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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Why should safeguards by design be a global effort?
Jeremy Whitlock
I can’t think of a more exciting time to be working in nuclear, with the diversity of advanced reactor development and increasing global support for nuclear in sustainable energy planning. But we can’t lose sight of the need to plan for efficient international safeguards at the same time.
Global nuclear deployment has been underpinned since 1970 by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), making it a key customer requirement for governments to demonstrate unequivocally that the technology is not being misused for weapons development.
The International Atomic Energy Agency (IAEA) has helped verify this commitment for more than 50 years, but it has never safeguarded many of the advanced reactors (and related fuel cycle processes) being developed today.
Abhishek Saxena, Jan Eiholzer, Harshank Agarwal, Horst-Michael Prasser
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 568-587
Technical Paper | doi.org/10.13182/NT16-20
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic design characteristics of a boiling water reactor are strongly dependent on the physics of heat-removing mechanisms from nuclear rods. Performance is often limited by a lack of understanding of the heat and momentum transfer in thin liquid films close to dryout. This is particularly important with regard to power uprates of reactors. Flow control by functional spacers equipped with vanes adds complexity to the flow behavior. Instead of improving the heat removal, they can cause a local reduction of the film thickness under unfavorable conditions. This work presents a novel experimental technique to measure the velocity of the liquid phase and to study the turbulent mixing of a passive scalar in the film. The studies were performed in vertical annular flow in a double-subchannel geometry. The liquid film was labeled by either continuous or pulsed tracer injection. An electrically conductive tracer (salt solution) is injected into the film consisting of deionized water. The salt is traced using a liquid film sensor, a high-frequency nonintrusive conductivity-based technique. The experiments are conducted with and without a swirl-type spacer to quantify the effect of the spacers on the film flow for different gas and liquid flow rates. An ensemble averaging of the data obtained from individual injection pulses provides time-averaged liquid velocities in the film. The turbulent dispersion was characterized by analyzing the spread of the tracer in axial and lateral directions. Spacer vanes are found to induce a characteristic transverse movement of the liquid in the film. The effect of waves on mixing is analyzed and is found to enhance it.