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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
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
2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Jae Jun Jeong, Deog Yeon Oh, Hee Cheon No, Soon Heung Chang, Sung Jae Cho, Hwang Yong Jun, Yong Kwan Lee
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 356-370
Technical Paper | RELAP/MOD2 / Fission Reactor | doi.org/10.13182/NT90-A34400
Articles are hosted by Taylor and Francis Online.
A compact real-time simulator for two-loop pressurized water reactor plants, FISA-2/WS (Fully Implicit Safety Analysis-2 /Work Station), has been improved and adapted to the Sun 386i computer, which was developed for classroom training in support of full-scale simulators, for transient analysis, engineering studies, and emergency drills. The FISA-2/ WS simulator package is divided into three modules: plant, on-line graphic display, and interactive communication. The plant module consists of models for core kinetics, reactor coolant system, steam generator, main steam line, and control and safety systems. Each of the models is optimized to obtain the capability of real-time simulation. Simulation results are displayed periodically at a user-specified time interval on a color monitor by the on-line graphic display module. The FISA-2/WS interactive communication module enables the user to initiate or mitigate accidents and to select one of the menu-driven graphic displays with the mouse and keyboard. Several nuclear steam supply system transients have been simulated by FISA-2/WS. The results presented here are obtained from simulations of steady state, turbine load change transient, and small-break loss-of-coolant accidents. The results of FISA-2/WS are in good agreement with plant data and the results of RELAP5/MOD2, and the fast running capability is also confirmed.