• Nuclear Engineering and Technology
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• 제38권3호
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• pp.301-310
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• 2006

Destructive methods were used for the burnup determination of U-Zr alloy nuclear fuel irradiated in the High-flux Advanced Neutron Application Reactor (HANARO) at KAERI. The dissolution rate of unirradiated U-Zr alloy fuel in $HNO_3$/HF mixtures was investigated for the experimental conditions of a different temperature, and initial concentrations of HF and $HNO_3$. The irradiated U-Zr alloy fuel specimen was dissolved in a mixed acid condition of 3 M HNO3 and 1 M HF at $90^{\circ}C$ for 8 hours under reflux. The total burnup was determined from measurement of the Nd isotope burnup monitors. The method includes U, Pu, $^{148}Nd,\;^P{145}Nd+^{146}Nd,\;^{144}Nd+^{143}Nd$ and total Nd isotopes determination by the isotope dilution mass spectrometric method (IDMS) using triple spikes $(^{233}U,\;^{242}Pu\;and\;^{150}Nd)$. The effective fission yield was calculated from the weighted fission yields averaged over the irradiation period. The results are compared with that obtained by the destructive -spectrometric measurement of the $^{137}Cs$ monitor.

• 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.

• Journal of Welding and Joining
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• 제33권1호
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• pp.24-29
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• 2015

Residual stresses arising from the materials processing such as welding and joining affect significantly the structural integrity depending on the external loading condition. The quantitative measurement of the residual stresses is of great importance in order to characterize the effects of the residual stresses on the structural safety. In this paper, we introduce a newly devised destructive technique, the contour method (CM), which is applied for the measurements of the residual stress distributions through the thickness of a 80 mm thick steel weld. Residual stresses are evaluated from the contour, which is the normal displacement on a cut surface produced by the relaxation of residual stresses, using a finite element model. The CM provides a two-dimensional map of the residual stresses normal to the cut surface. The CM developed in the present study was validated in comparison with the residual stress distribution determined by a well-established neutron-diffraction residual stress instrument (RSI) instrumented in HANARO neutron research reactor.

• 한국정보과학회:학술대회논문집
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• 한국정보과학회 2006년도 한국컴퓨터종합학술대회 논문집 Vol.33 No.1 (C)
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• pp.229-231
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• 2006

본 논문은 한국원자력연구소 내에서 가동 중인 하나로 원자로의 방사선감시시스템 소프트웨어 개발에 있어서 속성기반설계를 적용한 사례를 소개한다. 본 논문에서 채택한 속성기반설계는 시스템의 기능요건 및 품질요건 도출, 이를 만족하기 위한 전술 설정, 설정된 전술에 근거하여 시스템 아키텍처 결정, 확정된 아키텍처를 구현 및 검증하는 과정으로 이루어진다. 하나로 방사선감시시스템의 개발요건으로부터 사용성, 가용성, 유지보수성. 호환성, 확장성 과 같은 품질속성을 추출하였으며, 개발 전술로는 이중화된 서버에 다수의 클라이언트가 연결되는 클라이언트-서버클러스터링 전술과 객체지향적 데이터 처리 및 디스플레이 설계 전술을 채택하였다. 단기간 내에 개발을 완수해야하는 방사선감시시스템 개발에 속성기반설계를 적용함으로써 보다 효율적으로 과제를 성공시킬 수 있었다.

• Nuclear Engineering and Technology
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• 제45권2호
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• pp.219-222
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• 2013

Alloy 690 has been selected as a steam generator tubing material for SMART owing to a near immunity to primary water stress corrosion cracking. The steam generators of SMART are faced with a neutron flux due to the integrated arrangement inside a reactor vessel, and thus it is important to know the irradiation effects of the thermal conductivity of Alloy 690. Alloy 690 was irradiated at HANARO to fluences of (0.7-28) ${\times}10^{19}n/cm^2$ (E>0.1MeV) at $250^{\circ}C$, and its thermal conductivity was measured using the laser-flash equipment in the IMEF. The thermal conductivity of Alloy 690 was dependent on temperature, and it was a good fit to the Smith-Palmer equation, which modified the Wiedemann-Franz law. The irradiation at $250^{\circ}C$ did not degrade the thermal conductivity of Alloy 690, and even showed a small increase (1%) at fluences of (0.7~28) ${\times}10^{19}n/cm^2$ (E>0.1MeV).

