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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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2021 ANS Virtual Annual Meeting
June 14–16, 2021
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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Latest News
Consultant recommends subsidies for Exelon plants
A research and consulting firm hired by Illinois governor J. B. Pritzker’s administration to scrutinize the financial fitness of Exelon’s Byron and Dresden nuclear plants approves of limited state subsidies for the facilities, according to a redacted version of the firm’s report made available yesterday.
Tae-Hoon Lee, Young Soo Kim, Hee-Sung Shin, Ho-Dong Kim
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 147-154
Radiation Measurements and General Instrumentation | dx.doi.org/10.13182/NT11-A12549
Articles are hosted by Taylor and Francis Online.
A passive neutron coincidence counter for nuclear material measurement of the advanced spent fuel conditioning process (ACP) has been developed by the Korea Atomic Energy Research Institute (KAERI) since 2003 and was deployed in a hot cell of the ACP Facility (ACPF) in 2005. The most dominant neutron source among the spontaneous fission nuclides contained in spent fuel is 244Cm. To obtain the neutron counting rates of the singles, doubles, and triples coincidences of the neutron counter with an increment of the 244Cm mass, a hot test of the neutron counter was performed in 2007 with several spent fuel rod-cuts in the ACPF hot cell. The source term of the spent fuel rod-cuts was obtained using the ORIGEN-ARP burnup simulation code, and a set of preliminary calibration curves of the neutron counter for 244Cm was generated. The calibration curves were also obtained from the results of an MCNPX code simulation, but there was a wide difference of [approximately]30% in the slope of the double-rate calibration curve between the measurements and the MCNPX results. Chemical analysis results of the spent fuel samples were obtained in September 2008, and it was found that the difference between the measurements and the MCNPX results is due to an error in the declared burnup since the chemical analysis burnups of the samples differ from the declared ones by [approximately]10%. The expected burnup of each rod-cut was also obtained from the results of self-multiplication correction for the 244Cm mass of the rod-cuts, and the difference between the expected burnup results and the chemical analysis results is <2%. This study shows high performance of the neutron coincidence counter for 244Cm measurements of spent fuel and also shows that the burnup of spent fuel samples can be obtained through a series of ORIGEN-ARP code simulations if it is possible to acquire the measurement data of neutron counting rates for 244Cm of the samples.
