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
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Richard W. Smith, Gary S. Was
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 198-209
Nuclear Fuel | doi.org/10.13182/NT85-A33631
Articles are hosted by Taylor and Francis Online.
The FCODE-BETA/SS code, based on the Electric Power Research Institute’s FCODE-BETA, is constructed to model the thermal-mechanical performance of Type 304 stainless steel clad pressurized water reactor fuel rods. Specifically, thermal expansion, thermal conductivity, irradiation creep, temperature-dependent material parameters and gap conductance for Type 304 stainless steel clad fuel rods are modeled. FCODEBETA/SS is benchmarked against end-oflife fission gas release and creep strain data from Connecticut Yankee fuel rods. Benchmarking results on key performance variables are comparable to those of FCODEBETA and COMETHE. Using FCODE-BETA/SS to compare the performance of Type 304 stainless steel and Zircaloy clad fuel over a common power history reveals that Type 304 stainless steel clad rods display higher fuel temperatures, wider gaps, and longer times to gap closure than Zircaloy clad rods. The stainless steel cladding spends only a small fraction of life in a state of tensile stress at the ridge, but the magnitudes of these ridge stresses are significantly greater than those found in Zircaloy rods. Nevertheless, the thermal performance of the two rod types is very similar.
