• Proceedings of the Korean Society of Fisheries Technology Conference
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• 2001.05a
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• pp.248-249
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• 2001

인공방사성 물질이 해양으로 유입되는 경로는 대기권 핵실험에 의한 낙진, 원자력 관계시설에서 액체 방사성물질의 유출, 방사성패기물의 해양 투기 등이 있다. 현재 해양에서 검출되고 있는 인공방사성 핵종은 대부분이 과거의 핵폭발실험에 의해 해양으로 유입된 방사능 물질이 해양내에서 이동되어 검출되는 것으로 볼 수 있다. 이들 핵종 중에서 반감기가 긴 핵종($^{137}$Cs, $^{90}$ Sr, $^{238}$ Pu, $^{239+240}$ Pu)은 방사능 오염의 좋은 지표 일 뿐만 아니라 연안퇴적물의 거동과 분포를 이해하는데 유용하다. (중략)

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.630-635
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• 1997

본 연구에서는 원자력 선진국들의 원자력 미래기술의 예측 사례를 조사ㆍ분석하고, 이를 우리나라의 사례와 비교하였다. 조사된 미래 원자력 기술예측 및 수준 평가는 국외의 경우 일본, 독일 그리고 프랑스의 사례가 조사되었고 국내에서는 과학기술정책관리연구소와 한국원자력연구소의 사례를 원용하였다. 이들 사례에서 공통적으로 평가하고 있는 기술의 중요성, 실현시기 그리고 제약요인을 비교하였다. 기술평가 결과에 나타난 일반적인 특징은 우선 개별기술의 중요성 평가에서는 공통적으로 방사성패기물처리, 원전내진설계 그리고 원전해체기술 등과 같이 이미 활용중인 기술로서 기존 시설의 안전성을 향상시킬 수 있는 기술의 중요성을 높이 평가하고 있다. 다음으로 실현시기 평가에서는 레이저빔 이용기술과 같이 인접과학 분야의 발전에 따른 시너지 효과가 기대되는 분야의 기술이 2010년 이전에 실현될 것으로 평가하고 있다. 마지막으로 기술개발의 저해요인의 평가는 조사사례 별로 정도의 차이는 있으나 기술적 제약요인이 가장 높고, 다음으로 경제적 제약 그리고 사회적 제약의 순으로 평가하고 있다.

• Journal of Radiation Protection and Research
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• v.29 no.1
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• pp.1-8
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• 2004

Diphosil, a new version of the organic-inorganic composite resin developed by ANL has a structure of the chelating diphosphonic acid groups grafted to a silica support. To apply Diphosil for the treatment of liquid radioactive waste from nuclear power plants, the adsorption equilibrium and column experiments were carried out for the main radionuclides, $^{137}Cs\;and\;^{60}Co$, in the liquid radwaste stream. Through the adsorption equilibrium experiments, the removal efficiencies of $^{137}Cs\;and\;^{60}Co$, and the effects of non-radioactive ions on the removal efficiency have been measured in various conditions using radiotracers. The breakthrough curves for the tested tracers were obtained from the laboratory scale column tests using the simulated liquid radioactive waste. In addition, the removal capacity of Diphosil is compared with that of Amberlite IRN 77 resin, generally used in nuclear power plants.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.4
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• pp.257-263
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• 2008

We analyzed the statistical properties for the conductive background fractures in the Low and Intermediate Level Waste(LILW) disposal site to conceptualize of its groundwater flow system. The background fractures were classified to fracture sets based on their trends and plunges that were obtained from the borehole logging data, and then the fracture transmissivity distribution was inferred from the fixed interval hydraulic test results. The fracture size distribution of each fracture set was estimated using the fracture density and fracture mapping data. To verify the analyzed results, we compared observed field data to simulated one from the DFN model that was constructed with the analyzed statistical properties of the background fractures, and they showed a good agreement.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.2
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• pp.73-100
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• 2008

For the purpose of evaluating dose rate to individual due to long-term release of nuclides from the HLW repository, a biosphere assessment model and the implemented code, ACBIO, based on BIOMASS methodology have been developed by utilizing AMBER, a general compartment modeling tool. To show its practicability and usability as well as to see the sensitivity of compartment scheme or parametric variation to concentration and activity in compartments as well as annual flux between compartments at their peak values, some calculations are made and investigated: For each case when changing the structure of compartments and GBIs as well as varying selected input Kd values, all of which seem very important among others, dose rate per nuclide release rate is separately calculated and analyzed. From the maximum dose rates (Bq/y), flux-to-dose conversion factors (Sv/Bq) for each nuclide were derived, which are to be used for converting the nuclide release rate appearing from the geosphere through various GBIs to dose rate (Sv/y) for individual in critical group. It has been also observed that compartment scheme, identification of possible exposure group and GBIs could be all highly sensitive to the final consequences in biosphere modeling.

• The Journal of Engineering Geology
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• v.12 no.2
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• pp.151-166
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• 2002

Groundwater development as a means of acquiring subsidiary water resource is very important for the persistent security of water resource. Nowadays, pneumatic fracturing technology which was developed in the advanced countries is applied for increasing pumping rate and eliminating contaminants. This study gives an experimental data to clarify permeability characteristics of the single discontinuity which is newly developed or increased in aperture by the pneumatic fracturing or damage propagation of the natural barrier for the nuclear waste disposal. On the basis of understanding the relationship between permeability and hydraulic aperture the result could apply as one of the basic data for researches concerned with increasing pumping rate and eliminating contaminants. Hydraulic aperture is decreased exponentially with increasing confining pressure and proportioned to permeability in the same confining pressure. Especially, with the increasing aperture permeability of coarse- and medium- grained granite shows the more rapid increasing than that of fine- grained granite.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.1
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• pp.45-54
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• 2008

A new proposed repository has a final capacity of 800,000 drums radioactive waste. Most of foreign repositories have a general practice of segregating control zones which mainly contributes to classification of degree of control, whether it is called buffer zone or not. Domestic regulatory requirements of establishment of buffer zone in a repository are not much different from those of nuclear power plants for operation period, in which satisfactory design objective or performance objective is the most important factor in determination of the buffer zone. The meaning of buffer zone after closure is a minimum requested area which can prevent inadvertant intruders from leading to non-allowable exposure during institutional control period. Safety assessment with drinking well scenario giving rise to the highest probability of exposure among the intruder's actions can verify fulfillment of the buffer zone which is determined by operational safety of the repository. At present. for the repository to be constructed in a few years, the same procedure and concept as described in this paper are applied that can satisfy regulatory requirements and radiological safety as well. However, the capacity of the repository will be stepwise extended upto 800,000 drums, consequently its layout will be varied too. Timely considerations will be necessary for current boundary of the buffer zone which has been established on the basis of 100,000 drums disposal.