• Journal of the Korean Vacuum Society
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• v.14 no.3
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• pp.132-137
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• 2005

Neutron reflectometer has been installed at HANARO, research reactor in Korea. It has vertical sample geometry and the wavelength of incident neutron beam is $2.459\;\AA$ Neutron fluxes at monochromator and sample position were $4.5\times10^9\;n/cm^2/sec,\;6.64\times10^6\;n/cm^2/sec4 those were measured by gold wire activation method. Also, some reference thin films such as d-PS, $SiO_2$ were measured and analyzedwith HANARO neutron reflectometer. As result of the work, it was certified that minimum reflectivity and available Q range were $10^{-6},\;and\;0.003\sim0.3\;\AA^{-1}$ respectively.

• Transactions of the Korean Society for Noise and Vibration Engineering
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• v.25 no.12
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• pp.807-814
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• 2015

A control rod drive mechanism(CRDM) is a reactor regulating system, which inserts, withdraws or maintains a control rod containing a neutron absorbing material within a reactor core to control the reactivity of the core. The top-mounted CRDM for Jordan Research and Training Reactor(JRTR) with 5 MW power has been designed and fabricated based on the HANARO's experience through KAERI and DAEWOO consortium project. This paper describes the performance qualification test results to demonstrate the operability of a prototype and four production CRDMs during the reactor lifetime. The driving performance, the drop performance and the endurance tests for CRDM are carried out at a test rig simulating the actual reactor conditions. A vibration of internal components due to the coolant flow is also measured using a laser vibrometer. As a result, the CRDMs are driven having a good driving performance without a malfunction between command and output signals for the stepping motor. Also, the pure drop time and the impact acceleration are within 0.72 s and 4.2 g to meet the design requirements, and the vibrational displacement of control rod is measured as maximum $5.2{\mu}m$.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.168-171
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• 2003

The IMEF(Irradiated Materials Examination Facility), located in KAERI site, is a hot cell facility to test and evaluate the irradiation defects or embrittlement through post-irradiation examination(PIEs) of irradiated nuclear fuels and structural materials which are come from HANARO research reactor and commercial nuclear power plants. Therefore, to carry out its own function, the high level solid radioactive wastes, produced through PIEs, are periodically carried out and managed from hot cell to monolith. So far, approximately 30 drums which contains 50 liters are transported to monolith, and it is shown that the quantity is slowly increasing, In this paper, the procedures and work contents of the high level solid radwaste carrying out and management for IMEF are described in detail.

• Nuclear Engineering and Technology
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• v.24 no.3
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• pp.274-284
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• 1992

A 1/15-scale CREARE experiment, which simulates the thermal-hydraulic behavior in the reactor pressure vessel of a PWR during a hypothetical Loss Of Coolant Accident, has been analyzed using CATHARE code for the associated model assessment to represent the phenomenon. The key parameters examined in the CREARE experiment were known as ECC water injection rate. ECC water subcooling, system pressure, and steam flow rate coming out from the core bottom. The present CATHARE simulation, however, has been mainly focused on qualitative analysis of a countercurrent flow in the downcomer. The discrepancy of the simulation results with the experimental data is considered arising primarily from an inadequate numerical representation as well as an interfacial friction model. Accordingly it is suggested from the sensitivity studies that either multidimensional approach or further examination of momentum equations at a junction near a volume element in CATHARE be necessary in order to represent the phenomenon more realistically.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.2
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• pp.213-226
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• 2019

Regulatory agency and licensee are preparing for the site restoration of Kori unit 1, the first commercial NPP in Korea, scheduled for 2031. Developing regulatory guidelines and strategies is essential for effective restoration work. Unfortunately, Korea does not have experience of site restoration of commercial NPPs. Therefore, it is important to review cases from experienced countries to establish a strategy and regulatory standards. The U.S. has had numerous soil remediation experiences using RESRAD and MARSSIM. However, formalized evaluation methodologies for subsurface soil have not yet been established in MARSSIM. This survey focused on subsurface soil remediation by reviewing the five decommissioned NPPs under regulation of the US NRC. Overall process of remediating a contaminated subsurface soil and groundwater was reviewed to identify considerations and lessons that could be applicable in Korea. In addition, an applied methodology for evaluation of contaminated subsurface soil and related major issues between regulatory agency and licensees were reviewed in detail to support establishment of remediation strategy for Kori unit 1.

• Journal of Energy Engineering
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• v.16 no.4
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• pp.155-163
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• 2007

To insure nuclear reactor safety, the reactivity of control rods should be calculated by measuring the criticality of reactor core and it is regularly performed during the annual physics test period. Also, the core criticality should be monitored during the start-up operation to avoid reactivity induced accidents. Many research works on control rod reactivity measurement and subcriticality measurement have been accomplished throughout the world for decades and recently a new method named "Modified Neutron Source Multiplication Method (MNSM)" was proposed in Japan which is known to be improved overcoming limitations of traditional Neutron Source Multiplication Method (NSM). In this study, MNSM was tested in calculation of subcriticalities and in evaluation of application validity using the educational reactor in Kyung Hee University, AGN-201. For this study, a revised nuclear data library and a neutron transport code system TRANSX - PARTISN were established. Correction factors for various control rod positions were produced using the k-effective values and the corresponding flux distributions and adjoint flux distributions. Experimental values of the core criticality were obtained using the neutron count rates of the BF3 proportional counters. The results showed that the expected reactivity worth of control rods by MNSM agreed well with the theoretical values and the correction factors contributed much for this purpose.

