Development of a Focusing Device for Neutron Control in Nuclear Energetics

The development of methods and devices for effectively control the neutron flux and allowing greater depth of fuel burnup is discussed. Increasing the efficiency of neutron flux control in a device is based on the difference in the patterns of their interaction with the moderator substance and its s...

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Veröffentlicht in:Atomic energy (New York, N.Y.) N.Y.), 2022-04, Vol.131 (6), p.325-329
Hauptverfasser: Drobyshevsky, Yu. V., Stolbov, S. N., Korzhenevsky, A. V., Anfimov, I. M., Kobeleva, S. P., Varlachev, V. A., Nekrasov, S. A.
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Sprache:eng
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Zusammenfassung:The development of methods and devices for effectively control the neutron flux and allowing greater depth of fuel burnup is discussed. Increasing the efficiency of neutron flux control in a device is based on the difference in the patterns of their interaction with the moderator substance and its surface at the interface between media in an anisotropic structure. To experimentally check the effect of the selective separation of neutrons on profiled plates, three investigations were performed in the GEK-4 channel of the IRT-T reactor at Tomsk Polytechnic University. The neutron fluence 5.3·10 17 cm –2 was registered. It included the neutron fluence of the reactor 2.3·10 17 cm –2 and the neutron fluence from a sector of a moderating-focusing structure, which was selected and registered. The error of the measured values of the registered flux was equal to ±3%. The flux angle φ s contr = 4.8′ measured from the flux intensity reduction on the control plate of the detector is close to the tabulated angle of neutron reflection from the surface of aluminum plates φ s = 5′. It is of interest to evaluate the possibilities of focusing thermal neutron flux for subsequent applications in nuclear energetics.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-022-00887-z