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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
WIPP’s SSCVS: A breath of fresh air
This spring, the Department of Energy’s Office of Environmental Management announced that it had achieved a major milestone by completing commissioning of the Safety Significant Confinement Ventilation System (SSCVS) facility—a new, state-of-the-art, large-scale ventilation system at the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-related transuranic (TRU) waste in New Mexico.
Walter H. D'Ardenne, Henry E. Bliss, David D. Lanning, Irving Kaplan and Theos J. Thompson
Nuclear Science and Engineering | Volume 32 | Number 3 | June 1968 | Pages 283-291
Technical Paper | doi.org/10.13182/NSE68-A20210
Articles are hosted by Taylor and Francis Online.
Reactor physics parameters were measured in three heavy water lattices consisting of 0.250-in.-diam, 1.03 wt% 235U metal fuel rods in triangular arrays spaced at 1.25, 1.75, and 2.50 in. The following quantities were measured in each lattice: the ratio of epicadmium to subcadmium radiative captures in 238U (ρ28); the ratio of epicadmium to subcadmium fissions in 235U (δ25); the ratio of radiative captures in 238U to fissions in 235U (C); and the fissions in 238U to fissions in 235U (δ28). These experimental results were used to calculate the following reactor physics parameters for each lattice: the resonance escape probability p, the fast fission factor ϵ, the multiplication factor for an infinite system k∞, and the initial conversion ratio C. Analytical results obtained by using THERMOS and GAM-I are in fair agreement with the experimental results.