• Proceedings of the Korean Nuclear Society Conference
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• 1995.10a
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• pp.306-311
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• 1995

원자로 내부구조물의 진동감시를 위한 신호로 노외 중성자 잡음을 선정하고 중성자 잡음에 실려 있는 진동모우드 성분을 신호간의 위상차에 근거하여 분리하는 새로운 방법을 제안하였다. 이 방법은 기존의 방법에 비해 계산속도가 빠르고 3개 이상의 신호에도 적용할 수 있다. 제안한 방법을 토대로 울진 1호기의 노외 중성자 잡음 신호를 채취, 분석하여 내부구조물의 진동특성을 밝히고 진동 감시의 대상이 되는 진동모우드를 분리하므로써 방법의 효율성을 검증하였다. 또 한 핵연료주기동안 주기적으로 신호를 채취, 분석하여 중성자 잡음신호의 특성이 한 핵주기동안 점차 증가하는 경향을 갖는다는 것을 밝혔다.

• Journal of IKEEE
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• v.20 no.1
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• pp.61-67
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• 2016

In this paper, a hardware design method is proposed for high speed high precision neutron radiation measurements. Our system is fabricated to use a high performance A/D Converter for digital data conversion of high precision and high speed analog signals. Using a neutron sensor, incident neutron radiation particles are detected; a precision microcurrent measurement module is also included: this module allows for more precise and rapid neutron radiation measurement design. The high speed high precision neutron measurement hardware system is composed of the neutron sensor, variable high voltage generator, microcurrent precision measurement component, embedded system, and display screen. The neutron sensor detects neutron radiation using high density polyethylene. The variable high voltage generator functions as a 0 ~ 2KV variable high voltage generator that is robust against heat and noise; this generator allows the neutron sensor to perform normally. The microcurrent precision measurement component employs a high performance A/D Converter to precisely and swiftly measure the high precision high speed microcurrent signal from the neutron sensor and to convert this analog signal into a digital one. The embedded system component performs multiple functions including neutron radiation measurement for high speed high precision neutron measurements, variable high voltage generator control, wired and wireless communications control, and data recording. Experiments using the proposed high speed high precision neutron measurement hardware shows that the hardware exhibits superior performance compared to that of conventional equipment with regard to measurement uncertainty, neutron measurement rate, accuracy, and neutron measurement range.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.703-710
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• 1996

본 연구에서는 영광 3,4호기 원자로의 Core Support Barrel 거동을 중성자 잡음해석을 이용하여 분석하였다. 분석 방법은 원자로 노외계측기에서 취득한 교류 성분의 중성자 잡음 신호를 주파수분석하므로서 얻어진 PSD, Phase, Coherence 등을 이용하였다. 영광 3,4호기의 1 주기 동안의 신호를 분석결과, CSB의 Beam Mode 주파수는 영광 3호기의 경우 BOL, MOL, EOL에서 각각 7.75∼8.5Hz, 7.75Hz, 7.25∼7.75Hz로 나타났고, 영광 4호기 BOL에서 8.5∼8.75Hz 임이 도출되었다. 본연구 결과는 한국형 원전의 원자로 내부구조물의 진동 특성을 파악하고 운전중 CSB건전성 진단을 위한 기초 자료로 활용할 수 있다.

• Journal of the Korean Society of Radiology
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• v.7 no.3
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• pp.245-249
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• 2013

Neutron sources from photonuclear reaction with 46-MeV electron linear accelerator at Research Reactor Institute, Kyoto University used for resonance energy measurement of natural tantalum. BGO($Bi_4Ge_3O_{12}$) scintillation detectors used for measurement of the prompt gamma ray from the natural tantalum sample. The BGO spectrometer was composed geometrically as total energy absorption detector. The electric signal from the spectrometer was analyzed for TOF(Time-of-Flight) spectrum which is used identification of neutron capture resonance energy. In this study, the neutron energy region is from 1 to 200 eV, because of strong X-ray effect produced photonuclear reaction in Ta target, the measurement was performed to below 1 keV energy region. The resonance energy was compared with the evaluated values(ENDF/B-VI, Mughabghab). All of the resonances from 4.28 ~ 200 eV were seen in the present measurement except 144.3 eV resonance.

• Journal of Radiation Protection and Research
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• v.40 no.2
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• pp.79-86
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• 2015

$^3He$ gas has been used for neutron monitors as the neutron converter owing to its advantages such as high sensitivity, good ${\gamma}$-discrimination capability, and long-term stability. However, $^3He$ is becoming more difficult to obtain in last few years due to a global shortage of $^3He$ gas. Accordingly, the cost of a neutron monitor using $^3He$ gas as a neutron converter is becoming more expensive. Demand on a neutron monitor using an alternative neutron conversion material is widely increased. $^{10}B$ has many advantages among various $^3He$ alternative materials, as a neutron converter. In order to develop a neutron converter using $^{10}B$ (actually $B_4C$), we calculated the optimal thickness of a neutron converter with a Monte Carlo simulation using MCNP6. In addition, a neutron converter was fabricated by the Ar sputtering method and the neutron signal detection efficiencies were measured with respect to various thicknesses of fabricated a neutron converter. Also, we developed a 2-dimensional multi-wire proportional chamber (MWPC) for neutron beam profile monitoring using the fabricated a neutron converter, and performed experiments for neutron response of the neutron monitor at the 30 MW research reactor HANARO at the Korea Atomic Energy Research Institute. The 2-dimensional MWPC with boron ($B_4C$) neutron converter was proved to be useful for neutron beam monitoring, and can be applied to other types of neutron imaging.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.251-258
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• 1997

