14-MeV Neutron Generator Used as a Thermal Neutron Source Page: 3 of 11
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1 14-MeV Neutron Generator Used As a Thermal Neutron Source
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3 I. Dioszegi', G. Smith' and N. Schaknowskil
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5 'Brookhaven National Laboratory, Upton, New York 11973, USA.
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7 Abstract ID Number: #174
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9 PACS code- 29.25 Dz, Neutron sources, 28.41.Qb Shielding (Nuclear technology)
10 Keywords: Neutron, Monte Carlo method, Shielding
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12 Abstract: One of the most important applications of the general purpose Monte Carlo N-Particle (MCNP5 and
13 MCNPX)) codes is neutron shielding design. We employed this method to simulate the shield of a 14-MeV neutron
14 generator used as a thermal neutron source providing an external thermal neutron beam for testing large area neutron
15 detectors developed for diffraction studies in biology and also useful for national security applications.
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17 Nuclear reactors have been the main sources of neutrons used for scientific applications. In the past decade,
18 however, a large number of reactors have been shut down, and the importance of other, smaller devices capable of
19 providing neutrons for research has increased. At Brookhaven National Laboratory a moderated Am-Be neutron
20 source with shielding is used for neutron detector testing. This source is relatively weak, but provides a constant flux
21 of neutrons, even when not in use. The use of a 14 MeV energized neutron generator, with an order of magnitude
22 higher neutron flux has been considered to replace the Am-Be source, but the higher fast neutron yield requires a
23 more careful design of moderator and shielding. In the present paper we describe a proposed shielding configuration
24 based on Monte Carlo calculations, and provide calculated neutron flux and dose distributions.
25 We simulated the neutron flux distribution of our existing Am-Be source surrounded by a paraffin
26 thermalizer cylinder (radius of 17.8 cm), 0.8 mm cadmium, and borated polyethylene as biological shield. The
27 thermal neutrons are available through a large opening through the polyethylene and cadmium. The geometrical
28 model for the MCNP5' and MCNPX2 simulations is shown in Fig. 1.
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Dioszegi, I. 14-MeV Neutron Generator Used as a Thermal Neutron Source, article, August 10, 2008; United States. (https://digital.library.unt.edu/ark:/67531/metadc897340/m1/3/: accessed March 19, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.