Temat: Fluka - Katalog OPAC zbiorów

Skocz do pozycji: 1.

Tytuł:: Numerical model of thyroid counter
Autorzy:: Szuchta, M.
Ośko, J.
Powiązania:: https://bibliotekanauki.pl/articles/146317.pdf
Data publikacji:: 2016
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: iodine
Monte Carlo
FLUKA
gamma spectrometry
thyroid phantom
Opis:: The aim of this study was to develop a numerical model of spectrometric thyroid counter, which is used for the measurements of internal contamination by in vivo method. The modeled detector is used for a routine internal exposure monitoring procedure in the Radiation Protection Measurements Laboratory of National Centre for Nuclear Research (NCBJ). This procedure may also be used for monitoring of occupationally exposed nuclear medicine personnel. The developed model was prepared using Monte Carlo code FLUKA 2011 ver. 2b.6 Apr-14 and FLAIR ver. 1.2-5 interface. It contains a scintillation NaI(Tl) detector, the collimator and the thyroid water phantom with a reference source of iodine 131I. The geometry of the model was designed and a gamma energy spectrum of iodine 131I deposited in the detector was calculated.
Źródło:: Nukleonika; 2016, 61, 1; 45-47
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 2.

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

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Skocz do pozycji: 3.

Tytuł:: Monte-Carlo simulations of a neutron source generated with electron linear accelerator
Autorzy:: Wasilewski, A.
Wronka, S.
Powiązania:: https://bibliotekanauki.pl/articles/146272.pdf
Data publikacji:: 2006
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: Fluka
Monte Carlo simulation
neutron generation
electron linear accelerator
X-ray converter
Opis:: Neutron generator consisting of an electron linear accelerator and a tungsten X-ray converter can produce a neutron flux of 109 n/s and 1011 n/s at electron energies of 10 and 15 MeV, respectively, with an electron beam intensity of 1014 e/s which means 160 and 240 W of electron incident beam power, respectively. Two stage neutron production with an electron to photon natural tungsten converter and a photon to neutron 9Be converter are equal or less efficient than one stage tungsten converter only. There is a low neutron separation energy of 9Be and a small cross section for the photonuclear reaction g(9Be,8Be*)n in comparison to photonuclear cross section in all tungsten isotopes for the photon energy range in and below resonance region. Results of the neutron generator modeling performed with the Fluka Monte-Carlo code are presented in this article.
Źródło:: Nukleonika; 2006, 51, 3; 169-173
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 4.

Tytuł:: Fluka simulation of PGNAA system for determining heavy metal pollution in the soil sample
Autorzy:: Zhang, Can
Yang, Jianbo
Li, Rui
Qiao, Yujie
Zhang, Xu
Xu, Jie
Powiązania:: https://bibliotekanauki.pl/articles/146960.pdf
Data publikacji:: 2020
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: PGNAA
Fluka
heavy metal
prompt gamma-ray yield
metal ciężki
szybka wydajność
promieniowanie gamma
Opis:: This study presented a self-designed prompt gamma neutron activation analysis (PGNAA) model and used Fluka simulation to simulate the heavy metals (Mn, Cu, Hg, Ni, Cr, Pb) in soil samples. The relationship between the prompt gamma-ray yield of each heavy metal and soil thickness, content of heavy metals in the soil, and source distance was obtained. Simulation results show that the prompt gamma-ray yield of each heavy metal increases with the increase in soil thickness and reaches saturation at 18 cm. The greater the proportion of heavy metals in the soil, the greater the prompt gamma-ray yield. The highest content is approximately 3%, and the change in distance between the neutron source and soil sample does not affect the prompt gamma-ray yield of heavy metals.
Źródło:: Nukleonika; 2020, 65, 1; 13-17
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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