• 한국압력기기공학회 논문집
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• 제15권2호
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• pp.58-63
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• 2019

This paper presents preliminary analysis and results on IASCC sensitivity of a core shroud in the reactor pressure vessel. First, neutron irradiation flux distribution of the reactor internals was calculated by using the Monte Carlo simulation code, MCNP6.1 and the nuclear data library, ENDF/B-VII.1. Second, based on the neutron irradiation flux distribution, temperature and stress distributions of the core shroud during normal operation were determined by performing finite element analysis using the commercial finite element analysis program, ABAQUS, considering irradiation aging-related degradation mechanisms. Last, IASCC sensitivity of the core shroud was assessed by using the IASCC sensitivity definition of EPRI MRP-211 and the finite element analysis results. As a result of the preliminary analysis, it was found that the point at which the maximum IASCC sensitivity is derived varies over operating time, initially moving from the shroud plate located in the center of the core to the top shroud plate-ring connection brace over operating time. In addition, it was concluded that IASCC will not occur on the core shroud even after 60 years of operation (40EFPYs) because the maximum IASCC sensitivity is less than 0.5.

• 지구물리와물리탐사
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• 제15권2호
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• pp.102-115
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• 2012

이 논문은 퇴적물내 포함되어 있는 가스하이드레이트의 포화도를 계산하는 여러 방법에 대하여 토론하고자 한다. 가스하이드레이트의 포화도를 계산하는 방법은 물리검층 자료를 이용하는 방법과 코어자료(압력코어 포함)를 이용하는 방법, 그리고 탄성파 탐사자료로부터 얻을 수 있는 속도 자료를 이용하는 방법 등 크게 세가지 방법으로 나눌 수 있다. 물리검층 자료중 전기비저항 자료를 이용하는 방법의 경우 Archie 식을 주로 이용하는데 이 경우 각각의 변수 값을 정확하게 정의하는 게 중요하다. 또한 가스하이드레이트의 산출형태도 포화도 계산에 큰 영향을 주기 때문에 주의해야 한다. 코어자료를 이용하는 경우 공극수의 염소량을 측정하는 방법과 압력코어를 취득할 경우 이를 이용하는 방법이 있다. 지금까지 발표된 정량적이고 가장 정확한 가스하이드레이트 포화도값을 구할 수 있는 방법이 압력코어를 이용하는 것이다. 그러나 이는 비용과 시간이 많이 소요되기 때문에 연속적인 자료를 얻기가 어렵다는 단점이 있다. 지금까지 발표된 가스하이드레이트 포화도 값을 비교해 보면 전기비저항 값을 이용한 경우가 가장 높은 값을 압력코어를 이용하여 측정한 경우가 가장 낮은 값을 보여주는 경향이 있다. 그러나 이러한 값이 모든 경우에 있어서 절대적인 경향을 보여준다고 볼 수는 없다. 그러므로 가스하이드레이트의 포화도를 정확하게 계산하기 위해서는 여러 가지 방법을 이용하여 계산해야 하며 이를 비교하여 가장 적절한 값을 사용해야 할 것이다.

• 지질공학
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• 제24권3호
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• pp.423-429
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• 2014

본 연구에서는 국내 비전통에너지자원인 셰일가스, 석탄층메탄가스(CBM) 및 가스하이드레이트 개발사업의 정확한 매장량을 위해 온도와 압력을 실시간으로 기록하는 DLS (Data Logging System)가 내장된 저류층 PCS (Pressure Core Sampler)를 개발하여 국산화시키고, 지하심부의 시료가 채취된 순간부터 시료의 압력을 유지함으로써 시료 내 가스의 손실 없이 시추코어를 회수하는데 있다. 저류층 PCS는 일반적인 코어 샘플러와는 달리 입구 부분에 볼밸브와 같은 개폐 장치가 있어 일정 길이의 코어 샘플이 채취되면 입구를 밀폐하여 원위치 상태의 압력이 그대로 유지되게 하는 기능을 갖고 있다. 이것은 특히 셰일가스나 석탄층메탄가스 및 가스하이드레이트와 같은 기체를 포함한 시료의 정확한 분석을 위해 아주 중요한 역할을 하게 된다. 현재 PCS 장비 및 이를 활용한 기술은 미국과 유럽 등에서 독점하고 있는 상황이다. 이에 따라 기존 PCS의 동작원리 및 메커니즘 분석과 상세설계를 수행하여 저류층PCS를 개발중이며, 성능은 PCS 최대 사용압력 100 bar, PCS 최대 사용온도 $-20{\sim}40^{\circ}C$, PCS 압력 손실율 10%를 목표로 하고 있다.

