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Division Spotlight
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.
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
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
J. P. Adams, V. T. Berta
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 367-375
Technical Paper | doi.org/10.13182/NSE84-A18590
Articles are hosted by Taylor and Francis Online.
Changes in in-core self-powered neutron detector signals, recorded during a nuclear loss-of-coolant accident (LOCA) simulation, have been correlated with liquid level changes that occurred during the core uncovery and recovery events. The correlations indicate that these detectors can be used to monitor reactor vessel liquid level during a LOCA. A display and alarm system using these detectors to provide reactor operators with an indication of a core uncovery and subsequent thermal excursion and with a means to measure the effectiveness of LOCA recovery procedures is described.