• Journal of the Korean Magnetics Society
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• v.5 no.5
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• pp.683-686
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• 1995

Using by the x-ray diffractometry(XRD), the thermomagnetic analysis(TMA), a scanning electron microscopy (SEM-EDX), we knew that the $(Sm_{0.5}RE_{0.5})Fe_{11}Ti$ (RE=Ce,Pr,Nd,Sm,Gd,Tb) compounds were formed to tetragonal $ThMn_{12}$-type structure having a uniaxial magnetocrystalline anisotropy with easy magnetization c-axis. The intrinsic magnetic properties of those were determined by fitting the two magnetization curves of experimental and calculation magnetization. The anisotropy constant $K_{1}$ of this compounds was in the range of $1.75\;-\;9.2\;MJ/m^{3}$ and approximately one order higher than $K_{2}$. $SmFe_{11}Ti$ had the highest anisotropy of $K_{1}\;=\;9.2\;MJ/m^{3}$, $K_{2}\;=\;0.4\;MJ/m^{3}$ and ${\mu}_{o}H_{A}=\;19.8\;T$ among the compounds, substitution of any other rare earth elements for Sm decreased magnetocrystalline anisotropy.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05a
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• pp.213-218
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• 1996

가압 경수로의 노심설계에 있어서 제한된 우라늄 자원의 효율적인 이용을 위한 다양한 방안으로 장주기 운전, 고 방출연소도 및 저누출 장전모형 등을 강구하고 있는 추세이다. 이러한 노심들은 원자로 운전주기 전반에 걸친 공간적 출력 분포 제어와 잉여반응도 제어를 위해 가연성 흡수봉을 사용하고 있으며 이와 관련 하여 가연성 흡수봉에 대한 전략등이 다 각도로 검토되고 있으며 다양한 노심에 대한 최적의 가연성 흡수봉 혹은 그 전략에 대해 많은 연구가 진행되고 있다. 본 연구에서는 웨스팅하우스형 3-Loop 발전소에 대해, 장주기 (18 개월-480 EFPD), 저누출 장전 모형 전략을 채용하여, Er$_2$O$_3$, Gd$_2$O$_3$, ZrB$_2$의 일체형 가연성 흡수봉에 대한 노심특성 및 경제성을 평형노심개념을 적용, KNFC가 노심설계에 사용하고 있는 APA(ALPHA/PHOENIX-P/ANC) 8.0.0 코드 체계를 이용하여 평가하였다. 노심특성에 대해서는 감속재 온도계수, 첨두출력인자, 잔존흡수봉효과 및 노심 연소거동에 대한 평가가 수행되었고, 동일한 주기길이(480 EFPD) 에 대한 우라늄 적재량에 대해 원광비, 변환비, 농축비, 가공비 그리고 이자율 등을 고려하여 핵주기 경제성 평가 코드인 POCO 코드를 이용하여 경제성을 평가하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.19 no.3
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• pp.353-366
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• 2021

The solubilities of different multicomponent lanthanide oxide (Ln₂O₃) solid solutions including binary (Ln₁ and Ln₂ = La, Nd, Eu, or Tm), ternary (Ln₁, Ln₂, and Ln₃ = La, Nd, Eu, or Tm), and higher systems (Ln = La, Ce, Pr, Nd, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, and Lu) were studied after aging for four weeks at 60℃. Our recent study revealed that the phase transformations in binary ((La, Nd) and (La, Eu)) and ternary (La, Nd, Eu) systems are responsible for the formation of (La, Nd)(OH)₃, (La, Eu)(OH)₃, and (La, Nd, Eu)(OH)₃ solid solutions, respectively. The variations in the mole fractions of La³⁺, Nd³⁺, and Eu³⁺ in the sample solutions of these hydroxide solid solutions indicated that a thermodynamic equilibrium might account for the apparent La, Nd, and Eu solubilities. Conversely, the binary and ternary systems containing Tm₂O₃ as the heavy lanthanide oxide retained the oxide-based solid solutions, and their solubility behaviors were dominated by their congruent dissolutions. In the higher multicomponent system, the X-ray diffraction patterns of the solid phases, before and after contact with the aqueous phase indicated the formation of a stable oxide solid solution and their solubility behavior was explained by its congruent dissolution.

