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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2024 ANS Annual Conference
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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.
Jean-Claude Nimal
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 405-410
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9217
Articles are hosted by Taylor and Francis Online.
NAÏADE 1 shielding experiments were performed in the shielding laboratory at the Commissariat à l'Energie Atomique (French Atomic Energy Commission) in Fontenay aux Roses during the period 1965-1970. These experiments consisted of studying either the pure thermal neutron attenuation or the fission neutron attenuation in various materials such as water, iron, graphite, concrete, and multilayer shields. A reassessment of the experimental results was made between 2003 and 2005, and the results were evaluated again during the period 2007-2008. For each experimental configuration, the fission neutron source of a converter was calculated by using the TRIdimensionel POLYcinétique (TRIPOLI-4) Monte Carlo code. A part of the experimental results has been compared to the results of TRIPOLI-4. This work will be continued to analyze other benchmarks with integration into the Shielding INtegral Benchmark Archive Database (SINBAD).
