• Animal Systematics, Evolution and Diversity
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• 제31권4호
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• pp.247-256
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• 2015

A new cyclopoid species belonging to the genus Metacyclops Kiefer, 1927 is described, based upon the specimens from a temporary pool in a forest of Mt. Phnom Domnak Dambouk, situated in the southwestern part of Cambodia. Metacyclops woni sp. nov. is characterized by its quite short caudal rami, about 2.5 times longer than wide, with a spinule row on anterior quarter of lateral margin. This new species belongs to the species group with the spine formula 3,4,4,3 of swimming legs 1-4. Among the members of the species group with the combination of characters of 11-segmented antennule and a single apical spine on the second endopodal segment of leg 4, it most resembles M. deserticus Mercado-Salas and Suárez-Morales, 2013 from Mexico in carrying an outermost caudal seta slightly longer than the innermost caudal seta and an apical spine on the second endopodal segment of leg 4 slightly shorter than the segment. However, it differs clearly from the present new species by much longer caudal rami with lateral caudal seta at nearly halfway of lateral margin of the ramus and smooth posterior margin of intercoxal sclerites of legs 1-4. This is the first record of the genus Metacyclops from Cambodia and the fourth one from Southeast Asia.

• 한국환경복원기술학회지
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• 제17권2호
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• pp.61-71
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• 2014

A river fishway is a hydraulic structure enabling fish to overcome stream obstructions such as dams and weirs. The main aim of this paper is to investigate the collectibility of upstream-migrating fishes and hydraulic problems in pool-and-weir type fishway which has been established for upstream-migration at Namgang weir in the downstream of Namgang dam, and to grope for improvement measures which pool-and-weir type fishway can be switched to pool-and-partial weir type fishway through hydraulic field experiment. Exsisting fishway had problems which upstream-migrating fishes can not take a rest due to the seiche and vortex phenomena in pools and migrate to upstream because of height difference in entrance pool. In order to prevent hydraulically the seiche and vortex phenomena and establish rest area for fishes in each pool, we carried out hydraulic field experiments. In the fishway, it was to improve pool-and-weir into pool-and-partil weir, to decrease the height difference in entrance pool, and to reduce oriffice velocity of each pool. Also, we investigated fishes collectibility of after improving fishway for 6 days in September 2013. To resolve chronic problems(seiche-vortex phenomena and rest area for fishes), as weirs were remodeled into partial weir only which central part of weirs was part of non-overflow weir, we confirmed results that pool-and-weir type fishway could be switched to efficient pool-and-partial weir type fishway with relatively simple construction and low cost. Type-B which has the closed oriffices and the parts of non-overflow has the ideal conditions, but this conditions are limited to fishway of Namgang weir used in this study. Representative Ice-habor type fishway is pool-and-partial weir type fishway which has together parts of overflow and oriffices, and has excellent ability of upstream-migration. To switch from pool-and-weir type fishway to pool-and-partial weir type fishway, the size of oriffice has to be regulated by the discharge of fishway and the dimension on parts of non-overflow and overflow in weirs. Entrance pool is important facility which upstream-migrating fishes have to not only be collect but also charge with energy. In this study, entrance-pool is temporary and roughly-built, but fishes gather together more than the case of no entrance-pool. In the case of fishway which was protruded to downstream, as entrance of fishway turns toward or parallels to weir, the collectibility of fishway was excellent by attraction water.

• 유체기계공업학회:학술대회논문집
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• 유체기계공업학회 2005년도 연구개발 발표회 논문집
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• pp.503-508
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• 2005

An advanced Research Reactor (ARR) consists of an open-tank-type reactor assembly within a light water pool and generates thermal power of 20 MW. The thermal power is including a fission heat in the core, a fuel generated heat temporary stored in the pool, a circulating pumps generated heat and a neutron reflecting heat in the reflector vessel of the reactor. In order to remove the heat load, the primary cooling system will be installed. In this study, the conceptual design of the primary cooling system has been carried out using a design methodology of HANARO within a permissible range of safety. As results, it has been established that the conceptual design of the primary cooling system including design requirements, performance requirements, design restrictions, system descriptions and system operation to maintain the system functions.

• 생태와환경
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• 제43권1호
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• pp.142-149
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• 2010

