ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.