• 지구물리
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• 제2권3호
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• pp.225-233
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• 1999

암석의 비저항값은 암석 자체의 성질뿐만 아니라 유체의 종류, 온도, 물 포화율, 접촉상태, 유도분극, 측정기기 및 사용전원의 주파수 등, 여러 요인에 의하여 영향을 받는다. 이 연구는 암석의 비저항을 정확하고 정밀하게 측정하기 위한 기초 연구의 일환으로서, 비저항 실측자료를 비교 분석하는 과정을 통하여 비저항 측정에 영향을 주는 다양한 요소들을 추적하고, 아울러 비저항 측정에 있어서 최적의 환경 조건을 찾고자 하였다. 특히 온도, 물 포화율, 시료와 전극의 접촉상태, 측정 주파수의 영향 등이 종합적으로 분석되었으며, 전도성 접착제와 절연 테이핑 방법 그리고 시계열 비저항자료의 이용이 비저항 측정의 정확도와 정밀도 향상에 크게 기여할 수 있음을 보였다.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.80-99
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• 2023

This paper presents the results of investigating the change in welding residual stresses of the core shroud, which is one of subcomponents in reactor vessel internals, performing finite element analysis. First, the welding residual stresses of the core shroud were calculated by applying the heat conduction based lumped pass technique and finite element elastic-plastic stress analysis. Second, the temperature distribution of the core shroud during the normal operation was calculated by performing finite element temperature analysis considering gamma heating. Third, through the finite element viscoelastic-plastic stress analysis using the calculated temperature distribution and setting the calculated residual stresses as the initial stress state, the variation of the welding residual stresses was derived according to repeating the normal operation. In the viscoelastic-plastic stress analysis, the effects of neutron irradiation on mechanical properties during the cyclic normal operations were considered by using the previously developed user subroutines for the irradiation agings such as irradiation hardening/embrittlement, irradiation-induced creep, and void swelling. Finally, the effect of neutron irradiation on the welding residual stresses was analysed for each irradiation aging. As a result, it is found that as the normal operation is repeated, the welding residual stresses decrease and show insignificant magnitudes after the 10^th refueling cycle. In addition, the irradiation-induced creep/void swelling has significant mitigation effect on the residual stresses whereas the irradiation hardening/embrittlement has no effect on those.

• Journal of Korean Biological Nursing Science
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• 제14권1호
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• pp.25-32
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• 2012

Purpose: influence of benzodiazepine (midazolam)or cholinergic inhibitor (atropine or glycopyrrlate) on intra-operative body temperature remains unclear and controversial. This study compares intra-operative body temperature in 50 abdominal surgical patients under general anesthesia between the administration of midazolam and glycopyrrolate in combination, or glycopyrrolate alone. Methods: Patients who underwent abdominal surgery were recruited from September 2008 through October 2009 at Gachon University Gil hospital in incheon. Core body temperature was measured in the right ear using a tympanic membrane thermometer at induction of general anesthesia and at 1 hr, 2 hr, and 3 hr after induction. Results: There were no differences in core body temperature at any measurement point between either patient group (F=1.08, $p$=.377). Core body temperature decreased throughout the 3 hr after induction in both groups (F=9.22, $p$ <.001). Specially, core temperatures at induction of general anesthesia (p<.001), 1 hr (p<.001), 2 hr ($p$ <.001), and 3 hr ($p$ <.001) after induction were lower than before administration of midazolam and glycopyrrolate, or glycopyrrolate alone. Conclusion: We conclude that a cholinergic inhibitor (glycopyrrolate, 0.1 mg) therefore seems not to affect intra-operative body temperature of patients given a benzodiazepine (midazolam, 0.04 mg $kg^{-1}$), and not to increase body temperature in patients not given a benzodiazepine during the 3 hr after the induction of general anesthesia. Intra-operative warming therefore is needed to prevent hypothermia in surgical patients who receive pre-operative administration of midazolam and/or glycopyrrolate.

• Nuclear Engineering and Technology
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• 제41권9호
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• pp.1171-1180
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• 2009

The internal core baffle structure of a French Pressurized Water Reactor (PWR) consists of a collection of baffles and formers that are attached to the barrel. The connections are done thanks to a large number of bolts (about 1500). After inspection, some of the bolts have been found cracked. This has been attributed to the Irradiation Assisted Stress Corrosion Cracking (IASCC). The $Electricit\acute{e}$ De France (EDF) has set up a research program to gain better knowledge of the temperature distribution, which may affect the bolts and the whole structure. The temperature distribution in the structure was calculated thanks to the thermal code SYRTHES that used a finite element approach. The heat transfer between the by-pass flow inside the cavities of the core baffle and the structure was accounted for thanks to a strong thermal coupling between the thermal code SYRTHES and the CFD code named Code_Saturne. The results for the CP0 plant design show that both the high temperature and strong temperature gradients could potentially induce mechanical stresses. The CPY design, where each bolt is individually cooled, had led to a reduction of temperatures inside the structures. A new parallel version of SYRTHES, for calculations on very large meshes and based on MPI, has been developed. A demonstration test on the complete structure that has led to about 1.1 billion linear tetraedra has been calculated on 2048 processors of the EDF Blue Gene computer.

