• Nuclear Engineering and Technology
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• 제55권8호
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• pp.3017-3029
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• 2023

In the late in-vessel phase of a nuclear reactor severe accident, the internal heat transfer and crust evolution during the debris bed melting process have important effects on the thermal load distribution along the vessel wall, and further affect the reactor pressure vessel (RPV) failure mode and the state of melt during leakage. This study coupled the phase change model and large eddy simulation to investigate the variations of the temperature, melt liquid fraction, crust and heat flux distributions during the debris bed melting process in the hypothetical severe accident of HPR1000. The results indicated that the heat flow towards the vessel wall and upper surface were similar at the beginning stage of debris melting, but the upward heat flow increased significantly as the development of the molten pool. The maximum heat flux towards the vessel wall reached 0.4 MW/m². The thickness of lower crust decreased as the debris melting. It was much thicker at the bottom region with the azimuthal angle below 20° and decreased rapidly at the azimuthal angle around 20-50°. The maximum and minimum thicknesses were 2 and 90 mm, respectively. By contrast, the distribution of upper crust was uniform and reached stable state much earlier than the lower crust, with the thickness of about 10 mm. Moreover, the sensitivity analysis of initial condition indicated that as the decrease of time interval from reactor scram to debris bed dried-out, the maximum debris temperature and melt fraction became larger, the lower crust thickness became thinner, but the upper crust had no significant change. The sensitivity analysis of in-vessel retention (IVR) strategies indicated that the passive and active external reactor vessel cooling (ERVC) had little effect on the internal heat transfer and crust evolution. In the case not considering the internal reactor vessel cooling (IRVC), the upper crust was not obvious.

• Asian-Australasian Journal of Animal Sciences
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• 제27권1호
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• pp.77-82
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• 2014

The study aimed to evaluate the potential effects of feeding with phytase transgenic corn (PTC) on organ weight, serum biochemical parameters and nutrient digestibility, and to determine the fate of the transgenic DNA in laying hens. A total of 144 50-week-old laying hens were grouped randomly into 2 treatments, with 8 replicates per treatment and 9 hens per replicate. Each treatment group of hens was fed with diets containing 62.4% non-transgenic conventional corn (CC) or PTC for 16 weeks. The phytase activity for CC was 37 FTU/kg of DM, whereas the phytase activity for PTC was 8,980 FTU/kg of DM. We observed that feeding PTC to laying hens had no adverse effect on organ weight or serum biochemical parameters (p>0.05). A fragment of a poultry-specific ovalbumin gene (ov) was amplified from all tissues of hens showing that the DNA preparations were amenable to PCR amplification. Neither the corn-specific invertase gene (ivr) nor the transgenic phyA2 gene was detected in the breast muscle, leg muscle, ovary, oviduct and eggs. The digestibility data revealed no significant differences between the hens that received the CC- and PTC-based diets in the digestibility of DM, energy, nitrogen and calcium (p>0.05). Phosphorus digestibility of hens fed the PTC-based diet was greater than that of hens fed the CC-based diet (58.03% vs 47.42%, p<0.01). Based on these results, it was concluded that the PTC had no deleterious effects on the organ weight or serum biochemical parameters of the laying hens. No recombinant phyA2 gene was detected in muscle tissues and reproductive organs of laying hens. The novel plant phytase was efficacious in improving the phosphorus digestibility of laying hens.

• 전자공학회논문지 IE
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• 제46권4호
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• pp.1-7
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• 2009

ITS와 ETC 기술은 새로운 도로의 건설 없이 교통 능률과 이동 안전성을 개선하는 것을 목표로 한다. 이를 실현하는 한 방법으로 요즘 DSRC가 각광을 받고 있다. 2007년 5월에 공표된 중국 DSRC 표준은 낮은 비트 전송율, 단문 메시지 그리고 단순한 MAC 제어를 가지고 있다. DSRC 시스템 사용자들은 전지 1개로 1년 이상의 긴 사용기간을 원한다. 본 논문에서는 초저전력 소비 구조의 SoC를 설계하고자 한다. 몇몇 디지털 논리 개념과 아날로그 전력 제어 논리가 전력 소비를 줄이기 위한 기법으로 사용되었다. SoC 동작 모드, 클럭 속도, 동작 전압 범위, 웨이크업 신호 검출기, 아날로그 비교기, 그리고 내부 전압 조정기(IVR)와 외부 전력 스위치(EPS)등이 설계된 블럭들이다. 시뮬레이션으로 확인한 SoC 전력 소비는 동작모드에서는 8.5mA@20Mhz, 0.9mA@1Mhz 이하이며, 전력 정지 모드에서는 5uA 이하였다. SoC는 2008년 8월에 설계를 완료하고, 2008년 11월에 $0.18{\mu}m$ CMOS공정으로 제작을 마쳤다.

• 한국컴퓨터그래픽스학회논문지
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• 제23권5호
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• pp.39-49
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• 2017

본 연구는 HMD 사용자와 Non-HMD 사용자가 같은 공간에서 함께 행동하면서 다양한 경험과 높은 현존감을 이끌어낼 수 있는 비대칭 가상현실(asymmetric VR) 콘텐츠의 핵심 요인과 활용 방안을 제안한다. 제안하는 asymmetric VR 콘텐츠의 핵심은 사용자들이 HMD 착용 유무에 상관없이 사용자가 콘텐츠에 참여하는 범위, 환경을 폭넓게 반영하여 모두가 가상현실에 몰입하고, 새로운 경험을 이끌어내는 것이다. 이를 위해 본 연구는 asymmetric VR 콘텐츠 제작에 필요한 핵심 요인으로 HMD 사용자와 Non-HMD 사용자의 역할관계, 사용자들에게 제시되는 시점 그리고 사용자들 간의 대화를 통한 의사소통 구조를 정의하였다. 이를 기반으로 보조형 asymmetric VR 콘텐츠와 협력형 asymmetric VR 콘텐츠를 직접 제작하는 과정을 통해 핵심 요인을 검증하였다. 마지막으로 제안한 asymmetric VR 콘텐츠에서의 현존감, 경험을 검증하고 활용 방안을 분석하기 위하여 참가자들을 대상으로 한 설문 실험을 진행하였다. 설문 결과 asymmetric VR 콘텐츠의 목적과 이를 체험하는 사용자들간의 핵심 요인들을 명확히 구분하고, 정의한다면 모든 사용자가 만족하는 현존감과 함께 콘텐츠가 제시하는 독립적인 경험을 제공받을 수 있음을 확인하였다.

• 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.