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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
IAEA: Gunfire, drone attack at Ukraine’s Zaporizhzhia nuclear plant
The International Atomic Energy Agency team at Ukraine’s Zaporizhzhia nuclear power plant (ZNPP) reported hearing gunfire near the site this morning while a drone hit the plant’s training center.
In a news release today, IAEA director general Rafael Mariano Grossi said this is the third drone to target the training center, located just outside the site perimeter, so far this year. He called for an immediate end to drones being flown over or near nuclear facilities.
Rakesh Chawla, Kurt Gmür, Helmut Hager, Rudolf Seiler
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 360-380
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33495
Articles are hosted by Taylor and Francis Online.
Integral reaction rate ratios and other k∞-related parameters have been measured in the first three cores of the experimental program on light water high converter reactor (LWHCR) test lattices in the PROTEUS reactor. The reference tight-pitch lattice consisted of two rod types, with an average fissile-plutonium enrichment of 6% and a fuel/moderator ratio of 2.0. The moderators were H2O, Dowtherm (simulating an H2O voidage of 42.5%), and air (100% void). Comparisons of the measured parameters have been made with calculational results based mainly on the use of two separate codes and their associated data libraries, namely, WIMS-D and EPRI-CPM. A reconstruction of individual components of the k∞ void coefficient has been carried out on the basis of the measured changes with voidage of the various reaction rate ratios, as well as of k∞ itself. The subsequent more detailed comparisons between experiment and calculation should provide a useful basis for resolving the conflicting calculational results that have been reported in the past for the void coefficient characteristics of LWHCRs.