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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Randy L. Simmons, Niel D. Jones, Frank D. Popa, Donald E. Mueller, James E. Pritchett
Nuclear Technology | Volume 80 | Number 3 | March 1988 | Pages 343-348
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34058
Articles are hosted by Taylor and Francis Online.
The design advantages achievable from the use of zirconium diboride (ZrB2) integral fuel burnable absorbers (IFBAs) in two- and three-loop pressurized water reactor (PWR) cores are examined. The ZrB2 IFBAs were designed and have been extensively tested for use in PWRs. Two fuel loading patterns that utilize IFBAs are analyzed: (a) a three-loop core with an 18-month cycle, very low radial leakage loading pattern, and reduced vessel fluence concerns; and (b) a two-loop core with an annual cycle, very low radial leakage loading pattern, and natural uranium axial blankets (low axial leakage). Both designs demonstrate the versatility of IFBAs in difficult fuel loading patterns. Both designs demonstrate well-behaved radial and axial power peaking factors for annual (two-loop core) and 18-month (three-loop core) cycles. The ZrB2 IFBAs also provide added flexibility in the placement of fresh fuel. This flexibility can improve shutdown margin by placing fresh fuel under control rod locations and can improve fuel cycle cost. Neither design would have been possible with discrete burnable absorbers. By analyzing the two very different designs, it can be seen that ZrB2 IFBAs can be used in tightly constrained fuel loading patterns and will provide added flexibility and/or fuel cycle cost savings in future fuel management strategies.