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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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Nuclear Science and Engineering
Fusion Science and Technology
Advanced reactors: Now comes the hard part
Designing a reactor is complicated but building one may be harder. Even companies that have had lots of practice haven’t always done it well. And all the power reactors in service today were built by companies that had years of experience in other kinds of big steam-electric power plants. In contrast, some of the creative new designs now moving toward commercialization come from start-ups that have never built anything at all. How should they prepare?
K. Noack, A. Rogov, A. A. Ivanov, E. P. Kruglyakov (18R04)
Fusion Science and Technology | Volume 51 | Number 2 | February 2007 | Pages 65-68
Technical Paper | Open Magnetic Systems for Plasma Confinement | dx.doi.org/10.13182/FST07-A1315
Articles are hosted by Taylor and Francis Online.
In the last decade, a great progress was made in developing projects of sub-critical fission systems dedicated to transmutation of nuclear waste. In contrast to a fission reactor, such a device is fed with neutrons from an outer source in order to sustain a steady-state power generation. The Budker Institute of Nuclear Physics has made the proposal of a powerful 14 MeV neutron source based on a gas dynamic trap (GDT). This neutron source is primarily thought as irradiation facility for fusion material research. So, the question raises, whether the GDT based neutron source could be a candidate to efficiently drive such a sub-critical system too. The contribution pursues this question using results of first neutron transport calculations. The calculations were made for a simplified model of an actinides burner, which has been developed for an international benchmark exercise performed under the auspices of the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD). Important parameters of the burner are compared for two cases - when driven by a spallation or by the GDT neutron source. From this comparison some advices for further improvements of the GDT neutron source are concluded.