• Nuclear Engineering and Technology
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• 제41권6호
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• pp.813-820
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• 2009

A rapid pneumatic transfer system (PTS) for an instrumental neutron activation analysis (INAA) is developed as an automatic irradiation facility involving the measurement of a short half-life nuclide and a delayed neutron counting system. Three new PTS designs with improved functions were constructed at the HANARO research reactor in 2006. The new system is composed of a manual system and an automatic system for both an INAA and a delayed neutron activation analysis (DNAA). The design and basic conception of a modified PTS are described, and the functions of system operation and control, radiation protection and emissions of radioactive gas are improved. In addition, a form of capsule transportation of these systems is tested. The experimental results pertaining to the irradiation characteristics with variation of the neutron flux and the temperature of the irradiation position with the irradiation time are presented, as is an analysis of the reference material for analytical quality control and uncertainty assessments.

• 대한환경공학회지
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• 제38권1호
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• pp.42-46
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• 2016

환경에 존재하는 인공방사성핵종 중 방사성요오드($^{131}I$)는 주로 갑상선질환의 치료에 사용되며 환자의 배출과정을 통해 체외로 방출된다. 붕괴가 채 끝나지 않은 $^{131}I$는 환경으로 방출되어 공공수역에서 검출될 수 있다. 본 연구는 공공수역에서 검출된 $^{131}I$ 방사능 결과의 정확도 및 신뢰도에 영향을 미치는 불확도 중 계측 과정에서 발생하는 불확도에 대하여 금강수계의 실제 사례를 조사하였다. 시료는 금강권역 삽교천 수계의 하천수 및 그 상류의 하수처리장 방류수를 대상으로 하였으며, 시료량에 따른 불확도를 확인하기 위하여 각 지점의 시료를 1, 10, 20 L로 채수하였다. 채취한 시료는 시료량에 따라 전 처리를 거친 후 1 L 마리넬리 비커에 충전하여 HPGe (High Purity Germanium) 감마선 검출기를 이용하여 10,000초 단위로 계측 분석하여 계측시간 및 방사능에 따른 측정불확도를 비교하였다. 각 지점의 방사능 농도는 0.03~1.8 Bq/L로, 채취시점에 따라 차이가 있는 것으로 나타났다. $^{131}I$의 방사능 농도가 0.3 Bq/L 수준인 경우 시료량이 1 L이면 약 80,000초 계측 시까지 핵종의 존재여부를 판단하지 못하는 경우가 발생하였으나, 같은 조건에서 시료량을 증가시켜 계측한 경우 10,000초 이상의 계측시간부터 불확도 10% 범위에 포함되는 것으로 나타났다. $^{131}I$의 짧은 반감기를 고려하여 즉시 계측이 가능한 1 L 생시료 계측 방법을 사용할 수 있으나, 불확도 수준과 전처리 및 계측에 소요되는 시간을 비교하였을 때, 10 L 시료의 계측을 통해 높은 신뢰도의 측정 결과를 얻을 수 있는 합리적인 방법이라고 판단되었다.

• Nuclear Engineering and Technology
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• 제40권4호
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• pp.299-304
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• 2008

A detection system was set up to measure the neutron generation rate of a recently developed D-D neutron generator. The system is composed of a Si detector, He-3 detector, and electronics for pulse height analysis. The neutron generation rate was measured by counting protons using the Si detector, and the data was crosschecked by counting neutrons with the He-3 detector. The efficiencies of the Si and He-3 detectors were calibrated independently by using a standard alpha particle source $^{241}Am$ and a bare isotopic neutron source $^{252}Cf$, respectively. The effect of the cross-sectional difference between the D(d,p)T and $D(d,n)^3He$ reactions was evaluated for the case of a thick target. The neutron generation rate was theoretically corrected for the anisotropic emission of protons and neutrons in the D-D reactions. The attenuations of neutron on the path to the He-3 detector by the target assembly and vacuum flange of the neutron generator were considered by the Monte Carlo method using the MCNP 4C2 code. As a result, the neutron generation rate based on the Si detector measurement was determined with a relative uncertainty of ${\pm}5%$, and the two rates measured by both detectors corroborated within 20%.

• Journal of Radiation Protection and Research
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• 제45권2호
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• pp.76-80
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• 2020

Background: To improve the measurement accuracy of liquid-scintillation counting for activity standardization, it is necessary to significantly reduce the background caused by thermal noise or after-pulses. We have therefore improved a movable 3 photomultiplier (3PM)-γ coincidence-counting method using the logical sum of three double coincidences for β events. Materials and Methods: We designed a new data-acquisition system in which β events are obtained by counting the logical sum of three double coincidences. The change in β-detection efficiency can be derived by moving three photomultiplier tubes sequentially from the liquid-scintillation vial. The validity of the method was investigated by activity measurement of ¹³⁴Cs calibrated at the Korea Research Institute of Standards and Science (KRISS) with 4π(PC)β-γ(NaI(Tl)) coincidence counting using a proportional counter (PC) for the β detector. Results and Discussion: Measurements were taken over 14 counting intervals for each liquidscintillation sample by displacing three photomultiplier tubes up to 45 mm from the sample. The dead time in each β- and γ-counting channel was adjusted to be a non-extending type of 20 ㎲. The background ranged about 1.2-3.3 s^-1, such that the contributions of thermal noise or after-pulses were negligible. As the β-detection unit was moved away from the sample, the β-detection efficiencies varied between 0.54 and 0.81. The result obtained by the method at the reference date was 396.3 ± 1.7 kBq/g. This is consistent with the KRISS-certified value of 396.0 ± 2.0 kBq/g within the uncertainty range. Conclusion: The movable 3PM-γ method developed in the present work not only succeeded in reducing background counts to negligible levels but enabled β-detection efficiency to be varied by a geometrical method to apply the efficiency extrapolation method. Compared with our earlier work shown in the study of Hwang et al. [2], the measurement accuracy has much improved. Consequently, the method developed in this study is an improved method suitable for activity standardization of β-γ emitters.

