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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
J. J. MacFarlane, P. Wang, G. A. Moses
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 703-708
Inertial Fusion | doi.org/10.13182/FST91-A29427
Articles are hosted by Taylor and Francis Online.
We present results from radiation transport calculations for plasma conditions that are expected for the buffer gases of high-gain inertial confinement fusion (ICF) target chambers. In our calculations, the plasmas are not assumed to be in local thermodynamic equilibrium (LTE). The state of the plasmas is obtained by solving multilevel atomic rate equations self-consistently with the radiation field. Radiation is transported using an escape probability model. Atomic physics data is generated using a combination of Hartree-Fock, distorted wave, and semi-classical impact parameter models. Our results show that the self-attenuation of line radiation results in a significant reduction in the radiation flux at the target chamber first wall. We compare our results with those from other calculations and find that the heat fluxes at the first wall are significantly lower than previously predicted by multigroup radiation diffusion models. The lower heat fluxes suggest that thermal conduction within the first wall can act to keep temperatures near the surface of the wall much lower than previously thought, thus reducing problems associated with thermal stresses and vaporization. We discuss the ramifications of our results for the SIRIUS-T ICF reactor.