• Journal of Advanced Marine Engineering and Technology
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• 제39권9호
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• pp.973-980
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• 2015

비전통 에너지자원은 전통 에너지자원에 비해 지리적으로 넓은 지역에 걸쳐 연속적인 형태로 분포되어 있으나, 잔존 기술적 회수가능 자원량(TRR : Technical Recoverable Resource)은 전통자원과 비슷하여 그 개발이 확대되고 있으며, 특히 셰일가스, 치밀가스, 석탄층 메탄가스, 가스하이드레이트 등의 비전통 가스자원의 개발이 활기를 띄고 있다. 그러나 현재의 물리검층 기술로는 비전통 자원에 포함된 물성, 특히 가스의 함량을 정확히 계산하기 어려우며 관련 기자재 또한 일부 해외 업체에서 독점하고 있다. 따라서 본 연구에서는 지하심부의 시료채취 순간부터 그 지점의 심부압력을 유지하여 시료 내 가스의 손실 없이 코어를 회수하고, 온도와 압력을 실시간으로 기록하는 저류층 PCS(Pressure Core Sampler)를 개발하였으며, 제작된 시제품의 검증을 위한 성능실험을 수행하였다. 모든 성능평가를 통과한 시제품은 In-situ 물성자료의 취득은 물론이고 정확하고 신뢰성 있는 시추코어를 확보하는 데 기여할 것이다.

• Nuclear Engineering and Technology
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• 제42권6호
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• pp.656-661
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• 2010

Lead-alloys are very attractive nuclear coolants due to their thermo-hydraulic, chemical, and neutronic properties. By utilizing the HELIOS (Heavy Eutectic liquid metal Loop for Integral test of Operability and Safety of PEACER$^2$) facility, a thermal hydraulic benchmarking study has been conducted for the prediction of pressure loss in lead-alloy cooled advanced nuclear energy systems (LACANES). The loop has several complex components that cannot be readily characterized with available pressure loss correlations. Among these components is the core, composed of a vessel, a barrel, heaters separated by complex spacers, and the plenum. Due to the complex shape of the core, its pressure loss is comparable to that of the rest of the loop. Detailed CFD simulations employing different CFD codes are used to determine the pressure loss, and it is found that the spacers contribute to nearly 90 percent of the total pressure loss. In the system codes, spacers are usually accounted for; however, due to the lack of correlations for the exact spacer geometry, the accuracy of models relies strongly on assumptions used for modeling spacers. CFD can be used to determine an appropriate correlation. However, application of CFD also requires careful choice of turbulence models and numerical meshes, which are selected based on extensive experience with liquid metal flow simulations for the KALLA lab. In this paper consistent results of CFX and Star-CD are obtained and compared to measured data. Measured data of the pressure loss of the core are obtained with a differential pressure transducer located between the core inlet and outlet at a flow rate of 13.57kg/s.

• Nuclear Engineering and Technology
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• 제33권4호
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• pp.441-456
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• 2001

ABB-CE＇s regionalization methodology for the core inlet flow distribution map is reviewed. This methodology merges the test data of fuel assembly locations which are either in symmetry or strongly correlated with others. It increases the number of available test data for each regional flow factor It makes up effectively for the deficiency due to limited number of test data. It also contributes to making the core inlet flow distribution smoother not only locally but also over the entire core, and to relieving the impacts of test errors that may happen due to some do- calibrated local pressure measurement taps. As a result, the core inlet How distribution data becomes more statistically useful and thus the conservatism involved in handling the core inlet flow factors for the thermal margin analysis is expected to be reduced. Meanwhile, the regionalized map may lose the unique local characteristics in core inlet flow distribution too much. By an alternative approach introduced in the present work, it is shown that such a disadvantage can be mitigated somewhat if the engineering judgement is made more

• 한국응용과학기술학회지
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• 제37권3호
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• pp.496-508
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• 2020

This study reviews studies on the core stabilization of respiratory muscle training for the elderly health. Previous research data and presenting basic literature data suggest that respiratory activation is an important mechanism for core strengthening via exercise interventions for the elderly. The review found that first, the mechanism of improving the respiratory muscles weakened by aging to address the loss of core function due to old age sarcopenia among the elderly results entails promoting the autonomic nervous system by focusing on the respiratory muscle activation pattern, the core muscle sensation mobilized for body centering. Second, nerve roots, intraperitoneal pressure, and deep muscles in the trunk of the body can be promoted while controlling respiratory stimulation with cognitive feedback. Effortful inspiration increases the activation of respiratory assistive muscles and effortless exhalation can improve the core muscle mobilization by involving abdominal muscles. Third, through respiratory muscle training, the elderly can increase their awareness of spinal centering and improve the ability to control the deep core muscles that must be mobilized for core stabilization. In conclusion, respiratory muscle training to increase the utilization of the trunk muscles seems to be a useful core stabilization exercise for the elderly with chronic tension and joint degeneration.

