Neutronic model of the fusion neutron source Sample Clauses

Neutronic model of the fusion neutron source. The applications of neutrons are unique because of the interaction particularity of neutrons with matter. Neutrons interact with nuclei but not with the electron shells. Scattering length can be very different for different isotopes of one element. The neutron diagnostics is a powerful method of isotopic contrast giving a possibility to detect light nuclei within heavy ones. The capabilities of neutron diffraction are manifested most clearly in the hydrogen-containing systems, such as polymers, biological systems, organic and water solutions. Besides, a neutron has a magnetic moment. Therefore, neutron diffraction is a direct method for diagnosing the magnetic structures, both in the interior and on the surface. The beams of polarized neutrons are especially effective tool for magnetic diagnostics. Neutrons interact weakly with the matter, so they do not destroy even the delicate biological systems and can penetrate deeply into the interior that is important for studying their volumetric properties. Powerful sources of fusion neutrons with energies ~ 14 MeV are of particular interest. Stand-alone application of fusion neutrons is testing of materials for fusion reactor. The purpose of this study is to find a principal design of a steady-state fusion neutron source. The MCNPX numerical code has been used to model the neutron kinetics and to calculate the neutron flux in the contemplated location of sample exposure. In the calculation model the main part of the source has a cylindrical shape with an inner radius of 88 cm and a length of 4 m. A vacuum chamber with a radius of 0.5 m containing a 4 m long hot D-T plasma producing fusion neutrons is located inside. For the first wall a thickness of 3 cm was chosen. Behind the first wall there is a liquid-metal coolant for heat removal. There have been considered two versions of the coolant: lead and bismuth eutectic (LBE), and sodium. A shield surrounding the model was used to absorb the outcoming neutrons. The paper presents calculation results for the neutron flux and spectrum at the sample area and inside the first wall for 2 coolants. The radial leakage of neutrons through the shield has also been calculated. (S.V.
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