• 한국전기전자재료학회:학술대회논문집
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• 한국전기전자재료학회 2002년도 추계학술대회 논문집 Vol.15
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• pp.375-378
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• 2002

There has recently been a great deal of interest in amorphous selenium for application of digital x-ray image sensor. The initial number of the electron-hole induced by interaction a-Se with x-ray photons and the collection efficiency to surface of generated charges are important parameters for x-ray sensitivity of the a-Se. Therefore, in this paper, we analyzed that thickness of a-Se film and electric field is affected on the initial number of electron-hole and the collection efficiency. The experimental value of x-ray induced charge about the various thickness and the electric field is compared with estimated absorbed energy through MCNP 4C code to analyze the mechanism x-ray induced signal of a-Se. The experimental results showed that the electric field depends on initial escape coefficient and the thickness depends on collection coefficient than escape efficient.

• 한국전기전자재료학회:학술대회논문집
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• 한국전기전자재료학회 2002년도 추계학술대회 논문집 Vol.15
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• pp.420-423
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• 2002

In recent years, there has been keen interest in developing f1at panel detectors for all modalities of radiology, including gerneral radiology, fluoroscopy(angiography and cardiology), electronic portal imaging, and mammography. In this paper, we report the new hybrid x-ray detector consisted of CsI(Tl) photoemission layer and a-Se photoconductor layer to resolve conventional x-ray detector such as the direct detector using a-Se and the indirect detector using CsI(Tl)/a-Si. To design the structure of CsI(Tl)/a-Se detector, the penetrated energy spectrum and absorption fraction was estimated using MCNP 4C code. Experimental results showed that the absorption fraction of $500{\mu}m-Se$ film and $150{\mu}m-CsI\left(Tl \right)/a-Se\left( 30{\mu}m \right)$ film is 70% at 70 kVp. The absorption energy is 90% at $350{\mu}m-CsI(Tl)$.

• 방사선산업학회지
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• 제17권4호
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• pp.443-449
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• 2023

KAERI(Korea Atomic Energy Research Institute) is conducting research and development of large-scale radiation generators and the latest radiation measuring instruments. In particular, research and development of security screening equipment using an electron beam accelerator and a neutron generator is in progress recently. Globally, 20 ft containers are used to transport imports and exports, and electron beam accelerators are radiation sources to measure the shape of the material inside the container during customs inspections in each country. KAERI is developing a device that can use an electron beam accelerator and a neutron generator sequentially to grasp the shape of various materials as well as the location of the internal target material. In this study, when using the neutron generator, the radiation dose and the degree of activation by neutron for the facility and surrounding environment, facility equipment were simulated using MCNP and FISPACT code. As a result, the shielding structures inside and outside the radiation control area were satisfactory to the reference level established conservatively based on the Korean Nuclear Act.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2006년도 제33회 추계학술대회 발표논문집
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• pp.67-67
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• 2006

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(2)
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• pp.931-936
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• 1995

서울시 중심부 300m 상공에서 약 22kT의 플루토늄 원폭이 폭발했을 때를 가정하고 폭발시 나오는 초기 방사선에 의한 선량을 계산하였다. 계산을 위하여 몬테칼로 코드인 MCNP4A를 이용하였으며 방사선의 위해도를 알아보기 위하여 선량당량으로 환산 하였다. 계산 결과 가까운 거리에서는 평균자유행로가 짧은 중성자에 의한 선량이 높게 나왔으나 거리가 멀어질수록 감마선에 의한 영향이 더 큰 것으로 나타났다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.33-38
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• 1997

Criticality experiments with fixed neutron poison plates for water moderated and reflected low enriched(2.35 and 4.31 wt%) UO$_2$fuel rod clusters were evaluated to validate calculation techniques employed in analyzing fuel shipping and storage systems having steel, boral, or cadmium shield. Measurements were obtained for both the 2.35 wt% and the 4.31 wt% enriched rods in square pitched, water flooded lattices. The critical experiments with the 2.35 wt% enriched rods consists of three 20$\chi$ 16 or 20$\chi$ 17 fuel cluster. Critical separation were used in the experiments with the 4.31 wt% enriched fuel rods. In the experiments, the poison plates were placed on both sides of the centrally located fuel cluster. Critical separation between the three sub-critical fuel clusters were then measured for varying plate thicknesses and distances of the plates to the center fuel cluster. Calculations were performed for thirty eight critical configuration using KENO-V. a and MCNP. All of the results were within 1.23% in $\Delta$k when individually compared with the critical value of 1.0. Discrepancies of the code results are probably due to uncertainties in experiments and/or analytical modeling experiments. In general, MCNP predictions were observed to be in best agreement with the experiments.

