• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.534-538
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• 2003

Final disposal of radioactive waste generated from Nuclear Power Plant (NPP) requires the detailed knowledge of the natures and quantities of radionuclides in waste package. Many of these radionuclides are difficult to measure and expensive to assay. Thus it is suggested to the Indirect method by which the concentrations of DTM (Difficult-to-Measure) nuclide is decided using the relation of concentrations (Scaling Factor) between Key (Easy-to-Measure) nuclide and DTM nuclide with measured concentrations of Key nuclide. In general, scaling factor is determined by using of log mean average (LMA) and regression. These methods are adequate to apply most corrosion product nuclides. But in case of fission product nuclides and some corrosion product nuclides, the predicted values aren't well matched with the original values. In this study, the models using artificial neural network (ANN) for C-14 and Sr-90 are compared with those using LMA and regression. The assessment of models is executed in the two parts divided by a training part and a validation part. For all of two nuclides in the training part, the predicted values using ANN are well matched with the measured values compared with those using LMA and regression. In the validation part, the accuracy of the predicted values using ANN is better than that using LMA and is similar to or better than that using regression. It is concluded that the predicted values using ANN model are better than those using conventional model in some nuclides and ANN model can be used as the complement of LMA and regression model.

• Nuclear Engineering and Technology
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• 제21권4호
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• pp.267-276
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• 1989

중저준위 방사성 폐기물 처분 안전성 평가에 이용될 수 있는 유한 차분법에 의한 수치모델을 개발하였다. 이 모델은 처분장이 암반내에 위치한 경우에 대하여 처분장 주위 지하 암반 매질에서의 핵종의 이동을 기술하는 것으로 암반내의 단일한 균열으로의 지하수에 의한 이동과 균열에 수직한 방향으로의 확산을 고려하여 일차원적으로 해석하였다. 수치모델은 해석해와 병행하여 처분장 안전성 평가에 있어서 유용하게 이용될 수 있는 것으로 보다 실제적인 경계조건을 사용할 수 있게 하고, 불균질한 암반매질에 대해 다중매질 모델링을 제공한다. 수치모델의 검증을 위하여 균열에서의 Sr-90 농도 Profile을 구하여 해석해와 비교하였고, 몇몇 경계 조건에 따른 영향을 비교하고 암반매질을 파라미터 값이 단계적으로 변하는 이중 매질에 대하여 확장하였다.

• Nuclear Engineering and Technology
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• 제54권10호
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• pp.3878-3887
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• 2022

For the future energy-mix policy for carbon neutrality, demand for the capability of load-follow operation has emerged in nuclear power plants in order to accommodate the intermittency of renewable energy. The short-term decay heat analysis is also required to evaluate the decay heat level varied by the power level change during the load-follow operation, which is a very important parameter in terms of short-term decay heat removal during a grace time. In this study, the short-term decay heat level for 10 days after the shutdown was evaluated for both seasonal and daily load-follow cases. Additionally, the nuclide-wise contribution to the accumulated decay heat for 10 days was analyzed for further understanding of the short-term decay heat behavior. The result showed that in the seasonal case, the decay heat level was mainly determined by the power level right before the shutdown and the amount of each nuclide was varied with the power variation due to the long variation interval of 90 days. Whereas, in the daily case, the decay heat level was strongly impacted by the average power level during operation and meaningful mass variations for those nuclides were not observed due to the short variation interval of 0.5 days.