• Nuclear Engineering and Technology
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• v.51 no.7
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• pp.1729-1737
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• 2019

This paper presents neutronics design of VVER-1000 fuel assembly using burnable poison particles (BPPs) for controlling excess reactivity and pin-wise power distribution. The advantage of using BPPs is that the thermal conductivity of BPP-dispersed fuel pin could be improved. Numerical calculations have been conducted for optimizing the BPP parameters using the MVP code and the JENDL-3.3 data library. The results show that by using $Gd_2O_3$ particles with the diameter of $60{\mu}m$ and the packing fraction of 5%, the burnup reactivity curve and pin-wise power distribution are obtained approximately that of the reference design. To minimize power peaking factor (PPF), total BP amount has been distributed in a larger number of fuel rods. Optimization has been conducted for the number of BPP-dispersed rods, their distribution, BPP diameter and packing fraction. Two models of assembly consisting of 18 BPP-dispersed rods have been selected. The diameter of $300{\mu}m$ and the packing fraction of 3.33% were determined so that the burnup reactivity curve is approximate that of the reference one, while the PPF can be decreased from 1.167 to 1.105 and 1.113, respectively. Application of BPPs for compensating the reduction of soluble boron content to 50% and 0% is also investigated.

• Nuclear Engineering and Technology
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• v.51 no.1
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• pp.13-30
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• 2019

This paper presents the recent improvements in the DeCART code for HTGR analysis. A new 190-group DeCART cross-section library based on ENDF/B-VII.0 was generated using the KAERI library processing system for HTGR. Two methods for the eigen-mode adjoint flux calculation were implemented. An azimuthal angle discretization method based on the Gaussian quadrature was implemented to reduce the error from the azimuthal angle discretization. A two-level parallelization using MPI and OpenMP was adopted for massive parallel computations. A quadratic depletion solver was implemented to reduce the error involved in the Gd depletion. A module to generate equivalent group constants was implemented for the nodal codes. The capabilities of the DeCART code were improved for geometry handling including an approximate treatment of a cylindrical outer boundary, an explicit border model, the R-G-B checker-board model, and a super-cell model for a hexagonal geometry. The newly improved and implemented functionalities were verified against various numerical benchmarks such as OECD/MHTGR-350 benchmark phase III problems, two-dimensional high temperature gas cooled reactor benchmark problems derived from the MHTGR-350 reference design, and numerical benchmark problems based on the compact nuclear power source experiment by comparing the DeCART solutions with the Monte-Carlo reference solutions obtained using the McCARD code.

• Development and Reproduction
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• v.26 no.3
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• pp.127-133
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• 2022

The seven oligonucleotides primers were consumed to produce the quantity of unique loci shared to each pen shell team (ULSEPT) and quantity of loci shared by the binary pen shell teams. 154 quantities of LSBPP, with a mediocre of 22.0 per primer, were noticed in the binary pen shell (Atrina pectinata) teams. 328 fragments were recognized in the pen shell team A (PSTA), and 257 in the pen shell team B (PSTB): 77 quantities of ULSEPT (23.48%) in the PSTA and 121 (47.08%) in the PSTB. The band-sharing amount (BS amount) between entity's no. 01 and no. 05 was the highest (0.884) between the binary PSTs. The median band-sharing amount of entities in the PSTA (0.685±0.011) was higher than in those invented from the PSTB (0.640±0.009) (p<0.05). The highest genetic distance presenting substantial molecular difference was between entities PECTINATA no. 06 and PECTINATA no. 04 (0.498). Through this study, it is possible a certain degree to contribute to increasing the cultivation of pen shells, conservation of species, protection of the natural environment, and preservation of ecosystems.

• Nuclear Engineering and Technology
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• v.54 no.3
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• pp.1024-1029
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• 2022

Composite scintillation screens on a base of Gd_1.2Y_1.8Ga_2.5Al_2.5O₁₂:Ce (GYAGG) scintillator have been evaluated for neutron detection. Besides the powdered scintillator, the composite includes ⁶LiF particles; both are merged with a binder and deposited onto the light-reflecting aluminum substrate. Results obtained demonstrates that screens are suitable for use with a silicon photomultiplier readout to create a prospective solution for a compact and low-cost thermal neutron sensor. Composite GYAGG/⁶LiF scintillation screen shows a pretty matched sensitivity and γ-background rejection with a widely used ZnS/⁶LiF screens however, possesses forty times faster response.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.21 no.2
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• pp.271-281
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• 2023