임계 근처에서 반응도 미터로 계단식 반응도 변화를 측정할 때는 중성자원과 감마의 영향 하에서도 정확한 반응도를 결정할 수 있으며, 중성자원과 감마를 측정할 수도 있다. 중성자원과 감마의 영향은 없으나 중성자 분포 함수만 변하는 경우에는 계산으로 예측한 분포 함수의 변화로 측정된 중성자 신호를 보정하여 반응도를 예측할 수 있다. 그러나 중성자원, 감마, 분포 함수가 복합적으로 작용하는 경우에 대하여는 이러한 방법을 적용할 수 없다. 이 매 중성자원과 감마의 영향만 있는 경우에 적용하는 방법을 쓰면 분포 함수의 변화가 측정 결과에 어떤 영향을 미치는지 분석하였다. 그 결과 분포 함수의 변화도 어느 정도 측정이 가능하며, 계산으로 예측하는 분포 함수의 변화로 측정 결과를 단순 보정하여 실제 반응도를 예측할 수 있는 것으로 나타났다.

• Journal of Radiation Protection and Research
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• v.39 no.4
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• pp.199-205
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• 2014

In the field of neutron detections, $^3He$ gas, the so-called "the gold standard," is the most widely used material for neutron detections because of its high efficiency in neutron capturing. However, from variable causes since early 2009, $^3He$ is being depleted, which has maintained an upward pressure on its cost. For this reason, the demands for $^3He$ replacements are rising sharply. Research into neutron converting materials, which has not been used well due to a neutron detection efficiency lower than the efficiency of $^3He$, although it can be chosen for use in a neutron detector, has been highlighted again. $^{10}B$, which is one of the $^3He$ replacements, such as $BF_3$, $^6Li$, $^{10}B$, $Gd_2O_2S$, is being researched by various detector development groups owing to a number of advantages such as easy gamma-ray discrimination, non-toxicity, low cost, etc. One of the possible techniques for the detection is an indirect neutron detection method measuring secondary radiation generated by interactions between neutrons and $^{10}B$. Because of the mean free path of alpha particle from interactions that are very short in a solid material, the thickness of $^{10}B$ should be thin. Therefore, to increase the neutron detection efficiency, it is important to make a $^{10}B$ thin film. In this study, we fabricated a $^{10}B$ thin film that is about 60 um in thickness for neutron detection using well-known technology for the manufacturing of a thin electrode for use in lithium ion batteries. In addition, by performing simple physical tests on the conductivity, dispersion, adhesion, and flexibility, we confirmed that the physical characteristics of the fabricated $^{10}B$ thin film are good. Using the fabricated $^{10}B$ thin film, we made a proportional counter for neutron monitoring and measured the neutron pulse height spectrum at a neutron facility at KAERI. Furthermore, we calculated using the Monte Carlo simulation the change of neutron detection efficiency according to the number of thin film layers. In conclusion, we suggest a fabrication method of a $^{10}B$ thin film using the technology used in making a thin electrode of lithium ion batteries and made the $^{10}B$ thin film for neutron detection using suggested method.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.305-305
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• 2004

핵물질을 취급하는 시설에서는 핵물질 안전조치 목적의 달성, 즉 핵물질의 군사적 전용 및 도난을 방지하기 위한 하나의 수단으로서 핵물질의 취급 및 이동을 감시하기 위한 감시시스템이 요구된다. 이 연구에서는 이러한 요구에 부응하기 위해 시설 내에서 핵물질이 이동 가능한 모든 경로에 중성자 모니터와 카메라 같은 감시 장비를 설치하고, 이들로부터 실시간으로 방사선 신호와 영상 데이터를 취득ㆍ분석하여 핵물질의 거동을 진단할 수 있는 핵물질 감시시스템을 개발하였다.(중략)

• Geophysics and Geophysical Exploration
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• v.18 no.3
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• pp.154-161
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• 2015

For efficiently designing neutron induced gamma spectroscopy sonde, Monte Carlo simulation is employed to understand a dominant location of thermal neutron and classify the formation elements from the energy peak of capture gamma spectrum. A pulsed neutron generator emitting 14 MeV neutron particles was used as a source, and flux of thermal neutron was calculated from the twelve detectors arranged at each 10 cm intervals from the source. Design for reducing borehole effects using shielding materials was also applied to numerical sonde model. Moreover, principal elements and quantities of numerical earth models were verified through the energy spectrum analysis of capture gamma detected from a gamma detector. These results can help to enhance the signal-to-noise ratio, and determine an optimal placement of capture gamma detectors of neutron induced gamma spectroscopy sonde.

• Nuclear Engineering and Technology
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• v.20 no.4
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• pp.253-264
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• 1988

Our experience of neutron noise analysis in French-type 900 MWe pressurized water reactor (PWR) is presented. Neutron noise analysis is based on the technique of interpreting the signal fluctuations of ex-core detectors caused by core reactivity changes and neutron attenuation due to lateral core motion. It also provides advantages over deterministic dynamic-testing techniques because existing plant instrumentation can be utilized and normal operation of the plant is not disturbed. The data of this paper were obtained in the ULJIN unit 1 reactor during the start-up test period and the statistical descriptors, useful for our purpose, are power spectral density (PSD), coherence function (CF), and phase difference between detectors. It is found that core support barrel (CSB) motions induced by coolant flow forces and pressure pulsations in a reactor vessel were indentified around 8 Hz of frequency.