• 한국초전도ㆍ저온공학회논문지
• /
• 제16권1호
• /
• pp.9-13
• /
• 2014

Effects of neutron irradiation on the superconducting properties of the undoped $MgB_2$ and the carbon(C)-doped $MgB_2$ bulk superconductors, prepared by an in situ reaction process using Mg and B powder, were investigated. The prepared $MgB_2$ samples were neutron-irradiated at the neutron fluence of $10^{16}-10^{18}n/cm^2$ in a Hanaro nuclear reactor of KAERI involving both fast and thermal neutron. The magnetic moment-temperature (M-T) and magnetization-magnetic field (M-H) curves before/after irradiation were obtained using magnetic property measurement system (MPMS). The superconducting critical temperature ($T_c$) and transition width were estimated from the M-T curves and critical current density ($J_c$) was estimated from the M-H curves using a Bean's critical model. The $T_cs$ of the undoped $MgB_2$ and C-doped $MgB_2$ before irradiation were 36.9-37.0 K and 36.6-36.8 K, respectively. The $T_cs$ decreased to 33.2 K and 31.6 K, respectively after irradiation at neutron fluence of $7.16{\times}10^{17}n/cm^2$, and decreased to 22.6 K and 24.0 K, respectively, at $3.13{\times}10^{18}n/cm^2$. The $J_c$ cross-over was observed at the high magnetic field of 5.2 T for the undoped $MgB_2$ irradiated at $7.16{\times}10^{17}n/cm^2$. The $T_c$ and $J_c$ variation after the neutron irradiation at various neutron fluences were explained in terms of the defect formation in the superconducting matrix by neutron irradiation.

• Nuclear Engineering and Technology
• /
• 제52권5호
• /
• pp.869-877
• /
• 2020

A 24-month Advanced Power Reactor 1400 (APR1400) core with a very-low-boron (VLB) concentration has been investigated for an inherently safe and high-performance PWR in this work. To develop a high-performance APR1400 which is able to do the passive frequency control operation, VLB feature is essential. In this paper, the centrally-shielded burnable absorber (CSBA) is utilized for an efficient VLB operation in the 24-month cycle APR1400 core. This innovative design of the VLB APR1400 core includes the optimization of burnable absorber and loading pattern as well as axial cutback for a 24-month cycle operation. In addition to CSBA, an Er-doped guide thimble is also introduced for partial management of the excess reactivity and local peaking factor. To improve the neutron economy of the core, two alternative radial reflectors are adopted in this study, which are SS-304 and ZrO₂. The core reactivity and power distributions for a 2-batch equilibrium cycle are analyzed and compared for each reflector design. Numerical results show that a VLB core can be successfully designed with 24-month cycle and the cycle length is improved significantly with the alternative reflectors. The neutronic analyses are performed using the Monte Carlo Serpent code and 3-D diffusion code COREDAX-2 with the ENDF/B-VII.1.

• Nuclear Engineering and Technology
• /
• 제53권6호
• /
• pp.1769-1785
• /
• 2021

The Integral Pressurized Water Reactors (IPWRs) as the innovative advanced and generation-III + reactors are under study and developments in a lot of countries. This paper is aimed at the thermal hydraulic study of the hot and average fuel sub-channel in a Generation III + IPWR by loose external coupling to the neutronic simulation. The power produced in fuel pins is calculated by the neutronic simulation via MCNPX2.6 then fuel and coolant temperature changes along fuel sub-channels evaluated by computational fluid dynamic thermal hydraulic calculation through an iterative coupling. The relative power densities along the fuel pin in hot and average fuel sub-channel are calculated in sixteen equal divisions. The highest centerline temperature of the hottest and the average fuel pin are calculated as 633 K (359.85 ℃) and 596 K (322.85 ℃), respectively. The coolant enters the sub-channel with a temperature of 557.15 K (284 ℃) and leaves the hot sub-channel and the average sub-channel with a temperature of 596 K (322.85 ℃) and 579 K (305.85 ℃), respectively. It is shown that the spacer grids result in the enhancement of turbulence kinetic energy, convection heat transfer coefficient along the fuel sub-channels so that there is an increase in heat transfer coefficient about 40%. The local fuel pin temperature reduction in the place and downstream the space grids due to heat transfer coefficient enhancement is depicted via a graph through six iterations of neutronic and thermal hydraulic coupling calculations. Working in a low fuel temperature and keeping a significant gap below the melting point of fuel, make the IPWR as a safe type of generation -III + nuclear reactor.

