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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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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U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma
Nuclear Technology | Volume 206 | Number 5 | May 2020 | Pages 663-696
Critical Review | dx.doi.org/10.1080/00295450.2019.1698257
Articles are hosted by Taylor and Francis Online.
Flow and thermal performance analysis is an important area in the nuclear industry for the safe operation of reactors and the optimum design of fuel rod bundles with spacers in the reactor core. The spacer, an essential element in the nuclear fuel rod assembly, is used to support the fuel rods in the bundle and maintain suitable clearance between the rods. This paper represents a comprehensive review of the effects of spacer/mixing vane spacer on flow behavior and heat transfer performance in nuclear fuel rod bundles, annular channels, and circular tubes. This paper is based on the experimental and computational fluid dynamics (CFD) investigations performed by researchers in literature for both single-phase and two-phase fluid flow. In addition, the effects of some parameters, such as Reynolds number, hydraulic diameter, pitch-to-diameter ratio, blockage ratio, working fluid, and number of fuel rods in an assembly, on flow and thermal performance analysis have been reviewed. A detailed review has been carried out by considering both experimental and CFD methods used in the past for analysis of thermal-hydraulic performance in the fuel channels of nuclear reactors.