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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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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.
Shih-Jen Wang, Chun-Sheng Chien, Te-Chuan Wang
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 1-9
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2954
Articles are hosted by Taylor and Francis Online.
The MELCOR code, developed by Sandia National Laboratories (SNL), is capable of simulating the severe accident phenomena of light water reactor nuclear power plants (NPPs).A specific station blackout accident (TMLB' sequence) for Maanshan NPP is simulated using the MELCOR 1.8.3 code. The MELCOR input deck for Maanshan NPP is established based on Maanshan NPP design data and the MELCOR users' guides. The initial steady-state conditions are generated with a developed self-initialization algorithm. The main severe accident phenomena and the corresponding fission product release fractions associated with the TMLB' sequence were simulated. The sequence of events up to the vessel breach is similar to that in the SNL report simulated with MELCOR 1.8.2. The predicted results provide useful information for the probabilistic risk assessment (PRA) of Maanshan NPP. This tool will be applied to the PRA, the severe accident analysis, and the severe accident management study of Maanshan NPP in the near future.