• Nuclear Engineering and Technology
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• 제25권4호
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• pp.529-538
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• 1993

이전에 제신된 시간 균일적인 경우의 모델［1］에 대한 확장으로 균열암반내 핵종이동에 관한 연속시간 마코프 프로세스를 이용한 통계적 방법에 의한 모델이 제시되었다. 단일 평판 균일을 갖는 암반매질에서 핵종이 균열로부터 알반조직내로 확산 이동하는 경우 더 이상 균열시간적인 마코프 모델을 적용할 수 없으므로 암반으로의 확산항을 시간에 따라 변화하는 과정으로 보아 모델을 제시한 후 기존의 결정론적 해석해와 비교하였다. 통계적모델의 최종 결과는 시간의 함수로서의 상태변수에 대한 기댓값과 그 분산치일 것이다. 핵종의 시간 종속적인 확률분포가 전이강도가 주어질 때 매질내의 특성이 균질하다고 볼 수 있도록 나누어진 암반매질의 각 구획에 대해 주어지게 된다. 이 모델은 매질공간에 대해 불연속적이므로 핵종이동에 영향을 주는 변수들이 쉽게 균열암반이나 다중매질 등과 같은 비균질한 매질에 적용되어 질수 있다. 매질을 나눈 구획수가 수치적 분산에 민감한 것으로 나타났지만 분산계수의 보정에 의해 해석해와 잘 일치되는 것을 알 수 있었다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
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• pp.133-134
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
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• pp.72-73
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.254-254
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• 2004

Final disposal of radioactive waste generated from Nuclear Power Plant (NPP) requires the detailed information about the characteristics and the quantities of radionuclides in waste package. Most radionuclides are difficult to measure and expensive to assay. Thus it is suggested to the indirect method by which the concentration of the Difficult-to-Measure (DTM) nuclide is estimated using the correlations of concentration-it is called the scaling factor-between Easy-to-Measure (Key) nuclides and DTM nuclides with the measured concentration of the Key nuclide.(omitted)

• Nuclear Engineering and Technology
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• 제29권4호
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• pp.320-326
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• 1997

The nuclide transport in the one-dimensional porous medium is considered as a first step in developing a decay chain transport in multidimensional inhomogeneous media. A method of solving conventional advection-dispersion equation with decay chain of arbitrary length by using the method of characteristics (MOC) is introduced. In specific cases where the advection are dominant rather than dispersion, the method is known to be useful : one of the most distinctive advantages in applying the model is that the MU minimizes the numerical dispersion, which is distinguished in such common numerical schemes as finite element method and finite difference method. The suggested model is considered to be effective through several illustrations for the case that decay chain of arbitrary length is involved during transport which is difficult to solve by standard numerical solutions if the medium becomes more complicated.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 춘계학술발표회논문집(2)
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• pp.833-838
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• 1995

This study presents a method to predict plant-specific and operational history dependent scaling factors. Realistic and detailed approaches are taken to find scaling factors at reactor coolant. This approach begins with fission product release mechanisms and fundamental release properties of fuel-source nuclide such as fission product and transuranic nuclide. Scaling factors at various waste streams are derived from the predicted reactor coolant scaling factors with the use of radionuclide retention and build up model. This model makes use of radioactive material balance within the radioactive waste processing systems. According to input parameters of plant operation history, scaling factors predicted at reactor coolant and waste streams are well brought out the effects of plant operation history.

• Nuclear Engineering and Technology
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• 제49권5호
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• pp.1019-1030
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• 2017

Diffusion is a crucial mechanism that regulates the migration of radioactive nuclides. In this study, an innovative numerical method was developed to simultaneously calculate the diffusion coefficient of both parent and, afterward, series daughter nuclides in a sequentially reactive through-diffusion model. Two constructed scenarios, a serial reaction (RN_1 ${\rightarrow}$ RN_2 ${\rightarrow}$ RN_3) and a parallel reaction (RN_1 ${\rightarrow}$ RN_2A + RN_2B), were proposed and calculated for verification. First, the accuracy of the proposed three-member reaction equations was validated using several default numerical experiments. Second, by applying the validated numerical experimental concentration variation data, the as-determined diffusion coefficient of the product nuclide was observed to be identical to the default data. The results demonstrate the validity of the proposed method. The significance of the proposed numerical method will be particularly powerful in determining the diffusion coefficients of systems with extremely thin specimens, long periods of diffusion time, and parent nuclides with fast decay constants.