• 한국운동역학회지
• /
• 제29권3호
• /
• pp.129-135
• /
• 2019

Objective: The purpose of this study is to present the scientific and quantitative data by finding the common points and differences of the side-kick according to the height change through the difference of the side kick motion performance according to the three target height changes and the function of the lower limbs muscle in side kick motion of Taekwondo Poomsae. Method: For this, total 14 players were selected who were registered in Korea Taekwondo Association and skilled group 7 players who had a medal from national competition and 7 players who did not have Taekwondo experience from department of physics. 4 video cameras to the feature on side kick per target height, and the subjects' support foot was located on the ground reactor and the practice was conducted 3 times: waist, chest, and head as the target height. the basic materials were collected by using Kwon 3D XP program and the T-test was conducted to verify the statistic difference between groups (SPSS 24.0). At this time, the statistics significance level was set as .05 and the following conclusion was obtained. Results: The lower the proficiency and the higher the height, the more the joint coordination between the hip and the knee. Conclusion: Summary of the result shows a common point that the change of target's height makes the lower the proficiency and the higher the height, the more the joint coordination between the hip and the knee. Also, the higher the target's height became, the greater angular momentum of thighs, shanks, foot became in common.

• Nuclear Engineering and Technology
• /
• 제55권2호
• /
• pp.452-459
• /
• 2023

The core power control is an important issue for the study of dynamic characteristics in China initiative accelerator driven subcritical system (CiADS), which has direct impact on the control strategy and safety analysis process. The CiADS is an experimental facility that is only controlled by the proton beam intensity without considering the control rods in the current engineering design stage. In order to get the optimized operation scheme with the stable and reliable features, the variation of beam intensity using the continuous and periodic control approaches has been adopted, and the change of collimator and the adjusting of duty ratio have been proposed in the power control process. Considering the neutronics and the thermal-hydraulics characteristics in CiADS, the physical model for the core power control has been established by means of the point reactor kinetics method and the lumped parameter method. Moreover, the multi-inputs single-output (MISO) logical structure for the power control process has been constructed using proportional integral derivative (PID) controller, and the meta-heuristic algorithm has been employed to obtain the global optimized parameters for the stable running mode without producing large perturbations. Finally, the verification and validation of the control method have been tested based on the reference scenarios in considering the disturbances of spallation neutron source and inlet temperature respectively, where all the numerical results reveal that the optimization method has satisfactory performance in the CiADS core power control scenarios.

• 대한전기학회논문지:전기물성ㆍ응용부문C
• /
• 제49권12호
• /
• pp.654-664
• /
• 2000

Thin films of ZnO are deposited by using an RF magnetron sputtering with varying the substrate temperature(RT~39$0^{\circ}C$) and RF power(50~250W). Cu-doped ZnO(denoted by ZnO:Cu) films have also been prepared by co-spputtering of a ZnO target on which some Cu-chips are attached. Different substrate materials, such as Si, $SiO_{2}/Si$, sapphire, DLC/Si, and poly-diamond/Si, are employed to compare the c-axial growth features of deposited ZnO films. Texture coefficient(TC) values for the (002)-preferential growth are estimated from the XRD spectra of deposited films. Optimal ranges of RF powers and substrate temperatures for obtaining high TC values are determined. Effects of Cu-doping conditions, such as relative Cu-chip sputtering areas, $O_{2}/(Ar+O_{2})$ mixing ratios, and reactor pressures, on TC values, electrical resistivities, and relative Cu-compositions of deposited ZnO:Cu films have been systematically investigated. XPS study shows that the relative densities of metallic $Cu(Cu^{0})$ atoms and $CuO(Cu^{2+})$-phases within deposited films may play an important role of determining their electrical resistivities. It should be noted from the experimental results that highly resistive(> $10^{10}{\Omega}cm$ ZnO films with high TC values(> 80%) can be achieved by Cu-doping. SAW devices with ZnO(or Zn):Cu)/IDT/$SiO_{2}$/Si configuration are also fabricated to estimate the effective electric-mechanical coupling coefficient($k_{eff}^{2}$) and the insertion loss. It is observed that the devices using the Cu-doped ZnO films have a higher $k_{eff}^{2}$ and a lower insertion loss, compared with those using the undoped films.

