• 방사성폐기물학회지
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• 제21권4호
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• pp.571-576
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• 2023

The initial development plans for the six reactor designs, soon after the release of Generation IV International Forum (GIF) TRM in 2002, were characterized by high ambition [1]. Specifically, the sodium-cooled fast reactor (SFR) and very-high temperature reactor (VHTR) gained significant attention and were expected to reach the validation stage by the 2020s, with commercial viability projected for the 2030s. However, these projections have been unrealized because of various factors. The development of reactor designs by the GIF was supposed to be influenced by events such as the 2008 global financial crisis, 2011 Fukushima accident [2, 3], discovery of extensive shale oil reserves in the United States, and overly ambitious technological targets. Consequently, the momentum for VHTR development reduced significantly. In this context, the aims of this study were to compare and analyze the development progress of the six Gen IV reactor designs over the past 20 years, based on the GIF roadmaps published in 2002 and 2014. The primary focus was to examine the prospects for the reactor designs in relation to spent nuclear fuel burning in conjunction with small modular reactor (SMR), including molten salt reactor (MSR), which is expected to have spent nuclear fuel management potential.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.817-825
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• 2022

A recent benchmarking effort, under the auspices of the Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA), has been made to evaluate the current state of modeling and simulation tools available to model fluoride salt-cooled high temperature reactors (FHRs). The FHR benchmarking effort considered in this work consists of several cases evaluating the neutronic parameters of a 2D prismatic FHR fuel assembly model using the participants' choice of simulation tools. Benchmark participants blindly submitted results for comparison with overall good agreement, except for some which significantly differed on cases utilizing a molybdenum-bearing control rod. Participants utilizing more recently updated explicit isotopic cross sections had consistent results, whereas those using elemental molybdenum cross sections observed reactivity differences on the order of thousands of pcm relative to their peers. Through a series of supporting tests, the authors attribute the differences as being nuclear data driven from using older legacy elemental molybdenum cross sections. Quantitative analysis is conducted on the control rod to identify spectral, reaction rate, and cross section phenomena responsible for the observed differences. Results confirm the observed differences are attributable to the use of elemental cross sections which overestimate the reaction rates in strong resonance channels.

• 한국수소및신에너지학회논문집
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• 제23권6호
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• pp.573-580
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• 2012

Corrosion resistance and basic physical properties of solid tantalum are not comparable to most of the structural metallic materials. The relative high cost and melting temperature of tantalum are obstacles to be widely applied to general engineering processes. Electrodeposition in molten salt enables compact and uniform tantalum coating. In this study, Ta was coated onto base metal (SUS316L) with different current densities (0.5, 5, $20mA/cm^2$) by using MSE (Molten Salt Electrodeposition). In this study, it showed that deposition efficiency and microstructure of Ta coating layer were strongly depended on current density. In the case of the current density of $5mA/cm^2$, densest microstructure was obtained. The current density above $5mA/cm^2$ caused non-uniform microstructure due to rapid deposition rate. Dense microstructure and intact coating layer contributed to significant corrosion resistance enhancement.

• 한국재료학회지
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• 제10권7호
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• pp.471-477
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• 2000

Fe-Ni-Cr 합금의 용융염 부식거동을 $650~850^{\circ}C$ 온도범위에서 조사하였다. 용융염 LiCl에서 Cr을 포함하지 않는 KSA(Kaeri Superalloy)-1 합금은 Fe의 내부산화가 발생하고, Cr을 포함한 KSA-4, Incoloy 800H와 KSA-5는 LiCrO$_2$의 치밀한 보호막이 형성되었다. 혼합용융염 $LiCl-LiO_2$O에서 KSA-1은 Fe의 내부산화, KSA-4는 Cr의 내부산화가 발생하였고, Cr 농도가 높은 Incoloy 800H와 KSA-5는 $LiCrO_2$의 다공성 피 이 형성되었다. 혼합용융염 $LiCl-Li_2$O 에서는 Cr 농도의 증가에 따라 부식속도가 증가하였으며, 부식속도는 시간의존선을 8%Cr 이하의 합금에서는 포물선법칙, 8%Cr 이상의 합금에서는 직선법칙을 나타내었다. 이러한 현상은 Li$_2$O에 의한 보호성 산화물 $Cr_2O_3$의 염기성 용해기구로 설명할 수 있다.

• 방사성폐기물학회지
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• 제10권2호
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• pp.97-104
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• 2012

본 연구에서는 $850^{\circ}C$의 $CaCl_2$ 용융염계에서 전해환원공정을 통해 $TiO_2$로부터 금속티타늄을 제조하였다. Ni-$TiO_2$ 조합전극을 환원전극으로 그라파이트를 산화전극으로 사용하였으며, 셀전위를 제어하면서 $TiO_2$의 전해환원 특성을 관찰하였다. XRD 분석을 통해 $TiO_2$가 $CaTiO_3$, $Ti_2O$, $Ti_6O$와 같은 다양한 반응 중간생성물을 거쳐 Ti 스폰지로 환원되는 것이 밝혀졌다. 또한 SEM 분석을 통해 $TiO_2$ 전해환원 반응동안 펠렛의 바깥표면부터 환원반응이 시작되어 펠렛중심으로 진행이 되는 것이 확인되었다. 전해환원 반응도중 환원된 티타늄금속은 초기에는 다공성 스폰지 구조를 보이나 고온에서 반응이 진행됨에 따라 점차 소결에 의해 수축되어 다공성 구조가 사라지는 현상을 보였다.

