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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
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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Latest News
2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Rudolf Seiler, Rakesh Chawla, Kurt Gmür, Helmut Hager, Hans-Dieter Berger, Roland Böhme
Nuclear Technology | Volume 80 | Number 2 | February 1988 | Pages 311-323
Technical Paper | Advanced Light Water Reactor / Fission Reactor | doi.org/10.13182/NT88-A34054
Articles are hosted by Taylor and Francis Online.
Comparisons of calculated and measured neutron balance components are reported for the 7.5% fissile plutonium reference test lattice of the PROTEUS—light water high conversion reactor (LWHCR) phase II program, both wet (with H2O) and dry (100% void). Special experimental techniques have been developed and applied, particularly for k∞, and the range of directly measured reaction rate ratios has been extended. For the two cell codes tested, WIMS-D/1981 library and KARBUS/KEDAK-4, specific shortcomings have been identified; the new measurements have been found to be significantly more representative and accurate than the earlier phase I experiments. The k∞, void coefficient for the phase II reference lattice between 0 and 100% void has been found to be qualitatively different from those assessed for the earlier phase I test lattices. Consideration of the individual void coefficient components show this to be largely a consequence of the more LWHCR-representative fuel rod diameter and plutonium isotopic composition of the fuel currently being used. Results of control rod studies conducted for the phase II reference lattice—both wet and dry—serve to illustrate the efforts being made toward investigations of special power reactor features.