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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Moltex demonstrates its WATSS fuel recycling process
Advanced reactor company Moltex Energy Canada said it has successfully validated its waste to stable salt (WATSS) process on used nuclear fuel bundles from an unnamed Canadian commercial reactor through hot cell experiments conducted by Canadian Nuclear Laboratories.
E. Barnard, N. A. Khan, R. C. F. Mclatchie, M. J. Poole, J. H. Tait
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 513-522
Technical Paper | doi.org/10.13182/NSE63-A18441
Articles are hosted by Taylor and Francis Online.
In the experiment to be described the 28 Mev electron linac at Harwell was used as a neutron source to produce 1 µsec bursts of 1011 electrons 160 times per second. A natural uranium target was placed centrally against one face of a 60 cm x 62.2 cm x 71.1 cm graphite block, and a neutron beam extracted from a channel running into the center of the block. This beam was interrupted by a slow chopper running in synchronism with the pulses from the accelerator. In this way 100 µsec “time samples” of the neutrons in the block were taken and their spectrum determined by the time-of-the-flight method. The instant of the “time sample” relative to the fast neutron pulse could be varied by an electronic delay circuit. Neutron spectra are presented for the time varying between 300 µsec and 1000 µsec after the pulse. These spectra differ from the Maxwellian shape but approach asymptotically to a “cooled Maxwellian” from which they are indistinguishable after 1000 µsec. Detailed calculations of the spectra have been made using an IBM 7090 computer to obtain a numerical solution of the time and energy dependent diffusion equation; using a scattering kernel based on the scattering measurements made at Chalk River. The experimental results are also compared with spectra using a scattering kernel based on the heavy gas model with a fictitious mass of 33.