• Journal of Radiation Protection and Research
• /
• 제12권1호
• /
• pp.34-39
• /
• 1987

Radiation shielding analysis for a 6MeV X-ray facility was carried out. The primary and leakage radiation for the facility can be evaluated based on the methodology in NCRP No. 49 and 51. The present study deals with radiation scattering analysis for the outside and inside door of the facility based on the albedo concept. The calculated dose rates were compared with the results of MORSE-CG code calculation and the measured data, resulting in a good agreement, even though there existed some deviation for the inside door. These results can be utilized to the radiation shielding design of the medical and industrial X and gamma ray facilities, and to the safety evaluation of these facilities.

• Journal of Radiation Protection and Research
• /
• 제29권4호
• /
• pp.251-256
• /
• 2004

CsI(Tl), $CdWO_4(CWO),\;Bi_4Ge_3O_{12}(BGO)\;and\;Gd_2SiO_5:Ce(GSO)$ scintillators were studied to manufacture a phoswich detector. The maximum wavelengths of the CsI(Tl), CWO, BGO and GSO scintillators are 550 nm, 475 nm, 490 nm and 440 nm for the radioluminescence, and the absolute light outputs of the CsI(Tl), CWO, BGO and GSO scintillators are 54890 phonon/MeV, 17762 phonon/MeV, 8322 phonon/MeV and 8932 phonon/MeV with a neutral filter, and the decay time of the CsI(Tl), CWO, BGO and GSO scintillators is $1.3{\mu}s,\;8.17{\mu}s$, 213 ns and 37 ns by a single photon method. The phoswich detector which was manufactured with plastic and CsI(Tl) scintillators could separate the ${\beta}$ particle and ${\gamma}$ ray. The phoswich detector could also measure the pulse height spectra of the ${\beta}$ particle and ${\gamma}$ ray by a PSD method.

• Journal of Radiation Protection and Research
• /
• 제47권4호
• /
• pp.195-203
• /
• 2022

Background: The aim of the present study was to determine radioactive concentrations in fertilizers known to contain essential nutrients. Results of this study could be used as basic data to monitor the impact of chemical fertilizers on the environment and public health. Nitrogen fertilizers, calcium fertilizers, sulfur fertilizers, phosphate acid fertilizers, and potassium chloride fertilizers were used in this study. Materials and Methods: Five chemical fertilizers were pulverized, placed in polyethylene containers, and weighed. The time to measure each specimen was set to be 3,600 seconds for a scintillator-based gamma-ray spectroscopy system. Concentration of gamma radionuclide was analyzed based on obtained spectra. At the end of the measurement, the spectrum file was stored and used to calculate radioactive concentrations using a gamma-ray spectrometer software. Results and Discussion: In the nitrogen fertilizer, 3.49 ± 5.71 Bq/kg of ¹³⁷Cs, 34.43 ± 7.61 Bq/kg of ¹³⁴Cs, and 569.16 ± 91.15 of ⁴⁰K were detected whereas ¹³¹I was not detected. In the calcium fertilizer, 5.74 ± 4.40 Bq/kg of ¹³⁷Cs (the highest concentration among all fertilizers), 22.37 ± 5.39 Bq/kg of ¹³⁴Cs, and 433.67 ± 64.24 Bq/kg of ⁴⁰K were detected whereas ¹³¹I was not detected. In the sulfur fertilizer, 347.31 ± 55.73 Bq/kg of ⁴⁰K, 19.42 ± 4.53 Bq/kg of ¹³⁴Cs, 2.21 ± 3.49 of ¹³⁷Cs, and 0.04 ± 0.22 Bq/Kg of ¹³¹I were detected. In the phosphoric acid fertilizer, 70,007.34 ± 844.18 Bq/kg of ⁴⁰K (the highest concentration among all fertilizers) and 46.07 ± 70.40 Bq/kg of ¹³⁴Cs were detected whereas neither ¹³⁷Cs nor ¹³¹I was detected. In the potassium chloride fertilizer, 12,827.92 ± 1542.19 Bq/kg of ⁴⁰K was and 94.76 ± 128.79 Bq/kg of ¹³⁴Cs were detected whereas neither ¹³⁷Cs nor ¹³¹I was detected. The present study examined inorganic fertilizers produced by a single manufacturer. There might be different results according to the country and area from which fertilizers are imported. Further studies about inorganic fertilizers in more detail are needed to create measures to reduce ⁴⁰K. Conclusion: Measures are needed to reduce radiation exposure to ⁴⁰K contained in fertilizers including phosphoric acid and potassium chloride fertilizers.