A study was conducted on the vitrification of the rare earth oxide waste generated from the PyroGreen process. The target rare earth waste consisted of eight elements: Nd, Ce, La, Pr, Sm, Y, Gd, and Eu. The waste loading of the rare earth waste in the developed borosilicate glass system was 20wt%. The fabricated glass, processed at 1,200℃, exhibited uniform and homogeneous surface without any crystallization and precipitation. The viscosity and electrical conductivity of the melted glass at 1,200℃ were 7.2 poise and 1.1 S·cm^-1, respectively, that were suitable for the operation of the vitrification facility. The calculated leaching index of Cs, Co, and Sr were 10.4, 10.6, and 9.8, respectively. The evaluated Product Consistency Test (PCT) normalized release of the glass indicated that the glass satisfied the requirements for the disposal acceptance criteria. Furthermore, the pristine, 90 days water immersed, 30 thermal cycled, and 10 MGy gamma ray irradiated glasses exhibited good compressive strength. The results indicated that the fabricated glass containing rare earth waste from the PyroGreen process was acceptable for the disposal in the repository, in terms of chemical durability and mechanical strength.

• Nuclear Engineering and Technology
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• v.55 no.9
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• pp.3352-3358
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• 2023

Nuclear medicine seems to be a decent choice of medicine in the recent decade. The radioactive isotopes ⁵¹Cr, ⁸⁹Sr, ⁹⁹Tc, ¹³¹I, ¹³³Xe, ¹³⁷Cs and ¹⁵³Sm are extremely essential in nuclear medicine. The excitation functions of the ⁵⁴Fe (n, α) ⁵¹Cr, ⁹²Zr (n, α) ⁸⁹Sr, ¹⁰²Rh (n, α) ⁹⁹Tc, 134Cs (n, α) ¹³¹I, ¹³⁶Ba (n, α) ¹³³Xe, ¹⁴⁰La (n, α) ¹³⁷Cs and ¹⁵⁶Gd (n, α) ¹⁵³Sm reactions were calculated in this study using the EMPIRE 3.2.3 and TALYS 1.95 nuclear codes. Additionally, the cross sections at 14-15 MeV were calculated using empirical formulae and the experimental data. The computer codes were compared to the experimental data and Empirical formulas as well as the evaluated data (TENDL 2021, JENDL 3.3, JENDL 5, JEFF 3.3, EAF 2010, CENDL 3.1, CENDL 3.2, ROSFOND 2010, FENDL 3.2 b, and BROND 3.1).

• Proceedings of the Korea Water Resources Association Conference
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• 2020.06a
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• pp.271-271
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• 2020

GIS-Based Disaster Prevention Engineering Tools(이하 GDP Tools)는 수자원·방재 관련 설계 편의를 위해 개발된 도구로 직관적인 사용자 편의 인터페이스(GUI)를 바탕으로 한 독립실행형 응용프로그램이다. GDP Tools의 기능은 다음과 같이 세 가지로 구분할 수 있다. 1) GIS 관련 기능: 지오코드, 지도 관리, 래스터/벡터 파일 관리 등 2) 재해 발생가능성 분석 기능: 하천·내수·사면·토사·바람·가뭄·대설재해 등 자연재해저감종합계획에서 다루는 재해유형별 전지역단위 분석, 지형분석 3) 기타 기능: 현장조사표 작성, 저감대책의 개략사업비 산정, 각종 파일 관리, 기초통계 및 수문분석 등 GDP Tools는 실무에서 자주 사용되는 GIS 기능은 물론 각종 재해유형별 자연재해 발생가능성 분석, 지형분석 등 각종 편의 기능을 제공하고 있어서 수자원·방재 과업을 일괄적으로 진행할 수 있다. 여러 수치모형을 종합적으로 사용하는 기존 방법과 달리 별도로 자료 전·후처리 과정이 필요 없으며, 과업에 필요한 기본 자료가 전국 단위로 구축·준비되어 있어 사용자가 따로 준비해야할 사항을 최소화한다는 장점이 있다. 본 논문에서는 GDP Tools의 개발 내용과 세부 기능, 적용사례를 소개하고자 한다.