JOSE PATRICIO NAHUEL CARDENAS

JOSE PATRICIO NAHUEL CARDENAS

Página do item completo

Resultados de Busca

Agora exibindo 1 - 10 de 27

The growth and scintillation characteristics of lithium doped CsI crystals
2011 - PEREIRA, MARIA da C.C.; CARDENAS, JOSE P.N.; MADI FILHO, TUFIC
Inorganic scintillators play an important role in the detection and spectroscopy of gamma and X-rays, as well as in neutrons and charged particles. For a variety of applications, new inorganic scintillation materials are being studied. New scintillation detector applications arise continuously and the interest in the introduction of new fast scintillators becomes relevant. Scintillation crystals based on cesium iodide (CsI) have relatively low hygroscope, easy handling and low cost, features that favor their use as radiation detectors. In this work, lithium doped CsI crystals were grown using the vertical Bridgman technique. In this technique, the charge is maintained at high temperature for 10 h to for the material melting and complete reaction. The temperature gradient 21° C/cm and 1 mm/h descending velocity are chosen as technique parameters. After growth is finished, the furnace is cooled at a rate of 20° C/h to room temperature. The concentration of the lithium doping element (Li) studied was 10-3 M. Analyses were carried out to evaluate the scintillator developed concerning two responses: a) to the gamma radiation, in the energy range of 350 keV to 1330 keV and b) to neutron from AmBe source, with energy range of 1MeV to 12 MeV. T.S. Korolevaa et al [1] describe in their paper about new scintillation materials, for registration of gamma-rays, X-rays, neutrons and neutrinos. One of these materials is 6Li. Lithium can capture neutrons without gamma-ray emission and, thus, reducing the back-ground. The neutron detection reaction is 6Li(n,a)3H with a thermal neutron cross section that 940 barns. In this paper we investigated the feasibility of the CsI:Li crystal as a gamma ray and neutron detector which can be used for monitoring, due to the fact that in our work environment we have two nuclear research reactors, calibration systems and radioisotope production.
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.
Experimental and MCNP studies of paraffin and polyethylene in neutron moderation and BF3 detector efficiency
2013 - CARDENAS, JOSE P.N.; MADI FILHO, TUFIC; PETRI, ANNA R.; SANTOS, ROBINSON A. dos; MARTINS, JOAO F.T.; CARVALHO, DIEGO V.S.; ALVARENGA, T.; BELLEZZO, M.; LARANJO, G.; LIMA, M.; OLIVEIRA, P.; PEREIRA, MARIA da C.C.
The Nuclear and Energy Research Institute – IPEN, offers post-graduate programs, namely: Nuclear Technology - Applications (TNA), Nuclear Technology - Materials (TNM), Nuclear Technology - Reactors (TNR). The Institute programs mission is to form expert technicians and engineers with a strong knowledge in their discipline to work in the nuclear area. The course: “Theoretical Fundaments and Practices of the Instrumentation used in Nuclear Data Acquisition” covers the use of laboratory nuclear instrumentation and the accomplishment of experiments to obtain nuclear parameters. One of these experiments is object of this work: “Experimental and MCNP Studies of Paraffin and Polyethylene Neutron Moderation and BF3 Detector Efficiency”. Neutrons are uncharged particles and, therefore, cannot be detected by Coulomb interactions. Thus, the detector assembly used must contain some kind of material with high cross section for interaction with neutrons, called converters. A boron trifluoride (BF3) detector was used in this experiment to detect neutron in real time. However, the response of this arrangement varies according to the energy range of incident neutrons. Their efficiency for thermal neutrons is above 90%, but, this result decreases, significantly, for neutrons of energy greater than 0.5 eV. The neutron moderation and, consequently, its energy variation were obtained by interposing different thicknesses of moderator material (Paraffin or Polyethylene) between the source and the detector.
Am-Be neutron irradiator used for nuclear instrumentation training
2013 - MADI FILHO, TUFIC; CARDENAS, JOSE P.N.; PETRI, ANNA R.; SANTOS, ROBINSON A. dos; MARTINS, JOAO F.T.; CARVALHO, DIEGO V.S.; ALVARENGA, T.; BELLEZZO, M.; LARANJO, G.; LIMA, M.; OLIVEIRA, P.; PEREIRA, MARIA da C.C.
