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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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DOE fast tracks test reactor projects: What to know
The Department of Energy today unveiled 10 companies racing to bring test reactors online by next year to meet Trump's deadline of next Independance Day, leveraging a new DOE pathway that allows reactor authorization outside national labs. As first outlined in one of the four executive orders on nuclear energy released by President Trump on May 23 and in the request for applications for the Reactor Pilot Program released June 18, the companies must use their own money and sites—and DOE authorization—to get reactors operating. What they won’t need is a Nuclear Regulatory Commission license.
A. R. Boulogne, J. P. Faraci
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 75-83
Technical Paper | Radioisotope | doi.org/10.13182/NT71-A30903
Articles are hosted by Taylor and Francis Online.
Californium-252 makes an intense neutron point source that emits 2.34 × 1012 n/(sec g) through spontaneous fission. Sources are being prepared to investigate the value of this radionuclide for mineral, petroleum, and gas exploration, well logging and hydrology, activation analysis, neutron radiography, and other areas where isotopic neutron sources are used. Sources containing milligram amounts of 252Cf with active volumes of <25 mm3 are being prepared by precipitating and filtering californium oxalate on a small metallic filter, which is in the primary capsule in a totally enclosed apparatus. The oxalate is calcined to 252Cf2O3 before the primary capsule is sealed. These sources are doubly encapsulated under conservative design criteria to prevent leakage of radioactive material because they are used in a wide variety of environmental conditions. The neutron emission rate of the finished sources is within 10% of the desired value. Less than 1% of the 252Cf was lost in the process. Because the practical upper limit for the present capsule design is about ten milligrams of 252Cf, procedures are being developed for preparing sources containing up to several hundreds of milligrams of the isotope.