Wyniki wyszukiwania - BazTech

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Ambient dose equivalent measurements in secondary radiation fi elds at proton therapy facility CCB IFJ PAN in Krakow using recombination chambers

Jakubowska E. A., Gryziński M. A., Golnik N., Tulik P., Stolarczyk L., Horwacik T., Zbroja K., Góra Ł.

Nukleonika

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2016

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Vol. 61, No. 1

23--28

EN

This work presents recombination methods used for secondary radiation measurements at the Facility for Proton Radiotherapy of Eye Cancer at the Institute for Nuclear Physics, IFJ, in Krakow (Poland). The measurements of H*(10) were performed, with REM-2 tissue equivalent chamber in two halls of cyclotrons AIC-144 and Proteus C-235 and in the corridors close to treatment rooms. The measurements were completed by determination of gamma radiation component, using a hydrogen-free recombination chamber. The results were compared with the measurements using rem meter types FHT 762 (WENDI-II) and NM2 FHT 192 gamma probe and with stationary dosimetric system.

2

Studies of recombination chambers filled with nitrogen for BNCT dosimetry

Tulik P., Golnik N.

Nukleonika

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2009

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Vol. 54, No. 4

255-259

EN

Dosimetric characterization of therapy beams for boron neutron capture therapy (BNCT) involves determination of dose components and among them the “nitrogen” dose due to protons generated by neutron capture on 14N. In this work, investigations were carried out using a graphite recombination chamber in order to determine the 14N capture, gamma, and fast neutron dose components. The separation of the dose components is based on differences in the shape of the saturation curve, depending on the LET spectrum of the investigated radiation. The measurements were performed in reference radiation fields at the Institute of Atomic Energy at Świerk and at a reactor beam of the INP Řež (the Czech Republic). The gamma component was determined with an accuracy of about 5%, while the variations in its value could be monitored with an accuracy of about 0.5%. Relative changes in the beam components (thermal/fast neutrons) could be detected on line with an accuracy of about 5%. It was shown that the chamber with tissue-equivalent cups could be used for the determination of the 14N capture dose at different depths in tissue.

3

Ciśnieniowa komora jonizacyjna wypełniona trójfluorkiem boru jako wysokoczuły licznik neutronów termicznych

Golnik N., Rusinowski Z., Tulik P., Zielczyński M.

Elektronika : konstrukcje, technologie, zastosowania

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2009

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Vol. 50, nr 9

106-109

PL

W pracy przedstawiono wyniki pomiarów czułości neutronowej cylindrycznej komory jonizacyjnej, wypełnionej gazem ¹⁰ BF ₃ przy ciśnieniu kilkuset kPa, pracującej w reżimie impulsowym. Pomiary przeprowadzono w polach promieniowania źródeł ²³⁹ Pu-Be i ²⁵²Cf Komora ma długość 85 mm i średnicę 19 mm. Aluminiowa obudowa komory o grubości 0,3 mm stanowiła jedną z elektrod (na potencjale zerowym). Drugą, centralną, elektrodę wykonano z pręta miedzianego o średnicy 1,5 mm. Wykazano, że komora w moderatorze może spełniać rolę wysokoczułego detektora neutronów termicznych, a noszona przy pasku człowieka - również detektora przenośnego do detekcji małych strumieni neutronów termicznych. Czułość neutronowa pracującej w takich warunkach komory, napełnionej do ciśnienia 150 kPa dest rzędu 1 impulsu/neutron cm₃² w polu promieniowania źródła ²⁵²Cf.

EN

The paper presents neutron sensitivity values of a cylindrical ionization chamber, filled with ¹⁰ BF ₃ measurements were performed in radiation fields of neutron sources. The chamber is 85 mm long and 19 mm in diameter. The 0.3 mm thick aluminum housing of the chamber was connected as one of the electrodes (at zero potential). The second, central electrode was made of copper rod, with diameter of 1.5 mm. It was shown that the chamber in a moderator can serve as a sensitive neutron detector, and also as a pocket detector for detection of neutrons at low flux densities, if it is placed near the human body (by the belt). Neutron sensitivity of the chamber with gas pressure of 150 kPa and placed at the body was of order of 1 pulse/n cm₃² in the radiation field of ²⁵²Cf.

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Improved dosimetry for BNCT by activation foils, modified thermoluminescent detectors and recombination chambers

Bilski P., Golnik N., Olko P., Pytel K., Tracz G., Tulik P., Zielczyński M.

Nukleonika

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2004

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Vol. 49, nr 2

51-56

EN

Boron neutron capture therapy (BNCT) is an experimental therapy of selected tumours, based on a nuclear reaction initiated by the capture of thermal neutron by the 10B nucleus. After 10B had been delivered selectively to tumour cells, it can be activated by neutrons to deliver locally lethal high-LET radiation. BNCT beams are complex mixed radiation fields, because of broad neutron energy range, presence of gamma contamination and necessity of precise determination of several dose components. The paper presents some results of the research project on BNCT dosimetry with activation foils, recombination chambers and TL detectors.