• Journal of Radiation Protection and Research
• /
• 제33권1호
• /
• pp.13-20
• /
• 2008

The flow rate measurements in a multi-phase flow pipeline were evaluated quantitatively by means of a clamp-on sealed radioisotope based on a cross correlation signal processing technique. The flow rates were calculated by a determination of the transit time between two sealed gamma sources by using a cross correlation function following FFT filtering, then corrected with vapor fraction in the pipeline which was measured by the ${\gamma}$-ray attenuation method. The pipeline model was manufactured by acrylic resin(ID. 8 cm, L=3.5 m, t=10 mm), and the multi-phase flow patterns were realized by an injection of compressed $N_2$ gas. Two sealed gamma sources of $^{137}Cs$ (E=0.662 MeV, ${\Gamma}$ $factor=0.326\;R{\cdot}h^{-1}{\cdot}m^2{\cdot}Ci^{-1}$) of 20 mCi and 17 mCi, and radiation detectors of $2"{\times}2"$ NaI(Tl) scintillation counter (Eberline, SP-3) were used for this study. Under the given conditions(the distance between two sources: 4D(D; inner diameter), N/S ratio: $0.12{\sim}0.15$, sampling time ${\Delta}t$: 4msec), the measured flow rates showed the maximum. relative error of 1.7 % when compared to the real ones through the vapor content corrections($6.1\;%{\sim}9.2\;%$). From a subsequent experiment, it was proven that the closer the distance between the two sealed sources is, the more precise the measured flow rates are. Provided additional studies related to the selection of radioisotopes their activity, and an optimization of the experimental geometry are carried out, it is anticipated that a radioisotope application for flow rate measurements can be used as an important tool for monitoring multi-phase facilities belonging to petrochemical and refinery industries and contributes economically in the light of maintenance and control of them.

• Journal of Radiation Protection and Research
• /
• 제22권1호
• /
• pp.1-7
• /
• 1997

Radiation protection by post-irradiation injection of the ginseng extract in mice was studied. Male ICR mice, 7 weeks old, were orally injected with ginseng extrat(100mg/kg) for 10 days, and with physiologocal saline as the control. Immediately after final injection, mice were whole body irradiated with 5.08Gy(Cs-137 ${\gamma}$-ray, central dose rate : 654Gy/h) which induced Bone marrow death. At 24h after irradiation, micronucleus test and metaphase analysis in bone-marrow were carried, blood cell were counted and the survival rate were carried for 30 days after the irradiation. Stimulated recovery by the extract was observed in thrombocyte count, but that phenomenom was not showed in the erythrocyte and leucocyte counts. The 30-day survival ratio was 5% and 65% for the control and experimental group. Frequencies of micronuclei per 1000 polychromatic erythrocytes were 79.5${\pm}$1.5 in experimental group, 185.9${\pm}$35.8 in control. And Abnormal chromosomes per 50 metaphases were 112 in experimental group and 143 in control.

• Journal of the Korean Society of Food Science and Nutrition
• /
• 제33권1호
• /
• pp.22-27
• /
• 2004

In the present study, the protective effects of Artemisia capillaris (AC) on the DNA damage induced by $^{60}$ Co ${\gamma}$-rays were evaluated using alkaline single-cell gel electrophoresis (SCGE, comet assay) in the mouse peripheral lymphocytes and micronuclei (MN) formation test in the Chinese hamster ovary (CHO) cells. We also investigated the effect of AC on 8-hydroxy-2'-deoxyguanosine (8-OHdG) formation in the mouse liver and thymus exposed to ${\gamma}$-ray, The tail moment and the frequency of MN, which were markers of DNA damage in the SCGE and MN formation test, were decreased in the groups treated with AC extract before exposure to 200 cGy of ${\gamma}$-ray. We also observed its activities, lowering 8-OHdG level, an index of oxidative DNA damage, in the groups treated with AC extract before whole body ${\gamma}$-irradiation (800 cGy). It is plausible that scavenging of free radicals by AC may have played an important role in providing the protection against the radiation-induced damage to the DNA. These results indicated that AC protects the DNA damage induced by ${\gamma}$-rays and might be a useful radioprotector, especially since it is a relatively nontoxic product.