• Nuclear Engineering and Technology
• /
• 제52권6호
• /
• pp.1120-1130
• /
• 2020

The CREOLE experiment performed In the EOLE critical facility located In the Nuclear Center of CADARACHE - CEA have allowed us to get interesting and complete experimental information on the temperature effects in the light water reactor lattices. To analyze these experiments with accuracy an elaborate calculation scheme using the Monte Carlo method implemented in the MCNP6.1 code and the ENDF/B-VII.1 cross section library has been developed. We have used the ENDF/B-VII.1 data provided with the MCNP6.1.1 version in ACE format and the Makxsf utility to handle the data in the specific temperatures not available in the MCNP6.1.1 original library. The main purpose of this analysis is the qualification of the ENDF/B-VII.1 nuclear data for the prediction of the Reactivity Temperature Coefficient while ensuring the ability of the MCNP6.1 system to model such a complex experiment as CREOLE. We have analyzed the case of UO₂ lattice with 1166 ppm of boron in ordinary water moderator in specified temperatures. A detailed comparison of the calculated effective multiplication factors with the reference ones [1] in room temperature presented in this work shows a good agreement demonstrating the validation of our 3D calculation model. The discrepancies between calculations and the differential measurements of the Reactivity Temperature Coefficient for the analyzed configuration are relatively small: the maximum discrepancy doesn't exceed 1,1 pcm/℃. In addition to the analysis of direct differential measurements of the reactivity temperature coefficient performed in the poisoned UO₂ lattice configuration, we have also analyzed integral measurements in UO₂ clean lattice configuration using equivalency of the integral temperature reactivity worth with the driver core fuel reactivity worth and soluble boron reactivity worth. In this case both of the ENDF/B-VII.1 and JENDL.4 libraries were used in our analysis and the obtained results are very similar.

• Journal of Radiation Protection and Research
• /
• 제7권1호
• /
• pp.34-48
• /
• 1982

본 연구의 일차적 목적은 방사선 방호를 위하여 임의지점(任意地點)의 주변 방사선량의 수준을 특성(特性)짓는 방법의 하나로 ICRU가 정의(定義)한 흡수선량지수를 실측(實測)하는데 있는 바 이를 위한 실험은 에비실험과 본 실험의 두 단계로 나누어 수행하였다. 예비단계의 실험에서는 30cm 지름의 polyethylene구(球)를 사용한 반면 본 실험에서는 인체조직등가물질(人體組織等價物質)의 구(球)를 제작하였으며 두 실험 모두 $^{137}Cs$ 및 $^{60}Co$ 감마선장(線場)과 TRIGA Mark-II 원자로의 열중성자(熱中性子) column의 중성자공장(中性子工場)에서 행하여졌다. 감마선 흡수선량측정에는 TCD-700 $(^{7}LiF)$ chip을, 중성자선량측정에는 Au 방사화박(放射化薄)과 함께 TLD chip도 사용하였는데 이 경우에는 감마선의 기여를 판별해 내기 위하여 TLD-600 $(^{6}LiF)$과 TLD-700을 동시에 사용하였다. 감마선 조사(照射)의 경우 구(球) phantom내(內) 흡수선량의 이론적 해석은 Burlin의 공동이론(空洞理論)에서 유도된 Erlich의 방법을 썼으며, 중성자 선량해석에는 fluence-KERMA 변환방법을 사용하였다. 이들 선량에 관하여서는 특히 자세히 설명하였다. 해석에 실험결과는 모두 통계적으로 처리 분석하였으며 특히 심부선량분포(深部線量分布)는 규격화(規格化)한 값을 사용하여 도표(圖表)로 나타내는 한편, 결론에서는 방사선방호용 지수량(指數量) 실측(實測)의 가능성과 난점(難點)을 설명하고 해결하여야 할 문제점들을 언급(言及)하였다.

