ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Walter J. Eich, Mark L. Williams,Chun-Mou Peng
Nuclear Science and Engineering | Volume 90 | Number 2 | June 1985 | Pages 127-139
Technical Paper | doi.org/10.13182/NSE85-A17671
Articles are hosted by Taylor and Francis Online.
Analysis of critical experiments for cross-section evaluation has been conducted on the basis of one-dimensional four-group diffusion theory calculations that explicitly model the homogenized core and reflector in the radial plane. Such analyses require a reflector representation that models the leakage process as accurately as feasible. The development and testing of few-group ENDF/B-V based light water reflector constants for use in diffusion theory derived to reproduce leakage and other reaction rates from reference multifast group transport calculations are described. This work has been extended to parameterize similar higher order transport calculations with two- or four-group constants valid for application to typical pressurized water reactor baffle/reflector configurations as represented in coarse mesh diffusion (PDQ) representations.