일시적으로 조성되는 수환경에 서식하는 갑각류에 속하는 긴꼬리투구새우는 현존하는 화석생물로서 외국에서는 분포, 형태 및 번식 등 다양한 연구가 수행되었다. 그러나 우리나라에서는 환경부 지정 멸종위기야생동물로 지정될 만큼 희귀생물임에도 불구하고 기초연구가 매우 미흡하다. 본 연구는 한국산 긴꼬리투구새우 (T. longicaudatus)의 분포와 서식지의 특성을 파악하기 위하여 2006년 5월부터 2008년 7월까지 조사를 수행하였다. 조사결과 긴꼬리투구새우는 남한의 21개 지역의 논과 일시적으로 형성된 웅덩이에 서식하는 것으로 밝혀졌다. 긴꼬리투구새우는 조사기간 중 주로 5월에서 7월 사이에 발견되었으며, 이때 서식지의 온도범위는 약 $10.7{\sim}33.5^{\circ}C$ 이었으며, 서식지에서 약 30일 정도 생존하는 것으로 확인되었다. 환경요인 중 서식지의 평균 혼탁도는 176.8 (${\pm}239.3$) NTU로서 대조구로 선정한 논 ($28.9{\pm}26.7$ NTU)보다 상당히 높게 나타났다. 본 연구를 통해 긴꼬리투구새우는 일시적으로 형성되는 환경에 비교적 잘 적응하는 종이며, 물대기와 같은 영농활동이 이들의 개체발생과 생장에 큰 영향을 미치는 것을 확인하였다.

• 한국농림기상학회지
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• 제18권4호
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• pp.242-252
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• 2016

생태계 과정 모형인 BIOME-BGC를 이용해 국내 상록침엽수림의 탄소-물 순환 과정의 계절 및 연간 변화를 모의하여 국내의 소나무 고사 현상의 기후-토심 영향을 분석하였다. 연구지로 2009년과 2014년 각각 소나무 대량 고사가 발생한 밀양과 울진을 선정하였다. 두 지역의 표준강수지수를 산정한 결과 약 5년 내외의 주기의 가뭄현상을 판별하였다. 2000년 중반 이후 가뭄은 고온 건조 기후 특성을 보였다. 모형의 여러 변수를 조사한 결과, 임시탄소저장소인 Cpool 변수가 탄소기아에 의한 소나무고사 현상과 개연성이 큰 변수로 나타났다. Cpool의 감소는 총일차생산성(GPP) 감소 혹은 유지호흡(Rm) 증가의 결과로 발생하였고, 연구기간 중 Cpool이 최저값을 보인 해는 각 연구지역에서 소나무 대량 고사가 발생한 해와 잘 일치하였다. 두 지역 모두 가뭄에 의한 GPP 감소와 고온에 의한 Rm 증가가 Cpool의 감소를 초래하였는데, GPP와 Rm의 상대적 기여도는 지역별로 상이하였다. 특히 저온다습한 울진의 경우 Rm 증가 영향이 중요한 요인이었다. 한편 낮은 토심에서 생산성, 생체량, 증산량, Cpool 등 제반 탄소-물 관련 변수가 감소하였고 연간 변동폭이 증가하였다. 그러나 0.5 m 이하 토심에서는 Cpool에 큰 차이가 없는 것으로 보아 일정 수준 이하의 토심에서 생체량-생산성-유지호흡 간의 균형에 따라 Cpool이 유지되는 적응 메커니즘이 나타난 것으로 보인다. 이 연구의 결과 소나무 고사와 관련한 고온건조-탄소 기아 가설을 제안하였고, 보다 현실적 분석을 위한 향후 모형 개선 방향을 제안하였다.

• Journal of Chest Surgery
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• 제51권5호
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• pp.328-332
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• 2018

Background: Extracorporeal life support (ECLS) can be applied in brain-dead donors for organ perfusion before donation, thereby expanding the donor pool. The aim of this study was to examine the benefits and early clinical outcomes of ECLS for organ preservation. Methods: Between June 2012 and April 2017, 9 patients received ECLS with therapeutic intent or for organ preservation. The following data were collected: demographics, purpose and duration of ECLS, cause of death, dose of vasoactive drugs, and need for temporary dialysis before organ retrieval. The early clinical outcomes of recipients were studied, as well as survival and graft function at 1 month. Results: ECLS was initiated for extracorporeal cardiopulmonary resuscitation in 5 patients. The other patients needed ECLS due to hemodynamic deterioration during the assessment of brain death. We successfully retrieved 18 kidneys, 7 livers, and 1 heart from 9 donors. All organs were transplanted and none were discarded. Only 1 case of delayed kidney graft function was noted, and all 26 recipients were discharged without any significant complications. Conclusion: The benefits of protecting the vital organs of donors is significant, and ECLS for organ preservation can be widely used in the transplantation field.

• 한국압력기기공학회 논문집
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• 제16권1호
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• pp.110-116
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• 2020

As the management plan for domestic spent nuclear fuel is delayed, the storage of the operating nuclear power plant is approaching saturation, and the Kori 1 Unit that has reached its end of operation life is preparing for the dismantling plan. The first stage of dismantling is the transfer of spent nuclear fuel stored in storage at plants. The spent fuel management process leads to temporary storage, interim storage, reprocessing and permanent disposal. In this paper, the technical issues to be considered when transporting spent fuel in this process are summarized. The spent fuels are treated as high-level radioactive waste and strictly managed according to international regulations. A series of integrity tests are performed to demonstrate that spent fuel can be safely stored for decades in a dry environment before being transferred to an intermediate storage facility. The safety of spent fuel transport container must be demonstrated under normal transport conditions and virtual accident conditions. IAEA international standards are commonly applied to the design of transport containers, licensing regulations and transport regulations worldwide. In addition, each country operates a physical protection system to reduce and respond to the threat of radioactive terrorism.

