• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.789-794
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• 1998

중대사고 해석 전산 코드 국산화의 필요성이 대두되고 있는 이때 우리가 개발해야 할 코드의 요건을 다음 여섯 가지로 정리하였다: 1) 종합적인 해석 코드. 2) 1차계통과 격납건물 모사 능력의 유연성, 3) 자세한 발전소 거동 모사, 4) 사용자 편의성, 5) 개선 및 새로운 모델 접목의 용이성. 그리소 6) 최신 모델 포함. 이런 관점에서 기존의 중대사고 해석코드를 분석한 결과 코드 개발의 기준 코드로 MELCOR를 선정하였다. MELCOR는 계통 모사의 유연성 때문에 상용 발전소 뿐만 아니라 앞으로 개발 계획 중인 차세대나 중소형 원자로까지도 확장이 가능하며, 상세한 열수력 기본 지배 방정식을 활용하고. 모델 분석 및 개선에 필요한 코드에의 자유로운 접근이 허용되며, 지속적인 코드 개선이 이루어져 최신 모델을 보유하고 있다. 이미 MELCOR는 상당한 수준의 결과를 예측하고 있기만. 노심 손상 모델을 개선하고 격납건물 안에서의 주요 현상 모사 모델을 추가하며. 또한 국내에서 이루어지고 있는 SONATA 실험이나 증기 폭발 실험 결과들을 MELCOR에 반영하는 것이 가급적 짧은 시간에 기술 자립을 이를 수 있는 방법으로 판단된다.

• Nuclear Engineering and Technology
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• v.20 no.4
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• pp.241-245
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• 1988

It is very important to investigate the behaviors of the material parameters governing PCI fuel failure during power ramp because PCI fuel failure is considered to be related to the operations limits of power reactors. In this study, the behavior characteristics of the material parameters such as hoop stress, hoop strain, ridge height, creep strain rate and strain energy in cladding were studied as a function of the operating parameters such as power shock and ramp rate. The FEMAXI-IV fuel rod performance analysis code was used for this study.

• Proceedings of the KIEE Conference
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• 1998.07a
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• pp.46-48
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• 1998

This paper introduces the design method of a variable reluctace liner pulse motor to be analysed by a 3-dimensional problem in the 2-dimension. And it shows the thrust force density with respect to the ratio of the slot width to the teeth width, the height of mover and the height of tooth.

• The Transactions of the Korean Institute of Electrical Engineers B
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• v.49 no.5
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• pp.320-326
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• 2000

The canned motor of 3-phase induction is used for main coolant pump(MCP). The type of motor is canned-motor that stator and rotor are welded by sealed can. So, cooling water flows in the air gap of the canned motor as an independent cycling cooling system from the air gap to yoke of the motor to prevent high temperature of stator can and to lubricate bearing. Heat exchange is occurred between cooling water in the air gap and cooling water from the exterior pump to prevent rising of temperature in the motor. I has to analyze the characteristics of can exactly because the loss and the heat in the can are very important to design MCP. Therefore, thermal analysis is studied considering the effect of eddy-current los induced in the can.

• Proceedings of the KIEE Conference
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• 2006.07c
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• pp.1574-1575
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• 2006

보통의 AC PDP에서는 Ne, Xe 혼합가스를 사용한다. Xe %가 높아짐에 따라 PDP의 효율은 올라가지만 그와 함께 최초의 방전을 일으키는 방전 개시 전압 또한 올라간다. 이러한 이유로 실제 PDP에서 무한정 Xe %를 올릴 수는 없다. 그래서 우리는 Xe gas보다 원자번호가 낮은 불활성기체인 Kr gas를 첨가시킴으로써 동일한 효율에서 방전개시전압이 낮은 최적의 3원 가스 조성비를 찾아보았다.

• Journal of the Korean Society of Safety
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• v.36 no.2
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• pp.101-110
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• 2021

This paper presents the results of an initiating event analysis as part of a Level 1 probabilistic safety assessment (PSA) for at-power internal events for the Korea Research Reactor (KRR). The PSA methodology is widely used to quantitatively assess the safety of research reactors (RRs) in the domestic nuclear industry. Initiating event frequencies are required to conduct a PSA, and they considerably affect the PSA results. Because there is no domestic database for domestic trip events, the safety of RRs is usually assessed using foreign databases. In this paper, operating experience data from the KRR for trip events were collected and analyzed in order to determine the frequency of specific initiating events. These frequencies were calculated using two approaches according to the event characteristics and data availability: (1) based on KRR operating experience or (2) using generic data.

• Journal of Radiation Protection and Research
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• v.39 no.2
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• pp.109-117
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• 2014

Nuclear emergency planning is to plan sheltering, evacuation and iodine prophylaxis for the residents living in the area where the emergency plan is needed, the area is confirmed based on the dose assessment using the source-term through an accident analysis and the data measured from meteorological tower. In this study, the does change before and after protective measures was assessed stochastically based on the one year meteorological data in the condition of the maximum hypothetical accident which can be considered at the research reactor 'HANARO', and the optimized protective measures were derived based on the reference levels defined as a residual dose by ICRP 2007 recommendation which can be applied in a emergency exposure situation. The optimized protective measures for the HANARO in the maximum hypothetical accident were the evacuation to radius 300 m, the sheltering from 300 m to 800 m, the iodine prophylaxis only for the emergency workers under the protective measures for non emergency workers.

