• Journal of Radiation Protection and Research
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• 제18권2호
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• pp.47-59
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• 1993

본 연구에서는 사용후핵 연료를 안전하게 수송할 수 있는 수송용기의 여러 가지 설계 항목중에 수송용기 내부에 장전한 핵연료에 의한 핵임계반응을 방지하기 위한 핵임계해석을 수행하였다. 핵임계 해석에 사용한 HANSEN-ROACH-KENO-Va 전산시스템에 대한 검증계산을 수행하였고 수송용기의 핵임계측면에서의 안전성을 확보하기 위해 가능한 보수적인 가정을 하여 어떠한 경우에도 수송용기에 장전된 핵연료가 임계상태에 도달하지 않도록 수송용기 내부의 구조 및 적절한 핵임계 방지제를 선택하였고 정상수송 및 가상사고 조건 등에 대한 해석을 수행하였다. 그 결과 KSC-7 수송용기 의 설계조건을 만족하고 핵임계측면에서의 안전성을 보장할 수 있는 재료 및 구조에 대한 결론을 해석적으로 도출하였다.

• Journal of Radiation Protection and Research
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• 제18권2호
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• pp.17-25
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• 1993

액체섬광 계수기에 대한 $^3H,\;^{14}C,\;^{36}Cl$의 베타선 스펙트럼의 시뮬레이션을 Monte Carlo 법으로 수행하였다. 베타선의 손실에너지는 'continuous slowing down approximation(CSDA)' 모형으로부터 구하였다. 순 베타방출 핵종이 균일하게 용해되어 있는 섬광용액은 $1.25cm{\times}3.5cm$의 원통형 geome try로 가정하였다. $^{14}C,\;^{36}Cl$에 대한 계산결과는 계수효율의 경우 실험 값과 2%의 범위 내에서 잘 일치하였으나 $^3H$에 대해서는 상당한 편차를 나타내었다. 이는 저 에너지 베타선에 대한 섬광용액 자체의 quenching 효과에 기인하는 것으로 판단된다.

• Journal of Radiation Protection and Research
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• 제29권3호
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• pp.157-163
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• 2004

원자력시설에서 만일의 방사성 물질의 누출이나 화학시설에서 독성물질의 누출시 오염물질의 환경 중 거동을 파악하기 위해서 대기확산 모형이 많이 이용된다. 대기확산 모형을 통한 환경 중 유해물질의 농도 예측에 대한 정확도를 높이기 위해서는 무엇보다 모형으로 입력되는 선원항에 대한 정확한 정보를 필요로 한다. 본 연구는 이러한 선원항 추정을 위하여 최소자승법을 적용하였다. 영광원자력 시설에서 실시된 추적자 확산실험 자료를 이용하여 가우시안 모형으로 계산한 값과 비교를 시도하였으며, 가우시안 모형으로 계산한 값들과 추적자 확산실험 결과 값들의 오차의 제곱이 최소가 되도록 선원항을 추정하였다. 추정한 선원항은 확산실험시 실제추적자 방출량의 1.24정도로 비교적 정확한 예측력을 나타내었다.

• Journal of Radiation Protection and Research
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• 제30권1호
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• pp.45-54
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• 2005

원자력시설로부터 삼중수소 사고 누출시 시설 주변 농작물의 삼중수소 오염 평가를 위한 동적격실모델 ECOREA-H3를 개발하였다. 모델의 격실은 크게 대기, 토양, 농작물로 구성되며 농작물은 엽채류 곡물류, 근군류의 3개 소그룹으로 분류하여 각각 독립적으로 모델링하였다. 벼에 대한 삼중수소 피폭실험 해석을 통해 모델의 예측 정확도가 조사되었다. 모델링 결과 추수시 벼이삭의 TFWT 농도는 입력데이터 중 공기의 절대습도, 뿌리흡수비 강우량에 OBT 농도는 공기의 절대습도, 이삭의 성장기간, 유기물의 수소함량의 영향을 상대적으로 크게 받는 것으로 나타났다. 벼이삭 OBT 농도에 대한 모델 계산과 실험 측정값은 잘 일치하였다.

