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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.
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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.
Algirdas H. Marchertas, Ted B. Belytschko
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 433-442
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32579
Articles are hosted by Taylor and Francis Online.
A finite element analytical model involving an explicit time integration procedure is used to treat a prestressed concrete reactor vessel (PCRV) for liquid-metal fast breeder reactor containment. The model is axisymmetric and includes simulations of the tensile cracking of concrete, the reinforcement, and a prestressing capability under transient load. The quasi-static prestressing operation of the PCRV model is performed by an improved dynamic relaxation technique. The concrete material model used in these analyses accounts for tensile cracking in arbitrary directions, crushing of concrete, and the reinforcing steel The variation of the concrete tensile cracking limit with strain rate is taken into account. The prestressing tendons are modeled and relative slip is permitted. Several example solutions using the analytical model were compared with experimental results. The comparisons included simply supported beams and also small scale models of PCR Vs. It was shown that the analytical methods correlate quite well with experimental results, although in the vicinity of the failure load, the response of the models tends to be quite sensitive to input parameters.