• 콘크리트학회논문집
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• 제19권2호
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• pp.189-197
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• 2007

터널 라이닝은 대형 화재 등과 같은 고온에 노출될 경우, 폭렬이 발생하고 이로 인해 급격한 온도 전달 및 내력 저하로 구조체 붕괴의 원인이 될 수 있다는 것이 여러 사례를 통해 보고되고 있다. 본 연구는 터널라이닝의 내화뿜칠 재료로 매우 적합할 것으로 판단되는 고인성 고내화성 시멘트 복합체(FR-ECC)를 개발하고 이의 역학적 특성 및 내화 성능을 평가하고자 하였다. 이를 위하여 FR-ECC에 있어서의 배합 요인을 실험 변수로 내화 시험을 실시하였으며 비정상 온도 분포 해석 기법(nonlinear transient heat flow analysis)을 이용하여 이를 해석적으로 묘사 검증되었다. 또한, 실험 결과를 통해 검증된 해석 기법을 이용하여 터널라이닝에 대한 열전달 해석을 수행하여 FR-ECC를 내화 2차 라이닝재로 이용하는 경우의 거동 특성을 분석하였다. 실험 결과 내화 성능을 향상시키기 위한 FR-ECC의 최적 배합은 PVA 섬유 또는 PP 섬유 혼입률 $V_f=2.0%$, 다공성 세라믹재 혼입률 $V_C=3.6%$, 공기량 $V_A=15%$로 나타났으며, 검증된 비정상 온도 분포 해석 기법을 이용하여 기존 터널에 40mm FR-ECC를 추가 라이닝 한 경우에 대한 해석 결과, 콘크리트 및 철근의 온도 분포가 모두 $350^{\circ}C$ 이내에서 제어되어 터널 내 콘크리트 및 철근에 대한 화재 피해를 방지할 수 있을 것으로 판단되었다.

• 대한기계학회논문집 C: 기술과 교육
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• 제5권2호
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• pp.135-143
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• 2017

국내 유일의 연구용원자로인 하나로(Hi-flux Advanced Neutron Application ReactOr)는 다목적으로 중성자를 이용하기 위해 개방형 수조 내 노심이 존재하는 구조이며, 노심에서 발생되는 핵분열 열을 제거하기 위한 일차 냉각계통, 그리고 연결된 유체계통이 구비되어 있다. 원자로 수조 상부 근방에서 진행되는 방사성 작업 시 작업자의 방사능 피폭을 최소화하기 위해 수조고온층계통에 의해 상부에 고온층이 형성되어 있으며, 다소 저온 영역에 있는 방사능 가스 및 이물질이 상부로 올라오는 것을 방지하기 위해 수조수 온도를 $50^{\circ}C$이하로 제한하고 있으며 이를 위해 수조수관리계통이 연결되어 있다. 수조수관리계통의 구비된 판형열교환기의 열용량을 정상운전 조건에서 260 kW가 되도록 설계하여 각 수조에서 발생되는 열원을 제거하는지에 대해 평가하였고, 원자로 운전 모드와 관계없이 정상적으로 유체계통이 운전된다면 각 수조의 수조수 온도는 제한치 이하를 유지하고 있음을 확인하였다.

• 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.

• 한국의류산업학회지
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• 제16권6호
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• pp.945-953
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• 2014

This study aims to develop protective pants to relieve impact from falls and to present basic data for the development. The survey results are as follows; First, 45% of the respondents were in their 60s and 55% of them were in their over 70s and older. Also, 64% of them have fallen once for the past year and 36% of them have fallen twice or more. The older they were, the more there were those who have fallen twice or more. This indicated the older people has experienced more fall accidents again after a initial fall accident. Second, as per accident situations, the survey showed that fall accidents happened the most in the winter and in the afternoon (12-18 pm). Also, it happened on a street mostly and they were wearing sneakers or hiking boots when they got a hurt slipped in a front or side by missing their step in a walk. The injury areas are mostly knee and ankle. They had the bruises or a sprain in their knee and ankle mostly. The rate of bone fracture was 19.5%. Therefore, the protection area to falls in lower body is the knee. But hip and hip joint should be protected with knee as well because those are usually be broken when it is damaged. Third, approximately 80% of those who were hospitalized for treatment had surgery. Patients who had surgery were rather in their over 70s than in their 60s. The older they were, the more serious their fracture was. The period of hospital or outpatient treatment is more than three weeks in many cases. They responded their health got worse after falls. Aftereffects of accidents were physical discomfort, anxiety and medical costs. Falls to the old makes physical damage, psychological damage, which cause reduced physical activity and the increased cost of health care with economic losses. So it results on a negative impact on the life of the old. Fourth, elderly females were rarely aware of impact protective clothing and they have never purchased such clothing. For impact protective pants, the major consideration was suitable design for their body types. They liked casual style with front or side pockets and simple designs without any patterns or decorations. As per pants materials, they responded that they need functionality, activity and elasticity. Among the functional points, insulation of cloths are considered importantly, so the heat reservance of material in the impact protective pants should be considered carefully.