• 농업과학연구
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• 제39권3호
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• pp.427-439
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• 2012

In this study, an experiment with large-scale model was performed according to raising embankment in order to investigate the behaviour of failure due to overtopping. The pore water pressure, earth pressure and settlement by high water level, a rapid drawdown and overtopping were compared and analyzed. Also, seepage analysis and slope stability analysis were performed for steady state and transient conditions. The pore water pressure and earth pressure for inclined core type showed high value at the base of the core, but they showed no infiltration by leakage. The pore water pressure and earth pressure by overtopping increased at the upstream slope and core, it is considered a useful data that can accurately estimate the possibility of failure of the reservoir. The behavior of failure due to overtopping was gradually enlarged towards the downstream slope from reservoir crest, and the inclined core after the raising embankment was influenced significantly to prevent the reservoir failure. The pore water pressure distribution for steady state and transient condition showed positive (+) pore water pressure on the upstream slope, it was gradually changed negative (-) pore water pressure on the downstream slope. The pore water pressure by overtopping showed a larger than the high water level at the downstream slope, it was likely to be the piping phenomenon because the hydraulic gradients showed largely at the inclined core and reservoir crest. The safety factor showed high at the steady state, and transient conditions did not show differences depending on the rapid drawdown.

• Geomechanics and Engineering
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• 제14권1호
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• pp.19-27
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• 2018

It follows from the basic principles of mechanics of deformable solids relating to the strength, stability and propagation of elastic waves that the Earth's inner core cannot exist in the form of a spherical structure in the assumed thermobaric conditions and calculation values of physico-mechanical parameters. Pressure level reaches a value that is significantly greater than the theoretical limit of medium strength in the model approximations at the surface of the sphere of the inner core. On the other hand, equilibrium state of the sphere is unstable on the geometric forming at much lower loads under the influence of the "dead" surface loads. In case of the action of "follower" loads, the assumed pressure value on the surface of the sphere is comparable with the value of the critical load of "internal" instability. In these cases, due to the instability of the equilibrium state, propagation of homogeneous deformations becomes uneven in the sphere. Moreover, the elastic waves with actual velocity cannot propagate in such conditions in solid medium. Violation of these fundamental conditions of mechanics required in determining the physical and mechanical properties of the medium should be taken into account in the integrated interpretations of seismic and laboratory (experimental) data. In this case, application of the linear theory of elasticity and elastic waves does not ensure the reliability of results on the structure and composition of the Earth's core despite compliance with the required integral conditions on the mass, moment of inertia and natural oscillations of the Earth.

• Nuclear Engineering and Technology
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• 제51권6호
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• pp.1487-1503
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• 2019

The methods and performance of a pin-level nuclear reactor core thermal-hydraulics (T/H) code ESCOT employing the drift-flux model are presented. This code aims at providing an accurate yet fast core thermal-hydraulics solution capability to high-fidelity multiphysics core analysis systems targeting massively parallel computing platforms. The four equation drift-flux model is adopted for two-phase calculations, and numerical solutions are obtained by applying the Finite Volume Method (FVM) and the Semi-Implicit Method for Pressure-Linked Equation (SIMPLE)-like algorithm in a staggered grid system. Constitutive models involving turbulent mixing, pressure drop, and vapor generation are employed to simulate key phenomena in subchannel-scale analyses. ESCOT is parallelized by a domain decomposition scheme that involves both radial and axial decomposition to enable highly parallelized execution. The ESCOT solutions are validated through the applications to various experiments which include CNEN $4{\times}4$, Weiss et al. two assemblies, PNNL $2{\times}6$, RPI $2{\times}2$ air-water, and PSBT covering single/two-phase and unheated/heated conditions. The parameters of interest for validation include various flow characteristics such as turbulent mixing, spacer grid pressure drop, cross-flow, reverse flow, buoyancy effect, void drift, and bubble generation. For all the validation tests, ESCOT shows good agreements with measured data in the extent comparable to those of other subchannel-scale codes: COBRA-TF, MATRA and/or CUPID. The execution performance is examined with a mini-sized whole core consisting of 89 fuel assemblies and for an OPR1000 core. It turns out that it is about 1.5 times faster than a subchannel code based on the two-fluid three field model and the axial domain decomposition scheme works as well as the radial one yielding a steady-state solution for the OPR1000 core within 30 s with 104 processors.