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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
K. Oishi, Y. Ikeda, C. Konno, H. Maekawa, T. Nakamura
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 579-584
Fusion Nucleonics Experiments | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24806
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Irradiation of concrete aggregates by 14 MeV neutrons was performed to investigate the activation characteristics of concrete, and to verify the calculation code system THIDA using the FNS facility. From the result it was proven that 42K, 24Na, 43K, 48Sc, 47Ca, 46Sc, and 54Mn, in half life order, make an important contribution to the total activity. In addition, a comparison between experiment and calculation was made. For 24Na and 54Mn, whose cross sections were well estimated, good agreement between experiment and calculation was obtained, which proved the validity of the calculational code. For reaction rates caused by calcium and titanium isotopes, however, calculational results that differed from experimental ones between −20 % to +40 % were obtained. This inconsistency was caused by the uncertainty of the cross section around 14 MeV, because the incident neutron energy was almost 14 MeV. Cross section measurements around 14 MeV of these reactions were performed systematically. Since all samples, except 48Ca, were separated isotopes and were irradiated in the same irradiation field, highly precise data with small relative error could be obtained. Consequently, calculations were performed again using measured cross section values, and then agreement between experiment and calculation was improved with ± 10 %.