• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.386.1-386
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• 2002

• Bulletin of the Korean Chemical Society
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• 제27권10호
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• pp.1609-1612
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• 2006

The determination of the boron isotopic ratio in solutions was achieved by means of a solid state track detector by using an alpha track. The neutron flux was optimized by using a Cd-foil to find the optimum conditions for counting the number of alpha tracks on the selected solid detector caused by the (n, $\alpha$) nuclear reaction of boron. The home-made multi-dot detector plate was utilized in this study to increase the reproducibility of the measurement by uniformly drying the boron solution within the marked circle area on the detector plate. The experimental results of this study verified that the $^{11}B/^{10}B $ isotopic ratio can be measured by observing the number of alpha tracks for different concentrated standard solutions with various isotopic compositions. This technique was applied to the determination of $^{10}B$ enrichment factor in a biological sample for a boron neutron capture therapy.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 추계학술발표회요약집
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• pp.325-325
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• 1998

• Nuclear Engineering and Technology
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• 제37권4호
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• pp.395-400
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• 2005

An environmental radon monitoring system, comprising a radon-cup, an etching system, and a track counting system, was constructed. The radon cup is a cylindrical chamber with a radius of 2.2 cm and a height of 3.2 cm in combination with a CR-39 detector. Carbon is impregnated in the bodies of the detector chamber to avoid problem of an electrostatic charge. The optimized etching condition for the CR-39 exposed to a radon environment turned out to be a 6 N NaOH solution at 70^{\circ}$ over a 7hour period. The bulk etch rate under the optimized condition was $1.14{\pm}0.03\;{\mu}m\;h^{-1}$. The diameter of the tracks caused by radon and its progeny were found to be in the range of $10\~25\;{\mu}m$ under the optimized condition. The track images were observed with a track counting system, which consisted of an optical microscope, a color charged couple device (CCD) camera, and an image processor. The calibration factor of this system is obtained to be $0.105{\pm}0.006$ tracks $cm^2$ per Bq $m^{-3}$ d.

• Journal of Radiation Protection and Research
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• 제2권1호
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• pp.1-8
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• 1977

중성자(中性子) 선량(線量) 측정목적(測定目的)으로 사용(使用)할 Posi필름 고체비적검출기(固體飛跡檢出器)의 알파입자(粒子) 비적검출(飛跡檢出) 효율(效率)과 화학부식(化學腐蝕)에 의(依)한 그의 비적형성(飛跡形成) 최적조건(最適條件)을 실험적(實驗的)으로 결정(決定)하였다. $^{10}B$ 및 $^{27}Al$박(箔)과 posi 필름 고체비적검출기(固體飛跡檢出器)로 이루어진 중성자(中性子) 선량계(線量計)를 제작(製作)하고 이것에 의(依)한 중성자(中性子) 선속밀도(線束密度) 및 선량(線量)의 측정범위등(測定範圍等)을 실험결과(實驗結果)와 이론적(理論的)인 근거하(根據下)에서 산출(算出)하였다. 그 결과(結果) posi 필름 고체비적검출기(固體飛跡檢出器)는 핵분열성(核分裂性) 물질(物質)을 입자방출체(粒子放出體)로 병용(倂用)함이 없이 중성자(中性子) 측정(測定)에 효과적(效果的)으로 응용(應用)될 수 있음이 판명(判明)되었다.

• 한국의학물리학회지:의학물리
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• 제13권1호
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• pp.51-53
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• 2002

The results of the measured specific activities of Rn-222 in sewerage and drinking water of Ulaanbaatar City, Mongolia using the HP-Ge gamma-spectrometer, solid state nuclear track detector and liquid scintillator, are compared. The specific radioactivity for the Rn-222 in water of Ulaanbaatar City ranged 10-250 Bk/l, with an average of 110 Bk/l.

• Nuclear Engineering and Technology
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• 제5권4호
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• pp.334-338
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• 1973

$^{232}$ Th 핵분열 물질과 조합된 고체비적검출체를 사용하여 250kw로 정상운전되는 TRIGA Mark-II 원자로의 대차폐수조내에서 열중성자주(thermalizing column)의 중심으로부터 수평방향의 속 중성자 선속밀도 분포를 추정하였다. 속 중성자 스펙트럼이 $^{235}$ U가 열 중성자에 의하여 핵분열이 일어날매 방출되는 중성자 스펙트럼과 같다는 가정을 한 다음, 선속밀도는 고쳬비적검출체로 얻어진 실험 결과로부터 계산되었다. 이와 같은 방법으로 속 중성자 설속밀도 분포의 측정 결과는 도표로서 제시된다.

• Nuclear Engineering and Technology
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• 제38권4호
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• pp.353-358
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• 2006

Alpha track analysis for the determination of the trace amount of alpha emitting nuclides in a very small particle was performed as an efficient and powerful technique during safeguard inspection. Metal particles with well-defined spherical shape, size and isotopic compositions as a reference material were used to correlate the number of tracks or track diameter with an isotopic composition eventually to identify the uranium enrichment in the environmental swipe samples. Slopes in the number of tracks versus the exposure time curve provide a simple insight into the uranium enrichment of an unknown particle. Low enriched uranium metal particles result in slopes still steeper than the depleted or natural uranium metal particles. In addition, a linear relationship between track diameter and particle size Is thought to be a useful first stage analytical tool as an efficient and convenient inspection guide. The significance of the simple linear model was also judged using the usual statistical tests.

• 분석과학
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• 제17권1호
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• pp.8-15
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• 2004

수용액 시료에 포함된 미량의 보론 함량을 분석하는데 적합한 고체트랙 검출기를 선정하기 위하여 알파복합선원 등을 이용하여 검출능력을 비교 검토하였다. 보론의 알파트랙 검출에는 polycarbonate 재질(Lexan 및 CR-39)과 cellulose nitrate 재질(CN-85 및 LR-115))의 고체트랙 검출기를 사용하였다. 알파입자 방출물질로는 복합알파선원, 금속 우라늄 입자 및 보론 표준용액을 사용하였다. 본 연구에서는 에칭조건 및 중성자 조사조건 등에 따른 검출기의 특성을 비교하였으며, 실험 결과 보론 정량에는 CN-85 검출기가 가장 적합한 것을 알 수 있었다. 또한, 선정된 검출기를 이용하여 수용액 매질에 포함된 미량의 보론을 알파트랙 기입방법으로 측정한 실험결과에 대해 검토하였다.

• Nuclear Engineering and Technology
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• 제49권4호
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• pp.881-885
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• 2017

This work presents a new technique for discriminating between alpha particles of different energy levels. In a first study, two groups of alpha particles emitted from radium-226 and americium-241 sources were successfully separated using a CR-39 microfilm of appropriate thickness. This thickness was adjusted by chemical etching before and after irradiation so that lower-energy particles were stopped within the detector, while higher-energy particles were revealed on the back side of the detector. The number of tracks on the front side of the microfilm represented all alpha particles incident on that side from the two sources. However, the number of tracks on the back side of the microfilm represented only the long-range alpha particles of higher energy that arrived at that side. Therefore, by subtracting the number of tracks on the back side from the number of tracks on the front side, one could easily determine the number of tracks for the short-range alpha particles of lower energy that remained embedded in the microfilm. Discrimination of the two energy levels is thus achieved in a simple, fast, and reliable process.