• Journal of radiological science and technology
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• v.40 no.3
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• pp.501-508
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• 2017

The purpose of present research is to offer a specialized educational opportunity for potential users, university students in radiology, by developing specific curriculum on site at KAERI, using HANARO research reactor and National radiation research facilities. The specific items of this research accomplished are: First, Development and operation of various curricula for specific research using HANARO and National radiation research facilities to provide university students with opportunities to use the facilities. Second, Operation of the experiment training programs for university students in radiology to foster next generation specialists. Third, through the on-site experiment training for students in radiology, support future potential experts of the radiation research fields, and broaden the base. A textbook and a teaching aid, a questionnaire have been developed to support the program. 714 university students have completed the courses for radiology experiment from 2006 to 2017. It is hoped that these experiments broaden public awareness and acceptance by the present and potential future utilization of the research reactor and national radiation research facilities, thereby bring positive impacts to policy making.

• Nuclear Engineering and Technology
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• v.22 no.4
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• pp.337-350
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• 1990

A post-irradiation annealing study was conducted with use of reactor pressure vessel(RPV) steel A533B Cl.1 base metal irradiated to a dose of 4.84$\times$10$^{18}$ n/$\textrm{cm}^2$ at about 38$0^{\circ}C$. Microhardness and positron annihilation (PA) methods were used to obtain better understanding of the recovery of radiation hardening. Isochronal anneal experiments indicated that two recovery processes occur during annealing of irradiated specimens. The first recovery process occurs in the temperature range of 280-3O5$^{\circ}C$, Michrohardness and positron annihilation (PA) methods were used to obtain better understanding of the recovery of radiation hardening. Isochronal anneal experiments indicated that two recovery processes occur during annealing of irradiated specimens. The first recovery process occurrs in the temperature range of 280-305$^{\circ}C$. The variations of Ip, Iw and R parameters indicated that the formation of vacancy clusters by vacancy agglomeration and the annihilation of monovacancies are the first recovery process. The second recovery process occurs in the range of 405-49$0^{\circ}C$ and positron annihilation parameters measured indicated that the dissolution of carbon atoms decorated around vacancy-type defects and possible precipitates, and the annihilation of monovacancies give rise to the second recovery process. It was further indicated that radiation anneal hardening (RAH) in the range of 305-405$^{\circ}C$ between the temperature ranges for the two processes occurs due to the formation of carbon-decorated vacancy clusters and precipitates. The activation energies, orders of reaction and other characteristics of recovery processes were determined by the Meechan-Brinkman method. The activation energy for the first recovery process was determined as 1.76 eV and that for the second recovery process as 2.00eV. These values are lower than those obtained by other workers. This difference may be attributed to the lower copper content of the RPV steel used in the present study. The order of reaction for the first recovery process was determined as 1.78, while that for the second recovery process as 1.67 Non-integer orders of reaction for recovery processes seem to be attributed to the fact that several mechanisms for the first order and the second order of reaction are compounded in one process. This result also supports for the above conclusions from measurements of PA parameters.

• Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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• 2006.11a
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• pp.201-201
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• 2006

영구자석은 크게 Hard ferrite와 희토류계 자석, 그리고 Alnico 주조자석으로 구별되어진다. 그동안 Hard ferrite는 산업적으로 전자기 응용제품 또는 각종 구동 모터에 응용되어 왔지만, 최근 Nd계 희토류 자것이 고성능 모터의 소재로 급격히 대체되고 있다. 하지만, 희토류계 원료에 비해 동일 중량 대비 40~60배 가량 저렴한 Hard ferrite의 사용은 현재까지도 꾸준히 유지되고 있으며, 최근 자동차 고성능 모터용 Sr ferrite의 개발이 연구 중이다.[2] 본 연구에서는 제일원리 전산모사를 통하여 HCP 구조의 기본 Unit Cell 64개 원자를 가진 Sr-ferrite의 격자상수를 계산하여 기존 연구결과와 비교하였으며, 자화에너지와 자기모멘트를 계산하였다. 또한 향후 각종 첨가물의 영향에 대한 연구를 위해 기본 구조 및 치환 구조에 대해 고찰하였다. 그 결과 가장 안정한 에너지를 갖는 격자상수는 a=5.88, b=23.03으로 계산되어 Kimura et al의 측정 결과와 유사한 결과를 얻을 수 있었으며, $E_F$가 3.9171, $M_B$는 46.6481로 계산되었다. 항후 Sr-ferrite의 구조에서 Fe atom의 일부를 동일주기 원소인 Cr, Mn, Co, Ni, Cu로 치환하여 자기적 특성을 계산하여 본 연구결과와 비교하고자 한다.