A neutron irradiator was assembled at IPEN (Nuclear and Energy Research Institute) facility to perform qualitative-quantitative analysis of materials, using thermal and fast neutrons. In order to determine the 116mIn decay constant, a thermal flux obtained experimentally by Monte Carlo N-Particle Transport Code-MCNP, in a previous work, was used in the nuclear experiment. The activity calculated from the activation parameters was 13.51±0.17 kBq and the activity determined experimentally was 12.51± 0.36 kBq. The decay constant determined by the pulse height analyzer (PHA) measures was 211.4 μ·s-1, and that determined by fitting the data using a Multichannel Scaler (MCS) system was 200.3 ± 1.6 μ·s-1. The half-life of 116mIn found in the literature is 3256.8 s, which corresponds to a decay constant of 212.8 μ·s-1. The present experiment does not intend to establish a new value for the decay constant: it solely aims students’ practical exercises in nuclear properties of elements. This experiment is part of the nuclear experimental course.
Digital systems implemented at the IPEN nuclear research reactor (IEA-R1): results and necessities
2013 - CARDENAS, JOSE P.N.; MADI FILHO, TUFIC; RICCI FILHO, WALTER; CARVALHO, MARCOS R. de; BENEVENUTI, ERION de L.; GOMES NETO, JOSE
IPEN (Nuclear and Energy Research Institute) was founded in 1956 with the main purpose of doing research and development in the field of nuclear energy and its applications. It is located at the campus of University of Sao Paulo (USP), in the city of Sao Paulo, in an area of nearly 500,000 m2. It has over 1.000 employees and 40% of them have qualification at master or doctor level The institute is recognized as a national leader institution in research and development (R&D) in the areas of radiopharmaceuticals, industrial applications of radiation, basic nuclear research, nuclear reactor operation and nuclear applications, materials science and technology, laser technology and applications. Along with the R&D, it has a strong educational activity, having a graduate program in Nuclear Technology, in association with the University of Sao Paulo, ranked as the best university in the country. The Federal Government Evaluation institution CAPES, granted to this course grade 6, considering it a program of Excellence. This program started at 1976 and has awarded 458 Ph.D. degrees and 937 master degrees since them. The actual graduate enrollment is around 400 students. One of major nuclear installation at IPEN is the IEA-R1 research reactor; it is the only Brazilian research reactor with substantial power level suitable for its utilization in researches concerning physics, chemistry, biology and engineering as well as for producing some useful radioisotopes for medical and other applications. IEA-R1 reactor is a swimming pool type reactor moderated and cooled by light water and uses graphite and beryllium as reflectors. The first criticality was achieved on September 16, 1957. The reactor is currently operating at 4.5 MW power level with an operational schedule of continuous 64 hours a week. In 1996 a Modernization Program was started to establish recommendations in order to mitigate equipment and structures ageing effects in the reactor components, detect and evaluate obsolescence of some electrical and electronic systems. In this work we will show a retrospective and results of digital systems applied to IEA-R1 reactor concerning electronic equipments and systems refurbishment and modernization and the necessity of a new control console implementation.
Inorganic scintillation crystals for neutron detection
2016 - PEREIRA, MARIA da C.C.; MADI FILHO, TUFIC; CARDENAS, JOSE P.N.
Experimental and MCNP studies of neutron moderators and BF detector efficiency
2015 - CARDENAS, J.P.N.; MADI FILHO, T.; PEREIRA, M.C.C.; PETRI, A.R.
Study of plastic scintillator detector for beta and gamma radiation measurement
2015 - PEREIRA, MARIA da C.C.; MADI FILHO, TUFIC; CARDENAS, JOSE P.N.; VIVOLO, VITOR; BERRETTA, JOSE R.; FERNANDES, VAGNER; KUAHARA, LILIAN T.; MARQUES, CAIO P.; COSTA, PRISCILA
Study of a Li doped CsI scientillator crystal as a neutron detector
2015 - MADI FILHO, T.; PEREIRA, M.C.C.; BERRETTA, J.R.; CARDENAS, J.P.N.
Evaluation of a measurements system for uranium electrodeposition control to radiopharmaceuticals production
2015 - MADI FILHO, TUFIC; SALIBA SILVA, ADONIS M.; CARDENAS, JOSE P.N.; PEREIRA, MARIA da C.C.; LOPES, VALDIR M.; SILVA, ALEXANDRE P.; SANTOS, DIOGO F.; PURGATO, RAFAEL T.; AREDES, VITOR O.; FIGUEREDO, ANDERSON L.; SANTOS, LUCAS R. dos; SANTOS, BRIANNA dos S.; CORREA, EDUARDO L.