• 제목/요약/키워드: Cross-reactivity

검색결과 292건 처리시간 0.026초

Evaluation of commercial immunochromatography test kits for diagnosing canine parvovirus

  • Lee-Sang Hyeon;Dong-Kun Yang;Eun-Ju Kim;Yu-Ri Park;Hye Jeong Lee;Bang-Hun Hyun
    • 대한수의학회지
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    • 제63권2호
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    • pp.19.1-19.6
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    • 2023
  • Rapid immunochromatography test (RICT) kits are commonly used for the diagnosis of canine parvovirus (CPV) because of their rapid turnaround time, simplicity, and ease of use. However, the potential for cross-reactivity and low sensitivity can yield false-positive or false-negative results. There are 4 genotypes of CPV. Therefore, evaluating the performance and reliability of RICT kits for CPV detection is essential to ensure accurate diagnosis for appropriate treatment. In this study, we evaluated the performance of commercial RICT kits in the diagnosis of all CPV genotypes. The cross-reactivity of 6 commercial RICT kits was evaluated using 8 dog-related viruses and 4 bacterial strains. The limit of detection (LOD) was measured for the 4 genotypes of CPV and feline panleukopenia virus. The tested kits showed no cross-reactivity with the 8 dog-related viruses or 4 bacteria. Most RICT kits showed strong positive results for CPV-2 variants (CPV-2a, CPV-2b, and CPV-2c). However, the 2 kits produced negative results for CPV-2 or CPV-2b at a titer of 105 FAID50/mL, which may result in inaccurate diagnoses. Therefore, some kits need to improve their LOD by increasing their binding efficiency to detect all CPV genotypes.

어머니의 우울과 학령전기 유아의 정서 문제 간의 상호적 관계에 대한 단기 종단연구 (A Short-Term Longitudinal Study on the Reciprocal Relations between Mothers' Depression and Their Preschoolers' Emotional Problems)

  • 장영은;한효정
    • Human Ecology Research
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    • 제54권5호
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    • pp.551-564
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    • 2016
  • This study examined the causal relationship between a mothers' depression and the emotional problems of their preschool-aged children as indicated by anxiety, depression and emotional reactivity. We analyzed data from 1,528 mothers and their children from the Panel Study of Korean Children (PSKC) collected when the children were 4 years old and 5 years old. Autoregressive cross-lagged modeling was conducted using AMOS ver. 23.0 to investigate the longitudinal reciprocal effects between mothers' depression and children's emotional problems. The results indicated that both mothers' depression and children's emotional problems were relatively stable between the ages of 4 to 5. There were significant cross-lagged effects from the mothers' depression to children's emotional problems and from children's emotional problems to mothers' depression. Mothers reported higher levels of depression when the children were 4 years old and the children showed more anxiety, depression and emotional reactivity when they were 5 years old. Emotional problems when the children were 4 predicted greater depression among mothers 1 year later. We also examined the group difference (between boys and girls) in the study model. Gender differences were not statistically supported. The results suggested that early assessment and intervention for mothers' depression and children's emotional problems are essential for a healthy mother-child relationship and later child outcomes.

3차원 중성자 확산계산을 위한 KMRR Hafnium 조정집합체 균질화에 대한 연구 (Homogenization of KMRR Hafnium Control Assembly for 3-D Diffusion Calculation)

  • Park, Hang-Bok;Kim, Young-Jin;Kim, Hark-Rho;Lee, Ji-Bok
    • Nuclear Engineering and Technology
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    • 제20권4호
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    • pp.233-240
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    • 1988
  • KMRR은 잉여반응도 및 출력분포조절을 위하여 Hafnium관을 사용한다. 현재 노심해석은 핵연료집합체 단위로 균질화된 5군 군정수를 이용하여 중성자 확산코드인 VENTURE을 이용한다. Hafnium관내에 핵연료가 들어있는 특수한 조정 집합체에 대해서도 이러한 균질화된 군정수를 사용한 중성자 확산계산이 적용될 수 있는가를 조사하였다. 비교계산은 중성자 수송코드인 TWOTRAN을 사용하여 잉여반응도 및 출력 준위에 대해 수행하였다. 계산결과 현재의 균질화된 군정수를 사용하는 중성자 확산계산이 큰 오차없이 적용할 수 있는 것으로 나타났다.

