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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.
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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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Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
Edward P. Naessens, Jr., Kenneth S. Allen, Brian E. Moretti
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 306-313
Technical Paper | doi.org/10.13182/NSE06-A2584
Articles are hosted by Taylor and Francis Online.
Current burnable absorbers such as boron carbide placed in the control rod guide tubes of fresh fuel assemblies create a water displacement penalty at end of cycle (EOC) that reduces the overall maximum cycle length of the reactor. Other burnable absorbers such as gadolinium-oxide mixed in the fuel do not create the water displacement penalty but create a lower centerline melt temperature for the fresh fuel and reduce the overall enrichment for the assembly. This research proposes using a transuranic (TRU) isotope with a relatively high absorption cross section such as 240Pu to reduce excess criticality within the reactor at beginning of cycle. The added benefit of using this TRU isotope over a standard burnable absorber is that when it absorbs a neutron it no longer negatively affects the criticality of the reactor, and it will transmutate into a fissile material that will add to the overall criticality of the reactor at EOC.