• Journal of Radiation Protection and Research
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• 제37권3호
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• pp.138-145
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• 2012

국내에서는 2010년 말 기준으로 21기의 원전이 운전 중에 있다. 이에 따라 원전에서 배출되는 방사성유출물은 지속적으로 늘어나 2010년에는 547.12 TBq이 배출되었다. 국내원전의 기체와 액체 방사성유출물 배출량은 2001년에서 2010년까지 10년 동안 경수로원전의 경우에는 연평균 11.61 TBq/호기 수준으로 유지하고 있으며, 중수로원전의 경우 118.12 TBq/호기 수준으로 유지되고 있다. 이들 기체나 액체 방사성유출물의 배출 핵종의 대부분은 삼중수소로 나타났다. 이러한 배출경향과 분석 결과를 바탕으로 국내원전의 방사성유출물 관리에 대한 특성을 제시하였다.

• 방사성폐기물학회지
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• 제4권4호
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• pp.345-352
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• 2006

붕산폐액을 함유한 시멘트 및 파라핀 고화체, 폐이온교환수지를 함유한 시멘트 고화체 그리고 잡고체중의 제염지에 대하여 Co-60을 조사선원으로 하여 $10^8$ rads까지 조사하여 발생되는 분해가스의 종류 및 그의 발생량을 분석하였다. 그 결과 분해가스로는 $H_2,\;CH_4,\;N_2,\;C_2H_6,\;O_2,\;CO$ 및 $CO_2$ 등이 발생하였으며, $H_2$가 대부분을 차지하였다. 가스발생량은 폐기물과 고화매질의 종류에 따라 $0.029{\sim}0.788\;cm^3.atm/1.1g$으로 상당한 차이를 보였으며, 폐이온교환수지를 함유한 고화체에서 가장 높은 분해가스 발생량을 보였다. 그리고 수소가스는 제염지 폐기물에서 가장 많이 발생하였다. 제염지의 $G(H_2)$는 0.12이었다.

• 지질공학
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• 제24권4호
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• pp.535-550
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• 2014

지하수내 존재하고 있는 자연방사성물질인 우라늄과 라돈-222의 산출특성과 지화학적 기원을 알아보기 위해 괴산지역 연구부지내 120 m 깊이의 지하수 관정을 시추하여 심도별 시추코어의 암석화학적 특성과 지하수의 화학적 특성을 분석하였다. 시추코어 샘플 분석과 함께 더블패커시스템과 베일러를 이용하여 8개의 심도별 지하수 시료를 채취하여 지화학적 특성 분석을 수행하였다. 시추코어 분석결과, 주요 암종은 화강반암과 점판암이었으며 일부 구간에서는 탄산염암과 석회규산염암, 페그마타이트가 확인되었다. 심도별 지하수의 pH는 7.8~8.4의 범위이며, 화학적 유형은 Na-$HCO_3$형태를 보였다. 암석 및 광물 내 우라늄과 토륨의 함량은 각각 < 0.2~14.8 ppm과 0.56~45.0 ppm의 범위였으며, 암석현미경과 전자현미경(EPMA) 관찰 결과 자연방사성원소(우라늄) 함유 광물은 흑운모내 포획된 모나자이트 광물인 것으로 확인되었다. 우라늄은 이들 광물의 주요 구성원소를 치환하여 존재하는 것으로 보이며 파쇄대와 같은 주요 대수층 구간에서 용해되어 지하수와 함께 용출되는 것으로 보인다. 라돈-222의 함량은 우라늄의 함량과 어떠한 상관성을 보이지 않았으며 향후, 라돈가스 기원 추적을 위해서는 헬륨과 네온 등 영족기체 동위원소비를 이용한 간접적인 방법을 적용하여 분석할 필요가 있을 것으로 판단된다.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.315-319
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• 2001

It is shown, that both cosmic radiation (external source) and natural radioactive gases (inner source) are sources of neutrons near the Earth crust. Correlation between the Earth crust dynamics and variations of thermal and slow neutron flux near the Earth surface is studied. It is shown, that variations of neutron flux near the Earth crust can be used for short-term predicting of natural hazards.

