This study investigated the effectiveness of various chlorinating agents in partitioning light water reactor spent fuel, with the aim of optimizing the chlorination process. Through thermodynamic equilibrium calculations, the effects of using MgCl2, NH4Cl, and Cl2 as a single chlorinating agent or applying MgCl2, NH4Cl, and Cl2 sequentially for spent fuel chlorination were evaluated Furthermore, in this study, assuming the actual process operation situation, where only a part of the semi-volatile nuclides is removed during the heat treatment process, and including the process of precipitating the molten salt from the chlorination process with K3PO4 and K2CO3 precipitants, the percentage distribution of 50 nuclides in the light water reactor spent fuel into each process stream was quantitatively calculated using the simulation function of the HSC program and tabulated for intuitive viewing. Compared to a single chlorinator, sequential chlorination more effectively separated the heat and radioactivity of the spent fuel from the uranium-dominated product solids. Specifically, the sequential application of the chlorinating agents following heat treatment led to a final solid separation characterized by 93.1% mass retention, 5.1% radioactivity, and 15.4% decay heat, relative to the original spent fuel. The findings underscore that sequential chlorination can be an effective method for spent fuel partitioning, either as a standalone approach or in combination with other partitioning processes such as pyroprocessing.

In pyroprocessing, the residual salts (LiCl containing Li and Li2O) in the metallic fuel produced by the oxide reduction (OR) process are removed by salt distillation and fed into electrorefining. This study undertook an investigation into the potential viability of employing a separate LiCl salt rinsing process as an innovative alternative to conventional salt distillation techniques. The primary objective of this novel approach was to mitigate the presence of Li and Li2O within the residual OR salt of metallic fuel, subsequently facilitating its suitability for electrorefining processes. The process of rinsing the metallic fuel involved immersing it in a LiCl salt environment at a temperature of 650°C. During this immersion process, the residual OR salt contained within the fuel underwent dissolution, thereby reducing the concentrations of Li2O and Li generated during the OR process. Furthermore, the Li and Li2O dissolved within the LiCl salt were effectively consumed through chemical reactions with ZrO2 particles present within the salt. Importantly, even after the metallic fuel had been subjected to rinsing in a conventional LiCl salt solution, the concentration of Li and Li2O within the salt remained consistent with its initial levels, due to the utilization of ZrO2. Moreover, it was observed that the Li- Li2O content within the metallic fuel was significantly diluted as a result of the rinsing process.

In case of damaged spent fuels, it would require additional treatment for their transportation and storage to capture the radioactive fission products in a defined space. The canning container for the damaged spent fuels is one way to seal the radioactive fission products inside the container. In the Post Irradiation Examination Facility (PIEF) of KAERI, the Quiver container has been introduced for canning damaged spent fuels from Westinghouse Sweden. The main container body has been manufactured for particle-tightness of spent fuel. In addition, drying equipment is being prepared for gas-tightness of spent fuel. The drying equipment can remove water and fill the inert gas inside the container. Before drying inside the container, we evaluated the volatile fission products inventory because volatile fission products could be released during the drying process. Despite assuming highly conservative hypotheses for the inventory remaining in damaged fuel rods, the amount that could be released during the drying process was less and dose rate levels around the evacuation piping system were low.

Material balance evaluation is an important measure to determine whether or not nuclear material is diverted. A prototype code to evaluate material balance has been developed for uranium fuel fabrication facility. However, it is difficult to analyze the code’s functionality and performance because the utilization of real facility data related to material balance evaluation is very limited. It is also restricted to deliberately implement various abnormal situations based on real facility data, such as nuclear diversion condition. In this study, process flow simulator of uranium fuel fabrication facility has been developed to produce various process data required for material balance evaluation. The process flow simulator was developed on the basis of the Simulink-SimEvents framework of the MathWorks. This framework is suitable for batch-based process modeling like uranium fuel fabrication facility. It dynamically simulates the movement of nuclear material according to the time function and provides process data such as nuclear material amount at inputs, outputs, and inventories required for Material Unaccounted For (MUF) and MUF uncertainty calculation. The process flow simulator code provides these data to the material balance evaluation code. And then the material balance evaluation code calculates MUF and MUF uncertainty to evaluate whether or not nuclear material is diverted. The process flow simulator code can simulate the movement of nuclear material for any abnormal situation which is difficult to implement with real process data. This code is expected to contribute to checking and improving the functionality and performance of the prototype code of material balance evaluation by simulating process data for various operation scenarios.

