• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.05a
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• pp.391-392
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• 2011

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.10a
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• pp.45-46
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• 2011

2009년 4월에 신월성원전 건설현장의 차수벽이 파손되면서 해수가 유입되는 사고가 발생한적이 있다. 이때 주민의 요구에 따라 사업자와 주민이 참여하는 공동조사위원회가 구성되어 침수구조물에 대한 안전성을 공동으로 평가하였다. 최근에는 주민이 참여하는 지역공동협의회를 구성하여 방폐장 안전성을 확인하였고, 삼중수소 방사능에 대한 역학조사를 진행하고 있다. 본 논문에서는 경주 지역에 원자력현안 발생 시 지역주민이 해결과정에 참여하여 성공적으로 해결했던 사례를 살펴봄으로써, 현재 사회적 해결 과제로 떠오른 사용후핵연료 공론화 과정에서 고려해야 하는 시사점을 도출하고자 하였다.

• Transactions of the Korean hydrogen and new energy society
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• v.32 no.6
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• pp.649-655
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• 2021

The recently proposed Kalina based power and cooling cogeneration cycles (KPCCCs) have shown improvement in the energy utilization of the system compared to the basic Kalina cycle. This paper suggests a combined tri-cogeneration system for power, heating and cooling based on the Kalina cycle. And thermodynamic performances of the suggested system based on the first and second thermodynamic laws are parametrically investigated with respect to the ammonia mass fraction and the boiler pressure. Results showed that the thermodynamic performance of the system could be greatly improved compared to the former KPCCCs.

• Transactions of the Korean hydrogen and new energy society
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• v.24 no.1
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• pp.36-43
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• 2013

In this paper, a three-dimensional hydrogen desorption model is applied to a thin double-layered annulus ZrCo hydride bed and validated against the temperature evolution data measured by Kang et al. The present model reasonably captures the bed temperature evolution behavior and the 90% hydrogen discharging time. In addition, the performance of thin double-layered annulus bed is evaluated by comparing with a simple cylindrical bed using hydrogen desorption model. This study provides multi-dimensional contours such as temperature and H/M atomic ratio in the metal hydride region. This numerical study provides fundamental understanding during hydrogen desorption process and indicates that efficient design of the metal hydride bed is critical to achieve rapid hydrogen discharging performance. The present three-dimensional hydrogen desorption model is a useful tool for the optimization of bed design and operating conditions.

• Membrane Journal
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• v.34 no.2
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• pp.114-123
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• 2024

Hydrogen isotopes can be categorized into light hydrogen, heavy hydrogen, and tritium based on the number of neutrons, each of which is used in specific fields. Specifically, deuterium is of interest in the electronics industry, nuclear energy industry, analytical technology industry, pharmaceutical industry, and telecommunications industry. Conventional methods such as cold distillation, thermal cycling absorption processes, Girdler sulfide processes, and water electrolysis have their own advantages and disadvantages, leading to the need for alternative technologies with high separation and energy efficiency. In this context, membrane-based hydrogen isotope separation is one of the promising solutions to reduce energy consumption. In this review, we will present the state-of-the-art in hydrogen isotope separation using membranes and their operating principles. The technology for separating hydrogen isotopes using membranes is just beginning to be conceptualized, and many challenges remain to be overcome. However, if achieved, the economic benefits are expected to be significant. We will discuss future research directions for this purpose.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.394-394
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• 2001

• Journal of the Korean Chemical Society
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• v.45 no.4
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• pp.293-297
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• 2001

The existing vapor pressure measurements reported in the literature for parahydrogen between the triple point and the critical point have been employed to establish the constants and exponent of the following equation in the form of reduced vapor pressure and reduced temperature: ln $lnP_r=2.64-{\frac{2.75}{T_r}}+1.48129lnT_r+0.11T^5_r$Only the normal boiling point ($T_b$= 20.268K), the critical pressure ($P_c$= 1292.81 kPa), and the critical temperature ($T_c$= 32.976K) are necessary to calculate the vapor pressure for an overall average deviation of 0.21% for 153 experimental vapor pressure data.

