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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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.
S. Das
Nuclear Science and Engineering | Volume 122 | Number 3 | March 1996 | Pages 344-358
Technical Paper | doi.org/10.13182/NSE96-A24169
Articles are hosted by Taylor and Francis Online.
The method of point reactor kinetics in conjunction with the new concepts of delayed spectrum factor and beta growth factor is used to calculate the sensitivity of the dynamic behavior of a fast breeder reactor to large changes in delayed neutron energies following postulated reactivity accidents. The positive ramp rates are introduced not to simulate physical possibilities but solely to test the sensitivity to delayed neutron spectral changes under different conditions. A limited number of transient calculations are made using the point-kinetics code SENSTVTY, six precursor groups, and Doppler feedback. The calculational method and the reactor model are described. Delayed neutron requirements in reactor dynamics are discussed, and a brief review of the sensitivity studies is presented. The results of the sensitivity calculations indicate that the relative power, the peak power, and the accident energy release are sensitive to changes in βeff resulting from uncertainty in the delayed spectral data, but the sensitivity of the relative power is much greater than the peak power and the accident energy release. The spread in the maximum reactivity reached is found to be ∼18%, and the time spread in the melting of fuel and cladding is in milliseconds.
