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
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
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. R. Sarder, M. Q. Huda, M. Rahman, M. A. W. Mondal
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 196-204
Technical Paper | Radiation | doi.org/10.13182/NT99-A2967
Articles are hosted by Taylor and Francis Online.
The shielding effectiveness of locally developed polyboron and ilmenite-magnetite (I-M) concrete is investigated using the reactor neutron beam of the 3-MW TRIGA Mark II research reactor at the Atomic Energy Research Establishment, Savar, Dhaka. The effective removal cross sections for the foregoing individual shielding materials as well as their combinations are obtained from transmission data using two-group neutron fluxes defined by a Cd-cutoff value. The experimental transmission factors for I-M concrete and polyboron are compared with those obtained from transport calculations performed with the ANISN deterministic code in the forward mode and the MCNP4B Monte Carlo code. The ANISN code is used for the fast neutron group flux (Cd-cutoff flux), and the MCNP4B code is used for the total neutron flux. The agreement between the experiment and calculation is fairly good at deep penetration, but at initial points, some disagreement is observed. This observation is valid for both polyboron and I-M concrete.
