• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.1
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• pp.123-136
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• 2018

The objective of this study is to propose a new methodology to fabricate a reliable engineering-scale buffer block, which shows homogeneous and uniform distribution in buffer block density, for in-situ experiments. In this study, for the first time in Korea, floating die press and CIP (Cold Isostatic Press) are applied for the manufacture of an engineering-scale bentonite buffer. The optimized condition and field applicability are also evaluated with respect to the method of manufacturing the buffer blocks. It is found that the standard deviation of the densities obtained decreases noticeably and that the average dry density increases slightly. In addition, buffer size is reduced by about 5% at the same time. Through the test production, it is indicated that the stress release phenomenon decreases after the application of the CIP method, which leads to a reduction in crack generation on the surface of the buffer blocks over time. Therefore, it is confirmed that the production of homogeneous buffer blocks on industrial scale is possible using the method suggested in this study, and that the produced blocks also meet the design conditions for dry density of buffer blocks in the AKRS (Advanced Korea Reference Disposal System of HLW).

• Journal of the Korea Academia-Industrial cooperation Society
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• v.15 no.2
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• pp.688-697
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• 2014

The current accounting for the long term care facilities are enforced by either financial accounting stipulations of social welfare legal entity or the guiding principles of long term care insurance law. In addition, some facilities are not eligible to access to the Korea Health and Welfare information system and even don't have any obligation to report financial information. Thus financial position and performance of activities are not well known to the interested parties. This study investigated the way how to improve the current accounting stipulation of the long term care facilities. In conclusion, we should introduce the accounting standards based on the double entry system but on other aspect, also more simplified financial statement based on single entry system for smaller facilities. Also we should introduce three important appropriation accounts for the net income of institution which matches GAAP. For a successful plantation of accounting standards, it is necessary to establish provisions, government subsidy account, depreciations concept.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.3
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• pp.239-245
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• 2010

There are 11,811 LWR spent fuels stored at reactor sites, as of 2009. Source terms based on reference spent fuel which represents entire spent fuels with bounding values in the aspect of source term has been applied to a design of nuclear installations, instead of those which are generated by weighting respective source term for each spent fuel. Simplified regression models to estimate total decay heat, radioactivity, and ingestion hazard index for spent fuel from Westinghouse-type reactors were developed in this study, because it can be used as a fundamental model for weighting source term for respective spent fuel to exclude conservativeness in source terms. It was found that the estimated source terms agreed with calculated value from ORIGEN-ARP within 5%. It was also found that the conservativeness could be excluded if the weight source terms were used as reference source term in the design. Therefore, it is expected that the developed regression model could be widely used in the conceptual design process of nuclear facilities related with storage and disposal of spent nuclear fuel.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.261-267
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• 2004

Inventories, projections, and characteristics of spent nuclear fuel(SNF) generated from domestic nuclear power plants were updated to support high-level waste disposal system design. The historical and projected inventory by the end 2055 is expected to be 20,500 and 14,800MTU for PWR and CANDU spent nuclear fuel, respectively The ratio of quantity for TEX>$17{\times}17$ SNF was shown to be 0.6 as of 2003. The amount of TEX>$17{\times}17$ SNF, however, will be less than that of TEX>$16{\times}16$ KSFA after 2012, while the quantity of TEX>$16{\times}16$ KSFA will reach to 70% of the total spent fuels in the 2055. Average turnup of SNF revealed ~36GWD/MTU and ~40GWD/MTU for the period of 1994-1999 and 2000-2003, respectively. It is expected that the average burnup of SNF will exceed 45GWD/MTU at the end of 2000's. Therefore, it seems reasonable to use the TEX>$17{\times}17$ 4.5w/o, 45GWD/MTU as the Reference SNF at present state. The TEX>$16{\times}16$ KSFA 4.5w/o, 55GWD/MTU, however, should be Reference SNF after ~2010.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.3
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• pp.189-203
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• 2008

