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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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
Plans for the Bruce C project in Ontario open for public comment
As Bruce Power continues predevelopment work, public input is being sought on the potential Bruce C nuclear power expansion project in Ontario.
Bruce Power recently submitted its initial project description to the Impact Assessment Agency of Canada for an expansion that would add up to 4,800 MWe. Earlier this year, the Canadian government announced up to C$50 million ($36.8 million) in funding for the Bruce C project, which would be Canada’s first major expansion of a large nuclear plant in decades.
Samuel E. Bays, J. Stephen Herring, James Tulenko
Nuclear Technology | Volume 173 | Number 2 | February 2011 | Pages 115-134
Technical Paper | Fission Reactors | doi.org/10.13182/NT11-A11542
Articles are hosted by Taylor and Francis Online.
An axially heterogeneous sodium-cooled fast reactor design is developed for converting minor actinide waste isotopes into plutonium fuel. The reactor design incorporates zirconium hydride moderating rods in an axial blanket above the active core. The blanket design traps the active core's axial leakage for the purpose of transmuting 241Am into 238Pu. This 238Pu is then co-recycled with the spent driver fuel to make new driver fuel. Because 238Pu is significantly more fissionable than 241Am in a fast neutron spectrum, the fissile worth of the initial minor actinide material is upgraded by its preconditioning via transmutation in the axial targets. Because the 241Am neutron capture worth is significantly greater in a moderated epithermal spectrum than the fast spectrum, the axial targets serve as a neutron trap that recovers some of the axial leakage lost by the active core.A low transuranic conversion ratio is achieved by a degree of core flattening that increases axial leakage. Unlike a traditional "pancake" design, neutron leakage is recovered by the axial target/blanket system. This heterogeneous core design is constrained to have sodium void and Doppler reactivity worth similar to that of an equivalent homogeneous design. Contrary to a homogeneous design, concentrating minor actinides (MAs) in an axial blanket mitigates the problem of above-threshold multiplication during sodium voiding. Because minor actinides are irradiated only once in the axial target region, elemental partitioning of the minor actinides from plutonium is not required. This fact enables the use of metal targets with pyroprocessing. After reprocessing, the target's newly bred 238Pu and remaining unburned MAs become the feedstock for the next batch of driver fuel.