• 한국가스학회지
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• 제13권2호
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• pp.41-48
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• 2009

지난 30년 동안 발생한 천연가스자동차 사고사례를 수집하고 사고원인을 용기의 형태별로 분석하였다. 먼저 국내에서는 지금까지 6건의 사고가 발생하였는데 사고원인으로는 열처리 불량으로 인한 용기파열사고가 3건이고 복합재료의 손상에 의한 용기파열과 천연가스자동차 화재로 인한 용기파열, 그리고 정비불량으로 인한 연료배관 가스누출사고가 각각 1건씩을 기록하고 있다. 국외에서 발생한 사고를 용기 형태별로 살펴보면, 전체 사고용기의 약 29%가 Type I 용기에서 발생하였고, Type IV가 약 24%, Type II가 16%, 그리고 Type III가 14%를 차지하고 있다. 사고원인에 있어서는 원재료 및 제조과정의 오류에 의한 용기파열이 37%로 가장 높았고 용기의 반복사용으로 인한 응력부식균열이 16%로 위 두 가지 사고원인이 전체 사고용기의 절반을 차지하였다. 다음은 PRD의 결함과 과충전으로 인한 용기파열사고가 15%이고 그 밖에 화재 및 원인불명 등이 나머지를 차지하고 있음을 알 수 있다. 이상에서 용기제조자는 용기형태에 관계없이 원재료 및 용기제조공정의 품질관리와 라이너의 부식을 방지하는 도장을 강화해야 하고, 운송사업자는 연료장치의 일상점검을 통해 천연가스자동차의 시설을 항상 안전한 상태로 유지 관리하는 노력이 필요하다고 요약할 수 있다.

• 대한한의학회지
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• 제18권2호
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• pp.223-244
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• 1997

Clinical observation was done on 290 cases of patients who were diagnosed as CVA with brain CT, TCD, MRI scan and clinical observation. They were hospitalized in the oriental medical hospital of Kyung-Won University from 1st January to 31st December in 1996. 1. The cases were classified into the following kinds : cerebral infarction, cerebral hemorrhage, and transient ischemic attack. The most case of them was the cerebr진 infarction. 2. There is no significant difference in the frequency of strokes in male and female. And the frequency of strokes was highest in the aged over 50. 3. In cerebral infarction the most frequent lesion was the territory of middle cerebral artery, and in cerebral hemorrhage the most frequent lesion was the basal ganglia. 4. The most ordinary preceding disease was hypertension, and the next was diabetes. 5. The rate of recurrence was high in cerebral infarction. 6. The frequency of strokes seems to have no relation to the season. 7. The cerebral infarction occurred usually in resting and sleeping, and the cerebral hemorrhage in acting. 8. The course of entering hospital, most patients visited this hospital as soon as CVA occurred. And the half of patient visited this hospital within 2 days after CVA attack. 9. In the cases of patients who were unconscious at the admission, the prognosis was worse than that of the alert patients. 10. The common symptoms were motor disability and verbal disturbance. 11. The average duration of hospitalization was 27.4 days, and in case of cerebral hemorrhage the duration was prolonged. 12. The average time to start physical therapy was 13.3rd day after stroke in cerebral infarction and it was 19.9th day after stroke in cerebral hemorrhage. 13. The common complications were urinary tract infection, pneumonia, myocardial infarction and so on. 15. At the time of entering hospital, in most cases the blood pressure was high, but blood pressure was well controlled at the time of discharge. 16. Generally reported, hypercholesterolemia and hypertriglyceridemia are usually found in cerebral infarction. But in this study, they were found more frequently in cerebral hemorrhage than in infarction. 17, In the most cases, western and oriental medical treatments were given simultaneously. 18. In acute or subacute stage, the methods of smoothening the flow of KI(順氣), dispelling phlegm(祛痰), clearing away heat(淸熱) or purgation(瀉下) were frequently used. And in recovering stage, the methods of replenishing KI(補氣), tonifying the blood(補血) or tranquilization(安神) were frequently used.

• Nuclear Engineering and Technology
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• 제49권1호
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• pp.54-70
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• 2017

The accumulator is a passive safety injection device for emergency core cooling systems. As an important safety feature for providing a high-speed injection flow to the core by compressed nitrogen gas pressure during a loss-of-coolant accident (LOCA), the accumulator injects its precharged nitrogen into the system after its coolant has been emptied. Attention has been drawn to the possible negative effects caused by such a nitrogen injection in passive safety nuclear power plants. Although some experimental work on the nitrogen injection has been done, there have been no comparative tests in which the effects on the system responses and the core safety have been clearly assessed. In this study, a new thermal hydraulic integral test facility-the advanced core-cooling mechanism experiment (ACME)-was designed and constructed to support the CAP1400 safety review. The ACME test facility was used to study the nitrogen injection effects on the system responses to the small break loss-of-coolant accident LOCA (SBLOCA) transient. Two comparison test groups-a 2-inch cold leg break and a double-ended direct-vessel-injection (DEDVI) line break-were conducted. Each group consists of a nitrogen injection test and a nitrogen isolation comparison test with the same break conditions. To assess the nitrogen injection effects, the experimental data that are representative of the system responses and the core safety were compared and analyzed. The results of the comparison show that the effects of nitrogen injection on system responses and core safety are significantly different between the 2-inch and DEDVI breaks. The mechanisms of the different effects on the transient were also investigated. The amount of nitrogen injected, along with its heat absorption, was likewise evaluated in order to assess its effect on the system depressurization process. The results of the comparison and analyses in this study are important for recognizing and understanding the potential negative effects on the passive core cooling performance caused by nitrogen injection during the SBLOCA transient.