• Nuclear Engineering and Technology
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• v.25 no.2
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• pp.343-352
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• 1993

다목적연구로(KMRR)는 일반 발전용 원자로와는 매우 다른 특성을 가지고 있으며, 설계 개념 또한 특이하다. 위와 같은 특이한 설계 특성을 파악하기 위하여 열수력 실험을 수행하였으며 시운전 시험도 설계 개념의 입증에 중점을 두고 수행될 예정이다. 실증실험은 크게 설계 자료 생산을 위한 실험, 기기 설계 검증 시험, 시운전 성능 시험으로 나눌 수 있다. 설계 자료 생산을 위한 실험으로 핵연료의 열수력학적 특성을 규명하는 실험, 우회 유동에 의한 노심 출구 냉각수 상승 억제를 입증 또는 해석하기 위한 자료 생산용 실험 등이 이루어졌다. 기기 설계 검증 시험으로는 Pump 특성 시험, Flap valve 특성 시험 등을 들 수 있다. 또한, 시운전 성능 시험으로는 설계 개념을 입증하기 위한 여러 시험들이 행해질 예정이다. 이러한 실험들을 통하여 설계에 필요한 많은 자료들이 생산되었고, 시운전 시험을 통하여 설계를 검증하고 실제 운전에 필요한 많은 자료를 얻을 수 있으리라 기대된다. 본 기고를 통하여 이러한 실험의 중요성 및 내용에 대해 간략하게 기술하고자 한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.557-562
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• 1996

조사전 및 감시시험시 용접열영향부(heat affected zone, HAZ)의 인성평가를 위해 제작되는 샤피(Charpy) 충격시험편의 노치(notch) 위치에 대하여 현재의 규정에 대한 타당성을 검토하였다. 적용규정은 HAZ 시험편의 노치위치를 용접용융선(fusion line, FL) ＋ 모재측 0.8 mm 로 제한하고 있다. 그러나, 본 연구결과, 이 부위는 다층(multipass) 용접시 후속열이력에 의해 결정립이 미세화되어, 인장강도와 경도 및 충격인성이 모재나 용접부에 비하여 양호하게 나타났다. 한편, FL ＋ 4 mm 이상의 다른 위치에서는 강도와 경도 및 충격인성이 모두 모재와 용접부에 비하여 낮은 값을 보였다. 이는 다층용접에 의한 후속열이력 및 용접후열처리(post weld heat treatment, PWHT)에 의해 금속조직학적 영향을 받은 것으로 판단되었다. 일련의 시험결과로부터, 조 사전 및 감시시험용 샤피충격시험편의 HAZ 에 있어서의 노치위치에 대한 현재의 규정을 재검토할 필요가 있음을 제안하였다.

• Proceedings of the Korean Vacuum Society Conference
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• 2011.02a
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• pp.461-461
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• 2011

최근의 나노기술의 발전과 함께 나노미터크기의 물질들의 물성과 미세구조 등을 분석하기 위한 노력들이 활발히 이루어지고 있다. 투과전자현미경(transmission electron microscope; TEM)은 나노물질의 미세구조 관찰, 화학성분 분석, 전자기적 특성평가가 가능한 초정밀 분석장비이다. TEM 관찰을 위한 시편의 제작방법중 TEM 그리드(grid)를 사용하는 방법은, 분석하고자 하는 물질을 망(mesh) 형태의 그리드에 도포하여 샘플을 준비하는 방법으로 다른 방법에 비해 아주 빠르고 간편한 장점이 있다. 그러나 TEM 그리드에 나노물질을 분산/도포하여 공중에 떠있는 형태로 샘플을 제작하려면, 나노물질이 mesh 사이로 빠져나오지 않도록 그리드 mesh의 간격이 아주 미세하여야 하는데, 일반적으로 mesh의 크기가 미세할수록 그리드의 가격은 높아진다. 또한 기존에 사용되고 있는 비정질 탄소박막으로 덮여진 그리드는 극미세 크기의 나노물질 및 탄소나노물질을 분석할 경우, 고해상도의 TEM상을 얻는데 한계가 있다. 한편 그래핀은 2차원의 육각판상의 구조로 탄소원자가 빼곡히 채워진 흑연 한 층의 나노재료이다. 이는 원자단위 두께로 가장 얇은 물질로서 기계적 강도가 우수하여 지지막으로의 응용이 가능하다고 알려져 있다. 따라서 TEM grid막으로 사용할 경우 기존의 고가의 미세한 mesh가 형성된 그리드를 사용하지 않아도 나노물질을 효과적으로 분석할 수 있을 것으로 예상 된다. 본 연구에서는 열화학증기증착법(thermal chemical vapor deposition; TCVD)을 이용하여 300 nm 두께의 니켈박막이 증착된 기판위에 대면적으로 합성한 그래핀을 TEM 관찰용 그리드 위에 전사(transfer)함으로써 나노물질이 그리드 mesh사이로 빠져나오지 않는 저가의 TEM 그리드 제작 방법 및 응용 가능성에 대하여 보고한다.

• Analytical Science and Technology
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• v.12 no.4
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• pp.273-278
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• 1999

Simultaneous determination of mercury and arsenic has been studied by reductive vapor generation-ICP-AES. Samples were digested with a microwave digestion system and extracted with acids. Reductive vapor generation was carried out with 6N HCI and 2% $NaBH_4$. Detection limit of Hg and As are found to be 0.06 ppb and 0.08 ppb, respectively. Measured values of Hg and As in inorganic samples agree well with reference value of SRMs, but the recovery of As from organic samples is obtained approximately 80% of the reference values.