• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1079-1087
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• 2021

NTP-ERSN is a package developed for solving the multigroup form of the discrete ordinates, characteristics and collision probability of the Boltzmann transport equation in one-dimensional cartesian geometry, by combining pin cells. In this work, C5G7 MOX benchmark is used to verify the accuracy and efficiency of NTP-ERSN package, by treating reactor core problems without spatial homogenization. This benchmark requires solutions in the form of normalized pin powers as well as the vectors and the eigenvalue. All NTP-ERSN simulations are carried out with appropriate spatial and angular approximations. A good agreement between NTP-ERSN results with those obtained with OpenMC calculation code for seven energy groups. In addition, our studies about angular and mesh refinements are carried out to produce better quality solution. Moreover, NTP-ERSN GUI has also been updated and adapted to python 3 programming language.

• Nuclear Engineering and Technology
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• 제52권3호
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• pp.461-468
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• 2020

The improvements of the DeCART/MUSAD code system for uncertainty analysis of HTGR neutronic parameters are presented in this paper. The function for quantifying an uncertainty of critical-spectrumweighted few group cross section was implemented using the generalized adjoint B₁ equation solver. Though the changes between the infinite and critical spectra cause a considerable difference in the contribution by the graphite scattering cross section, it does not significantly affect the total uncertainty. To reduce the number of iterations of the generalized adjoint transport equation solver, the generalized adjoint B₁ solution was used as the initial value for it and the number of iterations decreased to 50%. To reflect the implicit uncertainty, the correction factor was derived with the resonance integral. Moreover, an additional correction factor for the double heterogeneity was derived with the effective cross section of the DH region and it reduces the difference from the complete uncertainty. The code system was examined with the MHTGR-350 Ex.II-2 3D core benchmark. The k_eff uncertainty for Ex.II-2a with only the fresh fuel block was similar to that of the block and the uncertainty for Ex.II-2b with the fresh fuel and the burnt fuel blocks was smaller than that of the fresh fuel block.

• 한국해양환경ㆍ에너지학회지
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• 제11권4호
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• pp.191-198
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• 2008

$CO_2$ 해양지중저장 처리 시스템 설계를 수행하는데 있어 전산모사를 통한 공정 설계는 필수적이다. 즉, 수치 모델링을 이용하여 $CO_2$ 해양지중저장 처리 공정 중 발전소 및 제철소 등 대규모 발생원에서부터 $CO_2$를 포집하는 포집공정, 포집한 $CO_2$를 파이프라인이나 선박 등을 통해 이송하는 수송공정, 이를 깊이 800m 이상의 해저 지질구조내 대규모로 수백-수천년 이상 장기간 저장하는 저장공정 등 일련의 공정을 열역학 상태방정식 등을 이용하여 모사하는 것이다. 본 논문에서는 $CO_2$ 해양지중저장 처리를 위한 공정 설계에 사용되는 열역학 상태방정식들을 비교 분석하고 이들이 압축 및 수송공정에 미치는 영향 등을 평가하였다. 이와 같은 연구결과에 근거하여 $CO_2$ 해양지중저장 처리를 위한 압축 및 수송 공정 설계 시 유용한 열역학 상태방정식을 제안하였다. 상태방정식 계산결과 간의 비교 및 영향 평가를 위하여 순수 단일성분 $CO_2$와 순산소 연소 석탄 화력발전소에서 포집된 $CO_2$ 혼합물의 압축 및 수송거동을 분석하였다. 순수 단일성분 $CO_2$의 압축 및 수송공정 계산결과에는 이상기체 상태방정식을 제외한 상태방정식 간에 큰 차이가 존재하지 않으나, NO, Ar 그리고 $O_2$ 등이 포함된 순산소 연소 석탄 화력발전소에서 포집된 $CO_2$ 혼합물의 압축 및 수송공정에는 PR 계열의 상태방정식과 BWRS 상태방정식에서 커다란 차이가 나타났다. 즉, 8bar 이상의 압력, $30^{\circ}C$ 내외의 온도 영역에서 $CO_2$ 혼합물을 서로 다른 상태로 예측하였다. 이러한 불순물의 영향으로 인하여 $CO_2$ 혼합물의 압축 및 수송공정 설계에 PR계열의 PRBM 상태방정식의 적용이 BWRS식 적용보다 유용하다고 판단된다.