A Cu-15Ag-5P filler metal (BCuP-5) is fabricated on a Ag substrate using a high-velocity oxygen fuel (HVOF) thermal spray process, followed by post-heat treatment (300oC for 1 h and 400oC for 1 h) of the HVOF coating layers to control its microstructure and mechanical properties. Additionally, the microstructure and mechanical properties are evaluated according to the post-heat treatment conditions. The porosity of the heat-treated coating layers are significantly reduced to less than half those of the as-sprayed coating layer, and the pore shape changes to a spherical shape. The constituent phases of the coating layers are Cu, Ag, and Cu-Ag-Cu3P eutectic, which is identical to the initial powder feedstock. A more uniform microstructure is obtained as the heat-treatment temperature increases. The hardness of the coating layer is 154.6 Hv (as-sprayed), 161.2 Hv (300oC for 1 h), and 167.0 Hv (400oC for 1 h), which increases with increasing heat-treatment temperature, and is 2.35 times higher than that of the conventional cast alloy. As a result of the pull-out test, loss or separation of the coating layer rarely occurs in the heat-treated coating layer.

In this study, a new manufacturing process for a multilayer-clad electrical contact material is suggested. A thin and dense BCuP-5 (Cu-15Ag-5P filler metal) coating layer is fabricated on a Ag plate using a high-velocity oxygen-fuel (HVOF) process. Subsequently, the microstructure and bonding properties of the HVOF BCuP-5 coating layer are evaluated. The thickness of the HVOF BCuP-5 coating layer is determined as 34.8 μm, and the surface fluctuation is measured as approximately 3.2 μm. The microstructure of the coating layer is composed of Cu, Ag, and Cu-Ag-Cu3P ternary eutectic phases, similar to the initial BCuP-5 powder feedstock. The average hardness of the coating layer is 154.6 HV, which is confirmed to be higher than that of the conventional BCuP-5 alloy. The pull-off strength of the Ag/BCup-5 layer is determined as 21.6 MPa. Thus, the possibility of manufacturing a multilayer-clad electrical contact material using the HVOF process is also discussed.

Currently, the Korean nuclear industry uses ZIRLO as material for nuclear fuel cladding(zirconium alloy). KEPCO Nuclear Fuel is in the process of developing a HANA alloy to enable domestic production of cladding. Cladding manufacture involves multistage heat treatments and pickling processes, the latter of which is vital for the removal of defects and impurities on the cladding surface. SMUT that forms on the cladding surface during such pickling process is a source of surface defects during heat treatment and post-treatment processes if not removed. This study analyzes ZIRLO, HANA-4, and HANA-6 alloy claddings to extensively study the SEM/EDS, XRD, and particle size characteristics of SMUT, which are second phase particles that are formed on the cladding surface during pickling processes. Using the analysis results, this study observes SMUT formation characteristics according to Nb concentration in Zr alloys during the washing process following the pickling process. In addition, this study observes SMUT removal characteristics on cladding surfaces according to concentrations of nitric acid and hydrofluoric acid in the acid solution.

This study investigates the microstructure and wear properties of cermet (ceramic + metal) coating materials manufactured using high velocity oxygen fuel (HVOF) process. Three types of HVOF coating layers are formed by depositing WC-12Co, WC-20Cr-7Ni, and Cr3C2-20NiCr (wt.%) powders on S45C steel substrate. The porosities of the coating layers are 1 ± 0.5% for all three specimens. Microstructural analysis confirms the formation of second carbide phases of W2C, Co6W6C, and Cr7C3 owing to decarburizing of WC phases on WC-based coating layers. In the case of WC-12Co coating, which has a high ratio of W2C phase with high brittleness, the interface property between the carbide and the metal binder slightly decreases. In the Cr3C2-20CrNi coating layer, decarburizing almost does not occur, but fine cavities exist between the splats. The wear loss occurs in the descending order of Cr3C2-20NiCr, WC-12Co, and WC-20Cr-7Ni, where WC-20Cr-7Ni achieves the highest wear resistance property. It can be inferred that the ratio of the carbide and the binding properties between carbide–binder and binder–binder in a cermet coating material manufactured with HVOF as the primary factors determine the wear properties of the cermet coating material.

바이오항공유 제조 공정 내 수첨업그레이딩 공정의 운전조건 선정은 반응물로부터 얻고자 하는 주생성물인 탄화수소 화합물에 대하여 바이오항공유로서 원하는 탄소수 분포의 물성을 갖도록 하기 위한 중요한 인자이다. 본 연구에서는 식물성 오일 유래 노말 파라핀계 탄화수소 화합물에 대한 수첨 업그레이딩 반응이 0.5 wt.% Pt/Zeolite 촉매 하에서 수행되었으며, 이를 통해 크래킹 반응과 이성질화 반응이 동반됨으로써 바이오항공유로서 물성을 갖는 탄소수 분포인 C8-C16에 해당하는 노말 파라핀계와 이소 파라핀계가 혼합된 탄화수소류 화합물이 제조되었다. 반응온도, 반응압력, 반응물 몰비와 공간속도를 변화하여 얻어진 생성물의 수율 및 조성을 분석하였다. 상기 공정 조건에 대한 정보는 수첨 업그레이딩 반응특성의 이해뿐 아니라 향후 증류를 통한 바이오항공유 제조에 도움을 줄 수 있다.

