Abstract

Argonauta, the only nuclear research reactor situated in Rio de Janeiro, located at the Institute of Nuclear Engineering (IEN), regularly serves a network of users focused on research and development, and also provides its infrastructure for experimental classes and completion work course. Due to increasing demand for non-destructive thermal neutron assays and production of radioisotopes, there is a search for new procedures and/or devices that optimize users' exposure to neutrons. The implementation of mechanisms that allow access to the irradiation channels without the reactor being turned off and with a shielding configuration that limits the occupational doses at this location is very useful for the operation of the reactor. In order to achieve this, the present work proposes the establishment of a neutron beam shutter of the J-9 irradiation channel of the IEN’s Argonauta reactor. In a first step, experimental measurements were made in the irradiation channel of the reactor using a BF3 detector, which is coupled to a spectrometer. In this phase, the neutron beam was aligned to the spectrometer, and different materials were used as shields, aiming the attenuation of the beam. To validate and/or change the configuration of the barrier that best meets the material irradiation needs, a second planned phase is involving the neutron flux simulation of the reactor and the various shields with different boundary conditions using the particle transport code, Monte Carlo N-Particle Extended (MCNP- X).

Highlights

  • Radiological Protection is the set of measures that aims to protect man, his descendants and the environment from possible harmful effects of ionizing radiation, allowing the activities that make use of this type of radiation [2,4]

  • The best position for the spectrometer would be the point where the largest direct beam was measured, as it would be possible to work with the largest neutron beam, and a better counting statistic

  • Measurements were made between the positions of 354 to 0 and 0 to 6 degrees, with an interval of 1 degree

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Summary

Introduction

Radiological Protection is the set of measures that aims to protect man, his descendants and the environment from possible harmful effects of ionizing radiation, allowing the activities that make use of this type of radiation [2,4]. The basic principle of radiological protection known as ALARA (As Low As Reasonably Achievable) states that all exposures should be kept as low as reasonably achievable. This is because lowdose radiobiological studies have shown that there is no real dose threshold for stochastic effects. One of the activities of radiological protection, which corroborates this principle, is the specification and design of materials that can be used as protection barriers, in order to minimize the effects of doses of ionizing radiation on workers and individuals in the public. This study will contribute to the attendance of the current neutron flux, and to the possibility of increasing this flow, in order to be made available in the future demand of the activities of the Argonauta

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