• 터널과지하공간
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• 제34권1호
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• pp.71-87
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• 2024

고준위방사성폐기물 심층처분 시, 처분공 주변의 근계암반은 높은 지중응력과 재포화된 벤토나이트 완충재의 팽윤압, 방사성 원소 붕괴열의 영향을 받아 국부적으로 투수계수가 변화될 수 있다. 본 연구에서는 국내 유력한 처분 대상 부지 암종 중의 하나인 결정질 경암으로서의 화강암을 대상으로, 실제 처분 환경에서 예상되는 다양한 구속압과 온도 조건을 적용하여 투수계수 변화 특성을 실험적인 방법을 통하여 고찰하고자 하였다. KURT 화강암 시험편 하나당 3개 이상의 정수압 조건에서 투수시험을 수행하여 구속압이 증가함에 따라 투수계수가 지수적으로 감소하는 관계를 도출하였다. 예상 최대 온도로 설정한 90℃ 이하 수준에서는 온도에 의한 투수계수 변화가 무시 가능할 정도로 작음을 확인하였다. 추가로 초기투수계수가 초기공극률의 거듭제곱에 비례하는 상관관계를 도출함으로써, 특정 공극률을 지닌 화강암이 일정 구속압 하에 있을 때 가지는 투수계수 값을 유추할 수 있었다.

• 한국콘크리트학회:학술대회논문집
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• 한국콘크리트학회 2004년도 춘계 학술발표회 제16권1호
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• pp.160-163
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• 2004

In domestic, various repair materials and method systems to keep up with these reinforced concrete deteriorated due to salt damage, carbonation, chemical decay et. developed and applied. However, on-site quality control of various repair materials and method systems isn't achieved desirably because it is depend completely on a men of experience' opinions above all else regardless of various on-site environments. In this background, mock up test with due regard to real on-site environments was performed to secure fundamental data for establishment of desirable on-site quality control. Mock up test using repair mortar analyzed from angles of construction methods, mechanical spraying pressures, W/M. Construction methods were designed manpower method and spraying method, spraying pressures were designed 32, 42, 52 psi, W/M were designed 14.4, 15.4, $16.4\%$. And compressive strength, Chloride ion diffusion coefficient, bond strength, SEM. of mock up test specimens were evaluated. In conclusion, we confirmed excellency of mechanical spraying pressures, fined extremely excellency of condition of spraying pressure 42 ps, W/M $14.4\%$ within this study. therefore the results of this study will be useful to provide fundamental data for establishment of desirable on-site quality control.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.83-89
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• 2003

조사후 시험시설내에는 사용후 핵연료 집합체의 취급을 위하여 감온, 감압 공정이 있다. 이 공정에는 3가지 공정으로 분류하는데 첫째, 사용후핵연료집합체 캐스크를 제염하기 위한 제염시키는 공정, 둘째, 사용후핵연료집합체 내의 붕괴열에 의해 온도, 압력이 상승된 폐액을 감온, 감압 시키기 위한 냉각 공정 셋째, 사용후핵연료 피폭관 결함에 의해 발생되어 캐스크 내에 존재하는 불용성 입자를 여과기를 통해 여과하는 공정으로 되어 있다. 본 보고서에서는 감온, 감압 공정과 관련하여 현재까지 수행된 기술검토와 사용후핵연료집합체에 의한 감온, 감압의 실용적 이론에 관해 고찰하였고 또한 각종 시험을 통한 시운전 내용과 실제 원자력발전소로부터 수송해온 사용후핵연료집합체 J-44, K-23 대한 감온, 감압 결과들을 상세히 기술하였다. 본 보고서는 향후 지속적인 가동과 도출되지 않은 문제점 등을 계속 보완하여, 원만하고 안전한 정상조업을 수행하는데 효과적으로 이용될 수 있을 것으로 본다.

