• 제목/요약/키워드: Neutron sensor

검색결과 35건 처리시간 0.027초

속중성자 탐지용 반도체 소자 개발 (Development of a Fast Neutron Detector)

  • 이남호;김승호;김양모
    • 대한전기학회논문지:전기물성ㆍ응용부문C
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    • 제52권12호
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    • pp.545-552
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    • 2003
  • When a Si PIN diode is exposed to fast neutrons, it results in displacement damage to the Si lattice structure of the diode. Defects induced from structural dislocation become effective recombination centers for carriers which pass through the base of a PIN diode. Hence, increasing the resistivity of the diode decreases the current for the applied forward voltage. This paper involves the development of a neutron sensor based on the phenomena of the displacement effect damaged by neutron exposure. The neutron effect on the semiconductor was analyzed. Several PIN diode arrays with various thickness and cross-section area of the intrinsic layer(I layer) were fabricated. Under irradiation tests with a neutron beam, the manufactured diodes have a good linearity to neutron dose and show that the increase of thickness of I layer and the decrease of cross-section of PIN diodes improve the sensitivity. Newly developed PIN diodes with thicker I layer and various cross section, were retested and then showed the best neutron sensitivity at the condition that the I layer thickness was similar to a side length. On the basis of two test results, final discrete PIN diodes with a rectangular shape were manufactured and the characteristics as neutron detectors were analyzed through the neutron beam test using on-line electronic dosimetry system. Developed PIN diode shows a good linearity as dosimetry in the range of 0 to 1,000cGy(Tissue) and its neutron sensitivity is 13mV/cGy at constant current of 5mA, that is three times higher than that of commercially available neutron detectors. And the device shows little dependency on the orientation of the neutron beam and a considerable stability in annealing test for a long period.

반도체형 실시간 전자적 선량계 개발 (Development of a real time neutron Dosimeter using semiconductor)

  • 이승민;이흥호;이남호;김승호;여진기
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2000년도 추계학술대회 논문집 학회본부 D
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    • pp.754-757
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    • 2000
  • Si PIN diodes are subject to be damaged from the exposure of fast neutron by displacement of Si lattice structure. The defects are effective recombination centers for carriers which migrate through the base region of the PIN diode when forward voltage is applied. It causes an increase in current and a decrease in resistivity of the diode. This paper presents the development of a neutron sensor based on displacement damage effect. PIN diodes having various structures were made by micro-fabrication process, and neutron beam test was performed to identify neutron damage effect to the diode. From a result of the test, it was shown that the forward voltage drop of the diode, at a constant current, has good linearity for neutron dosage. Also it was found that the newton dosage can be measured by the pin diode neutron dosimeter with constant current power.

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핀(PIN) 다이오드 소자를 이용한 중성자 측정장치 개발 (Development of a neutron Dosimeter using PIN diode)

  • 이승민;이홍호;이남호;김승호;여진기
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2001년도 하계학술대회 논문집 D
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    • pp.2522-2525
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    • 2001
  • Si PIN diodes are subject to be damaged from the exposure of fast neutron by displacement of Si lattice structure. The defects are effective recombination centers for carriers which migrate through the base region of the PIN diode when forward voltage is applied. It causes an increase in current and a decrease in resistivity of the diode. This paper presents the development of a neutron sensor based on displacement damage effect. PIN diodes having various structures were made bymicro-fabrication process, and neutron beam test was performed to identify neutron damage effect to the diode. From a result of the test, it was shown that the forward voltage drop of the diode, at a constant current, has good linearity for neutron dosage. Also it was found that the newton dosage can be measured by the pin diode neutron dosimeter with constant current power.

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EVALUATION OF FAST NEUTRON FLUENCE FOR KORI UNIT 3 PRESSURE VESSEL

  • Yoo, Choon-Sung;Kim, Byoung-Chul;Chang, Kee-Ok;Lee, Sam-Lai;Park, Jong-Ho
    • Nuclear Engineering and Technology
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    • 제38권7호
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    • pp.665-674
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    • 2006
  • Three-dimensional neutron flux and fluence of Kori Unit 3 were evaluated using the synthesis technique described in Regulatory Guide 1.190 for all reactor geometry. For this purpose DORT neutron transport calculations from Cycle 1 to Cycle 15 were performed using BUGLE-96 cross-section library. The calculated flux and fluence were validated by comparing the calculated reaction rates to the measurement data from the dosimetry sensor set of the $5^{th}$ surveillance capsule withdrawn at the end of cycle 15 of Kori Unit 3. And then the best estimation of the neutron exposures for the reactor vessel beltline region was performed using the least square evaluation. These results can be used in the assessment of the state of embrittlement of Kori Unit 3 pressure vessel.

