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
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.
G. W. Dixon, R. Sher
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 357-366
Technical Paper | doi.org/10.13182/NSE70-A19094
Articles are hosted by Taylor and Francis Online.
Thermal neutron spectra have been measured with good spatial resolution within a unit cell in several H2O-moderated natural uranium lattices and in one graphite-moderated lattice. The H2O-moderated lattices had water-to-uranium volume ratios of 1:1, 2:1, and 3:1, with fuel rod diameters of 2.54 cm. Dysprosium-164, 151Eu, 176Lu, and 115In were used as detectors, and both activation ratios and unfolded spectra are compared with THERMOS code calculations. The agreement between the results and the calculations is satisfactory; however, the agreement in the water regions is generally much better than in the fuel regions of the H2O-moderated lattices. In the graphite lattice, the agreement of results with THERMOS calculations using a free gas kernel is poor, while calculations with a crystalline kernel show better agreement.