• Journal of Radiation Protection and Research
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• 제33권3호
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• pp.113-120
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• 2008

이 연구에서는 국내 개발중인 초고온가스로 (VHTR: Very High Temperature Reactor)를 대상으로, 발생되는 삼중수소 양, 계통간 이송, 제거, 분포 그리고 최종적으로 생산된 수소에 대한 삼중수소에 의한 오염 준위를 예측할 수 있는 해석 모델인 TRITGO 코드를 소개하였고, 수소를 생산하는 IS (Iodine Sulfide) 계통으로의 삼중수소 투과양을 모의할 수 있도록 코드를 개선하였다. 또한 GT-MHR 600MW 열출력을 가정, 최종 수소 생산물의 삼중수소에 의한 오염치를 예측하였다. 예상 오염치는 약 0.055 Bq/$H_2-g$으로 일본 규제치 56 Bq/$H_2-g$에 약 1/1000 수준으로 낮게 예측되었다. 모의 결과 삼중수소 방출을 억제하기 위해서는 피복관의 건전성 유지 및 헬륨 냉각재와 흑연으로 구성된 반사체내 불순물인 $^3He$ 및 Li을 가능한한 낮은 준위로 유지하는 것이 필요함을 보여 주었다. 또한 냉각재내 불순물을 직접 제거할 수 있는 정화계통의 성능이 중요한 설계인자로 판단되었다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2007년도 춘계학술대회B
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• pp.2873-2878
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• 2007

The mixing vanes attached to the spacer grid of rod bundles are used to improve the heat transfer in heat exchanger devices by controlling the characteristics of the flow structures and turbulence. In this study, velocity patterns induced by two types of mixing vane(split and swirl vane) are measured by the PIV technique to better understand how to effect on the cross and secondary vortex flow patterns in $5{\times}$ rod bundle simulating the fuel assembly of the nuclear reactor. A successful measurement of the lateral velocity patterns was conducted using a specially designed beam sheet generator and experimental loop at KAERI. As the result, we found that for the cross flow between subchannels, the split vane is more effective than the swirl vane, while for the secondary vortex flow in each subchannel, the swirl vane's one is larger and longer than split vane's one.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.386-391
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• 1997

It is important to understand correctly a CHF under low flow condition for the purpose of enhancing the reactor safety and performance in the LWRs. The CHF experiments have been carried out for an internally heated vertical annulus in RCS loop facility. The experimental conditions cover ranges of pressure from 1.82 to 12.08 MPa, mass flux from 300 to 550kg/$m^2$. s and inlet subcooling of 210kJ/kg. The CHF data decrease with increasing pressure at high value of mass flux. For mass flux of about 300kg/$m^2$. s, the CHF rue little influenced by pressure. The CHF data are correlated well by using the dimensionless heat flux and dimensionless mass flux for a fixed inlet subcooling except the data group of 12.08 MPa. It seems that the Doerffer correlation and Katto correlation overestimate the CHF for low pressure and lower value of mass flux within this experimental ranges. The Bowling correlation gives a better prediction than the other two correlations.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.78-84
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• 2016

The FHX (Forced-draft sodium-to-air Heat Exchanger) employed in the ADHRS (active decay heat removal system) is a shell-and-tube type counter-current flow heat exchanger with M-shape finned-tube arrangement. Liquid sodium flows inside the heat transfer tubes and atmospheric air flows over the finned tubes. The unit is placed in the upper region of the reactor building and has function of dumping the system heat load into the final heat sink, i.e., the atmosphere. Heat is transmitted from the primary cold sodium pool into the ADHRS sodium loop via DHX (decay heat exchanger), and a direct heat exchange occurs between the tube-side sodium and the shell-side air through the FHX tube wall. This paper describes the DHRS and the structural design of the FHX.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1999년도 추계학술대회 논문집 전문대학교육위원 P
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• pp.1-3
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• 1999

EM (ElectroMagnetic) pump is used for the purpose of transporting liquid sodium coolant with electrical conductivity in the LMR(Liquid Metal Reactor). (In the present study, pilot EM pump has been designed by using of equivalent circuit method which is commonly employed to analyze linear induction machines for the test of removal of residual heat. The length and diameter of the pump have fixed values of 840 mm and 101.6 mm each by taking account of geometrical size of circulation loop for the installation of EM pump. Flowrate versus developing pressure is related from Laithwaite's standard design formula and the characteristic analyses of developing force and efficiency are carried out according to change of input frequency. From the characteristic curve, input frequency of 13 Hz is determined as the design frequency. On the other hand, The annular air gap size of 6.05 mm is selected not to bring about too much hydraulic loss. Resultantly design analysis makes pump have the electrical input of 604 VA and the hydrodynamical capacity of 1.3 bars and 40 l/min.