• Nuclear Engineering and Technology
• /
• 제1권2호
• /
• pp.91-101
• /
• 1969

인원자첨가농도가 6.4$\times$$10^{14}$ 부터 1.25$\times$$10^{17}$ ㎤까지인 n 형씰리콘 단결정들을 (1) 1 MeV 전자선과 (2) 두가지 연구용원자로와 (3) $Co^{6o}$ 감마선원으로 조사하고 이에 따르는 비저항의 변화를 측정하였고 이 측정결과를 Buehler가 제의한 실험식을 적용하여 분석했다. 이 지수실험식은 조사량이 적은 범위내에서는 대부분의 경우 잘 적용되나 1 MeV원자선조사에서는 측정결과와 잘 맞지 않으며 경우에 따라서는 선형변화식이 오히려 더 잘 적용된다는 것이 밝혀졌다. 특히 전자선조사 시료에서 조사량이 많을때 carrier 제거율에 큰 변화가 나타나는데 이것을 결함준위와 Fermi level과의 교환효과로 보고 자세히 살펴보았다. 위의 실험식이 적용되는 범위안에서 손상계수를 계산하고 손상계수에 의해서 n형 씰리콘의 비저항 변화에 미치는 여러가지 방사선원의 상대적효과를 비교하였다. 예컨대 TRIGA Mark II 연구로내의 중성자조사는 1 MeV 전자선 조사에 비하여 약 40배나 더 효과적으로 비저항 변화를 일으킨다는 것이 알려졌다. 조사전의 carrier농도와 손상계수와의 관계도 조사하였고 또 지수실험식의 물리적근거와 조사량이 많을때의 결함준위와 Fermi level와의 교차가 비저항변화에 미치는 효과도 아울러 고찰하였다.다.

• 한국의학물리학회지:의학물리
• /
• 제9권3호
• /
• pp.155-162
• /
• 1998

방사성 동위원소의 치료에 베타 방출 선원이 많이 이용되고 있다. 베타 방출 핵종 들은 투과력이 약해 방사선 도달거리 (range)가 짧아 병소내에 직접 주입하여 선택적으로 병소만을 조사하여 치료 의 효과를 얻을 수 있고 주변 정상 조직의 방사선 피폭을 줄일 수 있다. 최근 한국 원자력연구소의 원자로인 하나로를 이용하여 베타 입자 방출체인 Ho-l66 용액을 만들어 여기에 키토산 화합물을 표지 하였다. Ho-l66 은 고 에너지 베타 방출체라는 점과 일부 감마선이 방출됨으로써 감마카메라로 쉽게 영상을 얻을 수 있다는 장점이 있다. 본 연구에서는 감마카메라로 얻은 평면 영상을 이용하여 Ho-l66으로 치료한 부위와 그 주변의 정상 장기들의 방사선 홉수선량을 구하였다. 감마카메라는 Siemens 의 2중 head를 가진 Multispect2 시스템이 이용되었고, 콜리메이터는 medium energy, 최대 에너지는 80 keV, 창은 20%로 5분간 영상을 획득하였다. Ho-166 에 대한 투과인자 (transmission factor)는 환자 있을 때와 없을 때의 영상으로 관심영역의 ROIs 의 비로 구하였다 .3일간의 평면 영상으로 유효반감기를 구하여 Marinelli 공식과 MIRD 공식으로 베타입자에 대한 방사선 흡수선량을 구하였다. 감마선에 의한 흡수선량은 매우 적으므로 무시하였다. Transmission factor는 환자에 따라 다르지만 1110 MBq(30 mCi)을 주입하여 치료에 임한 간암 환자의 경우 간은 4.6, 비장은 4.65, 폐는 3.34, 뼈는 5.65 의 값을 보였다. 방사선 홉수선량은 tumor 에는 179.7, 정상간에는 16.3, 비장은 18.5, 폐에는 7.0, 뼈에는 9.0 Gy 가 각각 계산되었다. 이를 tumor dose 에 100%로 normalization 시킬 경우 정상간, 비장, 폐, 뼈에 각각 9.1, 10.3, 3.9, 5.0%로 분포되었음을 알았다. 본 연구를 통하여 tumor dose 뿐만이 아니고 주변 주요 위험장기 (critical organ) 에 대한 방사선 흡수선량을 전ㆍ후면 평면영상으로 얻을 수 있음을 보여 줌으로써 평면영상법을 이용한 dosimetry 의 가능성을 보았다. 또한 주변 주요 위험 장기의 한계선량에 맞는 주입할 양을 결정하는데 기초 자료가 될 수 있음을 보여준다.