ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
V. C. Boffi, G. Spiga
Nuclear Science and Engineering | Volume 82 | Number 1 | September 1982 | Pages 105-108
Technical Note | doi.org/10.13182/NSE82-A19033
Articles are hosted by Taylor and Francis Online.
The critical problem in a finite plane slab is studied by an appropriate extension of the integral transform method. For a given optical thickness, the value of the scattering ratio (or mean number of secondaries per collision) that makes the system critical is determined as an eigenvalue of a Fredholm integral equation, in which a continuous position dependence of the scattering ratio itself has been taken into account. The integral equation is solved by a suitable projection technique, and numerical results are presented and briefly discussed for a parabolic trend of the fuel enrichment inside the slab.