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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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Nuclear Science and Engineering
Fusion Science and Technology
The CORTEX project: Improving nuclear fleet operational availability
We often define noise as an unwanted disturbance, especially acoustic in nature. Neutron noise, by contrast, is a direct measure of the dynamics of a nuclear core. It can be used for core monitoring without disturbing plant operation and by using the existing core instrumentation. The European CORTEX project aims to develop an innovative core monitoring technique using neutron noise, while capitalizing on the latest developments in neutronic modeling, signal processing, and artificial intelligence.
A. G. Buchan, C. C. Pain, M. D. Eaton, A. J. H. Goddard, R. P. Smedley-Stevenson
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Pages 127-152
Technical Paper | dx.doi.org/10.13182/NSE159-127
Articles are hosted by Taylor and Francis Online.
This paper presents two new methods for discretizing the angular dimension of the Boltzmann transport equation that describes the transport of neutral particles such as neutrons and photons. Our methods represent the direction of particle travel using linear and quadratic varying approximations over a quadrilateral partitioning of the unit sphere's surface (which is used to represent a particle's direction), which is similar to the approximations provided by a finite element expansion. However, our approximations are generated using a second generation spherical wavelet technique. This method generates hierarchical sets of compactly supported basis functions that are important properties for our future work in applying adaptive resolution in the transport equation's angular dimension. These new wavelet methods are applied to five monoenergetic transport problems to demonstrate their capabilities to efficiently represent the angular flux. Particular emphasis is placed on their ability to approximate particle transport in problems involving extreme material cross sections, namely, particle streaming through voids and their transport through highly scattering media. We are able to show that the methods work well against the common methods SN and PN when used within established radiation transport codes.