title: Determination of neutron temperature in irradiation channels of reactor.
abstract: The neutron temperature is a characteristic parameter in irradiation channels of reactor. For nuclides which have resonances in the thermal neutron energy range, their Westcott g-factors are different from unity. The values of g-factors and cross-sections of (n, γ) reaction of these nuclides are temperature dependence. The standard energy for tabulation of thermal neutron cross-section (σ0) is that of room temperature (293.59 K or 20.43 °C), corresponding to a neutron energy 0.0253 eV or to a neutron velocity of 2200 m/s. However, in the irradiation channels of reactor, the temperature is not exact at 20.43 °C. Thus, the temperature at the irradiation position must be known to convert σ0to σ(T). A method for determination of the neutron temperature in irradiation channels of Dalat reactor is presented by fitting the thermal neutron spectrum obtained from the calculation using MCNP code.
authors.affiliation: Research and Development Center for Radiation Technology, 202A, 11 Str, Linh Xuan, Thu Duc, Ho Chi Minh, Vietnam.
authors.forename: Tran
authors.initials: T
authors.lastname: Van Hung
keywords: Dalat reactor; MCNP code; Neutron temperature; Westcott g-factor