• Nuclear Engineering and Technology
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• 제52권2호
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• pp.448-455
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• 2020

The H.B. Robinson Unit 2 (HBR-2) pressure vessel dosimetry benchmark is an in- and ex-Reactor Pressure Vessel (RPV) neutron dosimetry benchmark based on experimental data from the HBR-2 reactor, a 2300-MW PWR designed by Westinghouse and put in operation in March 1971, openly available through the SINBAD Database at OECD/NEA data Bank. The goals of the present work were to carry out three-dimensional (3D) fixed source transport calculations in both Cartesian (X,Y,Z) and cylindrical (R,θ,Z) geometries by using the TORT-3.2 discrete ordinates code on very detailed 3D HBR-2 geometrical models and to test the latest broad-group coupled (47 neutron groups + 20 photon groups) working cross section libraries in FIDO-ANISN format with same structure as BUGLE-96, such as BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7. The results obtained with all the cited libraries were satisfactory and are here reported and compared.

• Journal of Radiation Protection and Research
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• 제41권3호
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• pp.211-215
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• 2016

Background: The moderated neutron calibration fields using $^{241}Am$-Be sources and a graphite moderator have been constructed at the Facility of Radiation Standard (FRS) in the Japan Atomic Energy Agency (JAEA). Materials and Methods: The neutron spectra of the fields were evaluated by the Monte-Carlo calculations and measurements using the Bonner Multi-sphere Spectrometer. Results and Discussion: The fields have continuous neutron spectra from several MeV to thermal neutron energy, with fluence-averaged energies of 0.84 MeV and 0.60 MeV. Reference values of fluence rates and ambient/personal dose equivalent rates were determined from neutron spectra by measurements. Conclusion: Currently, the fields are available for calibration or performance test of neutron measuring instruments.

• 한국의학물리학회지:의학물리
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• 제8권2호
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• pp.45-57
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• 1997

속중성자선을 임상에 이용하기 위해서는 속중성자선의 선량 및 선량분포를 정확히 측정하는 것이 매우 중요하다. 현재 속중성자선의 측정법은 크게 나누어 American Associations of Physicists in Medicine, European Clinical Neutron Dosimetry Group 및 International Commission on Radiation Units and Measurements에 의하여 제시되고 있으나 측정의 복잡함으로 인하여 서로 약간씩 다른 방법을 제시하고 있다. 따라서 본 연구에서는 중성자 치료장치에서 방출되는 속중성자선의 방출선량 및 물질 내 선량분포 등의 측정을 통하여 독자적인 측정기술을 확보하고, 우리 실정에 알맞은 표준측정법을 개발하고자 하였다. 속중성자선의 선량 및 물질 내 선량 분포 측정에는 조직등가물질인 A-150 플라스틱으로 제작된 IC-17 및 IC-18 이온함, 마그네슘으로 제작된 IC-17M 이온함, TE 기체, Ar 기체 및 RDM 2A electrometer 등을 사용하였다. 연구 결과 중성자선에 혼합되어 있는 ${\gamma}$선의 오염도는 기준조사면 깊이 5cm에서 약 13% 로 나타났으며, 깊이가 깊어질수록 증가하였다. 기준 조사면에 대하여 중심축선상의 최대 선량 깊이는 1.32cm 이었으며, 50% 선량 깊이는 14.8cm로 나타났다. 표면선량율은 전 조사면에 걸쳐서 41.6%～54.1%이었으며 조사면가 커질수록 증가하였다. Beam profile 은 2.5cm 깊이에서 7.5% 정도 horne effect가 나타났으며 10cm 깊이에서 가장 평탄하였다.

