critical experiments. The experiments cover the entire range of possible moderation ratios, and the plutonium fuels contain as much as 23.2 isotopic percent 240Pu. All three basic geometries are represented by the experimental data examined. Where necessary, the criticality data were corrected, by means of additional experiments and/or calculations, to conform to one-dimensional, clean, homogeneous critical assemblies which could be adequately defined and used as a basis for establishing nuclear criticality safety guidelines.