• Wind and Structures
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• 제21권2호
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• pp.119-158
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• 2015

The characteristics of the coherence functions of X axial, Y axial, and RZ axial (i.e., body axis) wind forces on the Shanghai World Trade Centre - a 492 m super-tall building with section varying along height are studied via a synchronous multi-pressure measurement of the rigid model in wind tunnel simulating of the turbulent, and the corresponding mathematical expressions are proposed there from. The investigations show that the mathematical expressions of coherence functions in across-wind and torsional-wind directions can be constructed by superimposition of a modified exponential decay function and a peak function caused by turbulent flow and vortex shedding respectively, while that in along-wind direction need only be constructed by the former, similar to that of wind speed. Moreover, an inductive analysis method is proposed to summarize the fitted parameters of the wind force coherence functions of every two measurement levels of altitudes. The comparisons of the first three order generalized force spectra show that the proposed mathematical expressions accord with the experimental results well. Later, the influences of coherence functions on wind-induced dynamic responses are analyzed in detail based on the proposed mathematical expressions and the frequency-domain method of random vibration theory.

• 한국압력기기공학회 논문집
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• 제19권2호
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• pp.163-170
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• 2023

Since spent nuclear fuel assemblies (SFA) are transported to interim storage or final disposal facility after cooling the decay heat, finite element analysis (FEA) with simplification is widely used to show their integrity against cladding failure to cause dispersal of radioactive material. However, there is a lack of research addressing the comprehensive impact of shape and element simplification on analysis results. In this study, for the optimization of a typical pressurized water reactor SFA, different types of finite element models were generated by changing number of fuel rods, fuel rod element type and assembly length. A series of FEA in use of these different models were conducted under a shock load data obtained from surrogate fuel assembly transportation test. Effects of number of fuel rods, element type and length of assembly were also analyzed, which shows that the element type of fuel rod mainly affected on cladding strain. Finally, an optimal finite element model was determined for other practical application in the future.

• Nuclear Engineering and Technology
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• 제39권4호
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• pp.287-298
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• 2007

As part of the $AP1000^{TM}$ pressurized water reactor design certification program, a series of integral systems tests of the nuclear steam supply system was performed at the APEX-1000 test facility at Oregon State University. These tests provided data necessary to validate Westinghouse safety analysis computer codes for AP1000 applications. In addition, the tests provided the opportunity to investigate the thermal-hydraulic phenomena expected to be important in AP1000 small-break loss of coolant accidents (SBLOCAs). The APEX-1000 facility is a 1/4-scale pressure and 1/4-scale height simulation of the AP1000 nuclear steam supply system and passive safety features. A series of eleven tests was performed in the APEX-1000 facility as part of a U.S. Department of Energy contract. In all, four SBLOCA tests representing a spectrum of break sizes and locations were simulated along with tests to study specific phenomena of interest. The focus of this paper is the SBLOCA tests. The key thermal-hydraulic phenomena simulated in the APEX-1000 tests, and the performance and interactions of the passive safety-related systems that can be investigated through the APEX-1000 facility, are emphasized. The APEX-1000 tests demonstrate that the AP1000 passive safety-related systems successfully combine to provide a continuous removal of core decay heat and the reactor core remains covered with considerable margin for all small-break LOCA events.

• Nuclear Engineering and Technology
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• 제48권6호
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• pp.1321-1329
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• 2016

To get an insight into the operating characteristics of the passive residual heat removal system of molten salt reactors, a two-phase natural circulation test facility was constructed. The system consists of a boiling loop absorbing the heat from the drain tank, a condensing loop consuming the heat, and a steam drum. A steady-state experiment was carried out, in which the thimble temperature ranged from $450^{\circ}C$ to $700^{\circ}C$ and the system pressure was controlled at levels below 150 kPa. When reaching a steady state, the system was operated under saturated conditions. Some important parameters, including heat power, system resistance, and water level in the steam drum and water tank were investigated. The experimental results showed that the natural circulation system is feasible in removing the decay heat, even though some fluctuations may occur in the operation. The uneven temperature distribution in the water tank may be inevitable because convection occurs on the outside of the condensing tube besides boiling with decreasing the decay power. The instabilities in the natural circulation loop are sensitive to heat flux and system resistance rather than the water level in the steam drum and water tank. RELAP5 code shows reasonable results compared with experimental data.