The physical and chemical properties of radioactive waste drums, which have been temporarily stored on site, should be characterized before their shipment to a disposal facility in order to prove that the properties meet the acceptance guideline. The investigation of NDT(Nondestructive Test) method was figured out that the contents in drum, the quantitative analysis of free standing water and void fraction can be examined with X-ray NDT techniques. This paper describes the characteristics of X-ray NDT such as its principles, the considerations for selection of X-ray system, etc. And then, the waste drum characteristics such as drum type and dimension, contents in drum, etc. were examined, which are necessary to estimate the optimal X-ray energy for NDT of a drum. The estimation results were that: $(R)\acute{A}$ the proper X-ray energy is under 3 MeV to test the drums of 320 ${\beta}\S$ and less; $(R)\ddot{E}$ both X-ray systems of 450 keV and/or 3 MeV might be needed considering the economical efficiency and the realization. The number of drums that can be tested with 450 keV and 3 MeV X-ray system was figured out as 42,327 and 18,105 drums (based on storage of 2006. 12), respectively. Four testing scenarios were derived considering equipment procurement method, outsourcing or not, etc. The economical and feasibility assessment for the scenarios was resulted in that an optimal scenario is dependent on the acceptance guide line, the waste generator's policy on the waste treatment and the delivery to a disposal facility, etc. For example, it might be desirable that a waste generator purchases two 450 keV mobile system to examine the drums containing low density waste, and that outsourcing examination for the high density drums, if all NDT items such as quantitative analysis for 'free standing water' and 'void fraction', and confirmation of contents in drum have to be characterized. However, one 450 keV mobile system seems to be required to test only the contents in 13,000 drums per year.

• 한국신재생에너지학회:학술대회논문집
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• 2009.06a
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• pp.840-843
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• 2009

폐자동차의 최종처분 과정에서 발생하는 자동차 파쇄 폐기물(Automobile Shredder Dust)은 대부분이 고분자 화합물로 높은 발열량을 가지고 있다. 또한 할로겐족 원소가 포함된 난연성 고분자류가 많아 다이옥신의 생성 우려가 높은 고분자류와 다이옥신 생성의 촉매 역할을 할 수 있는 금속성분이 많이 함유되어 있어 가스화용융시스템에 적용하여 처리하기에 매우 적합한 폐기물이다. 본 연구에서는 ASR의 가스화 용융 시설에서 고농도 CO를 함유한 합성가스를 수성가스전환반응(Water Gas Shift reaction, WGS)을 이용하여 수소의 수율을 높이는 기술을 제시하였다. 가스화 용융 설비에서 배출되는 합성가스 조성을 기준으로 적합한 고정층 WGS 반응기를 설계하고, 고온 촉매(KATALCO 71-5M)와 저온 촉매(KATALCO 83-3X)를 사용하여 실험하였다. 수성가스 반응 후의 가스 조성은 온도가 상승할수록 일산화탄소가 줄어들고 이에 따라 수소와 이산화탄소 발생량이 증가 되어 고온 촉매를 사용했을 경우 일산화탄소 전환율 ($1-CO_{out}/CO_{in}$)은 55.6에서 95.8%까지 상승하였다. 동일한 온도조건에서는 촉매에 관계없이 $CO/H_2$가 감소할수록 전환율도 감소하는 경향을 보였지만 동일한 합성가스 조성에서 일산화탄소 전환율을 비교하면 저온 촉매가 고온 촉매보다 매우 우수함을 알 수 있었다.

• Tunnel and Underground Space
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• v.17 no.6
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• pp.464-474
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• 2007

An enhancement in the performance and safety of a high-level waste repository requires a validation of its engineered barrier. An engineering-scale test (named "KENTEX") has been conducted to investigate the thermal-hydro-mechanical behaviors in the engineered barrier of the Korean reference disposal system The validation test started on May 31, 2005 and is still under operation. The experimental data obtained allowed a preliminary and qualitative interpretation of the thermal-hydro-mechanical behaviors in the bentonite blocks. The temperature was higher as it became closer to the heater, while it became lower as it was farther away from the heater. The water content had a higher value in the part close to the hydration surface than that in the heater part. The relative humidity data suggested that a hydration of the bentonite blocks might occur by different drying-wetting processes, depending on their position. The total pressure was continuously increased by the evolution of the saturation front in the bentonite blocks and thereby the swelling pressure. Near the heater region, there was also a significant contribution of the thermal expansion of bentonite and the vapor pressure in the pores of the bentonite blocks.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.1
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• pp.11-21
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• 2013

