期刊
PROGRESS IN NUCLEAR ENERGY
卷 52, 期 6, 页码 569-572出版社
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.pnucene.2010.01.008
关键词
MNSR Reactor; Thermal; Epithermal; Neutron flux; Cadmium; MCNP-4C code
资金
- Atomic Energy Commission of Syria
A permanent epithermal neutron irradiation site was designed in the Syrian Miniature Neutron Source Reactor (MNSR) by using cadmium as a thermal neutron shielding material. This site was designed by Cd-shielding the internal surface of the outer aluminum tube of the FOIS (First Outer Irradiation Site) in the MNSR. The MCNP-4C calculations showed that, to have a permanent epithermal neutron irradiation site for the ENAA using the cadmium, it is necessary to add the top beryllium shims of the reactor to compensate for the reactivity losses due to the neutrons absorption in the cylindrical cadmium shell. The activation detectors were used to measure the thermal and epithermal neutron fluxes in the FOIS. Distribution of the thermal neutron flux along the vertical direction of the outer irradiation capsule used in the FOIS has been found using MCNP-4C code, and experimentally by irradiating five copper wires. Good agreements were obtained between the calculated and the measured results. (C) 2010 Elsevier Ltd. All rights reserved.
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