• Nuclear Engineering and Technology
• /
• 제54권1호
• /
• pp.283-292
• /
• 2022

Advanced radiation applications have been widely used and extended to many fields. As a result of this fact, choosing an appropriate shielding material based on the radiation application has become vital. In this regard, the integration of elements into polymer composites has been investigated and contributed to the quantity and quality of radiation shielding materials. This study reports photon attenuation parameters and electromagnetic shielding effectiveness of a novel polymer composite prepared with a matrix reinforced with three different proportions (5, 10, and 15 wt%) of niobium content. Addition of Nb dopant improves both photon attenuation and electromagnetic shielding effectiveness for the investigated composites. Therefore, Nb(15%) polymer composite with highest concentration has been found to be the best absorber for ionizing and non-ionizing radiations. Consequently, the performed analyzes provide evidences that the prepared Nb-reinforced polymer composite could be effectively used as photon radiation attenuator and electromagnetic shielding material.

• Journal of Radiation Protection and Research
• /
• 제31권3호
• /
• pp.129-134
• /
• 2006

A TL pellet for a neutron dose measurement (KCT-306) by embedding a $^6Li$-compound into a $CaSO_4:Dy$ phohphor was developed based upon the technical information of KCT-300. The KCT-300 is an another kind of $CaSO_4:Dy$ TL detector shich was developed at KAERI, in which small amounts of $NH_4H_2PO_4$ have been emvedded as a binding material. This paper presented the optimized manufacturing condition of KCT-306 and compared its sensitivity with that of the commercialized neutron TL pellets. $CaSO_4:Dy$ Phosphor with grain size ranging less than $45{\mu}m$ are used for the KCT-306. The optimum $CaSO_4:Dy$ TL phosphor, $^6Li$-compounds and P-compound as the binding material are determined as 20-40wt%, 50-70wt% and 20wt%. The TL pellet combination of our KCT-306/KCT-300, TLD-600/TLD-700 and TLD-600H/TLD-700H(Harshaw) have been irradiated in the neutron/gamma mixed fields from a $D_2O$ moderated $^{252}Cf$ neutron source. The KCT-300, TLD-700 and TLD-700H were used at the same time as gamma ray discriminators in the neutron/gamma mixed fields. It was found that the neutron/gamma response ratios of KCT-306/KCT-300, which were developed in this study, were approximately 4 times higher than those of the commercial TLD-600H/TLD-700H.

• Korean Journal of Veterinary Research
• /
• 제48권4호
• /
• pp.393-399
• /
• 2008

We investigated the potential of fucoidan for its ability to provide protection from gamma rayinduced damage. In our results, the fucoidan significantly improved the counts of endogenous colony forming unit to $9.5 {\pm} 1.5$, from $5.5 {\pm} 2.5$ compared with un-treated irradiated control group at 10 day after 7 Gy whole body irradiation. After 2 Gy irradiation, fucoidan treatment attenuated the percent of tail DNA of splenocytes, parameters of DNA damage, from $30.17 {\pm} 1.7%$ to $13.67 {\pm} 2.81%$ 2.81% by comet assay and also accelerated the proliferation of splenocytes, compared with un-treated irradiated control group by 3Hthymidine incorporation assay. Furthermore, fucoidan decreased the number of apoptotic fragments per intestinal crypt by 31.8% at 1 days after 2 Gy irradiation. These results indicated that the fucoidan significantly improved the hematopoietic recovery, prevented the DNA damage in immune cells and enhanced their proliferation, which had been suppressed by ionizing radiation. in addition, fucoidan rescued intestinal cells from radiation-induced apoptosis. Thus, this study raises the possibility of using fucoidan as adjuvant therapeutic agent after radiotherapy.

• Journal of the Korean Society of Radiology
• /
• 제14권5호
• /
• pp.643-650
• /
• 2020

The materials with a high processiblity for radiation shielding, in particular for 3D printable materials, are highly demanding for producing robots working in nuclear plants and designing customized personal protection equipment. In this study, we suspend tungsten particles in a polymeric matrix of either PLA or ABS to compose tungsten-polymer composite filaments; PLA and ABS are widely used for conventional FDM-based 3D printing. The weight fraction of tungsten particles can be increased up to 50% without forming macroscopic aggregates. The composite filaments can be used to print 3D architectures with any shape and geometry. To demonstrate one of potential applications, we print parts for robot actuator and assemble them to protect PCB against gamma ray.