Program

P.6 -- Poster, IWTCP-3

Date: Wednesday, 29 July 2015

Time: 08h30 - 10h00

Thermal neutron radiative capture cross-section of 186W(n,g)187W reaction

Vuong Huu Tan (1), Pham Ngoc Son (2)

(1) Vietnam Agency for Radiation and Nuclear Safety, 70-Tran Hung Dao, Ha Noi, Vietnam; (2) Nuclear Research Institute, 01-Nguyen Tu Luc, Dalat, Vietnam

Thermal neutron radiative capture cross section for 186W(n,g)187W reaction were measured by the activation method using the filtered thermal neutron beam at the Dalat research reactor. An optimal composition of Si and Bi single crystals has been used as neutron filters to create the high purity filtered thermal neutron beam with Cadmium ratio of 420. The induced activities in the irradiated samples were measured by a high resolution HPGe digital gamma-ray spectrometer. The present result is obtained relative to the reference value of the standard reaction 197Au(n,g)198Au. The necessary correction factors for gamma-ray true coincidence summing, and thermal neutron self-shielding effects were taken into account in this determination.

Presenter: Pham Ngoc Son