• 대한전기학회논문지:전기기기및에너지변환시스템부문B
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• 제51권9호
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• pp.522-529
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• 2002

In this paper, computer simulations of the physical Phenomena occurring in the arc region before and after current zero were carried out to evaluate the thermal recovery characteristics of a Laval nozzle. A commercial CFD program "PHOENICS" is used for the simulation and the user-coded subroutines to consider the arcing phenomena were added to this program by the authors. The computed results were verified by the comparison with the test results presented by the research group of GE Co.(General Electric Company). In order to investigate the state of the arc region after current zero, the simulation was carried out with three steps. They are steady state arc simulation, transient arc simulation before current zero, and transient hot-gas flow simulation after current zero. The semi-experimental arc radiation model is adapted to consider the radiation energy transport and Prandtl's mixing length model is employed as the turbulence model. The electric field and the magnetic field were calculated with the same grid structure used for the simulation of the flow field. The post-arc current was calculated to evaluate the thermal recovery characteristics after current zero. Compared with the results obtained by GE Co., it has been found that the critical RRRV(ratio of rise of recovery voltage) will be determined previously by this study.his study.

• Journal of Radiation Protection and Research
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• 제4권1호
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• pp.1-4
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• 1979

중성자(中性子) 수송이론(輸送理論)을 써서 기사용(旣使用) 핵연료(核燃料) 저장조(貯藏槽)에 있는 한 개(個)의 PWR용(用) 핵연료집합체(核燃料集合體)에 대(對)한 유효증배계수(有效增倍係數)($k_{eff}$)를 산출(算出)하였다. 이때 중성자(中性子) 수송방정식(輸送方程式)을 Sn-근이법(近以法)이라고 부르는 각분해법(角分害法)(Discrete ordinates method)으로 풀어서 유효증배계수(有效增倍係數)를 구했으며 이것이 핵임계(核臨界) 안전성(安全性) 결정(決定)이 된다. 본(本) 연구(硏究)에서는 각(角)과 에너지를 각각(各各) 4구간(區間)과 16군(郡)으로 분할(分割)하고 공간구간(空間區間)은 27구간(區間)으로 나누되 상이(相異)한 물질(物質)의 경계면근처(境界面近處)에서 세분(細分)하였다. 이와같은 방법(方法)으로 구한 유효증배계수(有效增倍係數)는 0.6145였는 데 이는 타연구자(他硏究者)가 계산(計算)한 반무한배열(半無限配列) 핵연료집합체(核燃料集合體)에 대한 유효증배계수(有效增倍係數)에 비(比)하여 상당히 낮은 값이었다.

• 한국군사과학기술학회지
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• 제24권2호
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• pp.211-218
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• 2021

This paper deals with the computational work to characterize the formation and pinching of a plasma in an X-pinch configuration. A resistive magnetohydrodynamic model of a single fluid and two temperature is adopted assuming a hollow conical structure in the (r,z) domain. The model includes the thermodynamic parameter of tungsten from the corrected Thomas-Fermi EOS(equation of state), determining the average ionization charge, pressure, and internal energy. The transport coefficients, resistivity and thermal conductivity, are obtained by the corrected Lee & More model and a simple radiation loss rate by recombination process is considered in the simulation. The simulation demonstrated the formation of a core-corona plasma and intense compression process near the central region which agrees with the experimental observation in the X-pinch device at Seoul National University. In addition, it confirmed the increase in radiation loss rate with the density and temperature of the core plasma.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2586-2591
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• 2022

