A person who performs or plans to conduct a physical protection inspection as stipulated by the law, the act on physical protection and radiological emergency, should obtain an inspector’s ID card certified and authorized by Nuclear Safety and Security Commission Order No.137 (referred to as Order 137). In addition, according to Order 137, KINAC has been operating some training courses for those with the inspector’s ID card or intending to acquire it. Also, strenuous efforts have been put to incrementally elevate their inspection related expertise. Since Republic of Korea has to import uranium enriched less than 20% in order to manufacture fuels of nuclear reactors in domestic and abroad, the physical protection for categorization III nuclear material in transit is significantly important along with an increase in transport. The expertise of inspectors should be constantly needed to strengthen as the increase in transport leads to an increase in inspection of nuclear material in transit. We have suggested a special way to improve the inspector’s capacities through Virtual Reality technology (VR). A 3-Dimensional virtual space was designed and developed using a 3-axis simulator and VR equipment for practical training. HP’s Reverb G2 product, which was developed in collaboration with VALVE Corporation and MicroSoft, was used as VR equipment, and the 3-axis motion simulator was developed by M-line STUDIO corp. in Korea for the purpose of realizing virtual reality. The training scenarios of transport inspection consist of three parts: preparation at the shipping point, transport in route including stops and handover at the receiving point. At the departure point, scenario of the transport preparation is composed with the contents of checking the transport-related documents which should be carried by shipper and/or carrier during transport and confirming who the shipper and/or carrier is. Second, scenario is designed for inspector to experience how carrier and/or shipper protect the nuclear material during transport or stops for rests or contingency and how they communicate with each other during transport. Lastly, scenario is developed focusing on key check items during handover of responsibilities to the facility operator at the destination. Those training scenarios can be adopted to strengthen the capabilities of those with inspector’s ID card of physical protection in accordance with Order 137 and to help new inspectors acquire inspectionrelated expertise. In addition, they can be used for domestic education to promote understanding of nuclear security, or may be used for education for people overseas for the purpose of export of nuclear facilities.

Various types of optical materials and devices used in special environments must satisfy durability and optical properties. In order to improve the durability of zinc sulfide multispectral (MS ZnS) substrates with transmission wavelengths from visible to infrared, Ge-Sb-Se-based chalcogenide glass was used as a sealing material to bond the MS ZnS substrates. Wetting tests of the Ge-Sb-Se-based chalcogenide glass were conducted to analyze flowability as a function of temperature, by considering the glass transition temperature (Tg) and softening temperature (Ts). In the wetting test, the viscous flow of the chalcogenide glass sample was analyzed according to the temperature. After placing the chalcogenide glass disk between MS ZnS substrates (20 × 30 mm), the sealing test was performed at a temperature of 485 °C for 60 min. Notably, it was found that the Ge-Sb-Se-based chalcogenide glass sealed the MS ZnS substrates well. After the MS ZnS substrates were sealed with chalcogenide glass, they showed a transmission of 55 % over 3~12 μm. The tensile strength of the sealed MS ZnS substrates with Ge-Sb-Se-based chalcogenide glass was analyzed by applying a maximum load of about 240 N, confirming its suitability as a sealing material in the far infrared range.

The nuclide management technology for separating high-heat generating/high-mobility/long-lived nuclides from high-level wastes based on the chemical reactions is under development. In order to secure the reliability of nuclear non-proliferation and to implement the effective safeguards, it is necessary to consider the safeguards from the conceptual design phase of the novel technologies. However, there was no experience and research on safeguards for the chemical reaction based nuclide management technology. In order to development the available monitoring techniques for the safeguards of nuclide management technology, the possible diversion scenarios were developed and the material flows of major nuclear materials were analyzed according to the various diversion strategies for each unit process in this study. The diversion strategies in this study is limited to the diversion of nuclear materials according to the change of operational parameters (temperature, chemical reagents, pressures, etc). The nuclear material distribution behaviors under the abnormal conditions were analyzed and compared with normal conditions using the HSC Chemistry. The results will be used to determine the proper signals and feasible techniques to monitor the abnormal operations.

