• 대한수학교육학회지:학교수학
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• 제15권4호
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• pp.921-940
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• 2013

본 연구는 Cabri 3D와 GSP를 이용하여 중심사영에 대한 탐구학습에서 나타나는 중학교 수학영재들의 수학적 사고특성과 교사의 역할을 분석하여 수학영재를 위한 교수 학습 자료의 개발에 시사점을 주는데 목적이 있다. 연구결과 중학교 수학영재들은 중심사영에 의한 도형의 변환을 탐구하고 이를 투시도의 작도를 통해 확인하는 과정에서 다양한 수학적 사고특성을 보였고, 교사는 학생들의 탐구문제해결을 위한 사고의 촉진과 새로운 지식의 형성을 도우면서 수업설계자, 학습촉진자, 기술적 보조자, 상담자의 역할을 하는 것으로 나타났다.

• Nuclear Engineering and Technology
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• 제39권5호
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• pp.591-602
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• 2007

The results of Reactivity-Initiated Accidents (RIA) experiments have been analysed and the main variables affecting the fuel failure propensity identified. Fuel burn-up aggravates the mechanical loading of the cladding, while corrosion, or better the hydrogen absorbed in the cladding as a consequence of corrosion, may under some conditions make the cladding brittle and more susceptible to failure. Experiments point out that corrosion impairs the fuel resistance for RIA transient occurring at cold conditions, whereas there is no evidence of important embrittlement effects at hot conditions, unless the cladding was degraded by oxide spalling. A fuel failure threshold correlation has been derived and compared with experimental data relevant for BWR and PWR fuel. The correlation can be applied to both cold and hot RIA transients, account taken for the lower ductility at cold conditions and for the different initial enthalpy. It can also be used for non-zero power transients, provided that a term accounting for the start-up power is incorporated. The proposed threshold is easy to use and reproduces the results obtained in the CABRI and NSRR tests in a rather satisfactory manner. The behaviour of advanced PWR alloys and of MOX fuel is discussed in light of the correlation predictions. Finally, a probabilistic approach has been developed in order to account for the small scatter of the failure predictions. This approach completes the RIA failure assessment in that after determining a best estimate failure threshold, a failure probability is inferred based on the spreading of data around the calculated best estimate value.

• 한국결정학회지
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• 제1권2호
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• pp.66-75
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• 1990

Pd-Te계의 상평형도를 시차열분석, X선회절분석, 전자현미분석, 반사현미경을 사용해 연구하였다. 본 계의 0-50 at.%Te 부분의 새로운 상관계가 정립되었다. 본 계에는 Pd17Te4, Pd20Te7, Pd8Te3, Pd7Te3, PdgTe4, Pd3Te2, PdTe, PdTe2 등 8개의 화합물이 존재하며 이중 Pd17Te4와 Pd7Te3는 처음 보고되는 신종 화합물이다. Pd17Te4는 등축정계이며 공간군 Fd3r에 속하며 단위포 크기 (a)는 12. 678(5)차이다. PdaTe.4와Pd7Te3의 X선회절분말자료는 사방정계의 단위포 a=12.843(3), b=15.126(3), c=11.304(2)A와 단사 정계의 단위포 a=7.444(1), b=13.918(2), c=8.873 (2)il, β=92.46(2)에 의해 각각 격자지수화가 가능하였다. 본계에 존재하는 합성 화합물의 일부 물리적, 광학적 자료를 새로 보고하였다.

• Nuclear Engineering and Technology
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• 제47권3호
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• pp.240-252
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• 2015

In the original licensing application for the prototype fast-breeder reactor, MONJU, the event progression during an unprotected loss of flow (ULOF), which is one of the technically inconceivable events postulated beyond design basis, was evaluated. Through this evaluation, it was confirmed that radiological consequences could be suitably limited even if mechanical energy was released. Following the Fukushima-Daiichi accident, a new nuclear safety regulation has become effective in Japan. The conformity of MONJU to this new regulation should hence be investigated. The objectives of the present study are to conduct a preliminary evaluation of ULOF for MONJU, reflecting the knowledge obtained after the original licensing application through CABRI experiments and EAGLE projects, and to gain the prospect of in-vessel retention for the conformity of MONJU to the new regulation. The preliminary evaluation in the present study showed that no significant mechanical energy release would take place, and that thermal failure of the reactor vessel could be avoided by the stable cooling of disrupted-core materials. This result suggests that the prospect of in-vessel retention against ULOF, which lies within the bounds of the original licensing evaluation and conforms to the new nuclear safety regulation, will be gained.