ANTONIO CARLOS IGLESIAS RODRIGUES

ANTONIO CARLOS IGLESIAS RODRIGUES

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Response of CsI:Pb scintillator crystal to neutron radiation
2018 - PEREIRA, MARIA da C.C.; MADI FILHO, TUFIC; BERRETTA, JOSE R.; CARDENAS, JOSE P.N.; RODRIGUES, ANTONIO C.I.
The helium-3 world crisis requires a development of new methods of neutron detection to replace commonly used 3He proportional counters. In the past decades, great effort was made to developed efficient and fast scintillators to detect radiation. The inorganic scintillator may be an alternative. Inorganic scintillators with much higher density should be selected for optimal neutron detection efficiency taking into consideration the relevant reactions leading to light emission. These detectors should, then, be carefully characterized both experimentally and by means of advanced simulation code. Ideally, the detector should have the capability to separate neutron and gamma induced events either by amplitude or through pulse shape differences. As neutron sources also generate gamma radiation, which can interfere with the measurement, it is necessary that the detector be able to discriminate the presence of such radiation. Considerable progress has been achieved to develop new inorganic scintillators, in particular increasing the light output and decreasing the decay time by optimized doping. Crystals may be found to suit neutron detection. In this report, we will present the results of the study of lead doped cesium iodide crystals (CsI:Pb) grown in our laboratory, using the vertical Bridgman technique. The concentration of the lead doping element (Pb) was studied in the range 5x10-4 M to 10-2 M . The crystals grown were subjected to annealing (heat treatment). In this procedure, vacuum of 10-6 mbar and continuous temperature of 350°C, for 24 hours, were employed. In response to neutron radiation, an AmBe source with energy range of 1 MeV to 12 MeV was used. The activity of the AmBe source was 1Ci Am. The fluency was 2.6 x 106 neutrons/second. The operating voltage of the photomultiplier tube was 1700 V; the accumulation time in the counting process was 600 s and 1800 s. The scintillator crystals used were cut with dimensions of 20 mm diameter and 10 mm height.
Study and project of the new rack with boron for storage of fuel elements burned in the IEA-R1 research reactor
2017 - RODRIGUES, ANTONIO C.I.; MADI FILHO, TUFIC; SILVA, DAVILSON G. da
The IEA-R1 research reactor works 40h weekly with 4.5 Mw power. The storage rack for spent fuel elements has less than half of its initial capacity. Under these conditions (current conditions of reactor operation 32h weekly will have 3 spend fuel by year, then, approximately 3 utilization rate Positions/year). Thus, we will have only about six years of capacity for storage. Whereas the desired service life of the IEA-R1 is at least another 20 years, it will be necessary to increase the storage capacity of spent fuel. Hence, it is necessary to double the wet storage capacity (storage in the IEA-R1 reactor's pool). After reviewing the literature about materials available for use in the construction of the new storage rack with absorber of neutrons, the BoralcanTM (manufactured by 3TMhis) wwaosr kc hporseesne,n dtsu es ttuod iitess :p r(oap) efrotrie tsh. e construction of new storages racks with double of the current capacity using the same place of current storages racks and (b) criticality analysis using the MCNP-5 code. Two American Nuclear Data Library were used: ENDF / B-VI and ENDF / B-VII, and the results obtained for each data bases were compared. These analyzes confirm the possibility of doubling the storage capacity of fuel elements burned in the same place occupied by the current storage rack attending to the IEA-R1 reactor needs and attending the safety requirements according to the National Nuclear Energy Commission - CNEN and the International Atomic Energy Agency (IAEA). To calculate the keff were considered new fuel elements (maximum possible reactivity) used in full charge of the storage rack. With the results obtained in the simulation we can conclude that doubling the amount of racks for spent fuel elements are complied with safety limits established in the IAEA standards and CNEN of criticality (keff < 0.95).
Design of a new wet storage rack for spent fuels from IEA-R1 reactor
2015 - RODRIGUES, ANTONIO C.I.; MADI FILHO, TUFIC; SIQUEIRA, PAULO T.D.; RICCI FILHO, WALTER
Borated stainless steel storage project to the spent fuel of the IEA-R1 reactor
2013 - RODRIGUES, ANTONIO C.I.; MADI FILHO, TUFIC; RICCI FILHO, WALTER
Application of prompt gamma source for n-16 detector system calibration
2011 - MADI FILHO, TUFIC; NAHUEL CARDENAS, JOSE P.; RODRIGUES, ANTONIO C.I.
Simulacao dos acidentes de partida a frio e queda de um elemento combustivel no reator IEA-R1m
1999 - RODRIGUES, A.C.I.; TEIXEIRA e SILVA, A.; CABRAL, E.L.L.; MESQUITA, R.N.; CONTI, T.N.
Analise de seguranca do reator IEA-R1 a 5MW
2000 - TEIXEIRA e SILVA, A.; MAPRELIAN, E.; RODRIGUES, A.C.I.; CABRAL, E.L.L.; MOLNARY, L.; MESQUITA, R.N.; MENDONCA, A.G.
Analise de acidentes de insercao de reatividade em reatores de pesquisa do tipo piscina
1996 - RODRIGUES, A.C.I.; SILVA, A.T.; CABRAL, E.L.L.; MESQUITA, R.N.; YAMAGUCHI, M.; GENTA, M.
Analise de acidentes de perda de vazao para o reator IEA-R1m
1997 - MESQUITA, R.N.; CABRAL, E.L.L.; RODRIGUES, A.C.I.
Analise de acidentes de insercao de reatividade postulados para o reator IEA-R1m
1997 - RODRIGUES, A.C.I.; TEIXEIRA e SILVA, A.; CABRAL, E.L.L.; MESQUITA, R.N.