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Wyszukujesz frazę "BNCT" wg kryterium: Temat


Wyświetlanie 1-3 z 3
Tytuł:
Improved dosimetry for BNCT by activation foils, modified thermoluminescent detectors and recombination chambers
Autorzy:
Bilski, P.
Golnik, N.
Olko, P.
Pytel, K.
Tracz, G.
Tulik, P.
Zielczyński, M.
Powiązania:
https://bibliotekanauki.pl/articles/971519.pdf
Data publikacji:
2004
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
BNCT
recombination chambers
TLD
activation foils
Opis:
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
Źródło:
Nukleonika; 2004, 49, 2; 51-56
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Studies of recombination chambers filled with nitrogen for BNCT dosimetry
Autorzy:
Tulik, P.
Golnik, N.
Powiązania:
https://bibliotekanauki.pl/articles/148169.pdf
Data publikacji:
2009
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
recombination chamber
BNCT
dose components
Opis:
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.
Źródło:
Nukleonika; 2009, 54, 4; 255-259
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Numerical optimisation of the fission-converter and the filter/moderator arrangement for the Boron Neutron Capture Therapy
Autorzy:
Tracz, G.
Dąbkowski, L.
Dworak, D.
Pytel, K.
Woźnicka, U.
Powiązania:
https://bibliotekanauki.pl/articles/148388.pdf
Data publikacji:
2003
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
BNCT
fission converter
Fluka
MCNP
Monte Carlo
neutrons
Opis:
The paper presents results of the numerical modelling of the fission-converter-based epithermal neutron source designed for a BNCT (Boron Neutron Capture Therapy) facility to be located at the Polish research nuclear reactor MARIA at Świerk. The unique design of the fission converter has been proposed due to a specific geometrical surrounding of the reactor. The filter/moderator arrangement has been optimised in order to moderate fission neutrons to epithermal energies and to get rid of both fast neutrons and photons from the therapeutic beam. The selected filter/moderator set-up ensures both the high epithermal neutron flux and the suitably low level of beam contamination. The elimination of photons originated in the reactor core is an exceptional advantage of the proposed design. It brings one order of magnitude lower gamma radiation dose than the permissible dose in such a type of therapeutic facility is required. The MCNP and FLUKA codes have been used for the computations.
Źródło:
Nukleonika; 2003, 48, 4; 177-185
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
    Wyświetlanie 1-3 z 3

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