• 한국조명전기설비학회:학술대회논문집
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• 한국조명전기설비학회 2009년도 추계학술대회 논문집
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• pp.137-140
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• 2009

본 논문에서는 반사판을 이용하여 LED 보안등기구의 배광을 제어하였다. 먼저, 광학 설계를 용이하게 하기 위하여 집적화된 LED 모듈의 적정 배열을 도출한 후 반사판 설계를 하였으며, 광학 성능 예측 프로그램을 이용하여 결과물의 성능을 확인하였다.

• 해양환경안전학회지
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• 제21권4호
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• pp.421-427
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• 2015

본 연구에서는 소형어선 및 예인선단의 해양사고 사례를 통해 선박의 규정된 등화 및 형상물로 오인할 수 있거나 그들의 특성 식별을 방해하는 등화 및 형상물 또는 적절한 경계(警戒)를 방해하는 등화 및 형상물의 문제점을 살펴보았다. 그리고 다음과 같이 선박의 등화 및 형상물에 관한 규칙을 규정하고 있는 국내법의 개정 필요성을 제시하고자 한다. 먼저 "총톤수 10톤 미만 소형어선의 구조 및 설비기준"은 소형어선이 "국제해상충돌예방규칙" 제26조 및 "해사안전법" 제84조에서 규정하고 있는 "어로에 종사하고 있는 선박"이 표시하여야 하는 등화 및 형상물을 비치하도록 개정하여야 한다. 둘째 소형어선의 항해등 및 레이더반사기에 관한 면제 규칙을 규정하고 있는 "어선설비기준"은 "해사안전법" 제20조의 규정을 충족하도록 개정하여야 한다. 셋째 "해사안전법" 제2조에서 규정하고 있는 "예인선열"의 정의는 "국제해상충돌예방규칙" 제24조의 규정을 충족하도록 개정하여야 한다. 또한 모든 항해사에게 해양사고 예방을 위하여 적절한 등화 및 형상물 표시의 중요성을 강조하고자 한다.

• 한국터널지하공간학회 논문집
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• 제13권5호
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• pp.385-393
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• 2011

경제성장의 달성과 직선도로의 증가에 따라 터널은 전보다 더 많이 만들어졌다. 이러한 터널들의 입구 조명은 안전하고 편안한 운전을 위해 중요하다. 대부분의 터널 조명은 인공조명으로 많은 에너지를 사용한다. 본 연구에서는 터널의 조명 개선과 에너지 절약으로 반사거울 시스템을 적용하여 평가하였다. 반사거울 시스템을 적용하면 주광을 유입하여 터널 조명 환경을 개선할 수 있으며, 본 연구는 터널 인공조명 에너지의 절약을 위한 선행연구의 일환으로 진행되었다.

• 한국안전학회지
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• 제27권6호
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• pp.14-19
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• 2012

The Helium cooled ceramic reflector(HCCR) test blanket module(TBM) has been designed and developed to participate the ITER(International Thermonuclear Experimental Reactor) test blanket program in Korea. The TBM was one of the main objectives for developing ITER for proving the tritium self-sufficiency and the heat transfers to produce the electricity with the breeding blanket concept. Among the TBM components, the first wall(FW) was the most important component in safety since it was directly faced a high level of a heat and fast neutrons from the plasma side and could protect the others components inside TBM. In this paper, the FW has been designed through the thermo-mechanical analysis considering ITER operation conditions. With the developed simple models, the stress limit analysis based on RCC-MR code which is the nuclear power plant design codes in France was evaluated for the allowable design criteria. The results showed that the designed FW model satisfied $1.5S_m$ or $3S_m$ of the allowable stress($S_m$) in RCC-MR code at the maximum stress region in the FW.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.147-159
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• 2024

Plutonium-238 has always been considered as the one of the promising radioisotopes for space nuclear power supply, which has long half-life, low radiation protection level, high power density, and stable fuel form at high temperatures. The industrial-scale production of ²³⁸Pu mainly depends on irradiating solid ²³⁷NpO₂ target in high flux reactors, however the production process faces problems such as large fission loss and high requirements for product quality control. In this paper, a conceptual design study of producing ²³⁸Pu in a multi-purpose high flux reactor was evaluated and analyzed, which includes a sensitivity analysis on ²³⁸Pu production and a further study on the irradiation scheme. It demonstrated that the target structure and its location in the reactor, as well as the operation scheme has an impact on ²³⁸Pu amount and product quality. Furthermore, the production efficiency could be improved by optimizing target material concentration, target locations in the core and reflector. This work provides technical support for irradiation production of ²³⁸Pu in high flux reactors.

