• Nuclear Engineering and Technology
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• 제51권7호
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• pp.1738-1748
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• 2019

Previous research has shown that the inclined condition has an impact on the natural circulation (natural circulation) mode operation of Floating Nuclear Power Plant (FNPP) mounted on the movable marine platform. Due to its compact structure, small volume, strong maneuverability, the Integral Pressurized Water Reactor (IPWR) is adopted as marine reactor in general. The OTSGs of IPWR are symmetrically arranged in the annular region between the reactor vessel and core support barrel in this paper. Therefore, many parallel natural circulation loops are built between the core and the OTSGs primary side when the main pump is stopped. and the inclined condition would lead to discrepancies of the natural circulation drive head among the OTSGs in different locations. In addition, the flow rate and temperature nonuniform distribution of the core caused by inclined condition are coupled with the thermal hydraulics parameters maldistribution caused by OTSG group operating mode on low power operation. By means of the RELAP5 codes were modified by adding module calculating the effect of inclined, heaving and rolling condition, the simulation model of IPWR in inclined condition was built. Using the models developed, the influences on natural circulation operation by inclined angle and OTSG position, the transitions between forced circulation (forced circulation) and natural circulation and the effect on natural circulation operation by different OTSG grouping situations in inclined condition were analyzed. It was observed that a larger inclined angle results the temperature of the core outlet is too high and the OTSG superheat steam is insufficient in natural circulation mode operation. In general, the inclined angle is smaller unless the hull is destroyed seriously or the platform overturn in the ocean. In consequence, the results indicated that the IPWR in the movable marine platform in natural circulation mode operation is safety. Selecting an appropriate average temperature setting value or operating the uplifted OTSG group individually is able to reduce the influence on natural circulation flow of IPWR by inclined condition.

• 한국자기학회지
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• 제3권3호
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• pp.179-184
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• 1993

비정질 합금 $Fe_{78}Si_{9}B_{13}$의 구조를 X-선 회절상을 분석하여 구하였다. 계산된 동경분포함수(RDF)의 첫번째 peak는 최인접 원자의 분포를 나타내는 것으로 Gaussian 함수형태를 나타낸다. 구조분석에서 본 시료의 최인접 원자배위수는 13.5이고, 최인접 원자간 평균거리 $r_{0}$는 $2.595{\AA}$, 인접원자들의 분포를 나타내는 Gaussian 함수의 변수 ${\delta}r$은 $0.27{\AA}$이다. 저온에서의 포화자화의 온도 의존성은 spin 파로 설명할 수 있으며, 이 때에 계산된 spin파 stiffness 상수는 $117.8\;meV\;{\AA}^2$ 이다. 또한, 포화자화의 온도 의존성을 Handrich의 분자장 이론식과 맞추어 얻은 변수는 각각 S=1/2 일때 ${\Delta}=0.32$이고, S=1 일때 ${\Delta}=0.23$으로 이론식과 실험결과가 전체적으로 잘 일치한다. 구조분석 결과와 분자장 이론식에서 구한 변수를 활용하여 spin파 stiffness 상수를 계산할 수 있으며, 이로써 구한 값은 S=1/2일때 $149\;meV\;{\AA}^2$ 이고, S=1 일 때 $138\;meV\;{\AA}^2$ 이다. 또한, 평균 교환결합상수 J($r_{0}$)는 S=1/2일때 17.9 meV이고, S=1일때는 J($r_{0}$)는 6.7 meV 으로 추정된다.