• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.509-514
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• 1998

ORIGEN-S 전산코드로 계산된 가압경수로(PWR)사용후핵연료 내에 존재하는 방사성핵종비 $^{134}$ Cs/$^{137}$Cs 및 $^{154}$ Eu/$^{137}$Cs 를 감마선 분광실험으로 측정한 값과 비교하여 핵연료의 연소도를 결정하였다. 고리 1호기 및 2호기 사용후핵연료봉에 대한 감마선 분광실험을 한국원자력연구소 조사재시험시설(IMEF)과 조사후시험시설(PIEF)의 시험기기 및 장치를 이용하여 수행하고 이 결과로부터 $^{134}$ Cs/$^{137}$Cs 와 $^{154}$ Eu/$^{137}$Cs 의 핵종비를 측정하였다. 이와 별도로 사용후핵연료의 연소도, 냉각시간, 초기농축도등에 따른 $^{134}$ Cs/$^{137}$Cs 와 $^{154}$ Eu/$^{137}$Cs의 핵종비를 ORIGEN-S 코드로 계산을 하였으며, 이 핵종비와 연소도 사이의 관계를 회귀분석하여 2차 다항식 함수로 유도하였다 이관계식과 감마선 분광실험으로 측정한 $^{134}$ Cs/$^{137}$Cs와 $^{154}$ Eu/$^{137}$Cs 의 핵종비를 이용하여 각각의 연소도를 결정할 수 있었다.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.545-550
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• 1998

PWR 사용후핵연료 내에 존재하는 $^{134}$ Cs/$^{137}$Cs 및 $^{154}$ Eu/$^{137}$Cs의 감마선 핵종비를 써서 각각 연소도를 결정하고, 그들의 차이가 최소가 되는 시간을 찾는 방법으로 사용후핵연료의 냉각시간을 결정하였다. $^{134}$ Cs/$^{137}$ Cs 및 $^{154}$ Eu/$^{137}$Cs의 핵종비로부터 연소도를 구하는 방법은 이들 핵종비에 대한 ORIGEN-5 코드 계산과 감마스캐닝 실험 결과를 비교하는 것이었다$^{[1]}$ . 사용후핵연료의 냉각시간을 임의의 시간으로 가정하고 핵종비 $^{134}$ Cs/$^{137}$ Cs을 써서 구한 연소도와 $^{154}$ Eu/$^{137}$Cs를 써서 구한 연소도의 차이를 계산했으며, 이 차이는 실제 측정대상 핵연료의 냉각시간에서 최소가 될 것을 기대하였다. 감마선 방출 핵분열생성물인 $^{134}$ Cs와 $^{154}$ Eu는 비교적 긴 반감기를 갖고 있으면서도 또 이들의 반감기 차이가 약 6.4년이나 되므로 기존의 방법$^{[2]}$ 에 비해 넓은 범위의 냉각시간을 정확하게 측정할 수 있었다.

• Nuclear Engineering and Technology
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• v.17 no.1
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• pp.1-7
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• 1985

Non-destructive gamma-ray spectrometry was carried out on the spent PWR fuel assemblies at the spent fuel pool of reactor-site. Attention was focused on the determination of burnup distribution and cooling time. For the measurement of burnup distribution, the concentration ratio of $^{134}$ Cs$^{137}$ Cs was used and the results showed these ratios varied with the positions of assemblies in the core during their irradiation. For the measurement of cooling time, $^{144}$ Ce$^{137}$ Cs was used and the results were agreed considerably well with the operator declared cooling time.

• Journal of IKEEE
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• v.20 no.4
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• pp.337-343
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• 2016

This study conducted the gamma ray spectroscopic analysis of the microcolumnar CsI:Tl deposited onto the SiPMs using thermal evaporation deposition. The SEM measured thickness of microcolumnar CsI:Tl and of its individual columns. From the SEM observation, the measured thickness of CsI:Tl were $450{\mu}m$ and $600{\mu}m$. The gamma ray spectroscopic properties of microcolumnar CsI:Tl, $450{\mu}m$ and $600{\mu}m$ thick deposited onto the SiPMs were analyzed using standard gamma ray sources $^{133}Ba$ and $^{137}Cs$. The spectroscopic analysis of microcolumnar CsI:Tl deposited onto the SiPMs included the measurements of response linearity over the $^{137}Cs$ gamma ray intensity; and gamma ray energy spectrum. Furthermore from the gamma ray spectrum measurement of $^{133}Ba$ and $^{137}Cs$, $450{\mu}m$ thick CsI:Tl showed good efficiency when measured with $^{133}Ba$ and $600{\mu}m$ thick CsI:Tl was highly efficient when measured with $^{137}Cs$.

• Nuclear Engineering and Technology
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• v.24 no.2
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• pp.178-182
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• 1992

Spent PWR fuel rods have been scanned axially and sectionally to measure the relative gamma-ray intensity of Cs-137 and then bumups of the scanned rods determined by measuring Nd-148 which has been chemically separated. From these experimental results, a linear relation(LR) between the gamma-ray intensity of Cs-137 and the bumup in the range of 10∼35 GWD/MTU was obtained. In order to validate the LR, the Cs-137 gamma-ray intensity of unknown sample was nondestructively measured and the bumup obtained by the LR was compared with that of the Nd-148 method. It is revealed that the results from both methods are in good agreement, and thus it seems to be possible to estimate the bumup of spent PWR fuel rod by measuring nondestructively gamma-ray of fission product Cs-137.

• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.310-311
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• 2011

• Progress in Medical Physics
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• v.5 no.2
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• pp.3-12
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• 1994

$\^$137/Cs gamma ray induced thermoluminescenc(TL) from Na$\^$+/ ion implanted Al$_2$O$_3$ and unimplanted Al$_2$O$_3$ and the TL from Na$\^$+/ ion implanted Al$_2$O$_3$ are measured over the temperature range of 340K～620K. The TL curve of Na$\^$+/ ion implanted Al$_2$O$_3$ induced by $\^$137/Cs gamma ray is split into iolated TL peak located at 415K, 452K, 508K, and 568K. Because that the concentration of trapped char he carries of $\^$137/Cs gamma ray induced Al$_2$O$_3$ implanted with Na$\^$+/ ion is larger than that of Na$\^$+/ ion only implanted Al$_2$O$_3$, and the trap concentration of Na$\^$+/ ion implanted Al$_2$O$_3$ is much than that of $\^$137/Cs gamma ray only irradiated Al$_2$O$_3$, the TL intensity of Na$\^$+/ ion implanted Al$_2$O$_3$ induced by $\^$137/Cs gamma ray is about 20 times and 5 times higher than that of Al$_2$O$_3$ only implanted with Na$\^$+/ ion and Al$_2$O$_3$ only irradiated with $\^$137/Cs gamma ray, respectively. In proportion as ion implantation does and energy are incresed, the number of generated defects and the rate of defect creation are incresed, respectively. Therefore the TL intensity of ion implanted Al$_2$O$_3$ is depend on ion dose and energy. Acccrding to increse of incident ion mass, the TL intensity of ion implanted Al$_2$O$_3$ is abruptly decresce. This result showes that the TL intensity of ion implanted Al$_2$O$_3$ is closely related to ion depth range as wll as rate of defect creatin. The TL intensity of ion implanted Al$_2$O$_3$ is found to be related with defects generated by ion implantation. Table Caption

• Journal of Radiation Protection and Research
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• v.29 no.4
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• pp.263-268
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• 2004

Using the Monte Carlo simulation, a study on the lion-proportionality of the prototype phoswich detector with $2'{\times}2'$ CSI(Tl) and plastic scintillator, which was made by KAERI, has been carried. The defector response functions (DRFs) calculated by simulations were compared with the experimental measurement on the $^{137}Cs\;and\;^{60}Co$. To precisely simulate the DRF for the phoswich, the CSI(Tl) non-proportionality was calculated using the electron response and the simplified electron cascade sequence for treating the photoelectric absorption event. The resulting DRFs of $^{137}Cs\;and\;^{60}Co$ sources obtained by simulations were compared with experiments for verification. For $^{137}Cs$, gamma-ray responses simulated by MCNP5 are generally good agreement with the measured ones. But the DRF of $^{60}Co$ does not match well with the results of experiment in the energy region below second peak due to the coincidence effect of two gamma-rays (1.17 MeV and 1.33 MeV). Through the analysis of the non-proportionality of CsI(Tl) in the prototype phoswich, the improved DRFs considering non-proportionality were produced and the simulation results were verified using the experimental measurements. However, to more precisely reproduce the DRF for the phoswich, further studies in relation to the electron channeling effect and the Doppler broadening effect of a scintillator are still needed as well as considering that effect of the transfer contribution.

• Journal of Radiation Protection and Research
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• v.9 no.1
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• pp.11-18
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• 1984

A Standard gamma-ray ionization chamber system was developed with a well type ionization chamber and micro current measuring circuit. Micro current was measured by the automatic Townsend balance with stepwise compensation method. For gamma emitting nuclides such as $^{241}Am,\;^{133}Ba,\;^{60}Co,\;^{134}Cs,\;^{137}Cs,\;and\;^{22}Na$ relative calibration factors to $^{226}Ra$ reference source were calculated and detection .efficiency curve was determined as a fudnction of gamma energy.

• Progress in Medical Physics
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• v.25 no.3
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• pp.123-127
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• 2014

The Cs-137 irradiator is widely used to irradiate biological samples for radiobiological research. To obtain the accurate outcomes, correct measurements of the delivered absorbed dose to a sample is important. The IAEA protocols such as TRS-277 and TRS-398 were recommended for the Cs-137 reference dosimetry. However in TRS-398 protocol, currently known as the most practical dosimetry protocol, the quality factor ($k_{Q,Q_0}$) for Cs-137 gamma rays is not suggested. Therefore, the use of TRS-398 protocol is currently unavailable for the Cs-137 dosimetry directly. The calculation method previously introduced for high energy photon beams in radiotherapy was used for deriving the Cs-137 beam qualities ($k_{Q,Q_0}$) for the 15 commercially available farmer type ionization chambers in this study. In conclusion, $k_{Q,Q_0}$ values were ranged from 0.998 to 1.002 for Cs-137 gamma rays. These results can be used as the reference and dosimeter calibrations for Cs-137 gamma rays in the future radiobiological researches.