• Journal of Radiation Protection and Research
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• 제48권1호
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• pp.44-51
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• 2023

Background: Aptamers are currently being used in various fields including medical treatments due to their characteristics of selectively binding to specific molecules. Due to their special characteristics, the aptamers are expected to be used to remove radionuclides from a large amount of liquid radioactive waste generated during the decommissioning of nuclear power plants. The radiological effects on the aptamers should be evaluated to ensure their integrity for the application of a radionuclide removal technique. Materials and Methods: In this study, Monte Carlo N-Particle transport code version 6 (MCNP6) and Monte Carlo damage simulation (MCDS) codes were employed to evaluate the radiological effects on the aptamers. MCNP6 was used to evaluate the secondary electron spectrum and the absorbed dose in a medium. MCDS was used to calculate the DNA damage by using the secondary electron spectrum and the absorbed dose. Binding experiments were conducted to indirectly verify the results derived by MCNP6 and MCDS calculations. Results and Discussion: Damage yields of about 5.00×10^-4 were calculated for 100 bp aptamer due to the radiation dose of 1 Gy. In experiments with radioactive materials, the results that the removal rate of the radioactive ⁶⁰Co by the aptamer is the same with the non-radioactive ⁵⁹Co prove the accuracy of the previous DNA damage calculation. Conclusion: The evaluation results suggest that only very small fraction of significant number of the aptamers will be damaged by the radioactive materials in the liquid radioactive waste.

• 한국정보통신학회논문지
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• 제24권12호
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• pp.1704-1710
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• 2020

컨테이너 검색을 위해 사용되는 고에너지 X-선 영상획득용 검출기는 입사되는 고에너지 X-선을 효과적으로 획득하기 위하여 MeV X-선 수집이 충분히 수행될 수 있는 두께의 섬광체를 사용한다. 컨테이너 검색기에서는 섬광체에 입사되는 X-선의 에너지는 일반적으로 최대 9MeV의 X-선이 사용된다. 그러므로 고에너지 X-선 광자를 효과적으로 수집하기 위해서는 수 cm 두께의 섬광체가 이용되어야 하며 섬광체의 두께는 신호의 수집효율에 영향을 미치게 된다. 본 연구에서는 컨테이너 검색에 사용되는 CdWO4 섬광체와 소면적의 센서를 활용한 영상검출기의 설계조건에 대한 연구를 기술하고 있다. 이를 위하여 본연구에서는 섬광체의 적절한 두께와 섬광체 표면의 반사율에 따른 빛 수집효율을 계산하기 위하여 MCNP6와 DETECT2000을 활용하여 다양한 조건에서 X-선 거동과 빛의 거동에 대한 모사를 수행하였다. 빛 수집효율 계산결과 섬광체 표면의 반사율이 낮은 경우 대략 15 ~ 20mm 두께의 섬광체를 선정하는 것이 적합하였으나 반사율이 높아짐에 따라 대략 25 ~ 30mm 두께의 CdWO4 섬광체를 선정하는 것이 적합한 것으로 확인되었다.

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2387-2393
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• 2020

In this study, a gradient material for shielding neutrons and gamma rays was developed, which consists of epoxy resin, boron carbide (B₄C), lead (Pb) and a little graphene oxide. It aims light weight and compact, which will be applied on the transportable nuclear reactor. The material is made up of sixteen layers, and the thickness and components of each layer were designed by genetic algorithm (GA) combined with Monte Carlo N Particle Transport (MCNP). In the experiment, the viscosities of the epoxy at different temperatures were tested, and the settlement regularity of Pb particles and B₄C particles in the epoxy was simulated by matlab software. The material was manufactured at 25 ℃, the Pb C and O elements of which were also tested, and the result was compared with the outcome of the simulation. Finally, the material's shielding performance was simulated by MCNP and compared with the uniformity material's. The result shows that the shielding performance of gradient material is more effective than that of the uniformity material, and the difference is most noticeable when the materials are 30 cm thick.

• Journal of Radiation Protection and Research
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• 제21권1호
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• pp.17-25
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• 1996

본 연구에서는 사용 후 핵연료의 안전수송을 위한 수송용기의 설계/해석 항목 중 용기 내부에 장전한 핵연료에서 방출되는 중성자의 방사선량률을 효과적으로 평가하는 방법을 구축하기 위하여 수송용기의 방사선차폐해석을 기존의 해석 수행방법인 결정론적인 방법으로 수행하고 확률론적인 방법으로 그 결과를 검증하였다. 결정론적 방법을 이용한 해석코드로 Discrete Ordinate 방법의 DOT4.2 코드를 사용하였으며, 이에 대한 비교와 검증을 위한 확률론적 방법의 차폐해석 코드로는 Monte Carlo 해법의 해석코드인 MCNP4A을 이용하였다. 동일한 대상물에 대한 방사선량율에 대한 평가를 두 방법으로 수행한 결과 두 방법으로부터의 해석결과는 큰 차이를 보이지 않았다. 이 결과비교를 통하여 사용후 핵연료 수송용기에 대한 방사선량율 평가가 올바르게 수행된 것을 확인할 수 있었고 또한 설계 및 해석에 관한 품질보중사항이 규정된 10CFR71 appendixH의 설계해석 및 전산코드 검증에 따한 요구조건을 만족시킬 수 있었다.