New approach for calibration the efficiency of HpGe detectors

Alnour, I. A.; Wagiran, Husin; Ibrahim, Norliza; Hamzah, Suhaimi; Wee, Boon Siong; Elias, M. S.

doi:10.1063/1.4866101

Cited by 16 publications

(6 citation statements)

References 1 publication

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“…5 shows that the flux reduces in a linear fashion for the 0.05 cm cladding thickness resulting in a neutron flux reduction by 14.5 %. The result is consistent with the observation that has been made according to the behaviors of the thermal neutron flux, which is the dominant neutron flux in the reactor (neutrons are well thermalized with about 95 % of thermal over epithermal neutrons) [9]. The axial thermal neutron flux at full core power of 750 kW is presented in Fig.…”

Section: Resultssupporting

confidence: 91%

Investigation on Neutron Flux Effect onto Irradiated Fuel Burn-up Stored in the Reactor TRIGA PUSPATI

et al. 2019

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An investigation on the out-core neutron flux in the Reactor TRIGA PUSPATI is carried out in this work to determine whether the thermal and/or fast neutron from the core would cause burn-up of the irradiated fuel stored in the same vicinity of the reactor core. The storage rack is positioned at 1 m from the central thimble. MCNPX code is used to calculate the fast and thermal neutron flux at 750 kW reactor power using 10 cm  10 cm  10 cm mesh while MATLAB model on 20 cm  20 cm mesh model is used to plot the axial and radial distribution of the neutron flux density. The results show that the thermal neutrons occurred at energy lower than 1  10 6 MeV and traveled to a maximum distance of 78 cm. The greatest flux for thermal and fast neutrons is 1  10 13 n.cm 2 .s 1 and 5  10 13 n.cm 2 .s 1 respectively. The fission-rate of the fuel in the core is determined to be 3.18  10 14 particle/s compared to 1.51  10 7 particle/s of the irradiated fuel in the storage rack. The burn-up of the fuel in the storage rack is in the order of micrograms and therefore is negligible. It is concluded that neutron flux from the core would not impart burn up effect onto the irradiated fuel stored at the storage rack in the reactor pool.

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Section: Resultssupporting

confidence: 91%

Investigation on Neutron Flux Effect onto Irradiated Fuel Burn-up Stored in the Reactor TRIGA PUSPATI

et al. 2019

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“…Granite is widely distributed throughout the continental crust and presents the most abundant plutonic rock present in mountain belts. Because of the large quantities of granite that occur in nature, geologists believe that most granites had been formed either by melting, partial melting or metamorphosis of deeply buried shale and sandstone (Alnour 2012). Some granite has been reported to have higher radioactivity, thereby raising some concerns about their safety.…”

Section: Resultsmentioning

confidence: 99%

Natural radioactivity in raw materials used in building industry in Serbia

Todorović

Bikit

Krmar

et al. 2014

Int. J. Environ. Sci. Technol.

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Natural radioactivity is responsible for most of the total radiation dose received by human population. Geological materials used in building industry usually become contaminated with naturally occurring radioactive materials. They are used as mixtures in building industry (kaolin, zircon, frit, feldspar) or mechanically processed and used for covering floors and walls of the rooms (granite). In this paper, activity concentrations of 226 Ra, 232 Th and 40 K in 6 kaolin, 11 zircon, 18 granite, 3 marble, 6 sand, 4 perlite, 4 feldspar, 5 korund and 1 frit samples imported in Serbia were determined by gamma-ray spectrometry. Activity concentration index, dose rate and annual effective dose were calculated for each of the investigated samples. Measurement of an external gamma dose rate by using a commonly available radiation survey meter can give some indication of the need for further investigations. The absorbed dose rate and annual effective doses for workers in the ceramic industry ''Keramika Kanjiza Plus'' in Serbia working with granite are determined.

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“…With the exception of 40 K, all gamma lines have a high branching ratio [11]. The efficiency curve (Fig 3) covers the photon energy range 121.78-1528 keV with a fitting polynomial of order 4, as given by Alnour et al PLOS ONE [12] and Gouda et al [13], shown in (1) below:…”

Section: Competing Interestsmentioning

confidence: 93%

The naturally occurring radioactivity of ‘scalar energy’ pendants and concomitant radiation risk

et al. 2021

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Forming part of a study of radiological risk arising from use of radioactive consumer products, investigation is made of pendants containing naturally occurring radioactive material. Based on use of gamma-ray spectrometry and Monte Carlo (MC) simulations, the study investigates commercially available ‘scalar energy pendants’. The doses from these have been simulated using MIRD5 mathematical phantoms, evaluation being made of dose conversion factors (DCFs) and organ dose. Metallic pendants code MP15 were found to contain the greatest activity, at 7043 ± 471 Bq from 232Th, while glass pendants code GP11 were presented the greatest 238U and 40K activity, at 1001 ± 172 and 687 ± 130 Bq respectively. MP15 pendants offered the greatest percentage concentrations of Th, Ce, U and Zr, with means of 25.6 ± 0.06, 5.6 ± 0.005, 1.03 ± 0.04 and 28.5 ± 0.08 respectively, giving rise to an effective dose of 2.8 mSv for a nominal wearing period of 2000 h. Accordingly, these products can give rise to annual doses in excess of the public limit of 1 mSv.

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New approach for calibration the efficiency of HpGe detectors

Cited by 16 publications

References 1 publication

Investigation on Neutron Flux Effect onto Irradiated Fuel Burn-up Stored in the Reactor TRIGA PUSPATI

Investigation on Neutron Flux Effect onto Irradiated Fuel Burn-up Stored in the Reactor TRIGA PUSPATI

Natural radioactivity in raw materials used in building industry in Serbia

The naturally occurring radioactivity of ‘scalar energy’ pendants and concomitant radiation risk

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