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
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!
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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.
Hyong Chol Kim, Ming-Yuan Hsiao, Samuel H. Levine
Nuclear Technology | Volume 79 | Number 3 | December 1987 | Pages 377-381
Technical Note | Fission Reactor | doi.org/10.13182/NT87-A34027
Articles are hosted by Taylor and Francis Online.
The objective of this effort is to minimize the excess reactivity of the liquid-metal reactor (LMR) over the core cycle, which will allow control rods to have less worth to control the core. This reduces the potential available transient reactivities and thus improves the LMR’s inherent safety characteristics. The core characteristics are modified to effect a constant keff over the cycle. Use of limited moderator and poison islands is incorporated into the core design to optimize the LMR core geometry and to help achieve the design objective. The feasibility of this concept is shown to be valid by an example, and further possible improvements in the method are suggested.