• 한국정보통신설비학회:학술대회논문집
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• 한국정보통신설비학회 2009년도 정보통신설비 학술대회
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• pp.391-394
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• 2009

In this paper, achieved rise temperature distribution about degradation phenomenon of 2 MVA distribution mold transformer using finite element method (FEM). Usually, life of transformer is depended on temperature distribution of specification region than thermal special quality of transformer interior. Specially, life of transformer by decline of dielectric strength decreases rapidly in case rise by strangeness transformer interior hot spot temperature value permits. Because calculating high-voltage winding and low-voltage winding of mold transformer and Joule's loss of core for improvement these life, forecasted heat source, and high-voltage winding and low-voltage winding of mold transformer and rise temperature distribution of core for supply of electric power and temperature distribution of highest point on the basis of the result Also, calculated temperature rise limit of mold transformer and permission maximum temperature using analysis by electron miracle heat source alculate and forecasted rise temperature distribution by heat source of thermal analysis with calculated result.

• 폴리머
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• 제25권5호
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• pp.617-624
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• 2001

음이온계 유화제를 사용하여 monomer pre-emulsion을 제조한 다음 ammonium persulfate를 개시제로 하여 단계 중합법에 의해 새로운 입자의 생성이 적고 중합 과정에서 안정성이 우수한 poly(methyl methacrylate)(PMMA)/polystyrene (PSt) 라텍스를 제조하였다. 본 연구에서는 shell 중합시에 새로운 입자의 생성이 적고 중합 중 안정성이 우수한 라텍스를 제조하기 위해 개시제농도, 유화제농도, 중합온도가 PMMA/PSt와 PSt/PMMA의 core-shell 구조에 미치는 영향을 알아보았다. 중합한 라텍스를 입도분석기 (particle size analyzer: PSA) 및 투과전자현미경(transmission electron microscope; TEM)을 이용하여 실제 입자측정과 입자형태 특성을 확인하였으며 시차주사열량계 (differential scanning calorimeter, DSC)를 이용하여 유리전이온도($T_g$)의 측정, 필름 조막성 (minimum film formation temperature: MFFT), NaOH 첨가에 의한 가수 분해에 따르는 pH를 측정하여 core-shell의 또 다른 특성을 확인하였다.

• 대한기계학회논문집
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• 제9권6호
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• pp.750-756
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• 1985

본 연구에서는 종횡비 0.1이고 상.하 수평경계면이 단열된 직각밀폐용기내에 서 Pr수가 1보다 큰 물(Pr=6.97, 20.deg. C) 및 실리콘 오일(Pr=1086.42, 20.deg. C)의 양단의 온도차에 의한 자연대류에서 아직 충분히 연구되지 않은 코어형상에 주안점을 두고 실 험적으로 관찰, 조사하였으며 그 결과를 Lee의 이론적인 예측과도 비교, 검토해 보았 다.

• 한국전산유체공학회지
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• 제20권1호
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• pp.84-91
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• 2015

SMART adopts, very unique facility, an FMHA to enhance the thermal and flow mixing capability in abnormal conditions of some steam generators or reactor coolant pumps. The FMHA is important for enhancing thermal mixing of the core inlet flow during a transient and even during accidents, and thus it is essential that the thermal mixing characteristics of flow of the FMHA be understood. Investigations for the mixing characteristics of the FMHA had been performed by using experimental and CFD methods in KAERI. In this study, the temperature distribution at the core inlet region is investigated for several abnormal conditions of steam generators using the commercial code, FLUENT 12. Simulations are carried out with two kinds of FMHA shapes, different mesh resolutions, turbulence models, and steam generator conditions. The CFD results show that the temperature deviation at the core inlet reduces greatly for all turbulence models and steam generator conditions tested here, and the effect of mesh refinement on the temperature distribution at the core inlet is negligible. Even though the uniformity of FMHA outlet hole flow increases the thermal mixing, the temperature deviation at the core inlet is within an acceptable range. We numerically confirmed that the FMHA applied in SMART has an excellent mixing capability and all simulation cases tested here satisfies the design requirement for FMHA thermal mixing capability.

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.933-940
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• 2024

A macroscopic cross section generation model was developed for the conceptual horizontal, compact high temperature gas reactor (HC-HTGR). Because there are many sources of spectral effects in the design and analysis of the core, conventional LWR methods have limitations for accurate simulation of the HC-HTGR using a neutron diffusion core neutronics simulator. Several super-cell model configurations were investigated to consider the spectral effect of neighboring cells. A new history variable was introduced for the existing library format to more accurately account for the history effect from neighboring nodes and reactivity control drums. The macroscopic cross section library was validated through comparison with cross sections generated using full core Monte Carlo models and single cell cross section for both 3D core steady-state problems and 2D and 3D depletion problems. Core calculations were then performed with the AGREE HTR neutronics and thermal-fluid core simulator using super-cell cross sections. With the new history variable, the super-cell cross sections were in good agreement with the full core cross sections even for problems with significant spectrum change during fuel shuffling and depletion.

• Steel and Composite Structures
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• 제32권2호
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• pp.239-252
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• 2019

Since conical sandwich shells are important structures in the modern industries, in this paper, for the first time, vibration behavior of the truncated conical sandwich shells which include temperature dependent porous FG face sheets and temperature dependent homogeneous core in various thermal conditions are investigated. A high order theory of sandwich shells which modified by considering the flexibility of the core and nonlinear von Karman strains are utilized. Power law rule which modified by considering the two types of porosity volume fractions are applied to model the functionally graded materials. By utilizing the Hamilton's energy principle, and considering the in-plane and thermal stresses in the face-sheets and the core, the governing equations are obtained. A Galerkin procedure is used to solve the equations in a simply supported boundary condition. Uniform, linear and nonlinear temperature distributions are used to model the effect of the temperature changing in the sandwich shell. To verify the results of this study, they are compared with FEM results obtained by Abaqus software and for special cases with the results in literatures. Eigen frequencies variations are surveyed versus the temperature changing, geometrical effects, porosity, and some others in the numerical examples.