• Journal of Radiation Protection and Research
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• v.32 no.1
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• pp.35-44
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• 2007

Sealed sources have to conducted the tests be done according to the classification requirements for their typical usages in accordance with the relevant domestic notice standard and ISO 2919. After each test, the source shall be examined visually for loss of integrity and pass an appropriate leakage test. Tests to class a sealed source are temperature, external pressure, impact, vibration and puncture test. The environmental test conditions for tests with class numbers are arranged in increasing order of severity. In this study, the apparatus of tests, except the vibration test, were developed and applied to three kinds of sealed source. The conditions of the tests to class a sealed source were stated and the difference between the domestic notice standard and ISO 2919 were considered. And apparatus of the tests were made. Using developed apparatus we conducted the tests for $^{192}Ir$ brachytherapy sealed source and two kinds of sealed source for industrial radiography. $^{192}Ir$ brachytherapy sealed source is classified by temperature class 5, external pressure class 3, impact class 2 and vibration and puncture class 1. Two kinds of sealed source for industrial radiography are classified by temperature class 4, external pressure class 2, impact and puncture class 5 and vibration class 1. After the tests, Liquid nitrogen bubble test and vacuum bubble test were done to evaluate the safety of the sealed sources.

• The Korean Journal of Nuclear Medicine Technology
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• v.21 no.1
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• pp.50-53
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• 2017

Purpose The change in uniformity due to the decreasement in dose should be known. $^{57}Co$ sealed sources are easy to manage and use as QC sources replacing $^{99m}Tc$. Overlapping sealed sources are expected to show variations in dose due to attenuation between sealed sources. Materials and Methods A total of three experiments were conducted. The first experiment is to observe the change in the degree of senescence of the $^{57}Co$ sealed source. The second experiment is to compare the single source and overlaped source at similar doses. In the third experiment, the sources of different doses were compared on each other to determine the changes due to the attenuation between the overlapping sources. Results The results of the first experiment did not exceed the acceptable range. but each crew showed a difference. There was no statistically significant difference in the measurement of uniformity on second and third experiment Conclusion It is believed that a $^{57}Co$ sealed source can be used as a superimposed source. It is not only economical but also convenient to use. daily uniformity measurements will help reduce scan time and speed up the testing process.

• Journal of Radiation Industry
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• v.11 no.3
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• pp.173-179
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• 2017

The small-scale electroplating device was designed and fabricated for Ni-63 sealed source (foil type) with a high specific activity needed for production of betavoltaic battery. The condition of Ni electroplating was optimized by using fabricated electroplating device to establish a Ni-63 electroplating condition on the Ni foil. The results showed that the optimum surface morphology and thickness of Ni deposit was obtained for 1,758 seconds at a current density of $15mA{\cdot}cm^{-2}$ with 0.5% tween 20. Radioisotope Ni-63 electroplating was implemented under established condition. The radioactivity of Ni-63 sealed source was calculated to $28mCi{\cdot}cm^{-2}$, and the thickness of Ni-63 deposit was about $2.4{\mu}m$.

• Progress in Medical Physics
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• v.12 no.1
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• pp.19-29
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• 2001

In dose modeling, the shape of actual source and sealed capsule are important parameter to determine the physical dose computation. The author investigated the effect of filter of source self-absorption and sealed capsule to designed the high dose rate Ir-192 source for Ralstron(Japan) unit. The size of source designed to 1.5 mm $\Phi$ x 1.5mm length of actual source sealed with stainless steel which is 3.0mm $\Phi$ x 12.0mm length connected to driving cable. The dose attenuation was derived 66.3 % from 2655 segmented source at reference point of 10mm lateral distance of source. The output dose rate factor in tissue for designed source showed 0.0013511 cGy/mCi-sec in reference point at 1cm lateral distance of source center. The dose distribution at inferior of source showed the 52% of that of source tip region, however, the filtering effect was small as 4% at 45degrees of source axis. The dose attenuation within 20 degrees of source axis at near source-cable connector showed large filtering effect as 40% over, but the small effect was revealed isotropic dose distribution at large angle.

