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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Mark S. Jarzemba
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 82-87
Technical Paper | Reprocessing | doi.org/10.13182/NT98-A2910
Articles are hosted by Taylor and Francis Online.
A method is described to estimate the heat generation rate of various high-level waste (HLW) forms composed primarily of either a sludge (with a composition similar to that in the Hanford HLW tanks) or borosilicate glass. The main heat source is from radioactive decay and subsequent self-absorption of particles emitted from 137Cs, 90Sr, or their radioactive daughters contained in the waste form. The heat generation rate of the waste form is usually an important parameter in safety and performance assessments and will likely be a part of the specifications required for the vitrified waste. The heat generation rate depends on the size of the waste because larger waste forms will tend to absorb a greater fraction of the gamma radiation from 137mBa decays (a short-lived radioactive daughter of 137Cs). Because beta radiation from these two nuclides is short ranged (only a few tenths of a millimetre in water), assumption of complete self-absorption of beta radiation is justifiable. Previous work in this area estimated upper and lower bounds for the volume-averaged heat generation rate per litre of waste based on total (i.e., large-sized waste forms) and zero (i.e., small-sized waste forms) self-absorption of gamma radiation emitted from 137mBa. This analysis extends the previous work to more adequately estimate the heat generation rate of intermediate-sized waste forms based on the composition of the waste (either borosilicate glass or a simulated sludge), and the size of the waste as characterized by the surface-area-to-volume ratio. The analyses are based on runs of the MCNP version 4A code.