• 한국정밀공학회지
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• 제30권2호
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• pp.223-230
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• 2013

When a new nuclear fuel is developed, an irradiation test needs to be carried out in the research reactor to analyze the performance of the new nuclear fuel. In order to check the performance of a nuclear fuel during the irradiation test in the test loop of a research reactor, sensors need to be attached in and out of the fuel rod and connect them with instrumentation cables to the measuring device located outside of the reactor pool. In particular, to check the temporary temperature change at the center of a nuclear fuel during the irradiation test, a thermocouple should be instrumented at the center of the fuel rod. Therefore, a hole needs to be made at the center of fuel pellet to put in the thermocouple. However, because the hardness and the density of a sintered $UO_2$ pellet are very high, it is difficult to make a small fine hole on a sintered $UO_2$ pellet using a simple drilling machine even though we use a diamond drill bit made by electro deposition. In this study, an automated drilling machine using a CVD diamond drill has been developed to make a fine hole in a fuel pellet without changing tools or breakage of workpiece. A sintered alumina ($Al_2O_3$) block which has a higher hardness than a sintered $UO_2$ pellet is used as a test specimen. Then, it is verified that a precise hole can be drilled off without breakage of the drill bit in a short time.

• Journal of Radiation Protection and Research
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• 제28권2호
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• pp.127-135
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• 2003

The primary contributors to the total occupational radiation exposure in operating nuclear power plants are operation and maintenance activities doting refueling outages. The Advanced Power Reactor 1400 (APR1400) includes a number of design improvements and plans to utilize advanced maintenance methods and robotics to minimize the annual collective dose. The major radiation exposure reduction features implemented in APR1400 are a permanent refueling pool seal, quick opening transfer tube blind flange, improved hydrogen peroxide injection at shutdown, improved permanent steam generator work platforms, and more effective temporary shielding. The estimated average annual occupational radiation exposure for APR1400 based on the reference plant experience and an engineering judgment is determined to be in the order of 0.4 man-Sv, which is well within the design goal of 1 man-Sv. The basis of this average annual occupational radiation exposure estimation is an eighteen (18) month fuel cycle with maintenance performed to steam generators and reactor coolant pumps during refueling outage. The outage duration is assumed to be 28 days. The outage work is to be performed on a 24 hour per day basis, seven (7) days a week with overlapping twelve (12) hour work shifts. The occupational radiation exposure for APR1400 is also determined by an alternate method which consists of estimating radiation exposures expected for the major activities during the refueling outage. The major outage activities that cause the majority of the total radiation exposure during refueling outage such as fuel handling, reactor coolant pump maintenance, steam generator inspection and maintenance, reactor vessel head area maintenance, decontamination, and ICI & instrumentation maintenance activities are evaluated at a task level. The calculated value using this method is in close agreement with the value of 0.4 man-Sv, that has been determined based on the experience aid engineering judgement. Therefore, with the As Low As Reasonably Achievable (ALARA) advanced design features incorporated in the design, APR1400 design is to meet its design goal with sufficient margin, that is, more than a factor of two (2), if operated on art eighteen (18) month fuel cycle.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2005년도 춘계 학술대회
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• pp.21-29
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• 2005

30 MW의 연구용 원자로인 하나로는 1995년 2월 초임계에 도달한 이후, 정상적으로 가동하고 있다. 가동 후 약 10년이 경과하여 1차 냉각펌프를 분해 점검하기 위해 펌프에 대한 화학제염이 2004년에 수행되었다. 제염을 수행하기 이전에 4개의 point를 설정하여 방사선량율 및 표면오염도를 측정하였고, 최종제염이 수행된 이후 같은 point에 대하여 방사선량율 및 표면오염도를 재측정 하였다. 펌프 외부는 노출되어 있어 쉽게 제염할 수 있으나 케이싱 내부에는 2중 볼류트가 있어 접근이 용이하지 않았다. 이를 제염하기 위하여 제염장치를 개발하였다. 이 장치는 일정 농도의 제염제 (DX-300)를 케이싱 내부에 담아 밀폐시킨 후 펌프의 임펠러를 저속으로 회전함으로서 제염제가 순환된다. 제염제의 유화작용에 의해 표면의 입자성 방사선 물질이 이완되고, 화학 작용에 의해 부식력과 용해성으로 표면 오염이 제거된다. 이 장치를 이용하여 하나로 1차 냉각펌프의 케이싱 내부를 제염하였다. 그 결과 1차 냉각펌프의 케이싱 내부는 반출허용표면오염도 이하로 낮출 수 있어 성공적으로 제염할 수 있었다.