In the present work, we have irradiated the DI-BSCCO superconducting tapes with the 100 keV deuterium ions to investigate the effect of ion irradiation on their critical current (Ic). The damage simulations are carried out using the binary collision approximation method to get the spatial distribution and depth profile of the damage events in the high temperature superconducting (HTS) tape. The point defects are formed near the surface of the HTS tape. These point defects change the vortex profile in the superconducting tape. Due to the long-range interaction of vortices with each other, the Ic of the tape degrades at the 77 K and self magnetic field. The radiation dose of 2.90 MGy degrades the 44% critical current of the tape. The results of the displacement per atom (dpa) and dose deposited by the deuterium ions are used to fit an empirical relation for predicting the degradation of the Ic of the tape. We include the dpa, dose and columnar defect terms produced by the incident particles in the empirical relation. The fitted empirical relation predicts that light ion irradiation degrades the Ic in the DI-BSCCO tape at the self field. This empirical relation can also be used in neutron irradiation to predict the lifetime of the DI-BSCCO tape. The change in the Ic of the DI-BSCCO tape due to deuterium irradiation is compared with the other second-generation HTS tape irradiated with energetic radiation.

• Journal of Radiation Protection and Research
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• 제48권3호
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• pp.131-143
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• 2023

Background: This study examined the detection limit of thyroid screening monitoring conducted at the time of the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident in 2011 using a Monte Carlo simulation. Materials and Methods: We calculated the detection limit of a NaI(Tl) survey meter to measure ¹³¹I accumulation in the thyroid gland of children. Mathematical phantoms of 1- and 5-year-old children were developed in the simulation of the Particle and Heavy Ion Transport code System code. Contamination of the body surface with eight radionuclides found after the FDNPP accident was assumed to have been deposited on the neck and shoulder area. Results and Discussion: The detection limit was calculated as a function of ambient dose rate. In the case of 40 Bq/cm² contamination on the body surface of the neck, the present simulations showed that residual thyroid radioactivity corresponding to thyroid dose of 100 mSv can be detected within 21 days after intake at the ambient dose rate of 0.2 µSv/hr and within 11 days in the case of 2.0 µSv/hr. When a time constant of 10 seconds was used at the dose rate of 0.2 µSv/hr, the estimated survey meter output error was 5%. Evaluation of the effect of individual differences in the location of the thyroid gland confirmed that the measured value would decrease by approximately 6% for a height difference of ±1 cm and increase by approximately 65% for a depth of 1 cm. Conclusion: In the event of a nuclear disaster, simple measurements carried out using a NaI(Tl) scintillation survey meter remain effective for assessing ¹³¹I intake. However, it should be noted that the presence of short-half-life radioactive materials on the body surface affects the detection limit.

• Nuclear Engineering and Technology
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• 제56권9호
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• pp.3558-3565
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• 2024

The linear attenuation coefficients (LAC) of four soils (Black cotton (S1), Sandy (S2), Clay (S3), and Sandy (S4)) samples were measured at photon energies released from radioisotopes Co⁵⁷ (122 keV), Ba¹³³ (356 keV), ²²Na (511 and 1275 keV), Cs¹³⁷ (662 keV), Mn⁵⁴ (840 keV), and Co⁶⁰ (1330 keV) using a gamma spectrometer includes a NaI (Tl) scintillation detector. The experimental measurements were confirmed utilizing the Monte Carlo N-particle transport code. The linear attenuation coefficient values enhanced from 0.256 cm^-1 to 0.296 cm^-1 (at E_γ of 122 keV), from 0.126 cm^-1 to 0.142 cm^-1 (at E_γ of 662 keV), and from 0.0938 cm^-1 to 0.105 cm^-1 (at E_γ of 1275 keV), raising the (Fe + Mn) concentration from 0.912 wt% to 11.214 wt%, as well as raising the soil samples density from 1.62 g/cm³ to 1.79 g/cm³. The study also shows an enhancement in the half value thickness, transmission factor, radiation protection efficiency and lead's equivalent thickness due to the enrichment of Fe + Mn concentrations within the studied soils. The results show that the Black cotton soil exhibits better shielding properties for γ-ray than the other soils.