The Geyoungju Ca-bentonite with dry density of 1.6 g/$cm^3$ has been considered as a standard buffer material for the disposal of high level waste in KAERI disposal system design. But it had relatively lower thermal conductivity compared with other surrounding materials, that was one of key parameters to limit the increase of the disposal density in the disposal system. In this study, various additives were selected and mixed with the Ca-bentonite in different mixing methods in order to increase the thermal conductivity from 0.8 W/mK to 1.0 W/mK. As an additive, CNT (Cabon Nano Tube), graphite, alumina, CuO, and $Fe_2O_3$ were selected, which are chemically stable and have good thermal conductivity. As mixing methods, dry hand-mixer mixing, wet milling and dry ball mill mixing were applied for the mixing. Above all, the ball mill mixing was proved to be most effective since the produced mixture was most homogeneous and showed higher increase in the thermal conductivity. From this study, it was confirmed that the thermal conductivity for the Geyoungju Ca-bentonite could be improved by adding small amount of highly thermal conductive material to 1.0 W/mk. In conclusion, it was believed that the experimental results will be valuable in the disposal system design if the additive effects on the swelling and permeability on the compact bentonite are also approved in further studies.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.2
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• pp.117-131
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• 2006

A coupled T-H-M(Thermo-Hydro-Mechanical) analysis was carried out for KENTEX (KAERI Engineering-scale T-H-M Experiment for Engineered Barrier System), which is a facility for validating the coupled T-H-M behavior in the engineered barrier system of the Korean reference HLW(high-level waste) disposal system. The changes of temperature, water saturation, and stress were estimated based on the coupled T-H-M analysis, and the influence of the types of mechanical constitutive material laws was investigated by using elastic model, poroelastic model, and poroelastic-plastic model. The analysis was done using ABAQUS, which is a commercial finite element code for general purposes. From the analysis, it was observed that the temperature in the bentonite increased sharply for a couple of days after heating the heater and then slowly increased to a constant value. The temperatures at all locations were nearly at a steady state after about 37.5 days. In the steady state, the temperature was maintained at $90^{\circ}C$ at the interface between the heater and the bentonite and at about $70^{\circ}C$ at the interface between the bentonite and the confining cylinder. The variation of the water saturation with time in bentonite was almost same independent of the material laws used in the coupled T-H-M processes. By comparing the saturation change of T-H-M and that of H-M(Hydro-Mechanical) processes using elastic and poroelastic material mod31 respectively, it was found that the degree of saturation near the heater from T-H-M calculation was higher than that from the coupled H-M calculation mainly because of the thermal flux, which seemed to speed up the saturation. The stresses in three cases with different material laws were increased with time. By comparing the stress change in H-M calculation using poroelasetic and poroelasetic-plastic model, it was possible to conclude that the influence of saturation on the stress change is higher than the influence of temperature. It is, therefore, recommended to use a material law, which can model the elastic-plastic behavior of buffer, since the coupled T-H-M processes in buffer is affected by the variation of void ratio, thermal expansion, as well as swelling pressure.

• Journal of the Korean Association of Geographic Information Studies
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• v.11 no.3
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• pp.107-117
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• 2008

Numerous debates and efforts have been made to utilize land resources more effectively especially for the state-owned land in an urban area. Currently most of small size state-owned lands within urban areas are not used effectively due to the limitations in physical conditions and profitability. Some of these properties are occupied illegally and being used for various private purposes. Considering the shortage of land supply in urban areas, there need to be some improvements in the utilization and management of public land. The purpose of this study, therefore, is to identify and evaluate the location, current uses, physical conditions, and development potential of small size public properties in Seoul area. Data analysis was conducted by using GIS. The results of the study indicate that it is possible to utilize small size state-owned lands within an urban area more rationally and systematically by evaluating the characteristics of neighborhood and the site.