• Journal of Radiation Protection and Research
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• 제19권2호
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• pp.133-145
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• 1994

최근, 개인방사선피폭선량평가에 관한 기술기준이 과학기술처에 의해 고시됨에 따라 국내에서도 개인선량계를 이용한 체외피폭선량평가결과의 신뢰성 문제가 크게 대두되고 있다. 한국원자력연구소에서는 이러한 국내의 상황을 인식하고 자체적인 신뢰성 확보를 위해 미국의 Oak Ridge국립연구소의 주관하에 개인피폭선량의 평가에 관한 국제상호비교검증시험(Personnel Dosimet Intercomparison Study ; PDIS)을 수행하였다. 비교검증시험에는 한국원자력연구소에서 사용하고 있는 Teledyne PB-3 열형광선량계가 사용되었으며 선량계산 알고리즘은 Teledyne PB-3 version 1.5-1989를 사용하였다. 본 연구에서는 지금까지 실시 된 PDIS의 결과를 요약하고 현재 PB-3 시스템의 개인선량평가성능에 대해 고찰하였으며, 선량평가절차에 대한 문제점 도출을 통하여 직업적 방사선피폭선량 평가능력의 향상을 위한 방안을 제시하였다.

• 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 Radiation Protection and Research
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• 제2권1호
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• pp.1-8
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• 1977

중성자(中性子) 선량(線量) 측정목적(測定目的)으로 사용(使用)할 Posi필름 고체비적검출기(固體飛跡檢出器)의 알파입자(粒子) 비적검출(飛跡檢出) 효율(效率)과 화학부식(化學腐蝕)에 의(依)한 그의 비적형성(飛跡形成) 최적조건(最適條件)을 실험적(實驗的)으로 결정(決定)하였다. $^{10}B$ 및 $^{27}Al$박(箔)과 posi 필름 고체비적검출기(固體飛跡檢出器)로 이루어진 중성자(中性子) 선량계(線量計)를 제작(製作)하고 이것에 의(依)한 중성자(中性子) 선속밀도(線束密度) 및 선량(線量)의 측정범위등(測定範圍等)을 실험결과(實驗結果)와 이론적(理論的)인 근거하(根據下)에서 산출(算出)하였다. 그 결과(結果) posi 필름 고체비적검출기(固體飛跡檢出器)는 핵분열성(核分裂性) 물질(物質)을 입자방출체(粒子放出體)로 병용(倂用)함이 없이 중성자(中性子) 측정(測定)에 효과적(效果的)으로 응용(應用)될 수 있음이 판명(判明)되었다.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2006년도 제33회 추계학술대회 발표논문집
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• pp.131-131
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• 2006

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2306-2312
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• 2020

Here we report on the first results of sensitivity evaluation of the gadolinium-aluminum-gallium- garnet (GAGG) scintillation detector with SiPM readout to fast and slow neutrons and, to the natural background and Co-60 γ-radiation as well. Data on sensitivity were obtained using certified dosimetry benches, so it can be utilized in the calculation of detection limits of neutron flux with such type of detectors. It was concluded that use of GAGG scintillator has a good prospect for neutron monitoring in different parts of nuclear research reactors and power plants.

• 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.

• Nuclear Engineering and Technology
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• 제53권7호
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• pp.2075-2083
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• 2021

The article provides a review of the research results obtained during of more than 20 years concerning using the gaseous radiochemical method (GRCM) for detecting of ionizing radiation. This method based on threshold nuclear reactions with production of radioactive noble gas which does not interact with the materials of gaseous tract. The applications of GRCM in the diagnostics of neutrinos, neutrons, charged particles, thermonuclear plasma thermometry, and the study of the structure and dynamics of astrophysical objects, position-sensitive dosimetry of neutron targets with accelerator driving, spatial distribution of the fast neutron flux density in a nuclear reactor allowing the transformation of longitudinal coordinate of neutron flux distribution into a temporal distribution of the radiochemical gas decay counting rate ("barcode" semblance) and measurement of bombarding particles spectra are described. Experimental testing of the described technologies was made on the neutron target driven with the linear proton accelerator of Institute for Nuclear Research of Russian Academy of Sciences (INR RAS).