• 전기전자학회논문지
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• 제20권1호
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• pp.61-67
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• 2016

본 논문에서는 중성자 방사선 측정을 위한 고속 고정밀 중성자 측정을 위한 하드웨어 설계방법을 제안한다. 제안된 고속 고정밀 중성자 측정 장치의 하드웨어 설계는 고성능 A/D 변환기를 사용하여 고정밀 고속의 아날로그 신호를 디지털 데이터로 변환할 수 있도록 구성된다. 중성자 센서를 사용하여 입사된 중성자 방사선 입자를 검출하고, 극저전류 정밀 측정 모듈을 통해 검출된 중성자 방사선을 보다 정밀하고 빠르게 측정하는 모듈을 설계한다. 고속 고정밀 중성자 측정을 위한 하드웨어 시스템은 중성자 센서부, 가변 고전압 발생부, 극저전류 정밀 측정부, 임베디드 시스템부, 디스플레이부 등으로 구성 된다. 중성자 센서부는 고밀도 폴리에틸렌을 통해 중성자 방사선을 검출하는 기능을 수행한다. 가변 고전압 발생부는 중성자 센서가 정상적으로 운영되기 위하여 발열 및 잡음 특성에 강인한 0 ~ 2KV 가변 고전압 발생장치의 기능을 수행한다. 극저전류 정밀 측정부는 중성자 센서에서 출력되는 고정밀 고속의 극저전류 신호를 고성능 A/D 변환기를 사용하여 정밀하고 빠르게 측정하고 아날로그 신호를 디지털 신호로 변환하는 기능을 수행한다. 임베디드 시스템부는 고속 고정밀 중성자 측정을 위한 중성자 방사선 측정 기능, 가변 고전압 발생장치 제어 기능, 유무선 통신 제어 기능, 저장 기능 등을 수행한다. 제안된 고속 고정밀 중성자 측정을 위한 하드웨어를 실험한 결과, 불확도, 중성자 측정 속도, 정확도, 중성자 측정 범위 등에서 기존의 장치보다 우수한 성능이 나타남을 확인할 수가 있다.

• 센서학회지
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• 제18권5호
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• pp.402-407
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• 2009

In this study, plastic optical fiber sensors which can measure thermal neutron dose in a mixed neutron-gamma field are developed and characterized. Using $^{252}Cf$ and $^{60}Co$ sources, the scintillators suitable for thermal neutron detection, are tested and the scintillating lights generated from a plastic optical fiber sensor in the Kyoto University Critical Assembly (kuca) core are measured. Also, the distributions of thermal neutron and gamma-ray are measured in a mixed field as a function of the distance from the center of the reactor core at KUCA and the distribution of thermal neutron is obtained using a subtraction method. Sensitivity of the fiber-optic radiation sensor system is about 0.49 V/mW according to power of the KUCA core and its relative error is about 1.2 %.

• 대한기계학회논문집A
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• 제24권9호
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• pp.2167-2173
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• 2000

The HANARO (High-flux Advanced Neutron Application Reactor) has operated since 1995. The Cold Neutron(CN) hole was implanted in the reflector tank from the design stage. Before a vacuum chamber and a moderator cell for the cold neutron source are installed into the CN hole, it is necessary to measure the exact size of the inside diameter and thickness of the CN hole to prevent the interference problem. Due to inaccessibility and high radiation field in the CN hole, a mechanical measurement method is not permitted. The immersion ultrasonic technique is considered as the best method to measure the thickness and the diameter. The 4 axis manipulator of the 2 channel of a sensor module was fabricated. The transducer of 10 MHz results in 0.03 nun of resolution. The inside diameter and thickness for 550 points of the CN hole were measured using 2 channel ultrasonic sensors. The results showed that the thickness is in the range of 13-6.7 mm and inside diameter is in the range of o 156-165. These data will be a good reference in the design of a cold neutron source facility.

