Effect of a boron carbide filter on the distribution of neutron doses in an ordinary concrete shield using a beam of reactor neutrons

• Published in: The International journal of applied radiation and isotopes 1981-01, Vol.32 (7), p.507-512
• Main Authors: Megahid, R.M., El Kolaly, M.A., Makarious, A.S., Abu El Nasr, T.Z.
• Format: Article
• Language: English
• ISSN: 0020-708X
• DOI: 10.1016/0020-708X(81)90127-7

Results are presented of an experimental study of the effect of a boron carbide filter on the distribution of neutron doses in an ordinary concrete shield of density 2.3 g cm −3. Measurements have been carried out using a collimated beam of reactor neutrons emitted from one of the horizontal channels of the ET-RR-1 reactor. Measurements were performed using a direct beam, then followed with measurements using a beam filtered with boron carbide. The neutron doses were monitored using Li 2B 4O 7:Mn thermoluminescent dosimeters. The data obtained give the attenuation of neutron doses with concrete thickness. A group of isodose curves were evaluated which give the shape and thickness of ordinary concrete shield required to attenuate the neutron doses to a certain value. The data were also transformed to that which could be obtained using neutron sources of other geometrics. The neutron relaxation lengths in ordinary concrete shield were derived from these results.