• Nuclear Engineering and Technology
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• 제32권1호
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• pp.17-33
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• 2000

A mechanistic model based on wall-attached bubble coalescence, previously developed by the authors, was extended to predict a vow high critical heat flux (CHF）in highly subcooled flow boiling, especially for high mass flux and small tube diameter conditions. In order to take into account the enhanced condensation due to high subcooling and high mass velocity in small diameter tubes, a mechanistic approach was adopted to evaluate the non-equilibrium flow quality and void fraction in the subcooled water flow boiling, with preserving the structure of the previous CHF model. Comparison of the model predictions against highly subcooled water CHF data showed relatively good agreement over a wide range of parameters. The significance of the proposed CHF model lies in its generality in applying over the entire subcooled flow boiling regime including the operating conditions of fission and fusion reactors.

• Journal of Welding and Joining
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• 제30권3호
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• pp.51-56
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• 2012

Different microstructures in the weld zone of a metal structure including a fusion zone and heat affected zone are formed as compared to the base material. Thus, the mechanical properties in the weld zone are different from those in the base material. As the basic data for reliably understanding the structural characteristics of welded nuclear material, the mechanical properties in the weld zone and base material for a Zircaloy-4 strap and Hastelloy${(R)}$-X alloy strap are measured using an instrumented indentation technique (IIT) in this study.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1210-1217
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• 2023

The assessment of radiation fields in the lithium loop pipes and dump tank during the operation were performed for International Fusion Materials Irradiation Facility - DEMO-Oriented NEutron Source (IFMIF-DONES) in order to obtain the radiation dose-rate maps in the component surroundings. Variance reduction techniques such as weight window mesh (produced with the ADVANTG code) were applied to bring the statistical uncertainty down to a reasonable level. The biological dose was given in the study, and potential shielding optimization is suggested and more thoroughly evaluated. The MCNP Monte Carlo was used to simulate a gamma particle transport for radiation shielding purposes for the current Li Systems' design. In addition, the shielding efficiency was identified for the Impurity Control System components and the dump tank. The analysis reported in this paper takes into account the radiation decay source from and activated corrosion products (ACPs), which is created by d-Li interaction. As a consequence, the radiation (resulting from ACPs and Be-7) shielding calculations have been carried out for safety considerations.

• 한국지진공학회논문집
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• 제24권3호
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• pp.123-128
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• 2020

Analysis of the 2016 Gyeongju earthquake and the 2017 Pohang earthquake showed the characteristics of a typical high-frequency earthquake with many high-frequency components, short time strong motion duration, and large peak ground acceleration relative to the magnitude of the earthquake. Domestic nuclear power plants were designed and evaluated based on NRC's Regulatory Guide 1.60 design response spectrum, which had a great deal of energy in the low-frequency range. Therefore, nuclear power plants should carry out seismic verification and seismic performance evaluation of systems, structures, and components by reflecting the domestic characteristics of earthquakes. In this study, high-frequency amplification factors that can be used for seismic verification and seismic performance evaluation of nuclear power plant systems, structures, and equipment were analyzed. In order to analyze the high-frequency amplification factor, five sets of seismic time history were generated, which were matched with the uniform hazard response spectrum to reflect the characteristics of domestic earthquake motion. The nuclear power plant was subjected to seismic analysis for the construction of the Korean standard nuclear power plant, OPR1000, which is a reactor building, an auxiliary building assembly, a component cooling water heat exchanger building, and an essential service water building. Based on the results of the seismic analysis, a high-frequency amplification factor was derived upon the calculation of the floor response spectrum of the important locations of nuclear power plants. The high-frequency amplification factor can be effectively used for the seismic verification and seismic performance evaluation of electric equipment which are sensitive to high-frequency earthquakes.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2006년 학술대회 논문집 정보 및 제어부문
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• pp.295-296
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• 2006

Prototype NBI(Neurtal Beam Injector), which Is tested at KAERI(Kaeri Atomic Energy Research Instutide), is the facility for tokamak plasma Ignition of the advanced nuclear fusion KSTAR(Korea Superconducting Tokamak Advanced Research). New NBI facility, which is the part of KSTAR tokamak, will be constructed during next three years. This investigation is focused on the preliminary test to construct the control system for KSTAR NBI, before KSTAR NBI facility is constructed.

• 핵의학기술
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• 제12권3호
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• pp.214-221
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• 2008

