• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2984-2996
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• 2023

A 100 kW thermal power pool-type light water reactor and Pu(Be) as a fast neutron source were used to determine the appropriate carrier for irradiating boron-containing samples with neutron beams. The tested materials (carriers) were subjected to neutron beams in the reactor's tangential channel. The geometrical arrangement of experimental facilities relative to the neutron beam trajectory, as well as the effect of sample thickness on the count rate, were investigated. The majority of the detectable charged particles emitted by the neutron beam's interaction with tested materials and the detector's detecting layer are protons (recoiled hydrogen) and particles generated in nuclear reactions (protons and alpha particles), respectively. Stopping and Range of Ions in Matter (SRIM) software was used to do theoretical calculations for the range of expected released particles in various materials, including human tissue. The results of measurement and calculation are in good agreement. According to experiments and theoretical calculations, the number of protons emitted by tissue-like materials may commit a dose comparable to that of boron capture reactions. Furthermore, the range of protons is significantly larger than that of alpha particles, which most probably changes dose distribution in healthy cells surrounding the tumor, which is undesirable in the BNCT approach.

• Nuclear Engineering and Technology
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• 제37권6호
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• pp.605-610
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• 2005

A method to estimate the relative sensitivity of a self-powered rhodium detector for an upcoming cycle is developed by combining the rhodium depletion data from a nuclear design with the site measurement data. This method can be used both by nuclear power plant designers and by site staffs of Korean standard nuclear power plants for determining which rhodium detectors should be replaced during overhauls.

• 대한방사선기술학회지:방사선기술과학
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• 제45권1호
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• pp.57-67
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• 2022

CZT detectors, which are compound semiconductors that have been widely used recently for gamma-ray detection purposes, are difficult to detect neutrons because direct interaction with them does not occur unlike gamma-rays. In this paper, a method of detecting and determining energy levels (fast neutrons and thermal neutrons) of neutrons, in addition of identifying energy and nuclide of gamma-rays, and evaluating gamma dose rates using a CZT semiconductor detector is described. Neutrons may be detected by a secondary photoelectric effect or compton scattering process with a characteristic gamma-ray of 558.6 keV generated by a capture reaction (¹¹³Cd + ¹n → ¹¹⁴Cd + 𝛾) with cadmium (Cd) in the CZT detector. However, in the case of fast neutrons, the probability of capture reaction with cadmium (Cd) is very low, so it must be moderated to thermal neutrons using a moderator and the material and thickness of moderator should be determined in consideration of the portability and detection efficiency of the equipment. Conversely, in the case of thermal neutrons, the detection efficiency decreases due to shielding effect of moderator itself, so additional CZT detector that do not contain moderator must be configured. The CZT detector that does not contain moderator can be used to evaluate energy, nuclide, and gamma dose-rate for gamma-rays. The technology proposed in this paper provides a method for detecting both neutrons and gamma-rays using a CZT detector.

• 한국방사선학회논문지
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• 제6권5호
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• pp.403-408
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• 2012

본 연구는 천연 인듐의 중성자폭획 후에 발생된 감마선을 12개의 BGO($Bi_4Ge_3O_{12}$) 섬광검출기로 구성된 검출장치를 이용하여 즉발감마선을 측정하여 중성자공명에 의해서 발생된 감마선을 분석하여 중성자의 에너지 1 ~ 300 eV 영역에 대하여 공명에너지를 분석하였다. 사용되어진 검출장치는 시료에서 발생된 즉발감마선에 대하여 모든 감마선을 측정할 수 있는 기하학적인 구조로 만들어졌다. 중성자원으로는 교토대학의 원자로연구소의 46-MeV 전자선형가속기의 광핵반응에서 발생하는 중성자를 이용하였다. 중성자발생원으로부터 검출기까지의 거리가 $12.7{\pm}0.02m$이므로 광핵반응에서 발생하는 강한 X선의 영향을 고려하여 수 keV영역이하의 중성자에너지에 대하여 중성자공명을 측정하였다. 측정되어진 공명들은 1 eV이상의 에너지 영역에서 거대 공명들을 측정하였고 이들 공명들은 이론에서 알려진 값들과 비교하였다. 본 연구를 통하여 기존에 알려진 거대 공명의 에너지를 확인하였고, 100 eV이상의 에너지 영역에서의 공명에너지들에 대한 평가에 의한 이론값들이 실제로 존재하는 공명임을 실험적으로 확인하였다. 1 keV 이상의 영역에 대하여는 공명이 연속적인 구조를 보이고 있음을 실험적으로 확인했으며 공명에 대하여 통계적인 평가가 있어야함을 알았다. 91.49 eV 공명은 본 연구를 통하여 처음 발견되어진 공명이라 볼 수 있다.

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.1036-1042
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• 2020

Fast-Neutron Multiplicity Counter based on Liquid Scintillator Detector can directly measure the fast neutron multiplicity emitted by UO₂ rod. HPGe gamma spectrometer; which has superior energy resolution; is routinely used for the gamma energy spectrum measurement. Combing Fast-Neutron Multiplicity Counter and HPGe γ-spectrometer, the n/γ joint measurement system is developed. The fast neutron multiplicity and gamma energy spectrum of UO₂ rod assemblies under different conditions are measured by the n/γ joint measurement system. The induced fission rate and the ²³⁵U abundance, thereby the ²³⁵U mass; can be obtained for UO₂ rod assemblies. The ²³⁵U mass deviation of the measured value from the reference value is less than 5%. The results show that the n/γ joint measurement system is effective and applicable in the measurement of the ²³⁵U mass in samples.

