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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis 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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The Civil Nuclear Credit Program: An overview
Officially established on November 15, 2021, with the signing of the $1.2 trillion Infrastructure Investment and Jobs Act—aka the Bipartisan Infrastructure Law, or BIL—the Department of Energy’s Civil Nuclear Credit Program was designed to give owners/operators of commercial U.S. reactors the opportunity to apply for certification and competitively bid on credits to help support the continued operation of economically troubled units. Finally, the federal government, and not just certain farsighted state governments, would recognize nuclear energy for its important grid reliability and decarbonization attributes.
Florent Heidet, Ehud Greenspan
Nuclear Technology | Volume 181 | Number 3 | March 2013 | Pages 381-407
Technical Papers | Fission Reactors | doi.org/10.13182/NT13-A15800
Articles are hosted by Taylor and Francis Online.
A sodium-cooled fast reactor breed-and-burn (B&B) core and fuel cycle concept are proposed to achieve uranium utilization in the vicinity of 50% without separation of most of the fission products from the actinides. This core is to be fueled with depleted uranium (DU) with the exception of the initial core loading that uses fissile fuel to achieve initial criticality. When the cladding reaches its radiation damage limit, the melt-refining process is used to recondition the fuel, and then the fuel is reloaded into the core. This fuel reconditioning continues until the fuel reaches the neutronically maximum attainable burnup. When a fuel assembly is discharged at its maximum attainable burnup, it is replaced with a fresh DU assembly.The maximum burnup attainable in a large 3000-MW(thermal) B&B core is found to be 57% fissions per initial metal atoms (FIMA). The discharged fuel characteristics such as the inventory of actinides, radiotoxicity, and decay heat are one order of magnitude smaller, per unit of energy generated, than those of a light water reactor operating with the once-through fuel cycle.It is also found that the minimum burnup required for sustaining the B&B mode of operation is 19.4% FIMA. The fuel discharged at this burnup has sufficient excess reactivity for establishing initial criticality in a new large B&B core. The theoretical minimum doubling time for new core spawning is estimated to be [approximately]10 effective full-power years; there is no need for any external fissile material supply beyond that required for the initial "mother" reactor.Successful development and deployment of the B&B core along with fuel reconditioning could possibly provide up to 3000 yr worth of the current global nuclear electricity generation by using the DU stockpiles already accumulated worldwide. However, a number of important feasibility issues are yet to be resolved.