• International Journal of Naval Architecture and Ocean Engineering
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• 제5권2호
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• pp.227-245
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• 2013

Reliable strength assessment of the Liquefied Natural Gas (LNG) cargo containment system under the sloshing impact load is very difficult task due to the complexity of the physics involved in, both in terms of the hydrodynamics and structural mechanics. Out of all those complexities, the proper selection of the design sloshing load which is applied to the structural model of the LNG cargo containment system, is one of the most challenging one due to its inherent randomness as well as the statistical analysis which is tightly linked to the design sloshing load selection. In this study, the response based strength assessment procedure of LNG cargo containment system has been developed and proposed as an alternative design methodology. Sloshing pressure time history, measured from the model test, is decomposed into wavelet basis function targeting the minimization of the number of the basis function together with the maximization of the numerical efficiency. Then the response of the structure is obtained using the finite element method under each wavelet basis function of different scale. Finally, the response of the structure under entire sloshing impact time history is rapidly calculated by synthesizing the structural response under wavelet basis function. Through this analysis, more realistic response of the system under sloshing impact pressure can be obtained without missing the details of pressure time history such as rising pattern, oscillation due to air entrapment and decay pattern and so on. The strength assessment of the cargo containment system is then performed based on the statistical analysis of the stress peaks selected out of the obtained stress time history.

• 한국운동역학회지
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• 제16권1호
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• pp.101-108
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• 2006

The purpose of this study was to compare GRF characteristics during walking wearing jogging and roller shoes. Twelve male middle school students (age: $15.0{\pm}0.0\;yrs$, height: $173.6{\pm}5.0\;cm$, weight: $587.6{\pm}89.3\;N$) who have no known musculoskeletal disorders were recruited as the subjects. Kinematic data from six S-VHS camcorders(Panasonic AG456, 60 fields/s) and GRF data from two force platform; (AMII OR6-5) were collected while subjects walked wearing roller and jogging shoes in random order at a speed of 1.1 m/s. An event sync unit with a bright LED light was used to synchronize the video and GRF recordings. GRF data were filtered using a 20 Hz low pass Butterworth. digital filter and further normalized to the subject's body weight. For each trial being analyzed, five critical instants and four phases were identified from the recording. Temporal parameters, GRFs, displacement of center of pressure (DCP), and loading and decay rates were determined for each trial. For each dependent variable, paired t-test was performed to test if significant difference existed between shoe conditions (p <.05). Vertical GRFs at heel contact increased and braking forces at the end of initial double limb stance reduced significantly when going from jogging shoe to roller shoe condition. Robbins and Waked (1997) reported that balance and vertical GRF are closely related It seems that the ankle and knee joints are locked in an awkward fashion at the heel contact to compensate for the imbalance. The DCP in the antero-posterior direction for the roller shoe condition was significantly less than the corresponding value for the jogging shoe condition. Because the subjects tried to keep their upper body weight in front of the hip to prevent falling backward, the DCP for the roller shoe condition was restricted The results indicate that walking with roller shoes had little effect on temporal parameters, and loading and decay rates. It seems that there are differences in GRF characteristics between roller shoe and jogging shoe conditions. The differences in GRF pattern may be caused primarily by the altered position of ankle, knee, and center of mass throughout the walking cycle. Future studies should examine muscle activation patterns and joint kinematics during walking with roller shoes.

• 한국지반공학회논문집
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• 제19권6호
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• pp.207-216
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• 2003

본 논문에서는 국내 서해안 연약 지반 현장에서 PBD 타설로 인한 교란 영역을 확인하기 위하여 현장지반에 10개의 간극수압계를 PBD 타설 위치로부터 10cm, 20cm, 30cm, 40cm 그리고 50cm 그리고 50cm 떨어져 설치하고 멘드렐을 이용한 PBD 강제 관입시 발생하는 과잉간극수압의 소산과정을 5m, 7m 깊이에서 측정하였다. PBD 타설로 인해 지반교란이 발생하면 연약점토 지반의 투수계수가 감소하게 되어 과잉간극수압의 소산시간에 영향을 미치게 되므로 PBD 타설거리로부터 PBD 타설 전후의 과잉간극수압 소산과정을 측정하여 Smear Zone의 범위를 정하였다. 또한 이러한 과잉간극수압 소산과정을 해석하여 PBD타설 전후의 지반 배수특성저하를 규명하였다. 과잉간극수압 소산을 해석하기 위하여 시험 지반의 강성지수가 필요한데 이러한 강성지수 측정을 위하여 Cone-Pressuremeter(CPM)시험을 병행하였다. 시험결과 멘드렐의 환산직경의 3.0-3.6배에 Smear Zone이 형성되는 것으로 조사되었으며 Teh & Houlsby의 식과 CPM을 이용한 수평압밀계수를 평가한 결과 PBD타설전후로 지반의 배수능력이 3-8배 저하된 것으로 계산되었다.