ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
Latest Magazine Issues
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
Li-Chi Cliff Po
Nuclear Science and Engineering | Volume 98 | Number 2 | February 1988 | Pages 154-161
Technical Paper | doi.org/10.13182/NSE88-A28495
Articles are hosted by Taylor and Francis Online.
The once-through steam generator version of the personal computer transient analyzer, PCTRAN/P, was used to simulate the overcooling event that occurred on December 26, 1985, at Rancho Seco. Loss of power to the integrated control system led to a reactor trip and overfeeding by the auxiliary feedwater with excessive steam dump. As a result, the plant cooled down rapidly in a short period. PCTRAN/P has successfully reproduced the transient using its interactive control functions. Areas of the system’s design deficiencies are thus identified and modifications can be made to prevent a similar event from recurring. The computation time on an IBM-PC/XT was ∼20 min for the 50-min transient. This demonstrates that PCTRAN/P can be used as a fast-turnaround tool for conducting reactor transient analyses.