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.209-214
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• 2023

The effect of thermal annealing on defect recovery of in-core neutron-irradiated 4H-SiC was investigated. Au/SiC Schottky diodes were manufactured using a 4H-SiC epitaxial wafer that was neutron-irradiated at the HANARO research reactor. The electrical characteristics of their epitaxial layers were analyzed under various conditions, including different neutron fluences (1.3 × 10¹⁷ and 2.7 × 10¹⁷ neutrons/cm²) and annealing times (up to 2 h at 1700 ℃). Capacity-voltage measurements showed high carrier compensation in the neutron-irradiated samples and a recovery tendency that increased with annealing time. The carrier density could be recovered up to 77% of the bare sample. Deep-level-transient spectroscopy revealed intrinsic defects of 4H-SiC with energy levels 0.47 and 0.68 eV below the conduction-band edge, which were significantly increased by in-core neutron irradiation. A previously unknown defect with a high electron-capture cross-section was discovered at 0.36 eV below the conduction-band edge. All defect concentrations decreased with 1700 ℃ annealing; the decrease was faster when the defect level was shallow.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2005년도 춘계 학술대회
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• pp.21-29
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• 2005

30 MW의 연구용 원자로인 하나로는 1995년 2월 초임계에 도달한 이후, 정상적으로 가동하고 있다. 가동 후 약 10년이 경과하여 1차 냉각펌프를 분해 점검하기 위해 펌프에 대한 화학제염이 2004년에 수행되었다. 제염을 수행하기 이전에 4개의 point를 설정하여 방사선량율 및 표면오염도를 측정하였고, 최종제염이 수행된 이후 같은 point에 대하여 방사선량율 및 표면오염도를 재측정 하였다. 펌프 외부는 노출되어 있어 쉽게 제염할 수 있으나 케이싱 내부에는 2중 볼류트가 있어 접근이 용이하지 않았다. 이를 제염하기 위하여 제염장치를 개발하였다. 이 장치는 일정 농도의 제염제 (DX-300)를 케이싱 내부에 담아 밀폐시킨 후 펌프의 임펠러를 저속으로 회전함으로서 제염제가 순환된다. 제염제의 유화작용에 의해 표면의 입자성 방사선 물질이 이완되고, 화학 작용에 의해 부식력과 용해성으로 표면 오염이 제거된다. 이 장치를 이용하여 하나로 1차 냉각펌프의 케이싱 내부를 제염하였다. 그 결과 1차 냉각펌프의 케이싱 내부는 반출허용표면오염도 이하로 낮출 수 있어 성공적으로 제염할 수 있었다.

• Journal of Radiation Protection and Research
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• 제31권1호
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• pp.31-35
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• 2006

Black mouse에 하나로 원자로의 BNCT시설을 이용하여 중성자(flux:1.036739E+09)를 머리를 정면으로 16 및 32 Gy 조사한 후 생물학적 효과를 관찰하는 일환으로 고환에 대한 물리학적 변화 및 조직 변화를 관찰하였다. 조사 후 90일이 경과한 후에 고환의 무게는 변화가 없었으나 고환의 부피는 약간 감소하였으며, 정자수도 감소하였다. 고환의 조직검사에서는 32 Gy 중성자 조사군에서 위축된 정세관의 수가 증가되었으며 stage VI에서의 정세관에서는 정조세포 및 비사기 정모세포가 고갈되어 있음을 알 수 있었다. 중성자 조사(32 Gy)후 고환의 손상이 장기간 경과 후에도 회복되지 않음을 알 수 있었다.

• Transactions on Electrical and Electronic Materials
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• 제14권1호
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• pp.20-23
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• 2013

When applying superconducting wire to power machines, an investigation needs to be carried out on the characteristics of wire phase changes in connection with the insulating layer. This study examined trends in the increase of the wire's resistance and the characteristics of its recovery from quenching by a current-applied cycle at temperatures of 90 K, 180 K, and 250 K. The procedure was conducted based on the thickness and presence (or absence) of the insulating wire layers. To achieve this, YBCO thin-film wires with the same critical temperatures were prepared with copper and stainless steel stabilizing layers. At levels (-one, three, and five-), with superior performance, polyimide pressure-sensitive adhesive tape was attached to the wires at a very low temperature. The eight prepared test samples were wound around the linear frames. The wire's voltage and current created from the phase change characteristics were measured at the wire's prescribed temperature, using the four-point probe method. The wire's resistance and recovery characteristics were examined for each cycle at temperatures of 90 K, 180 K, and 250 K.

• 대한기계학회논문집A
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• 제31권9호
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• pp.903-909
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• 2007

A fatigue capsule is one of the special capsules to investigate the fatigue characteristics of the nuclear materials during an irradiation test in a research reactor, HANARO. In this study, the performance test and the preliminary fatigue test results by using a cyclic load device newly developed for a fatigue capsule are described. In order to obtain the characteristics such as a realization and a controllability of the periodic wave shape and the relationship between the pressure and the load, a spring and rigid bar specimens are used. The fatigue test for the 316L stainless steel specimen with 1.8mm in diameter and 12.5mm in gage length is also performed under the same conditions as the temperature($550^{\circ}C$) of the specimen during irradiation tests. As a result of the test, the fracture of the specimen occurs at a total of 70,120 cycles(about 12 days), and the displacement in this case is 2.02 mm. It is expected that these results will be used for determining test conditions and a comparison of the in-pile fatigue test results.