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Development of a fast reactor multigroup cross section generation code EXUS-F capable of direct processing of evaluated nuclear data files

  • Lim, Changhyun;Joo, Han Gyu;Yang, Won Sik
    • Nuclear Engineering and Technology
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    • 제50권3호
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    • pp.340-355
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    • 2018
  • The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F are described that is capable of directly processing Evaluated Nuclear Data File format nuclear data files. RECONR of NJOY is used to generate pointwise XS data, and Doppler broadening is incorporated by the Gauss-Hermite quadrature method. The self-shielding effect is incorporated in the ultrafine group XSs in the resolved and unresolved resonance ranges. Functions to generate scattering transfer matrices and fission spectrum matrices are realized. The extended transport approximation is used in zero-dimensional calculations, whereas the collision probability method and the method of characteristics are used for one-dimensional cylindrical geometry and two-dimensional hexagonal geometry problems, respectively. Verification calculations are performed first for various homogeneous mixtures and cylindrical problems. It is confirmed that the spectrum calculations and the corresponding multigroup XS generations are performed adequately in that the reactivity errors are less than 50 pcm with the McCARD Monte Carlo solutions. The nTRACER core calculations are performed with the EXUS-F-generated 47 group XSs for the two-dimensional Advanced Burner Reactor 1000 benchmark problem. The reactivity error of 160 pcm and the root mean square error of the pin powers of 0.7% indicate that EXUF-F generates properly the broad-group XSs.

Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis

  • Nguyen, Tung Dong Cao;Lee, Hyunsuk;Lee, Deokjung
    • Nuclear Engineering and Technology
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    • 제53권9호
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    • pp.2788-2802
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    • 2021
  • Multigroup cross section (MG XS) generation by the UNIST in-house Monte Carlo (MC) code MCS for fast reactor analysis using nodal diffusion codes is reported. The feasibility of the approach is quantified for two sodium fast reactors (SFRs) specified in the OECD/NEA SFR benchmark: a 1000 MWth metal-fueled SFR (MET-1000) and a 3600 MWth oxide-fueled SFR (MOX-3600). The accuracy of a few-group XSs generated by MCS is verified using another MC code, Serpent 2. The neutronic steady-state whole-core problem is analyzed using MCS/RAST-K with a 24-group XS set. Various core parameters of interest (core keff, power profiles, and reactivity feedback coefficients) are obtained using both MCS/RAST-K and MCS. A code-to-code comparison indicates excellent agreement between the nodal diffusion solution and stochastic solution; the error in the core keff is less than 110 pcm, the root-mean-square error of the power profiles is within 1.0%, and the error of the reactivity feedback coefficients is within three standard deviations. Furthermore, using the super-homogenization-corrected XSs improves the prediction accuracy of the control rod worth and power profiles with all rods in. Therefore, the results demonstrate that employing the MCS MG XSs for the nodal diffusion code is feasible for high-fidelity analyses of fast reactors.

Evaluation of coolant density history effect in RBMK type fuel modelling

  • Tonkunas, Aurimas;Pabarcius, Raimоndas;Slavickas, Andrius
    • Nuclear Engineering and Technology
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    • 제52권11호
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    • pp.2415-2421
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    • 2020
  • The axial heterogeneous void distribution in a fuel channel is a relevant and important issue during nuclear reactor analysis for LWR, especially for boiling water channel-type reactors. Variation of the coolant density in fuel channel has an effect on the neutron spectrum that will in turn have an impact on the values of absolute reactivity, the void reactivity coefficient, and the fuel isotopic compositions during irradiation. This effect is referring to as the history effect in light water reactor calculations. As the void reactivity effect is positive in RBMK type reactors, the underestimation of water density heterogeneity in 3D reactor core numerical calculations could cause an uncertainty during assessment of safe operation of nuclear reactor. Thus, this issue is analysed with different cross-section libraries which were generated with WIMS8 code at different reference water densities. The libraries were applied in single fuel model of the nodal code of QUABOX-CUBBOX/HYCA. The thermohydraulic part of HYCA allowed to simulate axial water distribution along fuel assembly model and to estimate water density history effect for RBMK type fuel.

원자로 출력제어계통 개발 (Development of Power Control System for Nuclear Power Plants)

  • 이종무;김춘경;천종민;김흥주;권순만
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2007년도 심포지엄 논문집 정보 및 제어부문
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    • pp.253-254
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    • 2007
  • This paper deals with the development of power control system(PCS) for nuclear power plants. The PCS provides the control motive power to operate the CEDMs(Control Element Drive Mechanism) for reactivity control inside the reactor vessel. The CEDM is raise and lower the CEAs( Control Element Assemblies) inside the reactor core. The CEAs are constructed with the Boron-10 isotope which has a high microscopic cross section of absorption for thermal neutrons. This characteristic causes the addition of negative reactivity when a CEA is inserted and positive reactivity when it is withdrawn from the reactor core.

