• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.93-99
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• 2016

Background: Industrial X-ray CT system is normally applied to non-destructive testing (NDT) for industrial product made from metal. Furthermore there are some special CT systems, which have an ability to inspect nuclear fuel assemblies or rocket motors, using high power and high energy (more than 6 MeV) pulsed X-ray source. In these case, pulsed X-ray are produced by the electron linear accelerator, and a huge number of photons with a wide energy spectrum are produced within a very short period. Consequently, it is difficult to measure the X-ray energy spectrum for such accelerator-based X-ray sources using simple spectrometry. Due to this difficulty, unexpected images and artifacts which lead to incorrect density information and dimensions of specimens cannot be avoided in CT images. For getting highly precise CT images, it is important to know the precise energy spectrum of emitted X-rays. Materials and Methods: In order to realize it we investigated a new approach utilizing the Bayesian estimation method combined with an attenuation curve measurement using step shaped attenuation material. This method was validated by precise measurement of energy spectrum from a 1 MeV electron accelerator. In this study, to extend the applicable X-ray energy range we tried to measure energy spectra of X-ray sources from 6 and 9 MeV linear accelerators by using the recently developed method. Results and Discussion: In this study, an attenuation curves are measured by using a step-shaped attenuation materials of aluminum and steel individually, and the each X-ray spectrum is reconstructed from the measured attenuation curve by the spectrum type Bayesian estimation method. Conclusion: The obtained result shows good agreement with simulated spectra, and the presently developed technique is adaptable for high energy X-ray source more than 6 MeV.

• Nuclear Engineering and Technology
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• 제52권7호
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• pp.1495-1502
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• 2020

A new method of X-ray source spectrum estimation based on compressed sensing is proposed in this paper. The algorithm K-SVD is applied for sparse representation. Nonnegative constraints are added by modifying the L₁ reconstruction algorithm proposed by Rosset and Zhu. The estimation method is demonstrated on simulated spectra typical of mammography and CT. X-ray spectra are simulated with the Monte Carlo code Geant4. The proposed method is successfully applied to highly ill conditioned and under determined estimation problems with a good performance of suppressing noises. Results with acceptable accuracies (MSE < 5%) can be obtained with 10% Gaussian white noises added to the simulated experimental data. The biggest difference between the proposed method and the existing methods is that multiple prior knowledge of X-ray spectra can be included in one dictionary, which is meaningful for obtaining the true X-ray spectrum from the measurements.

• 한국방사선학회논문지
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• 제7권6호
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• pp.403-408
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• 2013

본 연구에서는 기존의 납을 대체할 수 있는 의료 방사선 차폐제품 적용을 위해 몬테카를로 시뮬레이션을 통해 바륨화합물의 두께별 차폐능을 모의 추정하였다. 차폐재 물질로는 황산바륨($BaSO_4$)을 이용하였고, 시편의 면적은 $15{\times}15cm^2$, 황산바륨의 밀도는 $4.5g/cm^3$, 납의 밀도 $11.34g/cm^3$를 적용하여 차폐재 시편의 두께를 0.1 mm부터 5 mm까지 시뮬레이션 하였다. 입력 선원은 연속 X-ray 에너지 스펙트럼(40 kVp ~ 120 kVp)에서 10kVp Step으로 시뮬레이션하였다. 40 kVp ~ 60 kVp에서의 흡수확률은 3 mm ~ 5 mm 두께에서는 납과 동일한 차폐능을 나타내었으나, 2 mm 이하에서는 차폐능이 기존 납 차폐재에 비해 다소 차폐능이 떨어지는 결과로 나타났다. 또한 70 kVp ~ 120 kVp 에너지 대역에서의 차폐능은 기존 납 차폐재와 유사한 성능을 보였지만, 0.5 mm 이하에서는 다소 낮은 차폐능으로 모의 추정되었다. 본 연구는 몬테카를로 시뮬레이션을 통해 의료용 엑스선 에너지 대역에 대한 두께 함수로써 바륨화합물의 차폐능을 추정하여 기존의 납과 비교 분석하였다. 또한 순수한 황산바륨의 의료용 방사선 차폐제품 적용가능성을 검증하고자 하였다. 그 결과 의료 방사선 에너지 대역 70 kVp ~ 120 kVp 에서 최소 2 mm 이상의 바륨화합물 두께에서 기존 납 1.5 mm 대비 95% 이상의 차폐효과가 있는 것으로 추정되었으며, 본 결과는 의료용 방사선 차폐제품의 경량화 제작에 기초 자료로 제공될 수 있을 것으로 사료된다.