• 대한기계학회논문집
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• 제8권5호
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• pp.416-424
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• 1984

본 연구에서는 다회로의 단상(single-phase) 자연순환계에 관한 실험 및 수치 해석적 연구로서, RWR에서의 자연순환 현상을 모사할 수 있는 fast-running code를 개 발하고 이를 실험을 통하여 입증하며, 또한 자연순환계에서 일어나는 여러 현상을 정 성적으로 관찰하는 것을 목적으로 삼았다. 이론부분은 저자의 다른 논문에 발표되었 으므로 여기에서는 요약하여 소개하며, 실험은 2-회로 PWR(고리 1호기) 1차계통을 약 1/15로 축소시킨 실험장치에서 행하였다.

• 대한기계학회논문집A
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• 제25권3호
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• pp.381-389
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• 2001

The objective of this paper is to evaluate the fracture resistance characteristics of SA508 Cl.1a to SA508 Cl.3 welds manufactured for the reactor coolant loop piping system of nuclear power plants. The effect of the crack plane orientation to the welding process orientation and the preheat temperature on the fracture resistance characteristics were discussed. Results of the fracture resistance test showed that the effect of the crack plane orientation to the welding process orientation of the fracture toughness is significant, while that of preheat temperature on the fracture toughness is negligible. The micro Vickers hardness test, the metallographic observation and the fractography analysis were conducted to analyse the crack jump phenomenon on the L-R crack plane orientation in the multi-pass welding zone. As these results, it is shown that the crack jump phenomenon was produced because of the inhomogeneity between welding beads and the crack plane orientation must be considered for the safety of the welding zone in the piping system.

• Membrane and Water Treatment
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• 제11권4호
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• pp.275-282
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• 2020

Hranfa's marl, a local natural mineral, is selected for the decontamination by adsorption of aqueous effluents in textile industry. Its physicochemical characterization is first performed. It is composed mainly of Calcite, Quartz, Ankerite and Muscovite. Its specific surface area is 40 ㎡ g^-1. Its adsorption performance is then tested in batch conditions using an industrial organic dye, Bemacid Red E-TL, as a model pollutant. The measured adsorption capacity of Hranfa's marl is 16 mg g^-1 which is comparable to that of other types of natural adsorbents. A hybrid process is tested coupling adsorption of the dye on marl in suspension and microfiltration. An adsorption reactor is inserted into the circulation loop of a microfiltration pilot using ceramic membranes. This makes possible a continuous extraction of the treated water provided that a periodic replacement of the saturated adsorbent is done. The breakthrough curve obtained by analyzing the dye concentration in the permeate is close to the ideal one considering that no dye will cross the membrane as long as the adsorbent load is not saturated. These first experimental data provide proof of concept for such a hybrid process.

• Nuclear Engineering and Technology
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• 제23권3호
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• pp.328-339
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• 1991

30 MW 열출력을 갖는 다목적 연구용 원자로(KMRR)가 원자력연구소에선 개발되고 있다. 열수력 연구의 일환으로 길이 방향으로 핀이 달린 연료봉다발의 압력강하특성을 실험으로 연구하였다. 본 논문에서는 넓은 유량범위에서 적용할 수 있는 핀 연료봉다발에서의 압력강하 상관식의 도출과 압력강하에 미치는 핀 영향의 조사에 중점을 두었다. 도출된 KMRR 핵연료봉다발의 마찰계수 상관식을 원형관의 실험결과와 비교하였을 때 저유량 실험영역에서는 충류시의 해석값인 64/Re 보다 큰 값을 가졌으나 Re가 증가되면 Blasius 상관식보다 낮아지는 경향을 나타내었다.

• The Journal of the Acoustical Society of Korea
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• 제18권1E호
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• pp.7-12
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• 1999

In relation to a non-destructive evaluation of irradiation damages, the changes in the hysteresis loop and Barkhausen noise amplitude and the harmonics frequency due to a neutron irradiation were measured and evaluated. The Mn-Mo-Ni low alloy steel of RPV was irradiated to a neutron fluence of 2.3 ×10/sup 19/ n/㎠ (E ≥1 MeV) at 288℃. The saturation magnetization of neutron irradiated metal did not change. The neutron irradiation caused the coercivity to increase, whereas susceptibility to decrease. The amplitude of Barkhausen noise parameters associated with the domain wall motion were decreased by a neutron irradiation. The spectrum of Barkhausen noise is analysed with an applied frequency of 4 Hz and 8 Hz, sampling time of 50 μ sec and 20 μ sec. The harmonic frequency shows 4 Hz, 8 Hz, 12 Hz and 16 Hz reflected from an unirradiated specimen. On the contrary, the harmonic frequency disappeared on the irradiated specimen. In addition to the amplitude, the harmonic frequency of Barkhausen noise is taken into accounts as a promising tool for monitoring the irradiation induced degradation of the reactor materials such as a SA508 of PWR-RPV steel and a Zr₄ of HANARO-CNH.