• Journal of Soil and Groundwater Environment
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• v.22 no.4
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• pp.33-48
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• 2017

An optimum disposal plan of disused sealed radioactive sources (DSRSs) should be established to ensure long-term disposal safety at the low- and intermediate-level radioactive waste (LILW) disposal facility in Gyeongju. In this study, an optimum disposal system was suggested and preliminary post-closure safety assessment was performed. The DSRSs disposal system was composed of a rock cavern and near surface disposal facilities at the Gyeongju LILW disposal facility. The assessment was conducted using GoldSim program, and probabilistic assessment and sensitivity analysis were implemented to evaluate the uncertainties in the input parameters of natural barriers. Deterministic and probabilistic calculations indicated that the maximum dose was below the regulatory limits ($0.1mSvyr^{-1}$ for the normal scenario, $1mSvyr^{-1}$ for the well scenario). It was concluded that the DSRSs disposal system would maintain environmental safety over a long-time. Moreover, the partition coefficient of Np in host rock, Darcy velocity in host rock, and density of the host rock were the most sensitive parameters in predicting exposure dose in the safety assessment.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.381.2-381
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• 2002

• Applied Chemistry for Engineering
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• v.16 no.6
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• pp.794-799
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• 2005

With the quantitative growth of the petroleum industry, the pipe facilities that connect each process increased significantly and the corresponding maintenance and repair costs of the pipe facilities increased as well. The diagnosis techniques to check a pipe efficiency while in operation are few in Korea, but in the advanced countries the pipe diagnosis using gramma-ray source was on-going research since 1960's. In this study, field experiments were performed to analyze the reasons for abnormal operation of the pipe connected to a distillation tower, and the degree of abnormality was estimated using a sealed gamma-ray source ($^{137}Cs$). Gamma radiation counts were measured by a detector (NaI) positioned outside the pipe-wall diametrically opposite to the gamma source. The results showed that a gas zone section's distribution pattern was different from the pattern of nearby fluid in a pipe. Th diagnosis technique using a gamma radiation source was proved to be an effective and reliable method, offering the information on the fluid distribution in pipe.

• Journal of the Korean Society for Nondestructive Testing
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• v.28 no.1
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• pp.25-32
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• 2008

[ $^{169}Yb$ ] industrial NDT sealed sources were developed by using $Yb_2O_3$ pellets as the target and demonstrated for their performance. To produce the pellets, optimal compacting and sintering conditions were determined experimentally. Source holders for $^{169}Yb$ were designed and fabricated. After assembling an active source produced from HANARO with the developed source holder, a demonstration experiment was performed to compare the quality of the radiographs from $^{192}Ir$ and soft X-rays. This demonstration study showed that the developed $^{169}Yb$ produced better radiographs than $^{192}Ir$ for a carbon steel with less than a 4 mm thickness.

• Journal of the Korean Society for Nondestructive Testing
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• v.26 no.3
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• pp.169-173
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• 2006

In-service diagnoses of pipeline facilities are important for a systematic maintenance of them. Field applications by using sealed gamma-ray sources $(^{60}Co,\;^{137}Cs)$ were performed to identify the heterogeneous zone in the pipelines of a distillation tower and a flare stack respectively. From the results, the heterogeneous zones in the pipelines were successfully identified. In the case of the pipeline connected to the distillation tower, a vapor pocket was detected in the fluid under hydrodynamic conditions, which could explain the reason for a decrease of the flow rate. In another case, an area with some amount of catalyst deposits was found at the bottom of the gas pipeline which was connected to the flare stack. And these findings provided important information for the process operators. Diagnosis technique by using gamma radiation sources has been proven to be an effective and reliable method for providing information on a media distribution in a facility.

• Proceedings of the Korean Institute of Building Construction Conference
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• 2016.10a
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• pp.109-110
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• 2016

This study is a absorbing Radon gas to occur indoor or outdoor. As a absorbent Radon gas, making cementless abso rbent matrix that accomplish experiment. In other to accomplish this experiment, Confirming Radon gas release ratio and accurating absorption, reduction of a half-life that 3,8 days from Radon gas source, we need to decide Radon absorbent experiment method. So, we accomplish to find Radon measurement method considering properties and a half-life that 3,8 days from Radon gas source. As the experimental factors, After stabilizing of Radon gas source and so on, we accomplish the experiment that is there or not and seal of Radon source.