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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Yoshiro Asahi, Hiroaki Wakabayashi
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 24-33
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33748
Articles are hosted by Taylor and Francis Online.
Transient characteristics of a process inherent ultimate safety (PIUS) reactor in typical accidental situations are investigated by using the plant dynamics analysis code THYDE-W. First, the modeling and steady-state adjustment for thermal hydraulics of a PIUS is described. Then the transient calculations are made for a pump coastdown, a steam generator feed-water trip, a flow blockage, and a boron dilution. They show that inherent safety of PIUS is ensured without control rod scram. The entrance of pool water to the primary loop, however, could give rise to a potential problem of thermal shock.