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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Joong Seok Suh, Samuel H. Levine
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 371-382
Technical Paper | doi.org/10.13182/NSE90-A21471
Articles are hosted by Taylor and Francis Online.
An efficient reload core design method, applicable to a commercial pressurized water reactor, has been developed. The objective of the reload core design is to achieve the maximum cycle length. The optimization of the reload core design is effected in three stages:. Use a linear programming method to find an optimum beginning-of-cycle (BOC) k∞ distribution, which yields maximum keffat the end of cycle when depleted by the Haling power distribution. Individual fuel assemblies are then loaded into the core using the optimum BOC k∞ distribution as a guide. Compute the optimum burnable poison requirements in parts per million/billion and their corresponding boron carbide weight percents for the fresh fuel assemblies using the gradient projection method. Deplete the optimum design using an accurate analysis. The application of the method to Three Mile Island Unit 1 (TMI-1) cycles 5 and 6 has shown that an optimum loading pattern for maximum cycle length is a low-leakage core. Compared with the TMI-1 loading patterns, the optimization has yielded an increase in cycle length by 12 effective full-power days (EFPDs) in cycle 6 and 41 EFPDs in cycle 5 plus saving about $3 million in fuel cost. The reason for the greater improvement in cycle 5 is that the cycle 5 loading pattern was a high-leakage core and the optimum design is a low-leakage core. The computer time required for computing one reload core design is ∼400 s on the IBM-3090 computer.