• 한국신재생에너지학회:학술대회논문집
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• 한국신재생에너지학회 2007년도 춘계학술대회
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• pp.668-671
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• 2007

A numerical study was conducted on a simplified model of a high-temperature solar receiver which incorporates liquid-metal heat pipe. The objective of this paper is to compare the isothermal characteristics of the heat pipe receiver with the conventional receiver utilizing convection of molten salt as heat carrier. The solar receiver was assumed to be subject to a concentration ratio between 50 and 1,000 to supply high-temperature heat to a stirling engine for electric power generation. For simplicity of the analysis, a cylindrical geometry was assumed and typical dimensions were used based on available literature. The heat pipe had a shape of double-walled cavity and the working fluid was a sodium. The analysis was performed assuming that the radiation heat flux on the inner walls of the receiver was uniform, since the focus of this study was laid on the comparison of the conventional type and heat pipe type receiver. The results showed that the heat pipe type exhibited superior performance when the operating temperature becomes higher. In addition, to explore the advantage of the heat pipe receiver, the channel shape and dimensions should be adjusted to increase the heat transfer area between the wall and the heat trnasfer medium.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2008년도 추계학술대회B
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• pp.2100-2105
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• 2008

A numerical analysis was conducted to predict the heat transfer characteristics of a high-temperature, high heat flux solar receiver as the end-wall angle varied. The concentration ratio of the solar receiver ranges from 200 to 1000 and the concentrated heat is required to be transported to a certain distance for specific applications. This study deals with a solar receiver incorporating high-temperature sodium heat pipe as well as a typical one that employs a molten-salt circulation loop with the same outer dimensions. The isothermal characteristics in the receiver section is of major concern. The diameter of the solar thermal receiver was 120 mm and the length was 400 mm. FLUENT, a commercial software, was employed to deal with the radiative heat transfer inside the receiver cavity and the convection heat transfer along the channels and heat pipes. The numerical results were compared and analyzed from the view point of heat transfer characteristics the solar receiver system.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.3879-3891
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• 2021

A heat pipe residual heat removal system is proposed to be incorporated into the reactor driven subcritical (RDS) facility, which has been proposed by MIT Nuclear Reactor Laboratory for testing and demonstrating the Fluoride-salt-cooled High-temperature Reactor (FHR). It aims to reduce the risk of the system operation after the shutdown of the facility. One of the main components of the system is an air-cooled heat pipe heat exchanger. The alkali-metal high-temperature heat pipe was designed to meet the operation temperature and residual heat removal requirement of the facility. The heat pipe model developed in the previous work was adopted to simulate the designed heat pipe and assess the heat transport capability. 3D numerical simulation of the subcritical facility active zone was performed by the commercial CFD software STAR CCM + to investigate the operation characteristics of this proposed system. The thermal resistance network of the heat pipe was built and incorporated into the CFD model. The nominal condition, partial loss of air flow accident and partial heat pipe failure accident were simulated and analyzed. The results show that the residual heat removal system can provide sufficient cooling of the subcritical facility with a remarkable safety margin. The heat pipe can work under the recommended operation temperature range and the heat flux is below all thermal limits. The facility peak temperature is also lower than the safety limits.

• 방사성폐기물학회지
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• 제8권1호
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• pp.33-39
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• 2010

산화물 사용 후 핵연료를 처리하는 전해환원공정에서는 LiCl 용융염계에서 산소가 생성되는 반응을 수반하게 되며, 생성된 산소로 인해 반응기의 구조재료를 상당히 부식시킬 수 있는, 화학적으로 심각한 반응환경을 조성한다. 따라서, 고온 용융염을 다루는 전해환원 공정장치를 위해서는 최적의 재료를 선택하는 것이 필수적이다. 본 연구에 서는 리튬용융염, $675^{\circ}C$, 216시간동안 산화분위기에서 코팅이 안 된 초합금과 코팅된 초합금 시편의 고온 부식연구를 수행하였다. IN713LC 초합금 시편에 aluminized NiCrAlY bond 코팅 후 $Y_2O_3$ top 코팅을 하였다. 코팅이 안 된 초합금은 부식층의 빠른 성장응력과 열적응력에 의한 부식층의 박리로 명확한 무게손실을 보인다. 탑 코팅의 화학적 및 열적 안정성으로 인해 고온 리튬용융염을 다루는 구조재료의 부식 저항성이 증가함을 확인할 수 있었다.

• 센서학회지
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• 제5권3호
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• pp.93-100
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• 1996

높은 큐리온도를 가진 다결정 세라믹스 $Sr_{2}(Ta_{1-x}Nbx)_{2}O_{7}$ 및 $La_{2}Ti_{2}O_{7}$을 고상반응법과 용융염합성법으로 제조하고 조성과 하소 및 소결조건에 따른 분말특성, 상구조, 소결특성, 입자배향도 및 전기적 특성을 조사하였다. 용융염합성법에 의해 합성된 하소분말의 단일상은 고상반응법에 의한 것보다 100 - $150^{\circ}C$ 낮은 하소온도에서 나타났다. 한편 $Sr_{2}(Ta_{1-x}Nbx)_{2}O_{7}$ 소결체에서 Nb의 조성이 커질수록 입자배향도가 커지고 소결성 및 고온에서의 유전특성이 좋아졌다. 또 용융염합성법으로 $A_{2}B_{2}O_{7}$ 세라믹스를 제조할 경우 고상반응법에 비해 소결온도를 낮출 수 있고 비유전율도 다소 높일 수 있으나 압전특성이나 입자배향도는 향상되지 않았다.