The design of a multisource americium–beryllium (Am–Be) neutron irradiation facility using MCNP for the neutronic performance calculation

Sogbadji, R.B.M.; Abrefah, R.G.; Nyarko, B.J.B.; Akaho, E.H.K.; Odoi, H.C.; Attakorah-Birinkorang, S.

doi:10.1016/j.apradiso.2014.03.017

Cited by 14 publications

(1 citation statement)

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“…This is disadvantageous when large samples need to be activated since the radiation intensity will be disproportionate closest to the source, as the sample periphery becomes activated at a slower rate than the parts of the sample closest to the source. An important property of 241 AmBe is its high ratio of thermal neutrons in its characteristic spectrum, compared to that of other radioisotopic sources [17].…”

Section: Ambe the Neutron Yield Of A 241mentioning

confidence: 99%

Design, Construction, and Modeling of a²⁵²Cf Neutron Irradiator

Anderson

Holbert

Bowler

2016

Science and Technology of Nuclear Installations

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Neutron production methods are an integral part of research and analysis for an array of applications. This paper examines methods of neutron production, and the advantages of constructing a radioisotopic neutron irradiator assembly using252Cf. Characteristic neutron behavior and cost-benefit comparative analysis between alternative modes of neutron production are also examined. The irradiator is described from initial conception to the finished design. MCNP modeling shows a total neutron flux of 3 × 105 n/(cm2·s) in the irradiation chamber for a 25 μg source. Measurements of the gamma-ray and neutron dose rates near the external surface of the irradiator assembly are 120 μGy/h and 30 μSv/h, respectively, during irradiation. At completion of the project, total material, and labor costs remained below $50,000.

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Section: Ambe the Neutron Yield Of A 241mentioning

confidence: 99%