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홍진태,손광재,김종범,박종한,김진주,양태호 한국항공우주학회 2015 한국항공우주학회 학술발표회 논문집 Vol.2015 No.11
미국, 러시아 등 우주기술 선진국에서는 달탐사 착륙선 또는 로버의 달탐사 작업을 위한 전원을 공급하기 위하여 수명이 길고, 신뢰성 높은 원자력전지를 이용하여 왔다. 원자력전지는 방사성동위원소의 붕괴열을 전력으로 변환하여 전기를 생산하므로 방사선 차폐, 열전 효율을 높이기 위한 열전재료 설계 및 단열성능 확보를 위한 열제어 구조체 설계, 사고상황에서의 구조 안전성을 위한 내충격 설계 등 다양한 분야에 대한 연구가 필요하다. 한국 정부는 2020 년 탐사선을 달에 보내기로 계획하고 있으며, 착륙선이나 로버의 전력원으로서 원자력전지의 공급이 필요한 상황이다. 본 연구에서는 한국형 달탐사선을 위한 원자력전지의 구성 및 설계현황에 대해 정리하였다. Nuclear batteries have been applied to supply electric source to lunar explorers and rovers for exploration of the lunar surface owing to their long lifetime and high reliability. Because a nuclear battery generates electricity by converting decay heat of radioisotopes into electric energy, many related researches such as radiation shield, conversion efficiency of thermoelectric material, heat insulation, and shock endurance of the structure for the accident status have been carried out. Korean government plans to send lunar explorer in 2020, and a nuclear battery should be supplied as a power source for lunar lander or rover. In this study, constitution of nuclear battery and current status of RTG design for lunar mission will be introduced.
Study on the Measurement Accuracy of Coolant Flowrate in a Nuclear Fuel Test Rig
홍진태,김종범,정창영,안성호,양태호,허성호 한국정밀공학회 2016 International Journal of Precision Engineering and Vol.17 No.10
To measure the heat generation rate of nuclear fuel rods during an irradiation test, the temperature deviation of the coolant that passes by the fuel rod and its flow velocity need to be measured. Although the temperature of the coolant can be measured by thermocouples instrumented in the nuclear fuel test rig, the flowrate of the coolant is difficult to measure owing to the narrow space of the test rig. Therefore, a noise analysis technique using fluctuation signals from thermocouples installed at both end parts of the fuel rod has been developed by several advanced groups. Although the noise analysis technique was also developed at the Korea Atomic Energy Research Institute, out of pile test results showed that the accuracy of the coolant flow measurement was more than 40%. In this study, the ground pattern of the control board and earth connection are enhanced to eliminate external noise. In addition, a heater unit is installed in the coolant flow simulator to obtain a strong fluctuation signal from the coolant. Thus, the coolant flow simulator is improved, and the accuracy of the coolant flow measurement shows an error of less than 5%.
Measurement of Coolant Flow in a Nuclear Fuel Test Rig
홍진태,김종범,Chang-Young Joung,안성호,허성호 한국정밀공학회 2015 International Journal of Precision Engineering and Vol.16 No.9
The heat generation rate is one of the most important characteristics in evaluating the performance of nuclear fuel. The heat generation rate of a nuclear fuel rod can be measured indirectly by calculating the heat flux that coolant absorbs while passing by the nuclear fuel rod. To calculate the heat flux from the fuel rod, it is necessary to measure the temperature deviation and flow velocity at both end parts of the fuel rod. Thus, measuring the flow velocity in the test rig during the irradiation test of nuclear fuel is important to measure the heat generation rate. In this study, a cross correlation technique that uses signals obtained from two thermocouples instrumented at both end parts of the fuel rod has been developed to measure the flow velocity of coolant in the test rig.