• 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.

• 대한방사선치료학회지
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• 제17권2호
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• pp.141-145
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• 2005

목 적 : 일반적으로 10 MV이상의 광자선에서 산란 중성자를 발생시키는 것으로 알려져 있다. 세관에 설치된 컨테이너 검색장치는 9 MV 이하였음에도 중성자가 누출되었다. 본 연구에서 의료기관에 설치된 방사선 치료기에서 산란 방출되는 중성자의 공간적인 측정을 통해 결과를 분석하고 평가하고자 한다. 대상 및 방법 : 본 연구의 방사선 발생장치는 의료용 선형가속기(linear accelerator, linac: Varian, Clinac 1800, USA)를 사용하였다. 중성자 측정용 검출기는 중성자가 발생하면 기포(bubble)이 생기는 Bubble 검출기(Bubble detector, BDPND type, BTI, Canada)를 사용하였다. 의료용 선형가속기 주변에 Bubble 검출기를 isocenter로부터 30 cm, 50 cm, 120 cm의 각각 3가지 거리별로 isocenter 상하 방향 네 곳에 위치시켜 측정하였다. 주변 구조물의 영향을 살펴보기 위해 Wedge와 Mount를 장착 후 50 cm 거리에서 각각 8방향에서 측정하였다. 광자선원부터 isocenter 까지의 거리(SAD: source-axis-distance)를 100 cm로 기준을 정하고 조사면의 크기(field size)는 $15{\times}15cm^2$로 정하였다. 방사선은 20 MU를 조사하여 Bubble 검출기에 발생한 기포수를 측정하며 mrem값으로 계산하였다. 결 과 : Isocenter부터 거리가 30 cm와 50 cm 떨어진 곳의 각각 8개 측정 지점 중에서는 모두 5번 위치(Gantry 우측 아래지점)에서 측정된 산란중성자의 양이 같은 거리라도 가장 높게 측정되었다. Bubble 검출기가 Isocenter부터 120 cm 떨어진 경우와 wedge를 장착한 경우는 7번 위치(Couch 우측 아래지점), mount 탈착한 경우는 2번 위치(Gantry 왼쪽 윗지점)에서 산란 중성자가 가장 높게 측정되었다. 결 론 : 산란중성자의 측정에서 직선상 같은 거리에 있는 곳이라도, 실제 측정한 결과 값에 따르면 서로 상이한 값을 보였다. 주변 구조물도 산란 중성자에 영향을 미치며, 직선상은 같은 거리라도 각각의 지점에서 다른 값을 보였다. 따라서, 산란중성자의 거리에 따른 영향은 단순히 직선으로의 거리뿐 아니라 방향과 주변 구조물에 대한 영향까지 고려하며 공간적인 측정과 평가가 필요하다.

• Communications for Statistical Applications and Methods
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• 제5권2호
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• pp.503-515
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• 1998

When a neutral particle beam(NPB) aimed at the object and receive a small number of neutron signals at the detector, it follows approximately Poisson distribution. Under the four assumptions in the presence of errors and uncertainties for the Poisson parameters, an exact probability distribution of neutral particles have been derived. The probability distribution for the neutron signals received by a detector averaged over the three sources of errors is expressed as a four-dimensional integral of certain data. Two of the four integrals can be evaluated analytically and thereby the integral is reduced to a two-dimensional integral. The monotone likelihood ratio(MLR) property of the distribution is proved by using the Cauchy mean value theorem for the univariate distribution and multivariate distribution. Its MLR property can be used to find a criteria for the hypothesis testing problem related to the distribution.

• Nuclear Engineering and Technology
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• 제39권6호
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• pp.725-730
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• 2007

This paper describes recently developed techniques for effective filtering of neutron detector signal noise. In this paper, three kinds of noise filters are proposed and their performance is demonstrated for the estimation of reactivity. The tested filters are based on the unilateral kernel filter, unilateral kernel filter with adaptive bandwidth and bilateral filter to show their effectiveness in edge preservation. Filtering performance is compared with conventional low-pass and wavelet filters. The bilateral filter shows a remarkable improvement compared with unilateral kernel and wavelet filters. The effectiveness and simplicity of the unilateral kernel filter with adaptive bandwidth is also demonstrated by applying it to the reactivity measurement performed during reactor start-up physics tests.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.433-433
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• 2004

Neutron induced prompt gamma-ray spectroscopy (NIPS) system measures the prompt gamma-ray, emitting by the interaction of a neutron with various materials. This system will be of great benefit to scientists worldwide, since it provides the non-destructive measurement of many elements in either solid or liquid wastes. A NIPS facility has been developed in Nuclear Chemistry Research Division, at Korea Atomic Energy Research Institute (KAERI) with the aim of analyzing the major component elements in both aqueous and solid samples.(omitted)