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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
Hussein Khalil
Nuclear Science and Engineering | Volume 90 | Number 3 | July 1985 | Pages 263-280
Technical Paper | doi.org/10.13182/NSE85-A17768
Articles are hosted by Taylor and Francis Online.
A diffusion theory method is developed for synthetic acceleration of nodal Sn calculations in multidimensional Cartesian geometries. The diffusion model is derived from the spatially continuous diffusion equation by applying spatial approximations that are P1 expansions of the corresponding approximations made in solving the transport equation. The equations of the diffusion model are formulated in a way that permits application of existing and highly efficient nodal diffusion theory techniques to their numerical solution. Test calculations for several benchmark problems in X-Y geometry are presented to illustrate the efficiency and stability of the acceleration method when applied to a “constant-linear” nodal transport approximation. The method is shown to yield point-wise flux convergence of 10-4 in fewer than ten synthetic iterations for all problems considered and to require substantially less computational effort than unaccelerated solutions.