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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
P. Barthelemy, R. Berger, R. Boucher, L. Hayet
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 201-214
Technical Paper | Radioisotope | doi.org/10.13182/NT75-A24419
Articles are hosted by Taylor and Francis Online.
In 1971 the French Atomic Energy Commission (CEA) established itself as a candidate for 252Cf commercial encapsulation services. A production facility, designed and built at the Fontenay-aux-Roses Centre for Nuclear Studies, allows handling of up to 10 mg of 252Cf. This unit started operation in Sep. 1973. The main features of the californium facility are: (a) remote manipulation by means of two electrical robots, (b) TIG welding of capsules and assemblies using two machines, with variable positioning of the electrode along the three axis that allows the soldering of pieces as large as 50 mm in diameter and 2 m in length, (c) capsule decontamination by an electrolytic pickling technique, and (d) neutron source emission counting by means of a uranium fission chamber giving relative measurements versus a 252Cf standard with an accuracy of 3%. All sealed sources developed at the CEA are made of 252Cf2O3-Pd cermets encapsulated in stainless steel, Zircaloy, or nickel and are qualified as special form nuclear material. Present applications of 252Cf sealed sources in France are directed toward physical research and nuclear reactor design, nuclear reactor startup and nuclear materials assay, neutron activation analysis development for in situ determinations in the earth science and mineral exploration, and for process control in metallurgy. Furthermore, the CEA is involved in a government-sponsored program on a 252Cf source projector for neutron therapy. For the afterloading interstitial technique, the CEA has designed miniaturized sources made of a 252Cf2O3-Pd cermet containing 0.32 μg of 252Cf sealed in a platinum capsule 0.70 mm in diameter and 4 mm long.