• Nuclear Engineering and Technology
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• 제51권1호
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• pp.293-302
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• 2019

Many researches have been done to develop and improve the performance of personal (individual) dosimeter response to cover a wide of neutron energy range (from thermal to fast). Depending on the individual category of the dosimeter, the semiconductor sensor has been used to simplify and lightweight. In this plan, it's very important to have a fairly accurate counting of doses rate in different energies. With a general design and single-sensor simulations, all optimal thicknesses have been extracted. The performance of the simulation scheme has been compared with the commercial and laboratory samples in the world. Due to the deviation of all dosimeters with a flat energy response, in this paper, has been used an idea of one semi-conductor sensor to have the flat energy-response in the entire neutron energy range. Finally, by analyzing of the sensors data as arrays for the first time, we have reached a nearly flat and acceptable energy-response. Also a comparison has been made between Lucite-PMMA ($H_5C_5O_2$) and polyethylene-PE ($CH_2$) as a radiator and $B_4C$ has been studied as absorbent. Moreover, in this paper, the effect of gamma dose in the dosimeter has been investigated and shown around the standard has not been exceeded.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1988년도 한국자동제어학술회의논문집(국제학술편); 한국전력공사연수원, 서울; 21-22 Oct. 1988
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• pp.804-809
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• 1988

PRNM(Power Range Neutron Monitoring) of BWR (Boiling Water Reactor) is a system that processes signals from about two hundred LPRM (Local Power Range Monitor) sensors in the nuclear reactor and this system monitors the neutron flux level during the plant operating region. Development has been made by employing a special technique for multiplexing neutron sensor signals and the recent advanced microelectronics technology. It is applicable to the total plant digital control system for a nuclear power plant.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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• pp.789-792
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• 2003

pMOSFET having 10 ${\mu}um$ thickness Gd layer has been tested to be used as a slow neutron sensor. The total thermal neutron cross section for the Gd is 47,000 barns and the cross section value drops rapidly with increasing neutron energy. When slow neutrons are incident to the Gd layer, the conversion electrons are emitted by the neutron absorption process. The conversion electrons generate electron-hole pairs in the $SiO_2$ layer of the pMOSFET. The holes are easily trapped in Oxide and act as positive charge centers in the $SiO_2$ layer. Due to the induced positive charges, the threshold turn-on voltage of the pMOSFET is changed. We have found that the voltage change is proportional to the accumulated slow neutron dose, therefore the pMOSFET having a Gd nuclear reaction layer can be used for a slow neutron dosimeter. The Gd-pMOSFET were tested at HANARO neutron beam port and $^{60}CO$ irradiation facility to investigate slow neutron response and gamma response respectively. Also the pMOSFET without Gd layer were tested at same conditions to compare the characteristics to the Gd-pMOSFET. From the result, we have concluded that the Gd-pMOSFET is very sensitive to the slow neutron and can be used as a slow neutron dosimeter. It can also be used in a mixed radiation field by subtracting the voltage change value of a pMOSFET without Gd from the value of the Gd-pMOSFET.

• Journal of Mechanical Science and Technology
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• 제16권7호
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• pp.927-934
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• 2002

The HANARO ( High-flux Advanced Neutron Application Reactor) has been operated since 1995. The Cold Neutron (CN) hole was implanted in the reflector tank from the design stage. Before a vacuum chamber and a moderator cell for the cold neutron source are installed into the CN hole, it is necessary to measure exactly the size of the inside diameter and thickness of the CN hole to prevent the interference problem. Due to inaccessibility and high radiation field in the CN hole, a mechanical measurement method is not permitted. The immersed ultrasonic technique is considered as the best way to measure the thickness and the diameter of the CN hole. The 4-Axis manipulator was designed and fabricated for locating the ultrasonic sensors. The transducer of an ultrasonic sensor having 10 MHz frequency leads to high resolution as much as 0.03mm. The inside diameter and thickness of 550 points of the CN hole were measured using 2 channel ultrasonic sensors. The results show that the thickness and inside diameter of the CN hole is in the range of 3.3∼6.7mm and 156∼ 165mm, respectively. This data will be a good reference for the design of the cold neutron source facility.