• 한국항해학회지
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• 제16권3호
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• pp.19-31
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• 1992

The Navigational System is the Fundamental System of Port Transportation System and comprises 3 Subsystems, say, the Waterway System, the Shiphandling System and the Support System. The Waterway System of Navigational System is the important and fundamental System for Traffic Safety inside the Port like a Car Road System on Land. This study aims to make a Guideline for the Optimal Waterway System of Port Development and Safety. The Conclusion of this Paper are drawn : 1) The complicated Shiphandling Operations should be avoided for the period of Physical night Time for eliminating the Human Errors. 2) For the Maneuverability and all-weather Combined Piloting the Inside Turn Point Buoy and Begin the-turn Buoy should be mounted with Racon(T) and Radar Reflector for foggy and bad weathers. 3) The Seabuoy located in the Approaching Area for Pilot Station and making Landfall should be mounted with Racon(G) and Morese A Light for giving a Hint of Pilot Station to the Captain on the Bridge, and these Equipments of Racon and Light should be operated normally and effectively even in a Heavy and stormy weathers. 4) A Basic Practical Expression, 1/2 L sin D, for calculating the Extra Width of Cutoff Turn Regions was derived Originally from the Viewpoint of Turn Maneuvers and Maneuverability of the Ship.

• Nuclear Engineering and Technology
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• 제50권7호
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• pp.1037-1042
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• 2018

The present study aims to assess the excess induced reactivity in a Miniature Neutron Source Reactor (MNSR) for a Beyond Design Basis Accident (BDBA) scenario. The BDBA scenario as defined in the Safety Analysis Report (SAR) of the reactor involves sticking of the control rod and filling of the inner and outer irradiation sites with water. At the end of the MNSR core life, 10.95 cm of Beryllium is added to the top of the core as a reflector which affects some neutronic parameters such as effective delayed neutrons fraction (${\beta}_{eff}$), the reactivity worth of inner and outer irradiation sites that are filled with water and the reactivity worth of the control rod. Given those influences and changes, new neutronic calculations are required to be able to demonstrate the reactor safety. Therefore, a validated MCNPX model is used to calculate all neutronic parameters at the end of the reactor core life. The calculations show that the induced reactivity in the BDBA scenario increases at the end of core life to $7.90{\pm}0.01mk$ which is significantly higher than the induced reactivity of 6.80 mk given in the SAR of MNSR for the same scenario but at the beginning of the core's life. Also this value is 3.90 mk higher than the maximum allowable operational limit (i.e. 4.00 mk).

• 한국정보처리학회:학술대회논문집
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• 한국정보처리학회 2017년도 추계학술발표대회
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• pp.462-463
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• 2017

Although the mirror has been used for a long time primarily for personal purposes, such as adornment by reflecting feature of mirror, it can also be used to expand from its legacy function to safety and lots of unpredictable applications. However, the mirror can be used as an information or investigation base, it is subject to human beings in the private region, objects and private purpose in the public and industrial fields. This paper suggests the wide usage of mirror equipped with smart technology, considering current Korea domestic regulation by law.

• 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.

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.1002-1007
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• 2020

The purpose of the current study was to evaluate a spectrum formulation set employed to modify the neutron spectrum of D-D fusion neutrons in a IS plasma focus device using GEANT4, MCNPX2.6, and FLUKA codes. The set consists of a moderator, reflector, collimator and filters of fast neutron and gamma radiation, which placed on the path of 2.45 MeV neutron energy. The treated neutrons eliminate cancerous tissue with minimal damage to other healthy tissue in a method called neutron therapy. The system optimized for a total neutron yield of 10⁹ (n/s). The numerical results indicate that the GEANT4 code for the cubic geometry in the Beam Shaping Assembly 3 (BSA3) is the best choice for the energy of epithermal neutrons.