• Journal of Advanced Marine Engineering and Technology
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• 제15권5호
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• pp.23-29
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• 1991

Uncertainty is studied in the measurements of average packing density, thickness of packed spheres and transmittance in the experiments to study the effect of the bed height and the existence of the bed side walls on the transmittance of radiative energy through packed spheres. The packing density of the bed is obtained by counting the number of the spheres packed in three pipes with different heights. The bed height of the packed spheres is estimated from the number of spheres contained in the bed by using the relation between the bed height and the sphere number. The transmittance is obtained by dividing the intensity of the transmitted laser beam by the incoming-beam intensity. From the analysis, the uncertainity in the measurements of transmittance is shown to be less than 10.2%(95% coverage).

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2004년도 추계학술대회논문집
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• pp.685-688
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• 2004

This paper addresses the study on developing the angular vibration calibration system which requires the highly accurate measurement technique of the amplitude and period of an oscillating angular motion. Two developed models for the low and high frequency ranges are introduced and their main features are also compared. In addition to the angular vibration exciters, a new measurement method, referred to the 'equi-angle sampling method', is proposed and its theoretical backgrounds are introduced. The proposed method is shown to provide much less measurement uncertainty, compared the fringe counting method. Experimental results demonstrate what amount of angular vibration amplitude measurement uncertainty is improved by suing the proposed equi-angle sampling method.

• Journal of Radiation Protection and Research
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• 제23권4호
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• pp.237-242
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• 1998

생체나 공기 등 일반 환경시료의 방사성탄소 측정을 위한 액체섬광측정기술의 최적화에 연구의 목적을 두었다 일반 환경시료의 경우 $CO_2$ 직접흡수법을 적용하였으며, 이산화탄소 흡수제 Carbosorb $E^{TM}$와 섬광용액 Permafluor $V^{TM}$기 혼합비율을 1:1로 결정하였다. 이 20 ml 혼합용액에 포화 흡수되는 이산화탄소의 양은 평균 2.35 g 이며, 포집에 소요되는 시간은 약 40 분이었다 백그라운드 계수율은 1.88±0.06 cpm 이었으며, NIST 옥살산표준시료 측정결과 계측효율은 58.8±1.4 % 이었다. 이산화탄소 흡수량에 따른 계측효율을 보정하기 위하여 소광보정곡선을 구하였다. 자연준위 시료의 경우 4시간 계측시 비방사능 측정에 따른 전반적인 오차는 95 % 신뢰도상 약 7 %이었다. 이 측정방법에 대하여 2주 동안 시료의 안정성을 조사한 결과 계측효율과 백그라운드 계수율의 안정성을 의심할 만한 현상은 발견되지 않았다.

• Nuclear Engineering and Technology
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• 제36권2호
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• pp.121-126
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• 2004

3-PM liquid scintillation counting using the geometry-efficiency variation technique has been applied to the activity measurement of $^{204}T1$, which decays to $^{204}Hg\;and\;^{204}Pb\;by\;{\beta}^-$ and E.C., respectively. The TDCR values K have been derived over a wide range, 0.78 < K < 0.97, by displacing the detectors up to 50 mm away from an unquenched liquid scintillation sample $^{204}Tl$. The derived plots of the logic sums of double coincidences $N_D(K)$ very K vary linearly in the observed regions. The fractions of losses due to electron capture decay have been taken into account by employing a PENELOPE Monte Carlo simulation. The calibrated activity is 102.3 kBq at a reference date of July 1st, 2002 (UT) with a combined uncertainty of $0.63\%$. This is consistent with the value determined by means of the CIEMAT/NIST method at KRISS.

• 대한환경공학회지
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• 제30권11호
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• pp.1123-1131
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• 2008

본 연구는 대기 중 PM2.5의 미량금속 중 As을 중성자방사화분석법을 이용하여 분석할 때 발생되는 측정불확도를 ISO GUM 방법과 MCS 방법을 모두 적용하여 비교, 평가하였다. 불확도의 요인은 ISO GUM을 엄격하게 준용하여 파악하였으며 특정일에 채취된 PM2.5 내 As 농도에 대해 두 방법의 계산 결과가 4% 미만으로 크게 다르지 않는 것으로 나타났다. 연구기간 중 채취된 총 60개의 PM2.5 시료에 대해 As 농도의 확장불확도를 역시 MCS 방법을 이용하여 산출하였는데, 연구지역에서의 As의 개별 농도값에 대한 95% 신뢰구간의 확장불확도는 대부분 10%의 범위에서 존재하는 것으로 나타났다. 확장불확도에 대한 표준불확도 요인의 기여율은 계측통계오차(62.3%), 검출효율(18.5%), 시료 채취 시 유량(12.3%), flux 변동(2.3%), 특정감마선 방출률(1.8%) 등의 순으로 크게 나타났다.

• Nuclear Engineering and Technology
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• 제13권4호
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• pp.229-236
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• 1981

중성자포획 감마선 방사화분석법을 이용하여 원자로급 알루미늄중 붕소를 분석하였다. 실험에 의한 검출한계는 10% 불확실도의 경우 5.7ppm 이었다. 함량이 더욱 미량인 경우를 위하여 양이온 교환수지를 이용하며 알루미늄으로 부터 붕소를 사전분리하는 농축법을 개발하였다. 이 두 방법 즉 직접 측정하는 방법과 농축후 측정하는 두가지 방법의 정확도를 첨가법으로 조사하였다. 그 결과 5% 편차 이내에서 잘 일치하였다.