본 논문은 국내 원전의 습식저장조에 저장 중인 경수로형 사용후핵연료를 금속겸용용기를 이용해 건식으로 운영하기 위한 운영공정을 개발하는 것이다. 국내 경수로형 원전의 사용후핵연료는 1990년대 초부터 습식으로 소내에서 운반을 한 경험은 많으나 건식으로 운전한 경험은 전혀 없는 실정이다. 이에 따라 금속겸용용기를 운영할 수 있는 세부 운영공정을 개발하 였으며 주요 운영공정에서 금속겸용용기의 주요 구성품 및 사용후핵연료의 안전성이 유지됨을 확인하였다. 단기운영공정은 총 21시간 내에 이루어지도록 절차를 수립하였고 단계별로 허용운전 시간(15시간 습식공정, 3시간 배수공정, 그리고 3시간 진공공정)도 제시하였다.

초고온가스로는 고온의 원자로 열을 이용하여 대량의 청정 수소와 고효율의 전기를 생산할 수 있는 제 4세대 원자로이다. 초고온가스로는 0.5mm 직경의 우라늄을 세라믹으로 3중 코딩해 직경 약 0.9mm의 TRISO라고 불리 는 피복입자를 사용한다. TRISO는 크기가 작을 뿐 아니라 특수 코팅 처리가 되어 있어 우라늄이 직접 공기 중 에 노출될 일이 없다. 핵연료 품질 유지 측면에서 TRISO 제작시 핵연료의 동일한 구형성, 밀도 및 피복층 두께 를 유지하는 것이 중요하다. 본 논문에서는 X-선 래디오그래피 기술을 이용한 비파괴 방법을 적용하여 측정한 TRISO 피복입자의 피복층 두께 자료를 바탕으로 피복입자핵연료의 대량 제조 관리를 가정하였고, 이 경우 X-R 관리도를 이용하여 생산 공정의 공정 이상 여부를 시뮬레이션하였다.(한글초록 300자 내외)

Much research into fuel cells operating at a temperature below 800℃. is being performed. There are sig-nificant efforts to replace the yttria-stabilized zirconia electrolyte with a doped ceria electrolyte that has high ionic con-ductivity even at a lower temperature. Even if the doped ceria electrolyte has high ionic conductivity, it also shows highelectronic conductivity in a reducing environment, therefore, when used as a solid electrolyte of a fuel cell, the power-generation efficiency and mechanical properties of the fuel cell may be degraded. In this study, gadolinium-doped ceriananopowder with Al2O3 and Mn2O3 as a reinforcing and electron trapping agents were synthesized by ultrasonic pyrol-ysis process. After firing, their microstructure and mechanical and electrical properties were investigated and comparedwith those of pure gadolinium-doped ceria specimen.

자동차 연료용 바이오가스의 고순도 메탄 분리정제를 위해 2단 재순환 분리막 공정을 연구하였다. 2단 재순환 분리막공정을 개발하기 위해 폴리설폰(Polysulfone) 중공사 모듈을 채택하여 이산화탄소, 메탄의 순수투과도를 측정하였다. 또한 모델 혼합가스를 대상으로 모듈의 메탄농도와 압력에 대해 투과실험을 수행하여 메탄의 농도와 회수율에 대한 연구를 수행하였다. 그 결과를 토대로 2단 재순환 분리막 파일럿 플랜트를 제작하였으며 현장에서 발생되는 바이오가스를 대상으로 공정변수에 대한 메탄 회수율과 농도에 관한 투과실험을 수행하였다. 제습기와 탈황설비 등의 전처리설비를 거쳐 가스 내의 수분을 500 ppm 이하, 바이오가스내의 황화수소 농도를 20 ppm 이하로 제거하였으며 그 정제된 혼합가스를 대상으로 파일럿 분리막 공정의 막면적비에 따른 운전결과를 알아보기 위하여 1, 2단의 막면적비가 각각 1:1, 1:3, 2:2가 되도록 구성하여 실험을 진행한 결과, 1단의 막면적은 1 m2로 동일하고 2단의 면적비가 1 m2에서 3 m2로 증가하였을 경우 최종 공급유량은 6.6 L/min에서 80.7 L/min로 그리고 메탄 회수율은 메탄순도 95%에서 47.1%에서 92.5%로 증가하였다. 또한, 막 면적비가 1:1로 동일한 경우 전체 면적이 2배로 증가함에 따라서 유량은6.6 L/min에서 100.8 L/min로 회수율은 47.1에서 88.3%를 나타내었다. 1:3 면적비에서 공급유량이 증가하는 경우, 최종 메탄 순도는 감소하고 메탄 회수율은 증가하는 것을 알 수 있었다. 운전압력이 증가할수록 공급유량은 증가하고 회수율은 다소 감소하는 것으로 나타났다. 실험을 통해 유효막면적, 공급압력과 공급유량의 변화가 공정 성능향상에 중요한 영향을 미친다는 것을 확인하였다.