In KAERI’s previous phosphate precipitation tests, the dispersed powder of lithium phosphate (Li3PO4) as a precipitation agent reacted with various metal chlorides in a simulated LiCl-KCl molten salt. The reaction of metal chlorides composed of actinides such as uranium and three rare earths (Nd, Ce and La) with lithium phosphate is a solid-liquid reaction. A phosphorylation reaction rate is very fast and the metal phosphates as a reaction product precipitated on the bottom of the molten salt crucible. One of the recovery methods of the metal phosphate precipitates is segregation the lower part (precipitates) of the salt ingot using the various cutting tools. Recently, a new phosphorylation experiment using lithium phosphate ingots carried out in order to collect the metal phosphate precipitates into a small recovering vessel, and the test result of this new method was feasible. However, the reaction rate of test using lithium phosphate ingot is extremely slower than that of test using lithium phosphate powder. In this study, the precipitation reactor design (a tapered crucible with polished inner surface) used for phosphorylation reaction showed that the salt ingot with metal phosphate precipitates could be detached from a tapered stainless steel crucible. We propose that the recovery of precipitates from a salt ingot is possible by introducing a dividing plate structure into a molten salt and by positioning it at the interface between salt and precipitated metal phosphate.

Some of the metal waste generated from KEPCO NF is being disposed of in the form of ingots. An ingot is a metal that is melted once and then poured into a mold to harden, and it is characterized by a uniform distribution of radioactive material. When measuring the uranium radioactivity in metal ingot with HPGe detector, 185.7 keV of U-235 is used typically because most gamma rays emitted at U-235 are distributed in low-energy regions below 200 keV. To analyze radioactivity concentration of U-235 with HPGe detector more accurately, self-attenuation due to geometrical differences between the calibration source and the sample must be corrected. In this study, the MCNP code was used to simulate the HPGe gamma spectroscopy system, and various processes were performed to prove the correlation with the actual values. First an metal ingottype standard source was manufactured for efficiency calibration, and the GEB coefficient was derived using Origin program. And through the comparison of actual measurements and simulations, the thickness of the detector’s dead layers were defined in all directions of Ge crystal. Additionally instead of making an metal ingot-type standard source every time, we analyzed the measurement tendency between commercially available HPGe calibration source (Marinelli beaker type) and the sample (metal ingot type), and derived the correction factor for geometry differences. Lastly the correction factor was taken into consideration when obtaining the uranium radioactivity concentration in the metal ingot with HPGe gamma spectroscopy. In conclusion, the U-235 radioactivity in metal ingot was underestimated about 25% of content due to the self-attenuation. Therefore it is reasonable to reflect this correction factor in the calculation of U-235 radioactivity concentration.

It has been studied that the aluminum extrusion with the ingot-recycled composite billet that is casted. The billet is composed of the inner rod with the recycled and the outer ring with the ingot aluminum. For easy producing the tensile specimens to evaluate the bonding strength between recycled and ingot material, the extrusion die was designed. Two types of the billet are extruded. One is a composite billet that is casted. The other is an assembled billet with the turned bars. The strength is measured from tensile tests with extruded specimens. The effect on the strength of the oxidized layer between the materials has been researched with EDS analysis.

Saw wires have been widely used in industries to slice silicon (Si) ingots into thin wafers for semiconductor fabrication. This study investigated the microstructural and mechanical properties, such as abrasive wear and tensile properties, of a saw wire sample of 0.84 wt.% carbon steel with a 120 μM diameter. The samples were subjected to heat treatment at different linear velocities of the wire during the patenting process and two different wear tests were performed, 2-body abrasive wear (grinding) and 3-body abrasive wear (rolling wear) tests. With an increasing linear velocity of the wire, the tensile strength and microhardness of the samples increased, whereas the interlamellar spacing in a pearlite structure decreased. The wear properties from the grinding and rolling wear tests exhibited an opposite tendency. The weight loss resulting from grinding was mainly affected by the tensile strength and microhardness, while the diameter loss obtained from rolling wear was affected by elongation or ductility of the samples. This result demonstrates that the wear mechanism in the 3-body wear test is much different from that for the 2-body abrasive wear test. The ultra-high tensile strength of the saw wire produced by the drawing process was attributed to the pearlite microstructure with very small interlamellar spacing as well as the high density of dislocation.

사용후핵연료 파이로프로세싱 공정 생성물인 우라늄 전착물을 잉곳 형태로 주조하는 공정이 있다. 이 논 문에서는 실험실 규모의 우라늄 전착물 잉곳 주조 장치에 대한 설계 개념을 소개하고, 이에 따라 제작된 장 치의 성능 시험 결과 및 우라늄을 사용한 잉곳 주조 시험 결과를 소개한다. 이 장치는 도가니를 경동시켜 우라늄 용탕을 주형에 주입하여 우라늄 잉곳을 제조하며, 우라늄 전착물을 연속으로 주입할 수 있는 컵 형태의 원료 장입장치를 장착하였다. 이러한 장치를 사용하면 우라늄 전착물의 잉곳 생산성을 높일 수 있다. 실험 결과 우라늄 원료를 장입하여 주조한 결과 수축공이 적은 양호한 주물을 제조하는데 성공하였으며, 이러한 실험실 규모의 장치를 개발한 경험을 활용하여 공학규모의 장치를 설계하 는데 활용하였다.

  In this research article, scheduling a casting sequence in a job-shop type foundry involving a variety of casts made of an identical alloy but with different shapes and weights, has been investigated. The objective is to produce the assigned mixed order

Nd5Pr7Fe82B6 및 Nd12Fe82B6 조성의 1차 용유된 ingot에 대하여 기계적 분쇄처리 및 열처리를 행하고 결정구조 및 자기적 특성을 측정하였다. Ar 분위기 하에서 330시간 분쇄처리한 결과 2~3μm크기의 입자가 얻어졌으며, x-선 회절도로부터 각 입자는 미세한 결정립으로 구성되어 있음을 알았다. 330시간 분쇄처리된 분말을 600˚C에서 2시간 열처리함으로써 항자계가 18.36-18.79kOe, 최대에너지적이 8.32-8.38 MGOe인 자기적 특성을 얻었다. 열처리 온도가 높아지면 자기적 특성이 향상되었으나, 기계적 분쇄처리에 의한 ingot의 미세결정화 과정이 최적의 자기적 특성을 얻는데 더욱 중요하였다.