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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
D. R. Wyman, A. A. Harms
Nuclear Science and Engineering | Volume 89 | Number 3 | March 1985 | Pages 273-279
Technical Note | doi.org/10.13182/NSE85-A17548
Articles are hosted by Taylor and Francis Online.
The buildup factor for a collimated neutron beam normally incident on a single infinite slab is derived for the cases in which the beam intensity is first taken as the total scalar flux and then as the forward partial current. These functions are specified in a series derived from a solution of the integral neutron transport equation. Relative magnitudes and other properties of these buildup factors are thereby quantitatively examined and their ready applicability suggested.
