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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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Marco Island, FL|JW Marriott Marco Island
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Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Yu. E. Titarenko, K. V. Pavlov, A. Yu. Titarenko, V. O. Legostaev, M. A. Zhigulina, R. S. Khalikov, V. M. Zhivun, T. V. Kulevoy, A. A. Kovalishin, A. A. Dudnikov, V. Yu. Blandinskiy, V. D. Davidenko, M. V. Ioannisian, V. I. Belousov, I. I. Dyachkov, K. G. Chernov, M. R. Malkov, B. V. Kuteev, Yu. A. Kashchuk, S. A. Meshchaninov, S. Yu. Obudovsky, A. Yu. Stankovskiy, A. Yu. Konobeyev
Fusion Science and Technology | Volume 78 | Number 7 | October 2022 | Pages 549-572
Technical Paper | doi.org/10.1080/15361055.2022.2076999
Articles are hosted by Taylor and Francis Online.
This paper presents the results of an experiment determining (n,2n), (n,p), (n,pn), (n,α), (n,n’γ), and (n,γ) reaction rates in 15 test samples of both natural and high-enriched composition: natMg, 27Al, natTi, natFe, 59Co, natNi, 63Сu (99.5%), 65Cu (99.7%), 64Zn (99.4%), natZr, 93Nb, natCd, natIn, 169Tm, and 197Au. Computer simulations in the NG-24M neutron generator spectrum were carried out using the MCNP5 and KIR2 radiation transport codes with different nuclear data libraries (JEFF-3.2, JEFF-3.3, JENDL-4.0, ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, ROSFOND-2010, FENDL-3.0, TENDL-2019, and IRDFF-II). The elaborated full-scale model for neutron transport analysis included the geometry and composition of the neutron generator, experimental samples, and laboratory room. The mean square deviation factor was used to compare the experimental and the simulated results. The best predictive results for both the MCNP5 code and the KIR2 code were obtained with the FENDL-3.0 and ENDF/B-VIII.0 libraries.