• 대한방사선방어학회:학술대회논문집
• /
• 2011.04a
• /
• pp.178-179
• /
• 2011

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05d
• /
• pp.63-68
• /
• 1996

열형광 선량계(TLD)를 사용한 피부 선량평가는 베타선의 에너지를 구분함으로 정확히 평가된다. 이는 차폐체에 의한 감쇄효과를 이용하는 방법으로 본 논문에서는 7개의 두께가 다른 알루미늄 차폐체를 사용하였고, TLD로는 미국 Teledyne Isotopes사의 LiF$_{7}$ 선량계를 채택하였다. 비상 베타 선량계의 베타선에 대한 특성실험을 위해 한국 원자력연구소가 확보 하고 있는 PTB 표준선원인 $^{90}$ Sr/ $^{90}$ Y (E$_{max}$=2.27MeV, E$_{avg}$=0.8MeV), $^{204}$Tl(E$_{max}$=0.76MeV, E$_{avg}$=0.26MeV), $^{147}$ Pm (E$_{max}$= 0.225MeV, E$_{avg}$=0.06MeV)에 대한 조사를 하였다. 이런 결과로 비상 베타 선량계의 표준 베타선원에 대한 보정계수와 소자별 반응비를 구할 수 있었고, 이것을 이용하여 미지의 베타선원에 대하여 정확한 선량평가를 하기위한 알고리즘을 개발하였다.

• Nuclear Engineering and Technology
• /
• v.26 no.3
• /
• pp.381-388
• /
• 1994

Recently, the American National Standards Institute (ANSI) had made some changes in the radiation sources specified from those in the original performance test criteria ANSI N13. 11-1983. In case or beta category, in addition to the high-energy $^{90}$ Sr/$^{90}$ Y beta source, the $^{204}$ Tl source was added because many workplaces have significant levels of lower energy betas. In this study, the performance or the Teledyne PB-3 personnel dosimetry system in the fields of $^{204}$ Tl and $^{90}$ Sr/ $^{90}$ Y beta was investigated using the PTB beta secondary standard sources. The new beta correction function of PB-3 personnel dosimetry system for $^{204}$ Tl beta was also developed in this response experiment. The results show that the Teledyne PB-3 personnel dosimetry system is very effective for $^{90}$ Sr/ $^{90}$ Y beta dose assessment. In case of $^{204}$ Tl beta radiation, however, the results of simple performance test indicated that the use of beta correction factor(=2.088) which was recommanded by manufacturer may result in unexpectable overestimation of delivered dose by about 60%, while the use of developed beta correction function could measure the delivered doses in errors of 15%.

• Analytical Science and Technology
• /
• v.20 no.6
• /
• pp.460-467
• /
• 2007

Dose rate conversion factor was calculated to estimate the absorbed effective annual doses for soils for the beta-rays and gamma-rays, which were emitted from $^{238,235}U$, $^{232}Th$, and $^{40}K$ isotopes. The most recent data of the emitted energies per decay, half-lifes, and branching ratios, which were obtained from National Nuclear Data Center, were used. When this factor and the effective annual doses for the beta-rays and the gamma-rays of natural radioisotopes were compared with those of Aitken, these of $^{238}U$, $^{232}Th$ and $^{40}K$ are estimated to have good agreements but a large difference is shown in this for $^{235}U$. Through the calculations of effective annual doses by using these factor and the measurements of gamma-ray spectra for soils, which were extracted from prehistoric remains (Mansuri) on Osong, Chungchengbuk-do, The annual effective doses were obtained to be 3.8~5.9 mGy/yr. Also, when these doses including decay elements upper Rn were compared with those on all isotopes, the differences within 9~30 % were obtained. The analysis method of the annual effective doses for the beta-rays and the gamma-rays of the natural isotopes of soils was established by this dose rate conversion factor.

• Proceedings of the Korean Society of Medical Physics Conference
• /
• 2003.09a
• /
• pp.70-70
• /
• 2003

경피적관상동맥성형술(CPTCA)이나 스텐트삽입술 후에 발생하는 재협착을 방지하기 위한 방사선을 조사하는 방법 중에 베타 입자를 방출하는 액체 선원을 catheter풍선 내에 넣어 일정 시간 방사선 조사 시키는 방법이 있다. 조사시킬 혈관의 길이가 길어 한번의 방사선 조사가 어려울 경우 영역을 분할하여 두 번에 나누어 조사할 경우가 있다. 조사영역의 겹치는 부근의 흡수선량이 고선량이나 저선량이 되는가를 알기 위하여 두 풍선간의 접근 거리에 따른 혈관내벽의 흡수선량 분포를 알아보았다. 풍선내의 액체 선원은 Ho-l66을 이용하였고 Ho-l66의 물리적 반감기는 26.8시간이고 최대에너지 1.85 MeV, 평균에너지 0.69 MeV와 최대에너지 1.77 MeV, 평균에너지 0.65 MeV를 갖는 베타 입자를 방출한다. Ho-l66 의 방사선 흡수선량을 측정하기 위하여 GafChromic 필름(Nuclear Associates, Carle Place, NY, USA)을 이용하였고, 방사선이 조사된 필름의 optical density는 videodensitometer(Wellhofer, Schwarzen-bruck, Germany)를 이용하여 값을 읽었다. Catheter 풍선은 직경이 3 mm 이고 길이가 20 mm인 것을 이용하였다. 혈관 내벽의 최대 흡수선량을 표준화하여 겹치는 부분의 흡수선량 분포를 접근 거리에 따라 구하였다. 또한 몬테카를로 시abf레이션으로 확인하였다. 두 풍선의 겹치는 부근의 선량 분포는 풍선 중앙에서 중앙사이의 거리가 21 mm 일 때 중앙에서 20% 증가하였고, 거리가 22 mm일 때와 23 mm일 때 각각 10%와 40%의 감소를 보였다. 풍선 도자의 풍선 안에 베타입자 방출 액체 선원을 넣어 혈관내벽에 방사선 조사하는 방법은 비정거리가 짧아 혈관 내벽 부근에만 방사선을 조사시키고 그 외 중요 장기에는 영향을 덜 미치는 장점이 있다. 그러나 혈관 내벽 표면으로 부터의 거리에 따라 흡수선량이 급격히 떨어지는 분포를 이루기 때문에 두 개의 풍선이 겹치는 부근의 흡수선량은 아주 작은 접근 거리에서도 급격한 변화를 보였다. 따라서 시술 중에 겹치는 부분을 아주 적게 분할하여 정확하게 차례차례로 조사시키기 위해서는 신중한 거리 조정을 하여야 한다.

