• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1603-1610
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• 2020

Due to ever-growing advancements in computers and relatively easy access to them, many efforts have been made to develop high-fidelity, high-performance, multi-physics tools, which play a crucial role in the design and operation of nuclear reactors. For this purpose in this study, the neutronic Monte Carlo and thermal-hydraulic sub-channel codes entitled MCNP and COBRA-EN, respectively, were applied for external coupling with each other. The coupled code was validated by code-to-code comparison with the internal couplings between MCNP5 and SUBCHANFLOW as well as MCNP6 and CTF. The simulation results of all code systems were in good agreement with each other. Then, as the second problem, the core of the VVER-1000 v446 reactor was simulated by the MCNP4C/COBRA-EN coupled code to measure the capability of the developed code to calculate the neutronic and thermohydraulic parameters of real and industrial cases. The simulation results of VVER-1000 core were compared with FSAR and another numerical solution of this benchmark. The obtained results showed that the ability of the MCNP4C/COBRA-EN code for estimating the neutronic and thermohydraulic parameters was very satisfactory.

• Nuclear Engineering and Technology
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• 제56권5호
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• pp.1574-1583
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• 2024

Small Modular Reactors (SMRs) are compact nuclear reactors designed to generate electric power up to 300 MWe. They could be assembled in factory, and then transported to be directly installed on-stie. CAREM (Central Argentina de Elementos Modulares) is a national SMR development project, based on light water reactor technology supervised by Argentina's National Atomic Energy Commission (CNEA). It is a natural circulation-based SMR with an indirect-cycle, including specific items and parts that simplify the design and improve safety performance. In this paper, the thermal-hydraulic study of CAREM-25 advanced small modular reactor is conducted by using COBRA-EN modified code and the Porous Media Approach (PMA) for the first time. According to PMA approach, each fuel assembly is modeled and divided into a network of lumped regions. While complex geometries are defined, the thermal-hydraulic parameters such as temperature and density are calculated for coolant and fuel rods. The obtained results show that the temperature in the fuel center may reach a peak around 1280 K in the hottest fuel assembly. Finally, the comparison of results from both methods (modified COBRA-EN and PMA) presented an appropriate consistency.

• Nuclear Engineering and Technology
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• 제31권3호
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• pp.314-327
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• 1999

A subchannel analysis code MATRA applicable to PWRs and ALWRs has been developed to be run on an IBM PC or HP WS based on the existing CDC CYBER mainframe version of COBRA-Rf-1. This MATRA code is a thermal-hydraulic analysis code based on the subchannel approach for calculating the enthalpy and How distribution in fuel assemblies and reactor cores for both steady-state and transient conditions. HATRA has been provided with an improved structure, various functions, and models to give more convenient user environment and to enhance the code accuracy. Among them, the pressure drop model has been improved to be applied to non-square-lattice rod arrays, and the models for the lateral transport between adjacent subchannels have been improved to enhance the accuracy in predicting two-phase flow phenomena. The predictions of MATRA were compared with the experimental data on the flow and enthalpy distribution in some sample rod-bundle cases to evaluate the performance of MATRA. All the results revealed that the predictions of MATRA were better than those of COBRA-IV-I.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 추계학술발표회논문집(1)
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• pp.579-584
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• 1997

HP Workstation 및 IBM PC에서 사용 가능한 부수로 해석 코드 MATRA $\alpha$-버전을 개발하였다. 이 코드는 정확도 향상 및 사용자 편리를 위해 COBRA-IV-I코드에 비해 여러가지 기능들이 추가되었으며, 코드의 적용 범위를 신형원자로의 비정방형 집합체 노심에 확장할 수 있도록 압력손실 모형 등이 개선되었다. 또한 이상 유동장에서의 예측 정확도 향상을 위하여 부수로 잔의 횡방향 전달 모형을 개선하였다. 코드의 예측 성능을 평가하기 위해 세 중류의 집합체 유동분포 및 엔탈피 분포 실험 자료와 비교하였으며, 그 결과 기존의 COBRA-IV-I코드보다 향상된 결과를 보였다.

• Nuclear Engineering and Technology
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• 제15권4호
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• pp.236-247
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• 1983

한국원자력 1호기(KNU-1)의 설계 및 운전자료를 이용하여 가압경수로 운전변수들의 변화에 대한 DNBR의 민감도를 분석하였다. 본 민감도 분석에는 원자로 출력, 압력, 냉각수 주입유량, 냉각수 주입온도, 반경방향 및 축방향 출력분포 그리고 축방향 출력편차 등의 운전변수가 고려되었다. 민감도 분석을 위하여는 노심의 열수력 해석용 전산코드인 COBRA-IV-K를 사용하였는데 본 코드는 COBRA-IV-i의 수정판으로써 한국에너지연구소에서 일부 프로그램을 수정하였고 또한 신뢰도도 확인하였다. 민감도 분석을 수행하기 전에 KNU-1 원자로심의 설계 및 운전조건을 근거로 하여 기초 계산을 수행하고 이 결과를 본 민감도 분석의 기본자료로 삼았다. 민감도 분석결과 원자로의 DNBR 열설계에 있어서 가장 민감한 운전변수는 냉각수 주입온도이고 가장 둔감한 변수는 축방향 출력분포라는 것이 밝혀졌다.

