• 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.

• Nuclear Engineering and Technology
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• v.26 no.2
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• pp.247-256
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• 1994

The nuclide chain model used in SAV90 has been modified for the CASMO3/MEDIUM3 procedure. Since the default nuclide chain in SAV90, using 21 nuclides, is not sufficient to reproduce the CASMO3 results in the MEDIUM3 calculation, the extended nuclide chain models have been investigated and verified with various types of fuel assemblies. Among the extended nuclide chain models proposed, the 22 nuclide chain model, which contains only Pu238 additionally to the 21 nuclide chain, is recommended in terms of both accuracy and computing efficiency. Using this model core follow calculations for YGN-1 have been performed. The results showed good performance when compared to plant measurements.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.4
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• pp.295-303
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• 2012

Based on the data observed and analyzed on a groundwater flow system in the KURT (KAERI Underground Research Tunnel) site, the transport of radionuclides, which were assumed to be released at the supposed position, was calculated on the time-domain. A groundwater pathway from the release position to the surface was identified by simulating the groundwater flow model with the hydrogeological characteristics measured from the field tests in the KURT site. The elapsed time when the radionuclides moved through the pathway is evaluated using TDRW (Time Domain Random Walk) method for simulating the transport on the time-domain. Some retention mechanisms, such as radioactive decay, equilibrium sorption, and matrix diffusion, as well as the advection-dispersion were selected as the factors to influence on the elapsed time. From the simulation results, the effects of the sorption and matrix diffusion, determined by the properties of the radionuclides and underground media, on the transport of the radionuclides were analyzed and a decay chain of the radionuclides was also examined. The radionuclide ratio of the mass discharge into the surface environment to the mass released from the supposed repository did not exceed $10^{-3}$, and it decreased when the matrix diffusion were considered. The method used in this study could be used in preparing the data on radionuclide transport for a safety assessment of a geological disposal facility because the method could evaluate the travel time of the radionuclides considering the transport retention mechanism.

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.293.1-293
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.639-644
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• 1998

온실내에서 $^{85}$ Sr, $^{103}$ Ru, $^{134}$ Cs의 혼합용액을 배추의 생육중 다섯 차례에 걸쳐 분무기를 이용하여 엽면 처리하고 오염경로를 해석하였다. 작물체에 의한 차단계수는 핵종간에 차이없이 처리시기가 수확기에 가까울수록 증가하여 최고 약 0.9에 달하였다. 작물체에 침적한 핵종의 수확시 잔류율은 처리시기에 따라 $^{85}$ Sr가 16~58%, $^{103}$ Ru이 15~73%, $^{134}$ Cs가 33～64%의 범위로 생육전기 처리 시에는 $^{134}$ Cs가, 후기 처리시에는 $^{103}$ Ru이 가장 높았다. 강우처리에 의해 수확시 핵종농도가 비교적 크게 감소됨을 확인하였다. 수확된 배추의 겉잎을 제거함으로써 배추내 핵종농도를 효과적으로 낮출 수 있다는 것이 입증되었다. 본 연구결과는 배추의 생육중 사고침적시 배추내 핵종농도 예측 및 대책 수립에 활용될 수 있다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.590-595
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• 1996

원자력발전소 냉각수 정화장치내의 운전중 핵종누적량을 계산하기 위하여 계산 프로그램을 작성하여 그 적용성을 평가하였다. 발전소내 측정자료를 재구성한 모의자료를 통한 검증 및 실험을 통해 프로그램의 핵종누적량 계산을 검증하였다. 모의 발전소 측정자료를 통한 예측기법의 적용성 평가에서는 제염계수 측정시 마다 제염계수의 변화폭이 클수록 본방법의 정확성이 상대적으로 향상되었다. 실험을 통한 검증에서는 일련의 정화장치를 통과하여 저장조에 수집된 모의냉각수내 핵종농도를 분석하여 정화장치내에 누적된 핵종량을 계산, 그 결과를 본방법에서의 계산값과 비교를 하였다. 본방법의 계산값의 오차가 상대적으로 작았으며 앞서 수행한 부식생성물의 운전상황에 따른 제염효율 변화예측에 있어서도 본방법이 제염효율 변화를 추적할 수 있음을 알 수 있었다.

• Journal of Radiation Protection and Research
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• v.18 no.1
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• pp.37-51
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• 1993

A standard radon chamber and a radon generator adjusted by ventilation system which had used in this research were assumed to calculate theoretically the concentration of radon progeny using Jacobi model theory. On the one hand, the filter sampled from the radon standard chamber and the radon generator was measured and analysed by the alpha spectrometry method. It is clear that measured result shows a good agreement with theoretical result. Therefore, it is observed that this research can made a great contribution to more accurate internal dose assessment by alpha emission of radon progeny in indoor radon environment, and fast individual measurement and determination of concentration for radon progeny.

• Journal of Radiation Protection and Research
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• v.17 no.1
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• pp.31-41
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• 1992

A study for the evaluation of selected filter media that need further characterization particularily in the context of alpha measurements of radon progeny has been carried out by investigating physical characteristics and using the alpha spectroscopy. Physical characteristics was investigated by electrostatic charging and mechanical strength of filters, and then pressure drop before and after sampling was tested. Alpha spectroscopy was used to analyze the energy spectra from the deposition of radon progeny into filters. The results of the assessment showed that the newer filter types do not have a great advantage over the 'old standard' Millipore type AA. But Metricel DM-800 is recommended for those situations where electrostatic charging is a problem. Also this method will be used more effective for the evaluation of new developing filters in future.

• Journal of radiological science and technology
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• v.39 no.4
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• pp.643-649
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• 2016

When a cyclotron produces $^{18}F^-$, accelerated protons interact with metal parts of the cyclotron machine and induces radioactivity. Especially, the target window and chamber of the target assembly are the main parts where long-lived radionuclides are generated as they are incident by direct beams. It is of great importance to identify radionuclides induced in the target assembly for the safe operation and maintenance of a cyclotron facility. In this study, we analyzed major radionuclides generated in the target assembly by an operation of the Cyclotron 18/9 machine and measured dose rates after the operation to establish the radiation safety guideline for operators and maintenance personnel of the machine. Gamma spectroscopy with HPGe was performed on samples from the target chamber and Havar foil target window to identify the radionuclides generated during the operation for production of $^{18}F^-$- isotope and their specific activity. Also, the dose rates from the target were measured as a function of time after an operation. These data will help improve radiological safety of operating the cyclotron facilities.

• Journal of Radiation Protection and Research
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• v.17 no.2
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• pp.49-59
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• 1992

A new model was developed in order to investigate the effects of chelating agents on the migration of a radionuclide in the form of ion or chelate. The migration behavior of the chelated radionuclide was analyzed by formulating a convective-dispersion transport equation which included a degradation of chelating agent and chelated radionuclide. The mathematical model was analytically solved and checked with the existing retardation factor. The results show that the migration velocity of the chelated radionuclide was much faster than the ionic one due to the decreased retardation. Therefore, it was concluded that a new remedial action should be developed to reduce the generation and release of chelating agents from the nuclear power plant into the environment.