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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
Wataru Shinoda, Susumu Mitake
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 372-388
Technical Paper | doi.org/10.13182/NSE69-A18735
Articles are hosted by Taylor and Francis Online.
We investigated the xenon-induced spatial oscillations in boiling-water cooled reactors by the use of a three-dimensional xenon dynamics code FILE-6, which solves the one-group neutron diffusion equation simultaneously with the steady state thermo-hydrodynamics equations and with the iodine-to-xenon equations in the time domain. The stability limit of the first azimuthal mode in terms of the void coefficient of reactivity was found to be in a 500 MWe heavy-water-moderated boiling-light-water-cooled reactor. When the height of the reactor core is larger than 7 m, the first axial mode becomes unstable for a void coefficient of +0.05. It has also been shown that (i) a positive (negative) void coefficient may have a stabilizing (destabilizing) effect on the axial higher modes depending on the inlet subcooling, (ii) the mode coupling between the axially zeroth and the first modes through voids has a stabilizing effect, and (iii) when the first azimuthal mode is oscillating, higher harmonics are excited in some of higher modes through the nonlinear reactivity feedback.