Please use this identifier to cite or link to this item: http://nopr.niscair.res.in/handle/123456789/44863
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dc.contributor.authorSubramanian, D Venkata-
dc.contributor.authorHaridas, Adish-
dc.contributor.authorKumar, D Sunil-
dc.contributor.authorArul, A John-
dc.contributor.authorPuthiyavinayagam, P-
dc.date.accessioned2018-08-10T11:53:03Z-
dc.date.available2018-08-10T11:53:03Z-
dc.date.issued2018-08-
dc.identifier.issn0975-0959 (Online); 0301-1208 (Print)-
dc.identifier.urihttp://nopr.niscair.res.in/handle/123456789/44863-
dc.description583-586en_US
dc.description.abstractProviding suitable shielding for neutrons is one of the challenging tasks in fast reactor fuel reprocessing facilities. The shield material should have good moderating and absorbing properties. In order to find cost effective prospective materials, a series of neutron attenuation measurements are performed with hydrogenous materials at the south beam end of Kalpakkam Mini (KAMINI) reactor to understand their attenuation characteristics. In the present experiment, the neutron attenuating properties of borated polyethylene (BPE) containing 30% natural boron have been studied. The thermal and fast neutron flux attenuation characteristics of the material have been compared with 5% and 10% BPE and other hydrogenous materials. The thermal/epithermal neutron flux attenuation obtained with 30% BPE for a thickness of 30 cm is 1.5 times more than 5% and 10% BPE and 10 times more than normal polyethylene. It is also observed that there is no significant difference in the fast flux attenuation of 30%, 10% and 5% BPE. The outcome of the study indicates that if 30% BPE is used instead of normal polyethylene in fuel reprocessing facilities, 50% reduction in volume of shields can be achieved for thermal and epithermal neutron flux attenuation and 16 to 22% reduction in volume shields for fast neutron flux attenuation.en_US
dc.language.isoen_USen_US
dc.publisherNISCAIR-CSIR, Indiaen_US
dc.rights CC Attribution-Noncommercial-No Derivative Works 2.5 Indiaen_US
dc.sourceIJPAP Vol.56(08) [August 2018]en_US
dc.subjectKAMINIen_US
dc.subjectBorated polyethyleneen_US
dc.subjectPolyethyleneen_US
dc.subjectNeutron fluxen_US
dc.subjectAttenuationen_US
dc.titleNeutron attenuation studies with borated polyethylene slabs containing 30% natural boron and its comparison with hydrogenous materialsen_US
dc.typeArticleen_US
Appears in Collections:IJPAP Vol.56(08) [August 2018]

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