• Transactions on Electrical and Electronic Materials
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• 제9권6호
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• pp.265-272
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• 2008

In this paper, AC losses of long wire Bi-2223 tapes with different twist pitch of superconducting core were fabricated, measured and analyzed. These samples produced by a powder-in-tube method are multi-filamentary tape with Ag matrix. Also, it's produced by non-twist. The critical current measurement was carried out under the environment in Liquid nitrogen and in zero field by 4-prob method. And the Magnetic measurement was carried out under the environment of applied time-varying transport current by transport method. From experiment, the susceptibility measurements were conducted while cooling in a magnetic field. Flux loss measurements were conducted as a function of ramping rate, frequency and field direction. The AC flux loss increases as the twist-pitch of the tapes decreased, in agreement with the Norris Equation. Neutron-diffraction measurements have been carried out investigate the crystal structure, magnetic structures, and magnetic phase transitions in Bi-2223([Bi, Pb]:Sr:Ca:Cu:O).

• Nuclear Engineering and Technology
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• 제3권3호
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• pp.121-128
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• 1971

중성자속의 각분포를 unified modal-nodal 방법으로 전개하였다. 몇몇 표준 nodal 해석법이나 modal 해석법은 이 방법의 특수한 경우임을 밝혔다. 중성자의 발생과 산란이 등방성인 경우에 단일에너지 수송방정식을 modal-nodal moment 형으로 도출하여 고유치를 구하였다. 중성자가 생성되지 않는 매질 내에서의 역확산거리를 근사적으로 계산한 결과 표준방법으로 한 것보다 더 정화하였다.

• 한국전기전자재료학회:학술대회논문집
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• 한국전기전자재료학회 1998년도 추계학술대회 논문집
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• pp.159-162
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• 1998

This paper describes the electron transport characteristics in $SF_6$+He gas calculated for range of E/N values from 50~700[Td] by the Monte Carlo simulation and Boltzrnann equation method using a set of electmn collision cross sections determined by the authors and the values of electron swarm parameters are obtained by M F method. The results gained that the values of the electron swarm parameters such as the electron drift velocity, the electron ionization or attachment coefficents, longitudinal and h-ansverse diffusion coefficients agree with the experimental and theoretical for a range of E/N.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1999년도 추계학술대회 논문집 전문대학교육위원 P
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• pp.16-19
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• 1999

This paper describes the electron transport characteristics in $SF_6$+He gas calculated for range of E/N values from $50{\sim}700[Td]$ by the Monte Carlo simulation and Boltzmann equation method using a set of electron collision cross sections determined by the authors and the values of electron swarm parameters are obtained by TOF method. The results gained that the values of the electron swarm parameters such as the electron drift velocity, the electron ionization or attachment coefficients, longitudinal and transverse diffusion coefficients agree with the experimental and theoretical for a range of E/N.

• 한국전산유체공학회지
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• 제18권2호
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• pp.9-16
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• 2013

The heat transfer enhancement of heat sink with mist flow is studied numerically by solving the conservation equations for mass, momentum and energy in the continuous and dispersed phases. A Lagrangian method is used for tracing dispersed water droplets in the heat sink and an Eulerian species transport model for air and steam mixture. The continuous and dispersed phases are interacted with the drag and evaporation source terms. The computed results show that addition of evaporating mist droplets enhances the cooling performance of heat sink significantly.

• 한국전기전자재료학회논문지
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• 제13권4호
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• pp.359-364
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• 2000

The paper describes the electron transport characteristics in SP$_{6}$+He gas calculated E/N values 0.1~700[Td] by the Monte Carlos simulation and Boltzmann equation method using a set of electron collision cross sections determined by the authors and the values of electron swarm parameters obtained by TOF method. This study gained the values of the electron swarm parameters such as the electron drift velocity the electron ionization or attachment coefficients longitudinal and transverse diffusion coefficients for SF$_{6}$+He gas at a range of E/N.E/N.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2001년도 학술대회 논문집 전문대학교육위원
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• pp.72-75
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• 2001

In this paper, we describe the results of a combined experimental theoretical study designed to understand and predict the dielectric properties of $SF_6$ and $SF_6+Ar$ mixtures. The electron transport, ionization, and attachment coefficients for pure $SF_6$ and gas mixtures containing $SF_6$ has been analysed over the E/N range $30{\sim}300Td$ by a two term Boltzrnann equation and by a Monte Carlo Simulation using a set of electron cross sections determined by other authors, experimentally the electron swarm parameters for 0.2% and 0.5% $SF_6+Ar$ mixtures were measured by time- of- flight method, The results show that the deduced electron drift velocities, the electron ionization or attachment coefficients, longitudinal and transverse diffusion coefficients and mean energy agree reasonably well with the experimental and theoretical for a rang of E/N values.