• Journal of Radiation Protection and Research
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• 제42권1호
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• pp.16-20
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• 2017

Background: The design of deuteron accelerator neutron source facilities requires reliable yield estimation of gamma-rays as well as neutrons from deuteron-induced reactions. We have so foar measured systematically double-differential thick target neutron yields (DDTTNYs) for carbon, aluminum, titanium, copper, niobium, and SUS304 targets. In the neutron data analysis, the events of gamma-rays taken simultaneously were treated as backgrounds. In the present work, we have re-analyzed the experimental data for a thick carbon target with particular attention to gamma-ray events. Materials and Methods: Double-differential thick target gamma-ray yields from carbon irradiated by 5 and 9 MeV deuterons were measured using an NE213 liquid organic scintillator at the Kyushu University Tandem accelerator Laboratory. The gamma-ray energy spectra were obtained by an unfolding method using FORIST code. The response functions of the NE213 detector were calculated by EGS5 incorporated in PHITS code. Results and Discussion: The measured gamma-ray spectra show some pronounced peaks corresponding to gamma-ray transitions between discrete levels in residual nuclei, and the measured angular distributions are almost isotropic for both the incident energies. Conclusion: PHITS calculations using INCL, GEM, and EBITEM models reproduce the spectral shapes and the angular distributions generally well, although they underestimate the absolute gamma-ray yields by about 20%.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1763-1774
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• 2023

In this study, a series of flexible neutron/gamma shielding composites are fabricated through the doping of Gd₂O₃ into the matrix of SEBS with (M_Gd2O3: M_SEBS) % from 5% to 100%. Neutron transmittance test shows an exponential attenuation with the increase of areal density of Gd, in which the transmittance T ranges from 59.1440% to 35.3026%, with standard deviation less than 2.2743%, mass attenuation coefficient 𝜇_m from 0.3194 cm²/g to 0.4999 cm²/g, and half value layer-HVL value from 2.4530 mm to 1.1313 mm. Shielding efficiency of the Gd₂O₃/SEBS composites is basically improved in comparison with that of B₄C/SEBS. The transmittance T, mass/linear attenuation coefficient 𝜇_m and 𝜇, HVL and effective atomic number Z_eff for the shielding of γ rays (39 keV, 59 keV and 122 keV) are measured and calculated with XCOM as well as MCX programs. Finally, plots of the three dimensional relationships between transmittance, doping amount and thickness are provided to the guidance for engineering shielding design. In summary, the Gd₂O₃/SEBS composite is proved to be an effective flexible neutron/low energy γ rays shielding material, which could be of potential applications in the field of nuclear technology and nuclear engineering.

• Nuclear Engineering and Technology
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• 제13권3호
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• pp.161-167
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• 1981

자주달개비(Tradescantia) BNL clone 4430을 본 연구소 감마농장(${\gamma}$-field)에 거리별로 배치하고 ${\gamma}$-선을 3.6mR/day~182R/day의 선량율로 완조사시켜, 이 식물의 수술털에 나타나는 분홍색 체세포돌연변이를 대상으로 돌연변이의 출현율을 조사하는 한편 화기에 미치는 형태변화를 조사하였다. 분홍색 체세포돌연변이율은 22.2R/day의 선량율에서 수술털 1,000개당 85.81$\pm$6.45개로 가장 높았고, 이보다 높은 선량율에서는 오히려 변이율이 감소하여 포화선량효과를 초래하였다. 또한 3.6mR/day의 낮은 선량율체서도 이 체세포돌연변이율이 자연돌연변이율보다 증가하였음을 볼 수 있었으며 비교적 낮은 선량율 조사에서는 꽃, 수술, 수술털등의 형태적 변화가 없이 돌연 변이율만의 증가를 볼수가 있어 감마농장내에서 과수나 화목등 영년식물에 저선량의 완조사를 통해 체세포돌연변이의 유기가 가능할것으로 보이며, 한편 이 식물의 특성을 이용하여 저위 방사선에 의한 유전적변화를 탐지하는데에도 적절한 수단이 될 것 같다.

• 한국방사선학회논문지
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• 제12권1호
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• pp.1-7
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• 2018

$^{68}Ga$ 방사성 핵종은 $^{68}Ge/^{68}Ga$ 제너레이터에서 생산되는 양전자 방출핵종으로서 PET 검사에 이용되는 방사성 핵종이다. $^{68}Ga$은 67.8분의 반감기를 가지고 88.9 %의 ${\beta}$+ 붕괴와 11.1 %의 전자포획으로 $^{68}Zn$으로 붕괴된다. ${\beta}$+ 붕괴 과정에서 87.7 %는 기저상태의 $^{68}Zn$로 붕괴되며, 1.2 %는 여기상태의 $^{68}Zn$로 붕괴된다. 여기상태의 $^{68}Zn$은 1.077 Mev의 ${\gamma}$선을 방출하며 기저상태의 $^{68}Zn$가 된다. 이때 방출되는 1.077 Mev의 ${\gamma}$선을 Prompt Gamma라 하며, Prompt Gamma-ray가 환자와 상호작용하게 되면 저에너지 ${\gamma}$선의 산란선이 발생되게 되는데 이 산란선이 PET의 동시계수 회로에 검출되어 질 수 있다. 이 연구의 목적은 $^{68}Ga$을 이용하는 PET검사 중 신경내분비 종양진단에 사용되는 $^{68}Ga$-DOTATOC PET/CT영상에 Prompt Gamma-ray 보정 전 후의 표준섭취계수(SUV)를 평가해 보고자 하였다. $^{68}Ga$-DOTATOC PET/CT를 시행한 15명의 환자에 대해서 병변부위(Pancreas, Liver, Thoracic Spine, Brain)와 정상으로 섭취되는 조직(Pituitary, Lung, Liver, Spleen, Kidney, Intestine)의 SUVmax와 SUVmean을 비교하였으며, 임상영상의 정량적 평가를 위해 Target to Background Ratio(TBR)을 산출하여 비교하였다. Prompt Gamma-ray 보정 후 Thoracic Spine을 제외한 병변부위와 Pituitary를 제외한 정상조직에서 SUVmax, SUVmean은 높은 값을 나타내었으며, TBR은 Prompt Gamma-ray 보정 전 후 각각 $51.51{\pm}49.28$, $55.50{\pm}53.12$로 보정 후 높은 값을 나타냈다. (p<0.0001)

