• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.3
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• pp.191-197
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• 2017

The Korea Atomic Energy Research Institute (KAERI) has developed a safeguards technology for pyroprocessing based on the Safeguards-By-Design (SBD) concept. KAERI took part in a Member-State Support Program (MSSP) to establish a pyroprocessing safeguards approach. A Reference Engineering-scale Pyroprocessing Facility (REPF) concept was designed on which KAERI developed its safeguards system. Recently the REPF is being upgraded to the REPF+, a scaled-up facility. For assessment of the nuclear-material accountancy (NMA) system, KAERI has developed a simulation program named Pyroprocessing Material Flow and MUF Uncertainty Simulation (PYMUS). The PYMUS is currently being upgraded to include a Near-Real-Time Accountancy (NRTA) statistical analysis function. The Advanced Spent Fuel Conditioning Process Safeguards Neutron Counter (ASNC) has been updated as Non-Destructive Assay (NDA) equipment for input-material accountancy, and a Hybrid Induced-fission-based Pu-Accounting Instrument (HIPAI) has been developed for the NMA of uranium/transuranic (U/TRU) ingots. Currently, performance testing of Compton-suppressed Gamma-ray measurement, Laser-Induced Breakdown Spectroscopy (LIBS), and homogenization sampling are underway. These efforts will provide an essential basis for the realization of an advanced nuclear-fuel cycle in the ROK.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.209-210
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• 2010

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.05a
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• pp.87-88
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• 2011

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.10a
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• pp.135-136
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• 2011

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2015.10a
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• pp.77-78
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• 2015

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.3
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• pp.225-232
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• 2008

An estimation has been made for inventories and characteristics of spent nuclear fuel(SNF) to be generated from existing and planned nuclear power plants based on the 3rd Basic Plan for Electric Power Demand and Supply. The characteristics under consideration in this study are dimensions, a fuel rod array, a weight, $^{235}U$ enrichment, and the discharge burnup in terms of fuel assembly. These are essentially needed for designing a pyroprocessing facility. It is appeared that the anticipated quantity by the end of 2077 is about 23,000 tU for PWR spent nuclear fuel. It is revealed that the proportion of SNF with the initial $^{235}U$ enrichment below 4.5 weight percent(wt.%) is approximately 95 % in total. For SNF with 16$\times$16 fuel rod array the proportion is expected approximately 74% in total. It appears that the average burnup of SNF will be 55 GWd/tU after the medium and/or latter part of 2010s while the average burnup is 45 GWd/tU at present. Finally, a requirement in terms of reference SNF for designing the pyroprocessing facility has been derived from the above-mentioned results. The anticipated SNF seems to be 16$\times$16 Korean Standard Fuel Assembly with a cross section of 21.4 cm$\times$21.4 cm, a length of 453 cm, a mass of 672 kg, the initial $^{235}U$ enrichment of 4.5 wt.%, and the discharge burnup of 55 GWd/tU.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.26 no.1C
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• pp.33-42
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• 2006

Lots of river embankments or levees in Korea are quite so old and unknown the origin even. The river deposits, moreover, obtainable easily somewhere were used for materials of embankment without any technical considerations such as the influence soil properties and construction methods on embankment stability. It's natural that safety would be threatened if the water level rises due to flood or rainfall when it comes to abnormal weather conditions, especially. From this point of view, enlargement of embankment, irrigation works, etc. are in progress recently at the situation from a reinforcement work. However, taking influence of soil properties and construction methods on embankment stability into account against cracking or piping is still insufficient. Fragmentary design criteria or irrational construction methods are applied rather as the case may be. In this study, therefore, a way to estimate piping and cracking resistance (Sherard, 1953) has been introduced and reevaluated for practical use with an eye to material properties and its applicability to piping-experienced embankments was examined. Piping possibility was also examined in the present design criteria and compared. In view of the results achieved, it reflects that both yield piping possibility. But it's still necessary to complement how to judge and verify piping resistance of given soils with gradation curves by the representative curve, quantitatively and that piping resistance should consider compaction effects as well.

• Journal of Biosystems Engineering
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• v.22 no.1
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• pp.21-29
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• 1997

