• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1995년도 추계학술발표회논문집(2)
• /
• pp.847-852
• /
• 1995

A shielding analysis for KSC-7, the shipping cask for transporting the 7 PWR spent fuel assemblies, has been carried out. Radiation source term has been calculated on spent fuel with burnup of 50,000 MWD/MTU and 1.5 years cooling time by ORIGEN2 code. The shielding calculation for the cask has been made by using MCNP4A code with continuous cross section data library from ENDF/B-V. As a result of neutron dose rate analysis, another shielding calculational model on spent fuel shipping cask was provided which is using the Monte Carlo method.

• 대기
• /
• 제29권5호
• /
• pp.537-550
• /
• 2019

To analyze the observation environment of solar radiation stations operated by the Korea Meteorological Administration (KMA), we analyzed the skyline, Sky View Factor (SVF), and solar radiation due to the surrounding topography and artificial structures using a Digital Elevation Model (DEM), 3D camera, and solar radiation model. Solar energy shielding of 25 km around the station was analyzed using 10 m resolution DEM data and the skyline elevation and SVF were analyzed by the surrounding environment using the image captured by the 3D camera. The solar radiation model was used to assess the contribution of the environment to solar radiation. Because the skyline elevation retrieved from the DEM is different from the actual environment, it is compared with the results obtained from the 3D camera. From the skyline and SVF calculations, it was observed that some stations were shielded by the surrounding environment at sunrise and sunset. The topographic effect of 3D camera is therefore more than 20 times higher than that of DEM throughout the year for monthly accumulated solar radiation. Due to relatively low solar radiation in winter, the solar radiation shielding is large in winter. Also, for the annual accumulated solar radiation, the difference of the global solar radiation calculated using the 3D camera was 176.70 MJ (solar radiation with 7 days; suppose daily accumulated solar radiation 26 MJ) on an average and a maximum of 439.90 MJ (solar radiation with 17.5 days).

• Nuclear Engineering and Technology
• /
• 제2권3호
• /
• pp.149-161
• /
• 1970

국내에서 산출되는 광물골재를 사용하여 방사선 차폐용 중차폐 콘크리트를 제조하고 감마선에 대한 차폐효능을 규명하는 동시에 방사선 차폐체로서의 활용가능성을 검토하였다. 10여종의 각기 다른 광물골재를 수집하여 방사선 차폐용 골재로서의 사용타당성을 검토하기 위한 물리시험과 화학분석이 실시되었고 이 결과를 토대로 최적한 골재를 선택하여 중차폐 콘크리트가 제조되었다. 차폐용 콘크리트를 제조하는데 골재의 배합비, 물-세멘트 비율, 세골재, 조골재 비율 등을 달리해주므로써 방사선 차폐효과가 달라지는 현상을 실험적으로 구해 보았고 그 결과 차폐체의 비중이 높고 균질성이 좋은 중차폐체의 설계 조건을 유도해 낼수 있었다. 각기 다른 중차폐체에 대한 차폐효능 실험은 60Co 감마선원을 사용한 방사선 투과시험법으로 구했다. 실험을 통하여 중차폐체에 대한 방사선 차폐능과 차폐콘크리트의 비중, 차폐가격등을 분석하므로써 차폐설계상 최적의 공간배치로서 가장 경제적으로 차폐치를 설계할 수 있는 최적의 조건을 얻을 수 있었다.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 2002년도 추계학술발표회요약집
• /
• pp.310.2-310
• /
• 2002

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 2003년도 추계학술발표대회 요약집
• /
• pp.446.2-446.2
• /
• 2003

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2018년도 추계학술논문요약집
• /
• pp.480-481
• /
• 2018

• 한국인터넷방송통신학회논문지
• /
• 제19권3호
• /
• pp.59-65
• /
• 2019

마그네틱 프로브와 노이즈 소스의 근거리장에 금속 차폐막이 놓여있을 때 차폐막 두께에 따른 EMI 차폐효과를 분석하였다. 노이즈 소스로는 마이크로스트립 라인을 이용하였으며, 금속 차폐막 재료로는 그래파이트와 페라이트를 선정하였다. 마그네틱 프로브는 IEC 61967-6 방식을 적용하여 마그네틱 프로브를 이용한 전자기 방사 측정 방법을 사용하였다. 마이크로스트립 라인과 마그네틱 프로브 사이의 투과계수를 분석하였고, 둘 사이의 거리는 단일 차폐막일 경우 1 mm, 다중 차폐막일 경우 5 mm로 수행하였다. 차폐막의 두께는 5 um, 10 um, 30 um, 50 um 으로 변화시켰다. 주파수를 150 kHz에서 1 GHz까지 변화시켰을 경우 최대 44.9 dB의 SE(Shielding Effectiveness)를 얻었다.