• Journal of Radiation Protection and Research
• /
• v.16 no.2
• /
• pp.17-26
• /
• 1991

Beta ray $(^{90}Sr+^{90}Y)$ absorbed dose at tissue surface was measured from the distance of 30cm by use of extrapolation chamber. In the measurement, following factors were considered: effective area of collecting electrode, polarity effect, ion recombination and window attenuation. The measured absorbed dose rate at tissue surface was $1.493{\mu}Gy/sec$ with ${\pm}2.9%$.

• Journal of Radiation Protection and Research
• /
• v.21 no.4
• /
• pp.255-262
• /
• 1996

This paper describes the results of intercomparison measurements of KAERI reference photon and beta radiation fields between the KAERI and the PNNL(Pacific Northwest National Laboratory), recently performed at KAERI radiation calibration and dosimetry laboratory on the basis of the ANSI N13.11 criteria for personal dosimeter performance test. Each laboratory used her own radiation detectors or measurement devices traceable to her national primary standard in measuring the exposure rates for photon fields, the absorbed dose rates for beta radiation fields. The agreements in reference radiation measurements between two laboratories were found to be less than ${\pm}2.0%$ for photon fields, ${\pm}1.0%$ for beta radiation fields. Therefore, it could be concluded that KAERI reference radiation fields comply well with the international standard and thus can further serve as a national basis for the researches and developments in radiation protection dosimetry in Korea.

• Progress in Medical Physics
• /
• v.3 no.2
• /
• pp.23-31
• /
• 1992

The thermally stimulated luminecence (Thermoluminescence:TL) of manufactured beta-eucryptite was studied for dose range of 200cGy-20000Gy. The TL spectrum from cesium irradiated beta-eucryptite was measured over the temperature range of 300K to 600K. The linearity of TL intensity vs irradiation dose is valid up to 50Gy and beyond higher dose supralinearity and saturation come out. At the dose of 2000Gy, the net number of supralinearity is maximum. The net amount of supralinearity form newly formed trapping center by photon irradiation and totally calculated TL intensity are accord with the experimental results except for the 50Gy range that supralinearity appears.

• Journal of Radiation Protection and Research
• /
• v.24 no.1
• /
• pp.39-43
• /
• 1999

Thermoluminescent (TL) response characteristics of a thin LiF:Mg,Cu,Na,Si Teflon detectors have been studied for use in beta radiation detection. The detectors were fabricated from a mixture of LiF:Mg,Cu,Na,Si phosphor and Teflon powder which was molded into a thin disk form of $50mg/cm^2$ thickness. These detectors were irradiated to beta fields of $^{147}Pm,\;^{204}Tl\;and\;^{90}Sr/^{90}Y$ sources with a covering of Kapton foil ($2mg/cm^2$) and photon irradiation was carried out with a $^{137}Cs$ source at the Korea Atomic Energy Research Institute (KAERI). Batch uniformity was estimated to be 4.7% and the beta dose response presented linear relationship from 0.1 mGy to 100 Gy. The beta energy responses of thin detectors normalized to $^{137}Cs$ were presented as 0.46, 1.09 and 1.06 for $^{147}Pm,\;^{204}Tl\;and\;^{90}Sr/^{90}Y$ beta rays, respectively. The evaluated values for angular responses were $0.93{\pm}0.03\;(^{147}Pm),\;0.94{\pm}0.04\;(^{204}Tl),\;and\;0.92{\pm}0.05\;(^{90}Sr/^{90}Y)$. The results satisfied well a proposed ISO Standard for beta ray dosimeters.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1995.05b
• /
• pp.895-898
• /
• 1995

베타선 흡수선량의 정밀측정에 사용되는 평판형전리함의 일종인 외삽형전리함(Extrapolation Chamber)으로 베타선 이온화전류의 정확한 측정을 위하여는 이온수집 단면적의 정화한 평가가 필요하다. 이를 위하여 표준 폴리축전기와 표준전압원을 이용한 충전용량 측정법으로 실제 유효 단면적을 구하였으며 측정결과는 기계적 측정치와 약 10.5%의 차이가 있음이 밝혀졌다.