[en] A simple non-solid multimonitor HAV-1 for the systematic evaluation of reactor neutron flux parameters for k₀ neutron activation analysis is presented. Solutions of Au, Zr, Co, Zn, Sn, U and Th (deposited in filter paper) are used to study the parameters α and f. Dissolved Lu is used to neutron temperature (T_n) determination, according to the Wescott's formalism. A multipurpose multimonitor HAV-1 preparation, certification and evaluation is presented. (author)

[en] A simple method non-solid multi monitor HAV-1 for the systematic evaluation of reactor neutron flux parameters for K_o neutron activation analysis is presented. Solution of Au, Zr, Co, Zn, Sn, U and Th (deposited in filter paper) are used to study the parameters alpha and f. Dissolved Lu is used to neutron temperature (Tn) determination, according to the Wescott's formalism. A multipurpose multi monitor HAV-1 preparation, certification and evaluations presented

[en] The possibility to use the subcritical assemblies of the High Institute of Nuclear Science as irradiator is presented, but it was designed with learning purposes. Its fuels haven it enrichment of ^235U. For this reason, is impossible to look for a better configuration to increase the multiplication on the facility. Increase of flux only can reach putting more radioisotopic sources around the irradiation position two configurations source.fuel: the original, with only one source and a new results of multiplication, the reactivity and the theoretical value of the thermal flux in the irradiation position

[en] The values of the f and alpha parameters are determined in the irradiation position of the neutron multiplier CS-ISCTN, with the aim to show the possibility to applied the parametric neutron activation analysis. The more used conventions to calculate the reaction rate; Hogdhal, Modified Stoughton-Halpering and Modified Wescott, the last is presents with some new variations. This comparison is combined with R-Cd multi monitors method, Cd-Cover Multi monitor Methods and a new method introduced in the present paper to reduce the errors in the alpha parameter determination named Minimal Difference Method. This last method show better results, according to the epithermal hardeners of the CS-ISCT

[en] The detection limit of 32 elements are determined after experimental evaluation of the neutron flux components in the irradiation position of the neutron multiplier CS-ISCTN. The control of the thermal flux was carry up, comparing the experimental results obtained through three convention used determination of the reaction rate, with the theoretical obtained before