Laser induced surface activation (LISA) technology requires refined selection of process variables to fabricate conductive microcircuits on a general polymer material. Among the process variables, laser mode is one of the crucial factors to make a reliable conductor pattern. Here we compare the continuous wave (CW) laser mode with the pulse wave (PW) laser mode through determination of the surface roughness and circuit accuracy. In the CW laser mode, the surface roughness is pronounced during the implementation of the conductive circuit, which results in uneven plating. In the PW laser mode, the surface is relatively smooth and uniform, and the formed conductive circuit layer has few defects with excellent adhesion to the polymer material. As a result of a change of laser mode from CW to PW, the value of Ra of the polymer material decreases from 0.6 m to 0.2 m; the value of Ra after the plating process decreases from 0.8 m to 0.4 m, and a tight bonding force between the polymer source material and the conductive copper plating layer is achieved. In conclusion, this study shows that the PW laser process yields an excellent conductive circuit on a polymeric material.

철도침목은 일반적으로 목재 및 콘크리트 침목을 많이 사용하고 있다. 그러나 목침목은 수분과 충해등으로 인해 썩기 쉽다. 게다가 짧은 수명으로 인해 교체를 자주해줘야 하지만 자원고갈로 인한 공급의 어려움이 있다. 콘크리트 침목은 중량이 무거워 시공장소에 제한이 있고 운반이 어려운 단점을 갖고 있다. 또한 균열발생이나 파손이 일어났을 때 소음이 발생하고 심한 진동으로 인해 레일의 수용저하등의 문제가 있다. 그러므로 이번 연구에서는 전통적으로 사용하던 목재 및 콘트리트 침목을 대신할 합성침목을 개발하는 것이다. 합성침목의 주원료는 폴리올과 이소시아네이트로 구성된 폴리우레탄이다. 폴리우레탄을 수지로 사용하게 되면 강도가 약해 이를 보완해야 하는데 현재까지는 유리섬유나 석탄재와 같은 원료를 사용하였다. 유리섬유 는 인체에 유해하고 침목의 폐기 시 자연에서 분해되지 않은 단점이 있으므로 이 연구에서는 자연에서 분해될 수 있는 천연보 강재를 사용하여 기계적 물성은 유지하면서 가공성 및 경제성이 우수한 합성수지 침목을 개발하는 실험을 진행하였다.

The EMI shield material with narrow width has some deficiencies in shielding capability and this deficiencies are caused by the inconsistent relationship between the inductance and temperature after heat treatment. This study is performed to develop a nano crystal magnetization heat treatment process technology and design a EMI shielding material with wide width up to 350mm. As a result, the performance of the developed wide EMI shield material satisfies all the objects of this study such as the inductance, thickness, permeability, ribbon productivity, lamination productivity. Also, we find that this wide EMI shield material can be used effectively for the EMI shield room, large medical equipment and so on.

최근 환경오염을 방지하고 자원소비를 절감할 수 있는 ‘자원순환사회’로의 전환을 서둘러야 한다는 공감대가 빠르게 확산되고 있으며, ‘자원순환사회’란 폐기물의 소각, 매립을 최소화하고 재활용을 극대화함으로써 환경오염을 방지하고 자원과 에너지를 절약이 큰 이슈화 되고 있는 실정이다. 리튬 이차전지 생산과정 중 전구체 제조공침 기술에서 암모니아수를 사용하게 되며, 공정 중 발생하는 암모니수에 질소제거를 위한 스트리핑법을 이용하여 최종 황산암모늄 수용액이 부산물로 발생 하고 있다. 황산암모늄 폐수 처리시 T-N이 함유되어 고도처리를 해야 하므로 고가의 폐수처리 발생비용 발생 되고 있는 실정이다. 현재 구미산업공단 및 경북 산업단지 내의 매월 약 150톤의 폐황산암모늄이 발생되어 지고 있으며, 주로 고가의 폐수비용을 지불하며 고도처리 방식으로 처리되고 있다. 따라서. 황산암모늄 폐수 활용하여 폐수비용을 경감시키고 부가가치를 창출 할 수 있는 기술에 대하여 관심이 높아지고 있다. 구미산업공단 및 경북 산업단지내의 매월 약 150톤의 폐황산암모늄이 발생되어 지고 있으며, 주로 고가의 폐수비용을 지불하며 고도처리 방식으로 처리되고 있어 환경오염 및 비용이 문제가 점차 확대되고 있는 실정이다. 따라서 본 연구에서는 전지소재 공정에서 발생되는 폐수를 이용하여 황산암모늄 정제기술 및 최적 결정화방법을 개발하였다. 이를 활용하여 폐수 발생량을 줄일 수 있으며, 처리비용을 절감시키는 효과를 통하여 자원순환화 할 수 있을 것으로 사료된다.