왕겨 재를 분쇄하여 콘크리트 混和용 재료로 이용하려는 연구의 일환으煙로서, 파이로트 規模의 多目的 왕겨 燒却爐를 設計, 裂作하고 그 性能을 分析하였다. 왕겨 燃燒時의 熱에너지는 回收하여 원예施設의 煖房이나 콘크리트의 高溫 養生水로써 이용하고자 熱交煥裝置를 제작하여 왕겨 燒각爐시스템에 장착하였고, 排煙가스내의 이산화탄소가 시설원예 作物의 光合成에 이용될 수 있는지 排煙가스의 造成을 조사하였다. 분쇄된 왕겨 재의 큰크리트 混和材로서의 적합성은, 燃燒 灰分의 성분 중 $SiO_2$ 의 結晶化 상태를 分析함으로써 判斷하였다. 연구결과를 要約하면 다음과 같다. 1. 왕겨 灰分의$SiO_2$ 結晶化는 燃燒온도 $750^circ C$ 이하에서는 거의 발생하지 않는 것으로 분석되었다. 2. 燒却爐의 작동은 매우 만족스러웠으며 最適 작동조건은 왕겨供給率 15kg/h. 制御온도 $600^{\circ}C$로 分析되었다. 最適 작동조건에서, 왕겨燃燒率은 97%, 熱交換機 效率은 59.5%, 전체 시스템의 熱效率은 57.7%로서 양호하였으며, 灰分의 $SiO_2$ 結晶化도 거의 발생하지 않아 生成된 왕겨 灰分은 훌륭한 큰크리트 混和在로 판단 되었다. 3. 燒却爐내 溫度分布는 대체로 均一하였으며, 排煙가스내의 大氣오염물질 중, 질소酸化物과 황酸化物 함량은 許容기준치보다 매우 낮았으나 일산화탄소 함량은 許容기준값 부근으로 나타나 排煙가스를 직접 원예시설 내에 공급하기 위해서는 약간의 연소실 구조 개선이 필요하다고 판단되었다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.3
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• pp.219-228
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• 2012

A long-term R&D program for HLW disposal technology development was launched in 1997 in Korea and Korea Reference disposal System(KRS) for spent fuels had been developed. After then, a recycling process for PWR spent fuels to get the reusable material such as uranium or TRU and to reduce the volume of radioactive waste, called Pyro-process, is being developed. This Pyro-process produces several kinds of wastes including metal waste and ceramic waste. In this study, the characteristics of the waste from Pyro-process and the concepts of a disposal container for the wastes were described. Based on these concepts, thermal analyses were carried out to determine a layout of the disposal area of the ceramic wastes which was classified as a high level waste and to develop the disposal system called A-KRS. The location of the final repository for A-KRS is not determined yet, thus to review the potential repository domains, the possible layout in the geological characteristics of KURT facility site was proposed. These results will be used in developing a repository system design and in performing the safety assessment.

• Proceedings of the Korea Water Resources Association Conference
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• 2016.05a
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• pp.103-103
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• 2016

최근 기후변화에 따른 집중호우로 도시홍수의 피해가 급격히 증가하고 있다. 특히 인구가 밀집하고 교통량이 많은 대도시의 경우 동일한 호우에 대하여 녹지나 농경지 등에 비해 그 피해가 더 심각하다. 일반적으로 홍수 피해의 직접원인은 외수로 인한 피해와 내수로 인한 피해로 크게 구분할 수 있다. 외수피해는 주로 소하천 및 지천의 범람, 제방의 붕괴 등으로 발생한 것이며 내수피해는 배수로, 하수도 및 펌프장의 내수배제능력 부족이 주된 원인이다. 따라서 도시홍수를 효과적으로 방어하기 위해서는 우선적으로 내배수시설의 성능개선이 선행되어야 할 필요가 있다. 이러한 내배수 시설의 성능 개선을 위해서는 현재 기 설치되어 있는 빗물펌프장의 설계 및 내배수 효율에 대한 성능평가가 필요하다. 하지만 현재 국내 펌프설계기준에는 빗물펌프장의 설계 및 운영에 대한 구체적인 성능 평가 방법이 제시되어 있지 않은 실정이다. 만약, 펌프 흡입수조 및 흡입파이프의 형상이 적절하게 설계되지 못한다면 물이 파이프 입구로 부드럽게 흡입되지 못하고 볼텍스 및 스월이 발생하게 된다. 이러한 볼텍스 및 스월은 펌프 입구 쪽으로 물 뿐 아니라 공기를 함께 흡입시킴으로써 펌프의 효율저하, 소음, 진동을 발생시키며 펌프 파손의 원인이 될 수 있다. 따라서 펌프를 설치하기 전 펌프 설치 후에 발생되는 펌프 흡입부 주변의 흐름특성 변화 및 흐름특성이 구조물에 미치는 영향 등을 고려하기 위하여 수리모형실험이 필요한데, 수리모형실험은 많은 시간과 비용이 들어가기 때문에 이를 대체할 수 있는 방안이 요구된다. 그런 이유로 최근에는 수리모형실험 대신 수치모의를 이용하는 경우가 많다. 수치모의의 결과는 수리실험의 결과와 비교, 검증을 거쳐 신뢰성을 얻는다. 본 연구에서는, 3차원 수치모형의 다양한 난류모델을 이용하여 흡입파이프로 물이 유입될 때 흡입부 내, 외의 수심 별 유속 변화를 분석하고, 그 결과를 이용하여 FLOW 3D 모형의 검증을 수행하였다.