• Nuclear Engineering and Technology
• /
• 제50권6호
• /
• pp.957-962
• /
• 2018

The gamma radiation shielding capability (GRSC) of two clay-materials (Ball clay and Kaolin)of Southwestern Nigeria ($7.49^{\circ}N$, $4.55^{\circ}E$) have been investigated by determine theoretically and experimentally the mass attenuation coefficient, ${\mu}/{\rho}(cm^2g^{-1})$ of the clay materials at photon energies of 609.31, 1120.29, 1173.20, 1238.11, 1332.50 and 1764.49 keV emitted from $^{214}Bi$ ore and $^{60}Co$ point source. The mass attenuation coefficients were theoretically evaluated using the elemental compositions of the clay-materials obtained by Particle-Induced X-ray Emission (PIXE) elemental analysis technique as input data for WinXCom software. While gamma ray transmission experiment using Hyper Pure Germanium (HPGe) spectrometer detector to experimentally determine the mass attenuation coefficients, ${\mu}/{\rho}(cm^2g^{-1})$ of the samples. The experimental results are in good agreement with the theoretical calculations of WinXCom software. Linear attenuation coefficient (${\mu}$), half value layer (HVL) and mean free path (MFP) were also evaluated using the obtained ${\mu}/{\rho}$ values for the investigated samples. The GRSC of the selected clay-materials have been compared with other studied shielding materials. The cognizance of various factors such as availability, thermo-chemical stability and water retaining ability by the clay-samples can be analyzed for efficacy of the material for their GRSC.

• 한국방사선학회논문지
• /
• 제15권7호
• /
• pp.957-964
• /
• 2021

PET/CT 검사 시 사용되는 F-18은 양전자를 방출하는 방사성동위원소이며, 높은 에너지의 소멸감마선과 베타선은 방사선작업종사자의 피폭을 초래하는 원인이 된다. 본 연구에서는 핵의학과에서 근무하는 방사선작업종사자의 피폭선량 저감방안의 일환으로, F-18에 대한 Apron의 낮은 차폐 효율의 원인을 규명하고, 아크릴로 이중 차폐한 Apron의 실효성을 평가하였다. L-Block, Apron+아크릴, Apron, 아크릴+Apron, 아크릴 다섯 개의 차폐체를 이용하여 선량을 측정하고, 몬테카를로 시뮬레이션을 수행하여 경향성을 비교하였다. 그 결과, 아크릴로 이중 차폐한 Apron의 차폐율이 Apron 단독 차폐한 경우보다 약 4~8% 높은 차폐효과가 있는 것으로 나타났다. 사용자의 활동성에 크게 영향이 가지 않는 범위 안에서 적절한 두께의 아크릴로 이중 차폐한 개인방호복은 방사선 작업종사자의 피폭저감화에 도움을 줄 수 있을 것이다.

• Journal of Radiation Protection and Research
• /
• 제43권4호
• /
• pp.154-159
• /
• 2018

Background: To prevent small leakage accidents, a real-time and direct detection system for small leaks with a detection limit below that of existing systems, e.g. $0.5gpm{\cdot}hr^{-1}$, is required. In this study, a small-size beta detector, which can be installed inside the reactor containment (CT) building and detect small leaks directly, was suggested and its feasibility was evaluated using MCNPX simulation. Materials and Methods: A target nuclide was selected through analysis of radiation from radionuclides in the reactor coolant system (RCS) and the spectrum was obtained via a silicon detector simulated in MCNPX. A window was designed to reduce the background signal caused by other nuclides. The sensitivity of the detector was also estimated, and its shielding designed for installation inside the reactor CT. Results and Discussion: The beta and gamma spectrum of the silicon detector showed a negligible gamma signal but it also contained an undesired peak at 0.22 MeV due to other nuclides, not the $^{16}N$ target nuclide. Window to remove the peak was derived as 0.4 mm for beryllium. The sensitivity of silicon beta detector with a beryllium window of 1.7 mm thickness was derived as $5.172{\times}10^{-6}{\mu}Ci{\cdot}cc^{-1}$. In addition, the specification of the shielding was evaluated through simulations, and the results showed that the integrity of the silicon detector can be maintained with lead shielding of 3 cm (<15 kg). This is a very small amount compared to the specifications of the lead shielding (600 kg) required for installation of $^{16}N$ gamma detector in inside reactor CT, it was determined that beta detector would have a distinct advantage in terms of miniaturization. Conclusion: The feasibility of the beta detector was evaluated for installation inside the reactor CT to detect small leaks below $0.5gpm{\cdot}hr^{-1}$. In future, the design will be optimized on specific data.