• Nuclear Engineering and Technology
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• 제31권3호
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• pp.344-363
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• 1999

A multi-dimensional thermal-hydraulic system analysis code, MARS 1.3.1, has been developed in order to have the realistic analysis capability of two-phase thermal-hydraulic transients for pressurized water reactor (PWR) plants. As the backbones for the MARS code, the RELAP5/MOD3.2.1.2 and COBRA-TF codes were adopted in order to take advantages of the very general, versatile features of RELAP5 and the realistic three-dimensional hydrodynamic module of COBRA-TF. In the MARS code, all the functional modules of the two codes were unified into a single code first. Then, the source codes were converted into the standard Fortran 90, and then they were restructured using a modular data structure based on "derived type variables" and a new "dynamic memory allocation" scheme. In addition, the Windows features were implemented to improve user friendliness. This paper presents the developmental work of the MARS version 1.3.1 including the hydrodynamic model unification, the heat structure coupling, the code restructuring and modernization, and their verifications.their verifications.

• 대한임상독성학회지
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• 제20권1호
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• pp.22-24
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• 2022

Elapid snakes have neurotoxic venom which causes diverse neuroparalytic manifestations, including fatal respiratory failure. In South Korea, since elapid snakebites are very rare, the cobra antivenom, which is effective against neurotoxicity, was only introduced recently. Most physicians in South Korea have little experience in the treatment of patients who have been bitten by elapid snakes. A 19-year-old man was brought to the emergency department with sudden diplopia, 1 hour after a snakebite on the left 2nd finger. The patient presented with drowsiness and complained of mild dizziness and binocular diplopia. After 1 hour, he had sudden onset of dyspnea and dysphagia and appeared to be agitated. He was immediately intubated and received mechanical ventilation as he was unable to breathe on his own. A total of 2.5 mg of neostigmine diluted with normal saline was slowly infused, and 1 vial of cobra antivenom was infused for an hour, 5 times every 2 hours, for a total of 5 vials. He slowly recovered self-breathing; on the 3rd day of hospitalization, he showed tolerable breathing and was extubated. He was discharged without any neurological deficits or other complications.

• 한국수자원학회논문집
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• 제52권4호
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• pp.301-312
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• 2019

기후 변화로 인한 국지성 호우의 증가로 도시의 내수침수피해가 증가함에 따라 이중배수체계 모형의 중요성이 증가하였다. 이중배수체계 모형은 지표면의 흐름과 관거의 흐름의 현상을 보다 정확히 표현하기 위하여 표면유출과 관거 유출을 각각의 관련 방정식과 매개변수들을 통해 해석하며, 이를 시각별로 연동하여 동시에 시뮬레이션하는 모형으로 이중배수체계 모형의 침수해석 결과는 도시계획 및 침수예방을 위한 계획 수립시 중요한 자료로 사용되고 있다. 본 연구에서는 자연유역과 도시유역이 혼재되어 있는 복합유역에 이중배수체계를 접목하여 해석이 가능한 COBRA 모형을 실제 유역에 적용하여 그 적용성을 파악해 보고 다른 이중배수체계 모형인 XP-SWMM, UFAM과 비교하여 결과의 적합성을 판단해 보았다. 동일한 대상유역에 대해 3가지 형태의 이중배수체계 모형의 침수해석 결과 및 침수양상을 분석한 결과를 종합해볼 때 우수관망의 용량 부족으로 발생하는 내수침수 특징은 XP-SWMM이 비교적 잘 모의하는 것으로 보였으며, UFAM은 도로의 빗물받이를 고려하는 특징에 따라 타 모형에 비해 가장 낮은 침수해석 결과를 나타내었다. 마지막으로 COBRA는 침수면적과 침수면적의 비율, 최대침수심이 강우량 증가에 비례하는 일반적인 결과와 토양조건에 따라 유효우량을 세밀하게 분류하여 모의하는 모형 특성 및 지표 저류에 의한 침수양상이 나타나는 현실성을 고려할 때 모형의 안정성 측면에서 양호하다고 판단되었다.

• 한국통신학회:학술대회논문집
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• 한국통신학회 1998년도 추계종합학술발표회 논문집(상)
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• pp.361-364
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• 1998

• 대한약침학회지
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• 제6권2호
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• pp.165-177
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• 2003

The study was carried out to investigate the researches of Snake which was published papers in the TOXlCON(1990-2000), one of the most famous Journal of toxicology. And the results were as follows : 1. The number related with Snake is 195papers. 2. There were great papers related wih Cobra, and next is Tigris, Viper, etc. 3. There were great papers related wih protein in the composition of snake venom. 4. There were great papers related wih neurotoxin in the research of poisonous character. 5. There were great papers related wih Viper according to the anticoagulation. 6 Eight papers were published to study the immune response of snake venom. 7. The papers of molecular study of snake venom were seven. 8. The papers of anti-snake venom study were three.