• 대한방사선치료학회지
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• 제4권1호
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• pp.12-16
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• 1990

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.539-540
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• 2018

• Journal of Astronomy and Space Sciences
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• 제30권2호
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• pp.91-94
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• 2013

We use the outer gap model to explain the spectrum and the energy dependent light curves of the X-ray and soft ${\gamma}$-ray radiations of the spin-down powered pulsar PSR B1509-58. In the outer gap model, most pairs inside the gap are created around the null charge surface and the gap's electric field separates the opposite charges to move in opposite directions. Consequently, the region from the null charge surface to the light cylinder is dominated by the outflow current and that from the null charge surface to the star is dominated by the inflow current. We suggest that the viewing angle of PSR B1509-58 only receives the inflow radiation. The incoming curvature photons are converted to pairs by the strong magnetic field of the star. The X-rays and soft ${\gamma}$-rays of PSR B1509-58 result from the synchrotron radiation of these pairs. The magnetic pair creation requires a large pitch angle, which makes the pulse profile of the synchrotron radiation distinct from that of the curvature radiation. We carefully trace the pulse profiles of the synchrotron radiation with different pitch angles. We find that the differences between the light curves of different energy bands are due to the different pitch angles of the secondary pairs, and the second peak appearing at E > 10 MeV comes from the region near the star, where the stronger magnetic field allows the pair creation to happen with a smaller pitch angle.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.328-332
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• 2016

Background: Boron Neutron Capture Therapy (BNCT) is a new radiation therapy. In BNCT, there exists some very critical problems that should be solved. One of the severest problems is that the treatment effect cannot be known during BNCT in real time. We are now developing a SPECT (single photon emission computed tomography) system (BNCT-SPECT), with a cadmium telluride (CdTe) semiconductor detector. BNCT-SPECT can obtain the BNCT treatment effect by measuring 478 keV gamma-rays emitted from the excited state of $^7Li$ nucleus created by $^{10}B(n,{\alpha})$ $^7Li$ reaction. In the previous studies, we investigated the feasibility of the BNCT-SPECT system. As a result, the S/N ratio did not meet the criterion of S/N > 1 because deterioration of the S/N ratio occurred caused by the influence of Compton scattering especially due to capture gamma-rays of hydrogen. Materials and Methods: We thus produced an arrayed detector with two CdTe crystals to test cross talk phenomenon and to examine an anti-coincidence detection possibility. For more precise analysis for the anti-coincidence detection, we designed and made a collimator having a similar performance to the real BNCT-SPECT. Results and Discussion: We carried out experiments with the collimator to examine the effect of cross talk of scattering gamma-rays between CdTe elements more practically. As a result of measurement the coincidence events were successfully extracted. Conclusion: We are now planning to carry out evaluation of coincidence rate from the measurement and comparison of it with the numerical calculations.

• Elastomers and Composites
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• 제33권4호
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• pp.238-245
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• 1998

이 논문은 원자력발전소에서 사용되고 있는 부분적으로 방사선 조사된 EPR 전력 케이블의 방사선 절연열화 진단을 행하기 위해서 전기특성을 조사한 것이다. 본 연구에서는 방사선 조사량을 100Mrad부터 200Mrad까지 증가시킨 케이블 시료를 열화비율에 따른 방사선 조사량에 의한 충전전류 및 방전전류를 측정한 결과 $4.3{\times}10^{-9}$(A)로부터 $1.03{\times}10^{-7}$(A)로 증가함을 알 수 있었다. 또한 100% 일때의 충전전류 및 방전전류를 50%, 16.7% 일때를 비교하면 후자의 케이블은 열화된 부분의 길이가 1/2, 1/6로 되므로 충전전류 및 방전전류로 1/2, 1/6로 흐름을 알 수 있었다. 열화하지 않은 22m와 66m의 케이블을 조사한 결과 66m의 케이블 시료쪽이 충전전류 및 방전전류 값이 22m 케이블보다 3배나 크다는 것을 확인했다. 이들 결과로부터 방사선을 조사한 EPR 케이블의 절연열화 진단법으로 충전전류 및 방전전류를 측정하는 것이 가능하다는 것을 확인했다.

• Journal of Radiation Protection and Research
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• 제6권1호
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• pp.8-24
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• 1981

This paper presents flux-to-dose-rate conversion factors for neutrons and gamma rays based on the American National Standard Institute(ANSI) N666. These data are used to calculated the dose rate distribution of neutron and gamma ray in radiation fields. Neutron flux-to-dose-rate conversion factors for energies from $2.5{\times}10^{-8}$ to 20 MeV are presented; the corresponding energy range for gamma rays is 0.01 to 15 MeV. Flux-to-dose-rate conversion factors were calculated, under the assumption that radiation energy distribution has nonlinearity in the phantom, have different meaning from those values obtained by monoetiergetic radiation. Especially, these values were determined with the cross section library. The flux-to-dose-rate conversion factors obtained in this work were in a good agreement to the values presented by ANSI. Those data will be a useful for the radiation shielding analysis and the radiation dosimetry in the case of continuous energy distributions.