ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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!
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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.
Kazuo Azekura, Kikuo Umegaki, Kotaro Inoue, Sang K. Rhow, James E. McElroy, Dennis M. Switick
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 325-336
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33918
Articles are hosted by Taylor and Francis Online.
An unprotected loss-of-flow (LOF) event has been analyzed for a lOOO-MW(electric) axially heterogeneous core (AHC) at the end of an equilibrium cycle, using a realistic model to evaluate the AHC safety potential. The SAS3D code was used for the initiating phase analysis, while a phenomenological approach was employed for the transition phase. The SAS3D results showed that the system rapidly approached subcriticality after experiencing a benign power burst, because of axially flattened fuel worth distribution and reduced sodium-void worth particularly around the core center. During the transition phase, fuel-steel discharge into the interassembly gaps, coupled with engagement of the upper axial blanket material in the core region, was found to result in permanent subcriticality and a nonenergetic termination of the LOF event.