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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
J. Richard Smith, John J. King
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1925-1930
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29623
Articles are hosted by Taylor and Francis Online.
Neutron multiplication occurs in beryllium because of the high (n, 2n) cross section. On the basis of calculations made using microscopic nuclear data, multiplication in a beryllium blanket should improve the efficiency of a tritium breeder. Previous experiments have indicated that the net multiplication is too low for beryllium to be an effective neutron multiplier. It seemed appropriate to make a further study of the multiplication of 14-MeV neutrons in bulk beryllium, utilizing the superior isotropy and flat energy response of the manganese bath. In the manganese bath method a 14-MeV neutron source is placed at the center of a large tank containing an aqueous solution of MnSO4. With a beryllium sample surrounding the neutron source in the sample chamber, the neutrons first multiply in beryllium and produce in the manganese bath an activity proportional to the source rate times the multiplication factor. The ratio of the “sample-in” and the “open beam” activities is the raw value of the multiplication. Several systematic corrections must then be applied to deduce the true multiplication in beryllium. Uncorrected values of the multiplication have been obtained for beryllium samples of four thicknesses. For beryllium thicknesses of 4.6, 12.0, 15.6, and 19.9 cm the multiplication values are 1.399, 1.928, 2.072, and 2.126, respectively. These values are affected by several systematic effects characteristic of the manganese bath. The values of these systematic corrections are established by a combination of calculation and experimental parameterization. The detailed calculations use the Monte Carlo program MCNP. The experimental values are in good agreement with those calculated from microscopic cross sections.