Bremsstrahlung spectral distributions have been experimentally measured for thick targets of lead and tantalum at 6 MeV electron energy, using Compton scattering technique. The experimental results are in agreement with the theoretical results.
14 MeV neutron activation analysis technique is used to estimate thickness of silicon films deposited on glass plates. The elemental barium present in the glass plate was used as an internal monitor. Measured values of film thickness are in agreement within ±5% with the results obtained by weight method.
Authors:V. Bhoraskar, S. Mahajan, S. Jayanthakumar, and V. Gogate
Ancient iron objects excavated from five different sites around Nagpur city in Maharashtra State /India/ were cut into small pieces and samples were prepared. Each sample was irradiated with 14 MeV neutrons for 8 min. From the recorded gamma ray spectrum for each sample, the presence of trace elements Cu, Si, Al, Mg and Mn were detected and their mutual ratios of activities were determined. The results show that all the iron objects obtained from five different sites are of the same origin.
Authors:N. Sardesai, P. Dighe, R. Patil, V. Bhoraskar, and V. Gogte
Elemental concentration has been estimated in aluminium based alloy samples, using 14-MeV neutron activation analysis. The results are in agreement with those obtained by atomic absorption spectroscopy.
Authors:P. Dighe, G. Pansare, S. Kulkarni, and V. Bhoraskar
Samples of explosive class materials were analyzed by 14 MeV neutron activation technique to estimate concentrations of oxygen, nitrogen, aluminium and chlorine. For aluminized explosives, test of stability against temperature was carried out by heating samples at 75 °C and loss of nitrogen was studied by measuring the ratio of aluminium to nitrogen in the sample. Loss of oxygen and nitrogen in a triple base propellant heated at 71.6 °C, was also estimated by measuring residual oxygen and nitrogen in the heated samples. This technique is convenient to adopt in the laboratory and useful to decide quickly the suitability of explosive class materials for practical applications.
Authors:H. Naik, S. Surayanarayana, V. Mulik, P. Prajapati, B. Shivashankar, K. Jagadeesan, S. Thakare, D. Raj, S. Sharma, P. Bhagwat, S. Dhole, S. Ganesan, V. Bhoraskar, and A. Goswami
The 238U(n, γ)239U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the 7Li(p, n)7Be reaction has been determined using activation and off-line γ-ray spectrometric technique. The 238U(n, γ)239U and 238U(n, 2n)237U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same 7Li(p, n)7Be reaction have been also determined using the above technique. The experimentally determined 238U(n, γ)239U and 238U(n, 2n)237U reaction cross-sections were compared with the evaluated data of ENDF/B-VII, JENDL-4.0, JEFF-3.1 and CENDL-3.1. The experimental
values were found to be in general agreement with the evaluated value based on ENDF/B-VII, and JENDL-4.0 but not with the
JEFF-3.1 and CENDL-3.1. The present data along with literature data in a wide range of neutron energies were interpreted in
terms of competition between different reaction channels including fission. The 238U(n, γ)239U and 238U(n, 2n)237U reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were also found to be in
agreement experimental data.