Spectrum average cross section measurement of 183W (n, p)183Ta and 184W (n, p)184Ta reaction cross section in 252Cf(sf) neutron field

Rajnikant Makwana; S Mukherjee; L Snoj; S S Barala; M Mehta; P Mishra; S Tiwari; M Abhangi; S Khirwadkar; H Naik

doi:10.1016/j.apradiso.2017.06.002

Spectrum average cross section measurement of ¹⁸³W (n, p)¹⁸³Ta and ¹⁸⁴W (n, p)¹⁸⁴Ta reaction cross section in ²⁵²Cf(sf) neutron field

Appl Radiat Isot. 2017 Sep:127:150-155. doi: 10.1016/j.apradiso.2017.06.002. Epub 2017 Jun 2.

Authors

Rajnikant Makwana¹, S Mukherjee², L Snoj³, S S Barala⁴, M Mehta⁵, P Mishra⁶, S Tiwari⁵, M Abhangi⁵, S Khirwadkar⁵, H Naik⁷

Affiliations

¹ Department of Physics, The Maharaja Sayajrao University of Baroda, Vadodara 390002, India. Electronic address: rajniipr@gmail.com.
² Department of Physics, The Maharaja Sayajrao University of Baroda, Vadodara 390002, India. Electronic address: sk.mukherjee-phy@msubaroda.ac.in.
³ Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, Slovenia.
⁴ Defence Laboratory, Jodhpur, Rajasthan 342011, India.
⁵ Institute for Plasma Research, Gandhinagar, Gujarat 382428, India.
⁶ Department of Physics, The Maharaja Sayajrao University of Baroda, Vadodara 390002, India.
⁷ Radiochemistry Division, Bhabha Atomic Research Centre, Mumbai 400085, India.

PMID: 28618352
DOI: 10.1016/j.apradiso.2017.06.002

Abstract

Neutron induced nuclear reactions are of prime importance for both fusion and fission nuclear reactor technology. Present work describes the first time measurement of spectrum average cross section of nuclear reactions ¹⁸³W(n,p)¹⁸³Ta and ¹⁸⁴W(n,p)¹⁸⁴Ta using ²⁵²Cf spontaneous fission neutron source. Standard neutron activation analysis (NAA) technique was used. The neutron spectra were calculated using Monte Carlo N Particle Code (MCNP). The effects of self-shielding and back scattering were taken into account by optimizing the detector modeling. These effects along with efficiency of detector were corrected for volume sample in the actual source-detector geometry. The measured data were compared with the previously measured data available in Exchange Format (EXFOR) data base and evaluated data using EMPIRE - 3.2.2.