• Nuclear Engineering and Technology
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• 제50권2호
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• pp.268-279
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• 2018

The ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF, and AREVA NP within the PLEIADES software environment models the behavior of fuel rods during irradiation in commercial pressurized water reactors (PWRs), power ramps in experimental reactors, or accidental conditions such as loss of coolant accidents or reactivity-initiated accidents (RIAs). As regards the latter case of transient in particular, ALCYONE is intended to predictively simulate the response of a fuel rod by taking account of mechanisms in a way that models the physics as closely as possible, encompassing all possible stages of the transient as well as various fuel/cladding material types and irradiation conditions of interest. On the way to complying with these objectives, ALCYONE development and validation shall include tests on $PWR-UO_2$ fuel rods with advanced claddings such as M5(R) under "low pressure-low temperature" or "high pressure-high temperature" water coolant conditions. This article first presents ALCYONE V1.4 RIA-related features and modeling. It especially focuses on recent developments dedicated on the one hand to nonsteady water heat and mass transport and on the other hand to the modeling of grain boundary cracking-induced fission gas release and swelling. This article then compares some simulations of RIA transients performed on $UO_2$-M5(R) fuel rods in flowing sodium or stagnant water coolant conditions to the relevant experimental results gained from tests performed in either the French CABRI or the Japanese NSRR nuclear transient reactor facilities. It shows in particular to what extent ALCYONE-starting from base irradiation conditions it itself computes-is currently able to handle both the first stage of the transient, namely the pellet-cladding mechanical interaction phase, and the second stage of the transient, should a boiling crisis occur. Areas of improvement are finally discussed with a view to simulating and analyzing further tests to be performed under prototypical PWR conditions within the CABRI International Program. M5(R) is a trademark or a registered trademark of AREVA NP in the USA or other countries.

• Nuclear Engineering and Technology
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• 제53권10호
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• pp.3217-3228
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• 2021

Flow blockage of the fuel assembly in the lead-based fast reactor (LFR) may produce critical local spots, which will result in cladding failure and threaten reactor safety. In this study, the flow blockage characteristics were analyzed with the sub-channel analysis method, and the circumferentially-varied method was employed for considering the non-uniform distribution of circumferential temperature. The developed sub-channel analysis code SACOS-PB was validated by a heat transfer experiment in a blocked 19-rod bundle cooled by lead-bismuth eutectic. The deviations between the predicted coolant temperature and experimental values are within ±5%, including small and large flow blockage scenarios. And the temperature distributions of the fuel rod could be better simulated by the circumferentially-varied method for the small blockage scenario. Based on the validated code, the analysis of blockage characteristics was conducted. It could be seen from the temperature and flow distributions that a large blockage accident is more destructive compared with a small one. The sensitivity analysis shows that the closer the blockage location is to the exit, the more dangerous the accident is. Similarly, a larger blockage length will lead to a more serious case. And a higher exit temperature will be generated resulting from a higher peak coolant temperature of the blocked region. This work could provide a reference for the future design and development of the LFR.

• Composites Research
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• 제36권3호
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• pp.186-192
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• 2023

최근, 철도차량 분야에서는 경량화 및 운송 효율화를 위해 복합재 활용에 대한 관심이 높아지고 있다. 이에 따라 다양한 차량 부품에 복합재를 적용하고자 하는 연구 및 상용화 개발이 활발히 이루어지고 있으며, 복합재 적용에 대한 품질 검증을 위해 완성품의 기계적 성능 평가와 같은 사후 측정을 중심으로 평가가 이루어지고 있다. 하지만, 제작 품질에 큰 영향을 미치는 요소인 복합재 성형 과정에서 발생하는 열과 응력에 대한 분석은 미비한 상황이다. 따라서, 본 연구에서는 철도차량용 복합재 부품의 성형 품질을 검증하기 위하여 가장 활발히 사용되는 복합재 내장재 패널 2종(라미네이트 패널, 샌드위치 패널)에 대한 성형 품질 분석을 진행하였다. 이를 위해 복합재 내부 적용에 용이한 FBG 광섬유 센서를 이용하여 성형 과정 동안 온도 및 변형률 변화를 모니터링 하고, 성형 완료 후 발생하는 잔류 변형률 값을 측정하였다. 결과적으로, 과열 현상과 과도 잔류응력이 발생하지 않은 것을 확인함으로써 철도차량용 복합재 내장재 패널의 우수한 성형 품질을 검증하였다.