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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
Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Yoshiro Asahi, Hiroaki Wakabayashi
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 24-33
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33748
Articles are hosted by Taylor and Francis Online.
Transient characteristics of a process inherent ultimate safety (PIUS) reactor in typical accidental situations are investigated by using the plant dynamics analysis code THYDE-W. First, the modeling and steady-state adjustment for thermal hydraulics of a PIUS is described. Then the transient calculations are made for a pump coastdown, a steam generator feed-water trip, a flow blockage, and a boron dilution. They show that inherent safety of PIUS is ensured without control rod scram. The entrance of pool water to the primary loop, however, could give rise to a potential problem of thermal shock.