The TRIGA IPR-R1 nuclear reactor at the Centro de Desenvolvimento da Tecnologia Nuclear CDTN/CNEN, Belo Horizonte, Brazil, has three irradiation facilities: a rotary specimen rack outside the reactor core with 40 irradiation channels which provide large scale isotope irradiation; the central tube placed at the center of the reactor core which permits sample irradiation with maximum neutron flux, as well as neutron beam extraction; a pneumatic transfer tube which makes possible the analysis of short half-life radioisotopes. The aim of this work is to evaluate the thermal and epithermal neutron fluence rates in the three irradiation facilities of the IPR-R1. Al-0.1%Au reference materials were irradiated bare and Cd-covered, at 100 kW thermal power, and gamma spectrometry was applied with an HPGe detector. For the rotary specimen rack, the values obtained for thermal and epithermal neutron fluence rates are (8.2 ± 0.2) × 10(11)n.cm-2.s-1 and (3.5 ± 0.1) × 10(10)n.cm-2.s-1, respectively. For the pneumatic transfer tube and the central tube, epithermal neutron fluence rate values are respectively (3.3 ± 0.2) ×10(9)n.cm-2.s-1 and (2.6 ± 0.1) x 10(11)n.cm-2.s-1. For these facilities, thermal neutron fluence rate values are (2.5 ± 0.2) × 10(11)n.cm-2.s-1 and (2.8 ± 0.1) × 10(12)n.cm-2.s-1, respectively. Knowledge of these parameters will be fundamental in the planning of sample irradiation for analysis or radioisotope production in a more accurate way.

The IPR-R1 TRIGA nuclear reactor at Nuclear Technology Development Center, CDTN/CNEN, Belo Horizonte, Brazil, has a rotary specimen rack, RSR, outside the reactor core, and it is composed for forty irradiation channels in a cylindrical geometry. The aim of this work is to evaluate the neutron fluence rate distribution at the RSR and its variation under different irradiation conditions by means of specific induced activity measurements. Al-0.1 % Au reference materials were irradiated simultaneously at 100 kW in these irradiation channels and gamma spectrometry was applied with HPGe detector to determine the specific induced activity. This procedure was repeated six times. The results show an asymmetrical neutron fluence rate distribution at the RSR. The variation between the minimum and the maximum specific induced activity values in the RSR channels is about 14%.

OBJETIVO: A análise crítica da metodologia de medida da camada semi-redutora em feixes de raios X teve como base o regulamento técnico para proteção radiológica e controle de qualidade em radiodiagnóstico médico e odontológico. MATERIAIS E MÉTODOS: Na medida da camada semi-redutora, a técnica radiográfica, o arranjo experimental, os meios espalhadores, a instrumentação, o tamanho de campo de radiação e a metodologia de análise dos dados foram considerados. RESULTADOS: A camada semi-redutora obtida em condições de boa geometria, para a técnica escolhida, foi de 2,44 ± 0,02 mmAl. Em relação a este valor, observaram-se desvios máximos na camada semi-redutora de 4,1% na variação da geometria, de 98,8% na variação da câmara de ionização e do meio espalhador, e de até 29,5% com outro tipo de detector. CONCLUSÃO: Os resultados mostraram que não ocorre variação significante na camada semi-redutora para diferentes tamanhos de campo de radiação, mas foram evidentes a influência do espalhamento na superestimação da camada semi-redutora e a redução desta na presença de blocos de chumbo como meio espalhador. O procedimento prático adotado mostrou-se bastante confiável e evidenciou a grande discrepância decorrente da adoção de metodologias impróprias, enfatizando a necessidade de estabelecer um procedimento padrão para a medida da camada semi-redutora.

OBJECTIVE: The critical analysis of the methodology for evaluating the x-ray beam half-value layer was based on technical standards for radiological protection and quality control in medical and dental diagnoses. MATERIALS AND METHODS: Exposure parameters, experimental set-up, scattering materials, instrumentation, size of radiation field and methodology of data analysis have been taken into consideration for measurements of half-value layer. RESULTS: The half-value layer, in good geometry, measured 2.44 ± 0.02 mmAl. A maximum deviation of 4.1% was found under other geometry conditions. A 98.8% deviation was observed with a different ionization chamber, and scattering material, and 29.5% with another type of detector. CONCLUSION: Results showed that no relevant variation is observed in the half-value layer for different radiation field sizes. On the other hand, the influence of the radiation scattering on the half-value layer overestimation was clearly observed, as well as the half-value layer reduction in the presence of lead used as scattering material. The practical methodology adopted for half-value layer evaluation has shown to be quite reliable, besides evidencing remarkable discrepancies resulting from the adoption of inappropriate methodologies, emphasizing the necessity of establishing a standard procedure for measuring the half-value layer.