Monte Carlo 방법을 이용한 바나듐 자발 중성자계측기 초기 민감도 계산 (Calculation of Initial Sensitivity for Vanadium Self-Powered Neutron Detector (SPND) using Monte Carlo Method)

  • 차균호;박영우
    • 센서학회지
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    • 제25권3호
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    • pp.229-234
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    • 2016
  • Self-powered neutron detector (SPND) is being widely used to monitor the reactor core of the nuclear power plants. The SPND contains a neutron-sensitive metallic emitter surrounded by a ceramic insulator. Currently, the vanadium (V) SPND has been being developed to be used in OPR1000 nuclear power plants. Some Monte Carlo simulations were accomplished to calculate the initial sensitivity of vanadium emitter material and alumina insulator with a cylindrical geometry. An MCNP code was used to simulate some factors (neutron self-shielding factor and beta escape probability from the emitter) and space charge effect of an insulator necessary to calculate the sensitivity of vanadium detector. The simulation results were compared with some theoretical and experimental values. The method presented here can be used to analyze the optimum design of the vanadium SPND and contribute to the development of TMI (Top-mount In-core Instrumentation) which might be used in the SMART and SMR.

GYAGG/6LiF composite scintillation screen for neutron detection

  • Fedorov, A.;Komendo, I.;Amelina, A.;Gordienko, E.;Gurinovich, V.;Guzov, V.;Dosovitskiy, G.;Kozhemyakin, V.;Kozlov, D.;Lopatik, A.;Mechinsky, V.;Retivov, V.;Smyslova, V.;Zharova, A.;Korzhik, M.
    • Nuclear Engineering and Technology
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    • 제54권3호
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    • pp.1024-1029
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    • 2022
  • Composite scintillation screens on a base of Gd1.2Y1.8Ga2.5Al2.5O12:Ce (GYAGG) scintillator have been evaluated for neutron detection. Besides the powdered scintillator, the composite includes 6LiF particles; both are merged with a binder and deposited onto the light-reflecting aluminum substrate. Results obtained demonstrates that screens are suitable for use with a silicon photomultiplier readout to create a prospective solution for a compact and low-cost thermal neutron sensor. Composite GYAGG/6LiF scintillation screen shows a pretty matched sensitivity and γ-background rejection with a widely used ZnS/6LiF screens however, possesses forty times faster response.

습식 저장시설 내 사용후핵연료 연소도 측정을 위한 감마선/중성자 검출기 개발 (Development of a Gamma/Neutron Detector to Measure the Burnup Profile of Spent Fuel in Wet Storage Facility)

  • 박혜민;김태영;이인호;장대헌;송양수;이운장;함철민
    • 방사선산업학회지
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    • 제18권3호
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    • pp.249-253
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    • 2024
  • For the safe management and disposal of spent fuel, it is essential to accurately determine the quantities of nuclides present within the spent fuel. In this study, a Gamma/Neutron detection system was developed as a part of basic research to measure the burnup profile of spent fuel, and a performance was evaluated using major nuclides. The prototype of the Gamma/Neutron detection system consisted of a CZT sensor and a 3He chamber. For quantitative evaluation, studies were conducted using calibrated 137Cs, 134Cs, 154Eu and 252Cf sources. In the performance evaluation, a field applicability was verified by analyzing the detection characteristics according to the nuclide.

지뢰탐지 실험플랫폼의 진동 특성 분석 (Analysis of the Vibration Characteristic for the Mine Detectable Test Platform)

  • 장유신;곽노진;한승훈;지언호;지창진
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2014년도 춘계학술대회 논문집
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    • pp.588-595
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    • 2014
  • In this paper, analysis of the vibration Characteristic for the Mine Detectable Test Platform is described. The test platform system is the multi-sensor mine detectable vehicle. This multi-sensor mine detectable unit is more efficient detection performance than other conventional methods. The test platform system has five subsystems, the UWB(Ultra Wide Band) sensor scanner, the MD(Metal Detector) sensor scanner, the neutron sensor scanner, and the detectable vehicle. We perform the vibration tests for the test platform and analyze the vibration characteristic, such as the max displacement, the max deformation and the max Von-Misses Stress.

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지뢰탐지 실험플랫폼의 진동 특성 해석 (Analysis of the Vibration Characteristic for the Mine Detectable Test Platform)

  • 장유신;곽노진;한승훈;지언호;지창진
    • 한국소음진동공학회논문집
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    • 제24권12호
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    • pp.927-934
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    • 2014
  • In this paper, analysis of the vibration characteristic for the mine detectable test platform is described. The test platform system is the multi-sensor mine detectable vehicle. This multi-sensor mine detectable unit is more efficient detection performance than other conventional methods. The test platform system has five subsystems, the UWB(ultra wide band) sensor scanner, the MD(metal detector) sensor scanner, the ND(neutron detector) sensor scanner, and the detectable vehicle. We perform the vibration tests for the test platform and analyze the vibration characteristic, such as the max displacement, the max deformation and the max Von-Misses stress.