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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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July 2025
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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.
Yang Tang, Yangping Zhou, Zhiwei Zhou, Lei Shi
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 27-44
Technical Paper | doi.org/10.1080/00295450.2017.1352329
Articles are hosted by Taylor and Francis Online.
Different from most current commercial nuclear power plants, the High-Temperature gas-cooled Reactor Pebble-bed Module (HTR-PM) power plant consists of two reactor modules connected to a common steam turbine system that will bring a special coupling effect between the two reactor modules. An engineering simulator of the HTR-PM plant was developed by embedding the THERMIX/BLAST code into the vPower simulation platform. Two sets of nuclear steam supply systems of HTR-PM, including two reactors, two steam generators, two helium blowers, and the helium flow ducts, were simulated by two THERMIX/BLAST code modules, respectively. The entire secondary loop system was simulated using intrinsic models of the vPower simulation platform. The vPower platform connects and synchronizes the two THERMIX/BLAST modules, as well as the simulation module for the secondary loop system. The engineering simulator was applied to simulate the behavior of HTR-PM under steady-state operation, startup and shutdown processes, and accident conditions. The coupling effect during the condition conversion process and the thermal characteristics under accident conditions of HTR-PM were analyzed by the engineering simulator.