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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
February 2025
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January 2025
Fusion Science and Technology
Latest News
Three nations, three ways to recycle plastic waste with nuclear technology
Plastic waste pollutes oceans, streams, and bloodstreams. Nations in Asia and the Pacific are working with the International Atomic Energy Agency through the Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative to tackle the problem. Launched in 2020, NUTEC Plastics is focused on using nuclear technology to both track the flow of microplastics and improve upstream plastic recycling before discarded plastic can enter the ecosystem. Irradiation could target hard-to-recycle plastics and the development of bio-based plastics, offering sustainable alternatives to conventional plastic products and building a “circular economy” for plastics, according to the IAEA.
M. A. Abdou, C. W. Maynard
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 381-398
Technical Paper | doi.org/10.13182/NSE75-A26684
Articles are hosted by Taylor and Francis Online.
The calculational methods developed for nuclear heating in an earlier paper are applied to fusion-reactor blankets and shields. The study shows that the nuclear heating in fusion-reactor blankets has been previously overestimated and is limited to ≈16 MeV per DT neutron in the absence of beryllium or fissionable materials. Methods are also examined for increasing the energy multiplication in the blanket by maximizing the rates of exothermic reactions. A general study of the sensitivity of the neutron energy deposition to changes in basic nuclear data is carried out: this study shows the following: 1. The (n, charged particles) reactions, in general, contribute ≈30 to 50% to the neutron heating in typical fusion-reactor spectra. The data for these reactions, however, are not well known and in some cases are absent from the literature. 2. Approximating the neutron heating due to the (n, n′, charged particles) reactions by that from the (n, n′) part only, amounts to ignoring 80 to 90% of the heating. 3. For reference fusion-reactor spectra, a change in the average secondary neutron energy, n′ l, of the 7Li(n, n′α)t reaction results in a relative change in the neutron heating in 7Li which is approximately one-third of that in n′, l. 4. The relative change in the neutron heating by elastic scattering due to a change in the angular distribution is larger than the relative change in . Ignoring the anisotropy of scattering can result in severely overestimated kerma factors. 5. The local energy deposition by radioactive decay is on the order of or less than 2% in most materials in typical spectra for controlled thermonuclear reactors.