• Journal of Radiation Protection and Research
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• 제41권3호
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• pp.237-244
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• 2016

Background: Korea Atomic Energy Research Institute is developing a fission product transport module for predicting the behavior of radioactive materials in the primary cooling system of a nuclear power plant as a separate module, which will be connected to a severe accident analysis code, Core Meltdown Progression Accident Simulation Software (COMPASS). Materials and Methods: This fission product transport (COMPASS-FP) module consists of a fission product release model, an aerosol generation model, and an aerosol transport model. In the fission product release model there are three submodels based on empirical correlations, and they are used to simulate the fission product gases release from the reactor core. In the aerosol generation model, the mass conservation law and Raoult's law are applied to the mixture of vapors and droplets of the fission products in a specified control volume to find the generation of the aerosol droplet. In the aerosol transport model, empirical correlations available from the open literature are used to simulate the aerosol removal processes owing to the gravitational settling, inertia impaction, diffusiophoresis, and thermophoresis. Results and Discussion: The COMPASS-FP module was validated against Aerosol Behavior Code Validation and Evaluation (ABCOVE-5) test performed by Hanford Engineering Development Laboratory for comparing the prediction and test data. The comparison results assuming a non-spherical aerosol shape for the suspended aerosol mass concentration showed a good agreement with an error range of about ${\pm}6%$. Conclusion: It was found that the COMPASS-FP module produced the reasonable results of the fission product gases release, the aerosol generation, and the gravitational settling in the aerosol removal processes for ABCOVE-5. However, more validation for other aerosol removal models needs to be performed.

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3310-3316
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• 2022

Owing to the rising concerns about the safety of nuclear power plants (NPP), it is essential to study the venturi scrubber in detail, which is a key component of the filtered containment venting system (FCVS). FCVS alleviates the pressurein containment byfiltering and venting out the contaminated air. Themain objective of this research was to perform a CFD investigation of different configurations of a circular, non-submerged, self-priming venturi scrubber to estimate and improve the performance in the removal of elemental iodine from the air. For benchmarking, a mass transfer model which is based on two-film theory was selected and validated by experimental data where an alkaline solution was considered as the scrubbing solution. This mass transfer model was modified and implemented on a unique formation of two self-priming venturi scrubbers in series. Euler-Euler method was used for two-phase modeling and the realizable K-ε model was used for capturing the turbulence. The obtained results showed a remarkable improvement in the removal of radioactive iodine from the air using a series combination of venturi scrubbers. The removal efficiency was improved at every single data point.

• 방사성폐기물학회지
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• 제5권1호
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• pp.39-52
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• 2007

사용후핵연료의 건식 재가공을 위한 핵연료 원격 제조공정중 분말제조를 위한 산화 및 OREOX(산화 환원공정)열처리 공정으로부터 $^{85}Kr$ 및 $^{14}C$ 핵분열기체의 방출거동을 정량적으로 평가하였다. 특히 사용후핵연료의 평균 연소도가 $27,000{\sim}65,000\;MWd/tU$ 범위내에서 연소도 변화에 따른 핵분열기체의 방출 분율은 측정한 실험결과와 ORIGEN 코드로부터 계산된 초기 inventory를 상호 비교하여 구하였다. $500^{\circ}C$ 1차 산화공정(voloxidation)에서 $^{85}Kr$ 및 $^{14}C(^{14}CO_2)$의 시간에 따른 방출거동은 $UO_2$ 핵연료의 $U_3O_8$으로의 분말화 정도와 밀접한 관련이 있는 것으로 보이며, 입계(grain-boundary)에 분포된 핵분열기체가 대부분 방출되는 것으로 여겨진다. 산화분말을 이용한 OREOX 공정으로부터 핵분열기체의 높은 방출율은 $700^{\circ}C$의 환원공정에서 온도 증가에 의한 기체 확산 및 $UO_2$으로의 환원에 의한 U 원자 이동성 증가에 의존하며 주로 inter-grain 및 intra-grain에 분포된 핵분열기체가 방출된 것으로 판단된다. 일차 산화공정시 $^{85}Kr$ 및 $^{14}C$ 핵분열기체의 방출 분율은 핵 연료 연소도가 증가함에 따라 높게 나타났고 방출 분율 범위는 총 inventory의 $6{\sim}12%$정도며, 산화분말의 OREOX 공정처리시 잔류 핵분열기체 대부분이 방출되는 것으로 보인다. 아울러 사용후핵 연료로부터 핵분열기체의 제거를 위해서는 고온 환원분위기보다는 산화에 의한 분말화가 더 효과적인 것으로 여겨진다.

