The Experts below are selected from a list of 78 Experts worldwide ranked by ideXlab platform
K E Khatuntsev - One of the best experts on this subject based on the ideXlab platform.
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a technique for estimating neutron fluxes in a large number of in core detectors by the monte carlo code prizma for a full scale model of a Water Moderated Reactor core
International Conference on Supercomputing, 2014Co-Authors: Y Z Kandiev, E A Kashaeva, G N Malyshkin, K E KhatuntsevAbstract:The paper describes a technique implemented in the PRIZMA code for calculating neutron flux in a large number of small detectors arranged in the core of the VVER-1000 Reactor.
Y Z Kandiev - One of the best experts on this subject based on the ideXlab platform.
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a technique for estimating neutron fluxes in a large number of in core detectors by the monte carlo code prizma for a full scale model of a Water Moderated Reactor core
International Conference on Supercomputing, 2014Co-Authors: Y Z Kandiev, E A Kashaeva, G N Malyshkin, K E KhatuntsevAbstract:The paper describes a technique implemented in the PRIZMA code for calculating neutron flux in a large number of small detectors arranged in the core of the VVER-1000 Reactor.
Yu. N. Drozdov - One of the best experts on this subject based on the ideXlab platform.
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Resistance to fretting corrosion of fuel rods in a VVER-440 Water-Moderated Reactor in contact with spacers
Russian Engineering Research, 2011Co-Authors: Yu. N. Drozdov, E. P. Osipova, V. N. Puchkov, V. V. Makarov, A. V. Afanas’ev, A. V. GrishakovAbstract:The wear resistance of fuel assemblies in the VVER-440 Water-Moderated Reactor is investigated, with small fuel-rod diameter. The experimental apparatus, the model of the fuel rods, and the similarity conditions are described; the possibility of applying the experimental results to regular fuel rods is noted.
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Friction of fuel-rod casings and spacing cells in the pile of a Water-cooled, Water-Moderated Reactor
Russian Engineering Research, 2011Co-Authors: Yu. N. Drozdov, E. P. Osipova, V. V. Makarov, A. V. Afanas’ev, T. I. Nazarova, V. V. Abramov, M. V. PuchkovAbstract:Fuel-rod casings and spacing cells are subjected to frictional tests, with variation in the technological and operational factors.
G N Malyshkin - One of the best experts on this subject based on the ideXlab platform.
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a technique for estimating neutron fluxes in a large number of in core detectors by the monte carlo code prizma for a full scale model of a Water Moderated Reactor core
International Conference on Supercomputing, 2014Co-Authors: Y Z Kandiev, E A Kashaeva, G N Malyshkin, K E KhatuntsevAbstract:The paper describes a technique implemented in the PRIZMA code for calculating neutron flux in a large number of small detectors arranged in the core of the VVER-1000 Reactor.
E A Kashaeva - One of the best experts on this subject based on the ideXlab platform.
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a technique for estimating neutron fluxes in a large number of in core detectors by the monte carlo code prizma for a full scale model of a Water Moderated Reactor core
International Conference on Supercomputing, 2014Co-Authors: Y Z Kandiev, E A Kashaeva, G N Malyshkin, K E KhatuntsevAbstract:The paper describes a technique implemented in the PRIZMA code for calculating neutron flux in a large number of small detectors arranged in the core of the VVER-1000 Reactor.
