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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
M. Z. Youssef, Y. Watanabe, A. Kumar, Y. Oyama, K. Kosako
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1843-1852
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29612
Articles are hosted by Taylor and Francis Online.
Performing integral experiments with a 14 MeV line source offers better simulation to the neutron source conditions (in terms of energy and angular distribution) of the toroidal plasmas in Tokamaks. Because of the linearity of the neutron transport equation, a line source can be simulated by superimposing results from many point sources aligned on one line, provided the number of these point sources is large. The simulation was experimentally realized at the FNS facility within the USDOE/JAERI Collaborative Program on Fusion Neutronics. In this paper, the theoretical aspects of a line source simulation are discussed. Specifically, analytical results for achieving this simulation by continuously moving a point source of speed V within a distance of length 2L; [continuous operation (CO.) mode] are compared to results obtained from several point sources located at discrete number of locations within the distance 2L [stepwise operation (S.O.) mode]. In the C.O. mode it was shown that for activation measurements, ideal simulation to a line source of length 2L with a point source moving at speed V could be achieved, provided the decay constant λ of the activated product satisfies the condition λ.(2L/V) << 1. In the S.O. mode, the number of point source locations, the distance from the simulated line source where the neutron radiation effects are measured, and the type of reactions (threshold vs. non-threshold) considered are important factors in determining the degree of simulation. For example, it was shown that better simulation can be achieved if the source locations are chosen to be at points that are directly related to the roots xi's of the Gauss-Legendre set PN(xi)=0, where N is the number of source locations. It was shown that larger number of point sources are needed to reproduce the line source effects on threshold-type reactions [e.g. 7Li(n,n'α)t] than on non-threshold reactions [e.g. 6Li(n,α)t]. Several transport calculations were also performed to study the degree of simulation from multiple point sources on the characteristics of the test assembly used in Phase IIIA of the program. In particular, the anisotropy of the incident neutron source arising from the structure of the target assembly, coolant channel, and water coolant was studied and compared to the case of isotropic point sources. It was shown that using N ≥ 20 points is adequate to the analysis of Phase III.A experiments.