목적 : 융합 SPECT/CT가 기존 SPECT에 비해 병소의 해부학적 위치를 정확히 판단할 수 있는지 정성 평가하고, CT 감쇠 보정이 SPECT 영상에 미치는 효과를 알아보아 SPECT/CT의 유용성을 제시하고자 한다. 실험재료 및 방법 : 1. 융합 영상의 평가 : 2008년 1월(月)부터 8월(月)까지 Precedence 16 혹은 Symbia T2에서 $^{131}I$-MIBG, Bone, $^{111}In$-Octreotide, Meckel 게실, Parathyroid MIBI 등을 SPECT/CT 시행한 환자를 대상으로 하였고, SPECT/CT영상을 융합한 것과 하지 않은 것을 비교하여 정성 평가하였다. 2. 감쇠보정의 평가 : Symbia T2로 2008년 6월에서 8월까지 $^{201}Tl$ 심근 검사를 한 환자 38명을 대상으로 Cedars-Sinai의 QPS를 이용하여 산출하였다. Ant, Inf, Lat, Septum, Apex로 5개부분으로 분류하고, 각 부분에 대한 관류의 상태를 백분율로 산출했다. CT AC와 Non AC를 평균${\pm}$표준편차로 각 부분에 대한 관류 상태를 비교하고 차이를 분석하였다. 결과 : 1. 융합 영상의 평가 : 에너지가 높은 $^{131}I$ SPECT의 경우 병소와 주위 조직 간의 섭취율 차이로 인해 (주위 조직이 saturation 됨) 병소의 위치 파악이 어려웠으나 CT로 융합한 결과 해부학적 위치를 정확히 평가할 수 있었다. 또한 멕켈게실이나 $^{111}In$과 같이 장이나 장기쪽에 질환을 찾는 경우에는 그 우수성이 더욱 뛰어 났다. Bone SPECT/CT는 척추간의 구별을 확실히 할 수 있어 임상의가 정확한 결과를 제시하는데 도움을 준다. 2. 감쇠 보정의 평가 : 감쇠 보정 전후의 관류 백분율의 차이가 Ant, Lat에서는 통계적으로 유의한 차이가 없었으나(p>0.05), Inferior, Apex, Septum에서는 유의한 차이가 있었다(p<0.05). 차이를 보이는 값 중 Inferior Wall에서 CT AC perfusion : $76.84{\pm}6.52%$, Non AC perfusion : $68.58{\pm}7.55%$로 CT 보정에 의한 차이가 $8.26{\pm}4.95%$로 가장 크게 측정되었다(t=10.29, p<0.01). 결론 : SPECT에 CT가 부착되면서 병변의 기능적 활성도를 나타내는 분자학적 영상은 물론 병변의 해부학적 위치 정보를 보다 정확하게 확인할 수 있게 되었다. 이것은 비정상적 부위를 찾아내는 것에 그치지 않고 복잡한 인체 부위에서 정상군과 비정상군을 분리하는데 많은 도움을 주게 되었다. 따라서 임상의는 하나의 검사 영상으로 진단과 치료계획을 동시에 시행할 수 있을 것이다. 또한 감쇠가 잘 되는 흉곽 부위 안에 있는 심근 검사에는, CT로 보다 정확한 감쇠 보정을 할 수 있기 때문에 SPECT 검사 시 관심부위의 관류 상태를 더욱 신뢰할 수 있어 치료 예후의 정당성을 입증할 수 있을 것으로 판단된다.

• 한국진공학회지
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• 제15권1호
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• pp.14-23
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• 2006

스크롤 펌프는 초청정 진공 시스템에서 많이 사용되고 있지만 막상 수소 배기 특성에 대해서 잘 알려져 있지 않다 이런 정보부족은 수소를 다량 사용하는 핵융합 실험장치에서 스크롤 점프가 사용 가능한지 판단하기 어렵게 만든다 이 논문에서는 특히 수소에 대한 스크롤펌프의 배기속도, 압측비 및 역류특성을 측정하기 위해 구성한 실험장치, 측정절차와 실험결과에 대해 기술하고 논의했다.

• KIEE International Transactions on Power Engineering
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• 제3A권2호
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• pp.100-108
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• 2003

This paper presents the design and performance results of a pair of 6-kA high-temperature superconducting (HTS)-copper current leads, in which, over a short length at the warm end (e.g.,77K) of each HTS section, comprised of paralleled Bi-2223/Ag-Au tapes, is operated in the current-sharing mode. Because of their reliance on vapor cooling, the leads are applicable only to liquid helium cooled superconducting magnets such as those used in high-energy Physics accelerators and fusion machines. The experimental measurements have demonstrated that key performance data of the new 6-kA HTS-Copper leads agree reasonably well with those expected from design.

• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1345-1356
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• 2021

Damage to nuclear power plants causes human casualties and environmental disasters. There are electrical facilities that control safety-related devices in nuclear power plants, and seismic performance is required for them. The 2016 Gyeongju earthquake had many high-frequency components. Therefore, there is a high possibility that an earthquake involving many high frequency components will occur in South Korea. As such, it is necessary to examine the safety of nuclear power plants against an earthquake with many high-frequency components. In this study, the shaking table test of electrical facilities was conducted against the design earthquake for nuclear power plants with a large low-frequency components and an earthquake with a large high-frequency components. The response characteristics of the earthquake with a large high-frequency components were identified by deriving the amplification factors of the response through the shaking table test. In addition, safety of electrical facility against the two aforementioned types of earthquakes with different seismic characteristics was confirmed through limit-state seismic tests. The electrical facility that was performed to the shaking table test in this study was a motor control center (MCC).

• 한국지진공학회논문집
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• 제27권1호
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• pp.69-75
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• 2023

In Korea, most nuclear power plants were designed based on the design response spectrum of Regulatory Guide 1.60 of the NRC. However, in the case of earthquakes occurring in the country, the characteristics of seismic motions in Korea and the design response spectrum differed. The seismic motion in Korea had a higher spectral acceleration in the high-frequency range compared to the design response spectrum. The seismic capacity may be reduced when evaluating the seismic performance of the equipment with high-frequency earthquakes compared with what is evaluated by the design response spectrum for the equipment with a high natural frequency. Therefore, EPRI proposed the inelastic energy absorption factor for the equipment anchorage. In this study, the seismic performance of welding anchorage was evaluated by considering domestic seismic characteristics and EPRI's inelastic energy absorption factor. In order to reflect the characteristics of domestic earthquakes, the uniform hazard response spectrum (UHRS) of Uljin was used. Moreover, the seismic performance of the equipment was evaluated with a design response spectrum of R.G.1.60 and a uniform hazard response spectrum (UHRS) as seismic inputs. As a result, it was confirmed that the seismic performance of the weld anchorage could be increased when the inelastic energy absorption factor is used. Also, a comparative analysis was performed on the seismic capacity of the anchorage of equipment by the welding and the extended bolt.