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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Jan-Ru Tang, Lainsu Kao, Der-Yeong Shiau, Lin-Yao Chou, Ching-Chuan Yao, Show-Chyuan Chiang
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 302-312
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2842
Articles are hosted by Taylor and Francis Online.
Two analyses for Chinshan nuclear power station (CSNPS) show the RETRAN applications in reactor operations. One was used to find the root cause of a reactor trip due to high neutron flux (APRM Hi-Hi). Two of the four turbine control valves failed and closed rapidly. Whether the pressure increase caused the APRM Hi-Hi reactor scram was questioned. An analysis was performed to determine the way to bring unit 1 back to power. The second analysis was conducted to provide an evaluation of the consequences before a plant test planned for late 1994 to consider a design change upgrading recirculation flow control. However, there were concerns about reactor scram during execution of the test and the potential of entering the exclusive region of instability. Sensitivity studies on several different combinations of initial conditions and feedwater flow coastdown curves indicated potential problems with reactor trip and stability.