• Title, Summary, Keyword: 중성자

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하나로 1차 배관의 중성자 발생원 분석

  • 김명섭;홍광표;전병진
    • Proceedings of the Korean Nuclear Society Conference
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    • pp.227-232
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    • 1998
  • 하나로 1차 배관에서 중성자를 측정하고 발생 원인을 분석하였으며, 이를 통하여 중성자 계측 계통을 이용하여 핵연료 파손을 감시할 수 있는 가능성을 검토하였다. 중성자 측정에는 BF$_3$비례 계수관을 이용하였고, 1차 배관의 주 방사선원인 N-16에 의한 감마선 펄스의 영향은 무시 할 정도로 작았다. 중성자의 발생 원인을 규명하기 위해 원자로 정지 전후에 중성자 계수율의 변화를 측정하였다. 편자로의 정상 운전시 1차 배관에서 발생되는 중성자는 물속의 중수소가 고에너지 감마선을 흡수하여 방출하는 광중성자와 핵연료의 표면 오염에 의해 발생된 지발 중성자라고 가정하여 원자로 정지 전후의 발생량 변화를 계산하였다. 계산 결과와 측정값을 비교하여 1차 배관 주변에서 측정된 중성자 가운데 지발 중성자가 약 70 %, N-16에 의한 광중성자가 약 30%임을 확인하였다. 핵연료의 표면 오염 정도로 발생하는 지발 중성자도 민감하게 측정되므로, 이러한 지발 중성자 계측법이 핵연료의 손상 여부를 알아낼 수 있는 유용한 방법임을 확인할 수 있었다.

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중성자흡수체를 이용한 사용후핵연료 저장대 설계에 관한 기술현황

  • 장상균;신태명
    • Proceedings of the Korean Nuclear Society Conference
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    • pp.853-859
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    • 1995
  • 원자력발전소내 사용후핵연료 습식저장 방식 중에서 중성자흡수체를 사용하여 핵연료를 보관하는 중성자흡수체 저장대에 대한 국내외 기술현황을 조사하였다. 핵연료저장대에 중성자흡수체를 사용하는 목적은 핵연료로부터 방출되는 중성자를 횹수하여 임계요건을 만족하면서 단위 핵연료 저장공간을 줄이기 위함이다. 본 논문에서는 국내 핵연료저장대 설치현황을 파악하고, 국내외 중성자흡수체 재료로 사용되는 Borated Stainless Steel, Boral 및 Boraflex의 재료특성 등을 조사하였다. 또한 국내외 특허 출원된 중성자흡수체 저장대에 관한 자료를 검토하였다. 현재 국내에 외국회사의 완성품 인도방식으로 설치되었던 중성자홉수체 저장대에 대한 조사결과는 차세대 원자로 핵연료저장대의 중성자흡수체 선정 및 구조설계에 참고자료로 활용될 것이다.

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A Study On Hardware Design for High Speed High Precision Neutron Measurement (고속 고정밀 중성자 측정을 위한 하드웨어 설계에 관한 연구)

  • Jang, Kyeong-Uk;Lee, Joo-Hyun;Lee, Seung-Ho
    • 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.

Evaluation of Response Functions for Activation Foil-based Bonner Spheres (중성자 방사화 포일 기반 보너구 반응함수 계산 방법)

  • Kim, Jung-Ho;Park, Hyeon-Seo
    • Journal of Radiation Protection and Research
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    • v.36 no.1
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    • pp.44-51
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    • 2011
  • Activation foil-based Bonner sphere spheres are used to obtain neutron energy spectra of nuclear power plants or accelerator-produced neutrons. The position and the foil mass dependence of response functions should be studied carefully before measurement of Bonner spheres. This study showed that the normal incidence to the foil surface made a large shift of responses while parallel and isotropic incidence made no position dependence. The correlation between foil mass and response was not linear. Therefore, the response functions of activation-foil based Bonner spheres should be calculated for every different foil mass and the direction of Bonner spheres for parallel incidence will be preferred for radioactive neutron source or accelerator target produced neutrons.

A Study on Neutron Resonance Energy of Tantalum by 46-MeV Electron Linac TOF Method (46-MeV 전자선형가속기의 TOF 방법을 이용한 탄탈의 중성자 공명 에너지 분석에 관한 연구)

  • Lee, Samyol
    • 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.

Feasibility Study Using GEANT4 Monte Carlo Simulations of a PET Cyclotron-Based Neutron Source for Boron Neutron Capture Therapy (GEANT4 몬테카를로 전산모사를 이용한 PET 사이클로트론 기반 중성자 선원의 BNCT 적용가능성 평가)

  • Choi, Jae Won;Kang, Bo Sun
    • New Physics: Sae Mulli
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    • v.67 no.11
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    • pp.1319-1326
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    • 2017
  • This report presents the results of a feasibility study on a cyclotron-based neutron source for boron neutron-capture therapy (BNCT). Neutron yields from a beryllium target bombarded by a proton beam accelerated by a cyclotron were calculated using the GEANT4 simulation tool kit. The calculations were performed with different proton energies and different target thicknesses to find the changes in neutron spectra and yield at various angles. The main parameters for the design of a target with a neutron reflector were determined based on the calculated results, and epithermal neutron fluxes generated from the target were calculated. The epithermal neutron flux generated by a proton beam with an energy lower than 20 MeV was not sufficient for BNCT. However the flux generated by a 30 MeV, $500{\mu}A$ proton beam was $1.03{\times}10^9n/cm^2{\cdot}s$, which satisfies the flux recommandation for a BNCT neutron source.