• Journal of Radiation Protection and Research
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• v.35 no.1
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• pp.12-20
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• 2010

In a primary system at nuclear power plants (NPPs), various radionuclides including fission products and corrosion products are generated due to the complex water conditions. Particularly, $^3H,\;^{14}C,\;^{58}Co,\;^{60}Co,\;^{137}Cs,\;and^{131}I$ are important radionuclides in respect of dose assessment for radiation workers and management of radioactive effluents. In this paper, the dominant contributors of radiation exposure for radiation workers and the member of public adjacent to NPPs were reviewed and the process of dose assessment attributable to those contributors were introduced. Furthermore, the analysis for some examples of radiation exposure to radiation workers and the public during the NPP operation was carried out. This analysis included the notable precedents of internal radiation exposure and contamination of demineralized water occurred in Korean NPPs. Particularly, the potential issue about the dose assessment of tritium and carbon-14 was also reviewed in this paper.

• Journal of Radiation Protection and Research
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• v.37 no.3
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• pp.138-145
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• 2012

As of the end of 2010, 21 nuclear power reactors were operating in Korea. Radioactive effluents from nuclear power plants (NPPs) had been increased continuously and the radioactivity of effluents released in 2010 was 547.12 TBq. From 2001 to 2010, the annual average radioactivity of gaseous and liquid effluents per reactor was 11.61 TBq for pressurized water reactor (PWR) plants and 118.12 TBq for PHWR (pressurized heavy water reactor) plants. Most of the radioactivity from gaseous and liquid effluents was came from $^3H$. Based on the results of release trends and analysis, effluents characteristics was suggested for the management of radioactive effluents from NPPs.

• Proceedings of the Korean Vacuum Society Conference
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• 2010.02a
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• pp.279-279
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• 2010

한국형 헬륨 냉각 고체형 증식(Helium Cooled Solid Breeder : HCSB) 시험 블랑켓(Test Blanket Module : TBM)은 삼중수소 증식을 위해서 $Li_2TiO_3$ 및 $Li_4SiO_4$ 페블을 고려하고 있으며, 중성자 반사 재료로는 SiC가 코팅된 흑연 페블을 사용할 예정이다. $Li_2TiO_3$ 및 $Li_4SiO_4$ 페블을 제조하기 위해서는 먼저 각각의 분말 제조가 선행되어야 한다. $Li_2TiO_3$ 분말을 합성하기 위해서는 먼저 Lithium 금속염과 Isopropoxide를 용매 및 폴리머 캐리어로서의 두 가지 기능을 하는 에틸렌글리콜에 첨가한 후 가열하여 완전히 용해시킨 후 혼합 용액을 건조시켜 겔형의 전구체를 제조한다. 이를 하소한 후 결정화시켜 Titanate 분말을 얻는데 이때의 건조, 하소 및 결정화 온도의 조건에 따른 분말의 크기 및 특성이 각각 다르다. 즉 하소 온도가 $600^{\circ}C$ 미만이면 열분해된 폴리머로부터 잔유 탄소가 남게 되고, $700^{\circ}C$를 초과하면 결정화가 시작된다. 이렇게 얻어진 Titanate분말은 지르코니아 볼을 이용하여 약 24 시간 동안 볼 밀링 과정을 통해 입도분포가 좁은 미세한 Titanate 분말로 만들었다. $Li_2TiO_3$ 페블은 위의 과정에서 얻어진 미세분말에 바인더를 이용하여 페블화 시킨 후 $1200^{\circ}C$의 전기로에서 최종 소결한 것이다. 중성자 반사 재료인 흑연페블은 강도가 약하기 때문에 표면에 SiC를 수 ${\mu}m$ 코팅해서 사용할 예정이다. 선행실험으로 건식법을 이용하여 SiC 코팅을 실시했으며, 그 결과를 소개할 것이다.