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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Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
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Latest News
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
F. U. Ahmed, S. I. Bhuiyan, A. S. Mollah, M. M. Rahman
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 379-386
Technical Note | Radiation Protection | doi.org/10.13182/NT92-A34667
Articles are hosted by Taylor and Francis Online.
Gamma-ray shielding properties of ilmenite-magnetite (I-M) concrete and polyboron are measured with an NaI(Tl) detector. The detector response function is studied, and the inverted detector response matrix is generated. Using this inverted response matrix, the pulse-height spectra of gamma rays transmitted through the shields are converted into photon spectra, and the respective dose rates are calculated. The instantaneous relaxation lengths and the buildup factors for gamma rays from a 252Cf source penetrating I-M concrete and polyboron slabs are reported. Buildup factors and instantaneous relaxation lengths are fitted to the appropriate functions, and the related coefficients are also reported.