• 센서학회지
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• 제25권4호
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• pp.264-270
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• 2016

Self-powered neutron detector (SPND) is a sensor to monitor a neutron flux proportional to a reactor power of the nuclear power plants. Since an SPND is usually installed in the reactor core and does not require additional outside power, it generates electrons itself from interaction between neutrons and a neutron-sensitive material called an emitter, such as rhodium and vanadium. This paper presents the simulations of the depletion sensitivity evaluations based on MCNP models of rhodium and vanadium SPNDs and light water reactor fuel assembly. The evaluations include the detail geometries of the detectors and fuel assembly, and the modeling of rhodium and vanadium emitter depletion using MCNP and ORIGEN-S codes, and the realistic energy spectrum of beta rays using BETA-S code. The results of the simulations show that the lifetime of an SPND can be prolonged by using vanadium SPND than rhodium SPND. Also, the methods presented here can be used to analyze a life-time of those SPNDs using various emitter materials.

• 센서학회지
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• 제22권3호
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• pp.223-226
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• 2013

We designed a single polyethylene bonner sphere with several thermo-luminescence dosimeters (TLD), for measurement of neutron energy spectrum. For the separation of the neutron dosage in the neutron-gamma mixed field, we used 21 ea TLD-600s and TLD-700s, respectively. Because, TLD-600 is sensitive to neutron and gamma rays, and, TLD-700 is sensitive only to gamma-rays, we could determine the each dose by neutron and gamma rays. The neutron response function of the bonner sphere with TLDs was calculated by MCNPX (ver. 2.5.0) Monte Carlo simulation in the energy range from $10^{-1}$ to 20 MeV. For the Cf-252 standard neutron source in KRISS, we could estimate the neutron energy spectrum by unfolding method using the response function.

• 전기전자학회논문지
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• 제21권4호
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• pp.408-411
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• 2017

본 논문에서는 중성자, 감마선, 엑스선 등의 방사선을 측정하는 통합 제어 시스템을 제안한다. 제안하는 시스템은 원격 또는 네트워크상으로 측정 및 분석한 데이터를 디스플레이를 통해 모니터링 및 제어할 수 있는 장비로서, 현장에 가지 않고도 시스템 각 구성 부분의 상태를 보고 변경하여 원격으로 감시 및 관리할 수 있다. 제안하는 시스템은 감마선/엑스선 센서부, 중성자 센서부, 주제어 임베디드 시스템부, 전용 디스플레이 장치 및 GUI부, 원격 UI부 등으로 구성된다. 감마선/엑스선 센서부는 NaI(Tl) Scintillation Detector를 사용하여 저준위의 감마선 및 엑스선을 측정한다. 중성자 센서부는 Proportional Counter Detector(저준위 중성자)와 Ion Chamber Type Detector(고준위 중성자)를 사용하여 중성자를 측정한다. 주제어 임베디드 시스템부는 방사선을 검출하여 초단위로 샘플링하고 누적된 펄스 및 전류값에 대한 방사선량으로 변환한다. 전용 디스플레이 장치 및 GUI부는 방사선 측정 결과와 변환된 방사선량 및 방사능량 측정 수치를 출력하고, 사용자에게 제어 조건 설정 및 검출부에 대한 캘리브레이션 기능을 제공한다. 원격 UI부는 측정된 값들을 취합, 저장하여 원격 감시 시스템에 전달한다. 제안된 시스템의 성능을 평가하기 위하여 공인시험기관에서 실험한 결과는 중성자 검출부는 ${\pm}8.2%$ 이하의 측정 불확도가 측정되었고, 감마선, 엑스선 검출부는 7.5%이하의 불확도가 측정되어 국제 표준인 ${\pm}15%$ 이하에서 정상동작 됨이 확인되었다.