An Am/Be neutron source and its use in integral tests of differential neutron reaction cross-section data

An Am/Be neutron source, installed recently at the Rajshahi University, is described. Neutron flux mapping was done using the nuclear reactions 197Au(n,γ) 198Au, 113In(n,γ) 114mIn, 115In(n,n′γ) 115mIn and 58Ni(n,p) 58Co. An approximate validation of the neutron spectral shape was done using five neu...

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Bibliographic Details
Published in:Applied radiation and isotopes 2010-09, Vol.68 (9), p.1656-1661
Main Authors: Uddin, M.S., Zaman, M.R., Hossain, S.M., Spahn, I., Sudár, S., Qaim, S.M.
Format: Article
Language:English
Subjects:
Activation product
Algorithms
Am/Be neutron source
Americium - analysis
Americium - chemistry
Beryllium - analysis
Beryllium - chemistry
Excitation function
Integral test of differential data
Neutron flux mapping
Neutron spectral shape validation
Neutron threshold reaction
Neutrons
Radiation Dosage
Radiometry - methods
Spectrum averaged cross section
γ-ray spectrometry
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Summary:An Am/Be neutron source, installed recently at the Rajshahi University, is described. Neutron flux mapping was done using the nuclear reactions 197Au(n,γ) 198Au, 113In(n,γ) 114mIn, 115In(n,n′γ) 115mIn and 58Ni(n,p) 58Co. An approximate validation of the neutron spectral shape was done using five neutron threshold detectors and the iterative unfolding code SULSA. Integral cross sections of the reactions 54Fe(n,p) 54Mn, 59Co(n,p) 59Fe and 92Mo(n,p) 92mNb were measured with fast neutrons ( E n >1.5 MeV) and compared with data calculated using the neutron spectral distribution and the excitation function of each reaction given in data libraries: an agreement within±6% was found.
ISSN:0969-8043
1872-9800
DOI:10.1016/j.apradiso.2010.02.006