• 방사성폐기물학회지
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• 제18권2호
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• pp.169-177
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• 2020

Here, the stability of stainless steel 316 (SS-316) was investigated to identify its applicability in the oxide reduction process, as a component in related equipment, to produce a complicated gas mixture composed of O₂ and Cl₂ under an argon (Ar) atmosphere. The effects of the mixed gas composition were investigated at flow rates of 30 mL/min O₂, 20 mL/min O₂ + 10 mL/min Cl₂, 10 mL/min O₂ + 20 mL/min Cl₂, and 30 mL/min Cl₂, each at 600℃, during a constant argon flow rate of 170 mL/min. It was found that the corrosion of SS-316 by the chlorine gas was suppressed by the presence of oxygen, while the reaction proceeded linearly with the reaction time regardless of gas composition. Surface observation results revealed an uneven surface with circular pits in the samples that were fed mixed gases. Thermodynamic calculations proposed the combination of Fe and Ni chlorination reactions as an explanation for this pit formation phenomenon. An exponential increase in the corrosion rate was observed with an increase in the reaction temperature in a range of 300 ~ 600℃ under a flow of 30 mL/min Cl₂ + 170 mL/min Ar.

• Nuclear Engineering and Technology
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• 제51권4호
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• pp.1176-1179
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• 2019

Measurements of activity concentrations of radionuclides in atmospheric releases were performed in 2017-2018 at vent stacks of seven Russian nuclear power plants. The selected instruments and research methods, with detection limits significantly lower than the existing detection limit of Russian NPPs routine control, allowed to reliably determine up to 26 radionuclides. Analysis of experimental data allows to determine the list of radionuclides for calculation the effective dose rates to public and the permissible annual discharge levels for each Russian NPP. Radiocarbon is determined as major contributor for the dose from the atmospheric releases of LWGR reactors - up to 98% for EGP-6 and RBMK-1000 (Smolensk NPP) reactors. For PWR reactors (VVER) radionuclides contribution to the annual dose from atmospheric releases is more complicated, but, in general, dose is formed by tritium, $^{14}C$ and noble gases. The special monitoring results with ranking of measured radionuclides according to their contribution to the effective dose makes it possible to optimize the list of controlled radionuclides in airborne releases of Russian NPPs from 94 to 8-16 for different NPPs.

• Nuclear Engineering and Technology
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• 제53권2호
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• pp.386-392
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• 2021

MACCS (MELCOR Accident Consequence Code System), WinMACCS, and MelMACCS now facilitate a multi-unit consequence analysis. MACCS evaluates the consequences of an atmospheric release of radioactive gases and aerosols into the atmosphere and is most commonly used to perform probabilistic safety assessments (PSAs) and related consequence analyses for nuclear power plants (NPPs). WinMACCS is a user-friendly preprocessor for MACCS. MelMACCS extracts source-term information from a MELCOR plot file. The current development can combine an arbitrary number of source terms, representing simultaneous releases from a multi-unit facility, into a single consequence analysis. The development supports different release signatures, fission product inventories, and accident initiation times for each unit. The treatment is completely general except that the model is currently limited to collocated units. A major practical consideration for performing a multi-unit PSA is that a comprehensive treatment for more than two units may involve an intractable number of combinations of source terms. This paper proposes and evaluates an approach for reducing the number of calculations to be tractable, even for sites with eight or ten units. The approximation error introduced by the approach is acceptable and is considerably less than other errors and uncertainties inherent in a Level 3 PSA.