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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.
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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!
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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.
Serge M. Orlowski
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 423-431
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33165
Articles are hosted by Taylor and Francis Online.
The radioactive waste management program started in the mid-1970s is being carried out by the Commission of European Communities (CEC) Joint Research Centre and by research bodies within the European community under CEC coordination and partial financing. The program deals with the management of the radioactive waste resulting from uranium-plutonium fuel cycle. During its first phase (1973–1979), various treatment and conditioning processes were investigated; high temperature incineration and acid digestion of alpha-bearing waste, immobilization of highly active waste in borosilicate glasses, inter alia, appeared promising. Geological disposal was recognized as a feasible option; transmutation of long-lived products did not appear to be an advantageous alternative to geological disposal, and the studies were discontinued. The second phase (1980–1984) of the program is a followup to the first. The needs of the European nuclear industry and of the national radioactive waste agencies or operators recently created are, however, taken into account. A new emphasis is being placed on the management of low and medium active waste, the characterization of waste forms, and the reliability and safety of the various options for geologic disposal. A multilaboratories approach is used for concerted studies on container materials, testing, and evaluation of waste products, migration of selected radionuclides, and on the Performance Assessment of Geologic Isolation Systems (PA GIS project). The continuity of the R&D effort is ensured by a “Community plan of action on waste management,” (1980–1992). A third phase, 1984–1989, should demonstrate the availability and validity of the waste management techniques and be convincing about their safety.