• Nuclear Engineering and Technology
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• 제39권5호
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• pp.603-616
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• 2007

Roy Huddle, having invented the coated particle in Harwell 1957, stated in the early 1970s that we know now everything about particles and coatings and should be going over to deal with other problems. This was on the occasion of the Dragon fuel performance information meeting London 1973: How wrong a genius be! It took until 1978 that really good particles were made in Germany, then during the Japanese HTTR production in the 1990s and finally the Chinese 2000-2001 campaign for HTR-10. Here, we present a review of history and present status. Today, good fuel is measured by different standards from the seventies: where $9*10^{-4}$ initial free heavy metal fraction was typical for early AVR carbide fuel and $3*10^{-4}$ initial free heavy metal fraction was acceptable for oxide fuel in THTR, we insist on values more than an order of magnitude below this value today. Half a percent of particle failure at the end-of-irradiation, another ancient standard, is not even acceptable today, even for the most severe accidents. While legislation and licensing has not changed, one of the reasons we insist on these improvements is the preference for passive systems rather than active controls of earlier times. After renewed HTGR interest, we are reporting about the start of new or reactivated coated particle work in several parts of the world, considering the aspects of designs/ traditional and new materials, manufacturing technologies/ quality control quality assurance, irradiation and accident performance, modeling and performance predictions, and fuel cycle aspects and spent fuel treatment. In very general terms, the coated particle should be strong, reliable, retentive, and affordable. These properties have to be quantified and will be eventually optimized for a specific application system. Results obtained so far indicate that the same particle can be used for steam cycle applications with $700-750^{\circ}C$ helium coolant gas exit, for gas turbine applications at $850-900^{\circ}C$ and for process heat/hydrogen generation applications with $950^{\circ}C$ outlet temperatures. There is a clear set of standards for modem high quality fuel in terms of low levels of heavy metal contamination, manufacture-induced particle defects during fuel body and fuel element making, irradiation/accident induced particle failures and limits on fission product release from intact particles. While gas-cooled reactor design is still open-ended with blocks for the prismatic and spherical fuel elements for the pebble-bed design, there is near worldwide agreement on high quality fuel: a $500{\mu}m$ diameter $UO_2$ kernel of 10% enrichment is surrounded by a $100{\mu}m$ thick sacrificial buffer layer to be followed by a dense inner pyrocarbon layer, a high quality silicon carbide layer of $35{\mu}m$ thickness and theoretical density and another outer pyrocarbon layer. Good performance has been demonstrated both under operational and under accident conditions, i.e. to 10% FIMA and maximum $1600^{\circ}C$ afterwards. And it is the wide-ranging demonstration experience that makes this particle superior. Recommendations are made for further work: 1. Generation of data for presently manufactured materials, e.g. SiC strength and strength distribution, PyC creep and shrinkage and many more material data sets. 2. Renewed start of irradiation and accident testing of modem coated particle fuel. 3. Analysis of existing and newly created data with a view to demonstrate satisfactory performance at burnups beyond 10% FIMA and complete fission product retention even in accidents that go beyond $1600^{\circ}C$ for a short period of time. This work should proceed at both national and international level.

• 방사성폐기물학회지
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• 제3권3호
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• pp.249-256
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• 2005

우라늄 변환시설의 라군 슬러지에 함유된 질산염의 안정적 처리를 위해 물 첨가 용해를 실시한 뒤, 여과 케이크의 안정화 특성에 대하여 알아보았다. 물 용해에 의해 대부분의 질산염은 고농도 질산염 용액으로 제거되었으므로, 여과 케이크의 열분해는 $900^{\circ}C$에서 하나의 단계로 수행하였다. Muffle furnace를 이용하여 $900^{\circ}C$에서 5시간동안 여과 케이크의 열분해를 실시한 결과 라군 1 슬러지에 포함된 U은 $NaNO_3$의 열분해와 함께 $Na_{2}O{\cdot}2UO_3$의 형태로 안정화 되었다. 라군 2 열분해 잔류물의 경우에는 열분해 시 생성된 CaO가 냉각과정에서 수분과 반응하여 $Ca(OH)_2$로 전환되는 것을 TG/DTA 분석과 XRD 분석을 통해 확인할 수 있었지만, 처분장에서 대기중 노출이나 지하수의 침출 등에는 안정한 화합물로 알려져 있으므로, 특별한 첨가제의 첨가 없이 단순 열분해 후 처분이 가능할 것으로 판단된다.

• 방사성폐기물학회지
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• 제1권1호
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• pp.11-23
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• 2003

국내의 가동 중지된 우라늄 변환시설의 해체 시 우라늄 화합물로 오염되어 대량으로 발생될 금속폐기물의 재활용 또는 자체처분을 위한 제염기술로 전해제염 공정의 적용성을 평가하였다. 이를 위하여 우라늄 변환시설 내부설비의 주 구성 재료인 SUS-304 와 Inconel-600 금속시편을 대상으로 전해용해 실험을 수행하였다. SUS-304 와 Inconel-600 금속시편에 대한 전해용해 성능에 있어서 중성염 전해용액으로 $Na_2$SO$_4$가 가장 효과적이었으나, 우라늄변환시설의 가동 시 질산 매질과 주로 접촉했던 설비 표면의 이력과 시설 가동 중 발생한 우라늄 폐액의 성상을 고려하여 $Na_2$SO$_4$ 전해용액 내에서의 SUS-304 시편에 대한 전해용해와 비교해서 약 30%, 그리고 Inconel-600 시편에 대해서는 거의 동등한 성능을 보인 NaNO$_3$ 중성염 용액을 금속성폐기물의 전해제염 용액으로 선정하였다. 본 연구에서는 NaNO$_3$ 중성염 전해용액에서 전류밀도, 전해시간 및 전해 용액의 농도가 SUS-304 및 Inconel-600 금속시편의 전해용해 성능에 미치는 영향을 조사하였다. 이 실험결과를 바탕으로 실제 우라늄 변환시설로부터 인출하여 $UO_2$, AUC 및 ADU 등의 우라늄 화합물로 오염된 시편에 대해 전류밀도 100mA/$\textrm{cm}^2$, IM NaNO$_3$ 전해용액 내에서 전해 제염 실증시험을 수행하였으며, 오염물의 종류 및 오염준위의 대소와는 관계없이 모든 시편에 대하여 10분 이내의 짧은 시간 내에 자체처분 기준치 이하로 $\alpha$ 및 $\beta$ 방사능 준위를 감소시킴으로써 본 중성염 전해제염이 매우 성공적임을 확인하였다.nely regimented hierarchical language. I try, in this paper, to develop the idea that hierarchical regimentation of Korean language uses is not humane. 1 of for the main argument for the thesis as what follows: How could one justify the hierarchical regimentation of a language like Korean\ulcorner Only if there is an essential structure in which the fine grades of differences of social positions of all the people are distinct; The essentialism here involved is not plausible. And I may add that language is to be used fur the purposes of communication, rationalization and expression. If true, language use is a genuine art of liberation or humanization. Any overt hierarchical language tends to damage those purposes and more to enforce those oppressive elements already existing in the community. Then, a hierarchical language is to defeat its own purpose.중 행정부가 북한에 대해 실시한 포용정책이 어떠한 성과를 거두고 어떠한 문제점을 간과하고 있는가에 대해 논의하고, 대북 정책의 새로운 지평을 논의하는 것을 목적으로 하고 있다. 1) 포용 정책은