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Conceptual Core Design of 1300MWe Reactor for Soluble Boron Free Operation Using a New Fuel Concept

  • Kim, Soon-Young;Kim, Jong-Kyung
    • Nuclear Engineering and Technology
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    • 제31권4호
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    • pp.391-400
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    • 1999
  • A conceptual core design of the 1,300MWe KNGR (Korean Next Generation Reactor) without using soluble boron for reactivity control was developed to determine whether it is technically feasible to implement SBF (Soluble Boron Free) operation. Based on the borated KNGR core design, the fuel assembly and control rod configuration were modified for extensive use of burnable poison rods and control rods. A new fuel rod, in which Pu-238 had been substituted for a small amount of U-238 in fuel composition, was introduced to assist the reactivity control by burnable poison rods. Since Pu-238 has a considerably large thermal neutron capture cross section, the new fuel assembly showed good reactivity suppression capability throughout the entire cycle turnup, especially at BOC (Beginning of Cycle). Moreover, relatively uniform control of power distribution was possible since the new fuel assemblies were loaded throughout the core. In this study, core excess reactivity was limited to 2.0 %$\delta$$\rho$ for the minimal use of control rods. The analysis results of the SBF KNGR core showed that axial power distribution control can be achieved by using the simplest zoning scheme of the fuel assembly Furthermore, the sufficient shutdown margin and the stability against axial xenon oscillations were secured in this SBF core. It is, therefore, concluded that a SBF operation is technically feasible for a large sized LWR (Light Water Reactor).

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0세부터 3세까지 영유아의 부정적 정서성과 어머니의 온정성/반응성 간의 양방향적 관계 (Bidirectional Associations between the Negative Emotionality of 0-to 3-year-old Children and Maternal Warmth / Reactivity)

  • 김수정;정익중
    • 아동학회지
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    • 제36권4호
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    • pp.1-16
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    • 2015
  • The purpose of this study was to examine the bidirectional relationship between the negative emotionality of 0-to 3-year-old and maternal parenting styles, focusing on warmth and reactivity. Four waves of panel data from the Korean Children Panel Study(KCPS) were analyzed in this study by means of autoregressive cross-lagged modeling. The results of this study were as follows. First, negative emotionality and maternal parenting styles were consistently stable for 0-to 3-year-old. Second, a bidirectional relationship between negative emotionality and maternal warmth parenting styles was confirmed according to the appearance of both parent and child effects. In other words, higher levels of negative emotionality was associated with lower maternal warmth parenting styles across time and in both directions. Additionally, the relationship between negative emotionality and maternal reactivity parenting styles were partially identified as being bidirectional in nature, whilst also being related to age. These findings suggested that parent education aimed at strengthening parenting skills, and programs designed to relieve negative emotionality of 0-to 3-year-olds are clearly needed.

A Study on Reusable Metal Component as Burnable Absorber Through Monte Carlo Depletion Analysis

  • Muth, Boravy;Alrawash, Saed;Park, Chang Je;Kim, Jong Sung
    • 방사성폐기물학회지
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    • 제18권4호
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    • pp.481-496
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    • 2020
  • After nuclear power plants are permanently shut down and decommissioned, the remaining irradiated metal components such as stainless steel, carbon steel, and Inconel can be used as neutron absorber. This study investigates the possibility of reusing these metal components as neutron absorber materials, that is burnable poison. The absorption cross section of the irradiated metals did not lose their chemical properties and performance even if they were irradiated over 40-50 years in the NPPs. To examine the absorption capability of the waste metals, the lattice calculations of WH 17×17 fuel assembly were analyzed. From the results, Inconel-718 significantly hold-down fuel assembly excess reactivity compared to stainless steel 304 and carbon steel because Inconel-718 contains a small amount of boron nuclide. From the results, a 20wt% impurity of boron in irradiated Inconel-718 enhances the excess reactivity suppression. The application of irradiated Inconel-718 as a burnable absorber for SMR core was investigated. The irradiated Inconel-718 impurity with 20wt% of boron content can maintain and suppress the whole core reactivity. We emphasize that the irradiated metal components can be used as burnable absorber materials to control the reactivity of commercial reactor power and small modular reactors.