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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
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.
