Inorganic and organic ion exchange materials were generally applied to liquid processes in nuclear reactor. In the case of heavy-water reactor (HWR), zeolite, active carbon, anion resin, and cation resin were used to treat liquid processes such as reactor primary coolant cleanup and liquid radioactive waste management system. Then, used ion exchangers were stored at storage tanks. Various kinds of nuclides were adsorbed in ion exchange materials. Especially, C-14, long half-life nuclide, was highly concentrated in anion resin, and waste resin was treated as intermediated level radioactive waste (ILW). Thermal and non-thermal methods such as pyrolysis, incineration, catalytic extraction, acid digestion, and wet oxidation have been studied for treating spent resin. However, destructive methods are not suitable due to massive off gas waste containing radioactive species. To solve this problem, various kinds of processes were developed such as acid stripping, PLO process, activity stripping, thermal treatment, and etc. In this study, microwave method is suggested to treat HWR waste resin. C-14 nuclide was selectively removed from waste resin without decomposition of main structure in waste resin. Radioactive waste resin generated from Wolsung HWR unit 1 and unit 2 was treated using microwave method and 95% of C-14 was successfully removed from the radioactive waste resin.

Starting with the permanent shutdown of Kori Unit 1, the first waste treatment facility in Korea will be built on the Kori site. In this facility, major process such as decontamination, cutting, radiation measurement and volume reduction of decommissioning waste are performed, and radioactive liquid waste is generated by the waste treatment process and personnel decontamination. The generated liquid waste is finally discharged to the sea through radioactive monitoring system after sufficient treatment to meet the standard radiological effluent control. Whereas the treated liquid waste is additionally diluted through the circulation water discharge conduit and discharged to the sea in the operating nuclear power plants, there is no circulation water in the waste treatment facility. Therefore, a new discharging method for dilution after treatment should be considered. In this paper, the treatment concept and discharge method of radioactive liquid waste system in waste treatment facility are reviewed.

The purpose of this study was to effectively purify U-contaminated soil-washing effluent using a precipitation/distillation process, reuse the purified water, and self-dispose of the generated solid. The U ions in the effluent were easily removed as sediments by neutralization, and the metal sediments and suspended soils were flocculated–precipitated by polyacrylamide (PAM). The precipitate generated through the flocculation–precipitation process was completely separated into solid–liquid phases by membrane filtration (pore size < 45 μm), and Ca2+ and Mg2+ ions remaining in the effluent were removed by distillation. Even if neutralized or distilled effluent was reused for soil washing, soil decontamination performance was maintained. PAM, an organic component of the filter cake, was successfully removed by thermal decomposition without loss of metal deposits including U. The uranium concentration of the residual solids after distillation is confirmed to be less than 1 Bq·g−1, so it is expected that the self-disposal of the residual solids is possible. Therefore, the treatment method of U-contaminated soil-washing effluent using the precipitation/distillation process presented in this study can be used to effectively treat the washing waste of U-contaminated soil and self-dispose of the generated solids.

After the Fukushima accident in 2011, a huge amount of radioactively contaminated water is being generated by cooling the melted fuel of units 1, 2 and 3. Most of contaminated water is seawater and underwater containing not only salt elements but also nuclear fission products with radioactivity. To treat the contaminated water, Cs/Sr removal facilities such as KURION and SARRY are being operated by TEPCO. Additionally, three ALPS facilities are on operation to meet the regularity standards for discharge to the sea. However, massive secondary wastes such as Zeolite, sludge and adsorbent is being generated by these facilities for liquid water treatment. The secondary wastes containing various radionuclide with Cs and Sr is difficult to store due to highly radioactive concentration and corrosive properties. In Japan, a variety of technologies such as GeoMelt vitrification, In-Can vitrification and CCIM vitrification is considered as a promising solution. In this study, they were reviewed, and the advantage and disadvantage of each technology were evaluated as the candidate technologies for thermal treatment of sludge radwaste.

The permanent shutdown of Wolseong 1, PHWR (Pressurized Heavy Water Reactor) was decided. Accordingly, there is need for C-14 treatment technology to spent resin generated by PHWR in classified Medium Level Radioactive Waste by C-14 specific activity. However, spent resin by PHWR is mixed and stored with activated carbon and zeolite (mixture), not a single storage, and separation from the mixture must be carried out in advance for C-14 treatment in the spent resin. This study developed a C-14 treatment facility that combined with the technology of separating spent resin from spent resin mixture by PHWR NPP and the technology of C-14 treatment for disposal. The C-14 treatment facility consists of spent resin separation (Part 1) and treatment of separated spent resin. (Part 2) Part 1 is applied with a process of separating the mixed and stored spent resin from the spent resin mixture by applying a drum screen method. In the case of Part 2, spent resin treatment process for desorbing and collecting C-14 nuclides in the separated spent resin using microwave reactor was applied. Except for the adsorbent used to collect C-14 detached in the process of separating and treating spent resin, no additional material is introduced into the facility, and thus secondary waste is significantly reduced. In addition, pollution prevention banks at the bottom of the facility and a sealed automated circulation system were applied to prevent unexpected leakage and diffusion of radioactive materials and ensure stability of workers. Currently, the C-14 treatment facility has been verified for spent resin separation and spent resin treatment using simulated spent resin mixture, and the facility will be demonstrated and verified for field applicability. According to derived results, it is believed that it will be possible to apply the C-14 treatment facility when decommissioning of PHWR.

Liquid scintillation cocktail is liquid waste, which consists of an organic solvent, scintillator, surfactant, and radionuclide. Large volumes of liquid scintillation waste are generated each year, and both the organic compound and radionuclide content can negatively affect on the health and the environment. Therefore, the liquid scintillation waste should be treated in an appropriate way. In this study, to facilitate the treatment of liquid scintillation waste, the sulfate-radical advanced oxidation process (SR-AOP) was performed for the mineralization of liquid scintillator waste. In SR-AOP, highly reactive sulfate radicals, which react more selectively and efficiently with organic compounds, are produced in situ by cleaving the peroxide bond in the persulfate molecule. For the experiment, 100 times diluted ULTIMA GOLD-LLT (initial TOC=699,800 ppm) was used as a liquid scintillation waste. The TOC removal efficiency of liquid scintillation waste by the OXONE (potassium peroxymonosulfate, PMS, 2KHSO5+KHSO4+K2SO4) and sodium persulfate (PS) with varying dosages (4–12 mM) was tested, and the effects of Co2+ and Cu2+ catalysts were compared at a range of pHs (3, 7, and 9). The experimental results demonstrated that 91% TOC removal of ULTIMA GOLD-LLT could be achieved for SR-AOP at initial pH=9, Co2+=1.2 mM (catalyst), PMS=4.8 mM (oxidant) for 60 min reaction. Compared to traditional Fenton AOP which is effective only at low pH, PMS based SR-AOP with Co2+ catalyst is effective at wide range of pHs and less dependent on the treatment efficiency of the operational pH. Therefore, it can be useful for the mineralization of liquid scintillation waste which is difficult to treat with a general treatment method due to the mixture of various organic compounds.

Currently, KHNP has 24 operating nuclear power plant units with a toal combined capacity of about 23 GWe and two units are under construction. However, permanent stop of Kori unit 1 nuclear power plant was decided in 2017. Accordingly, interest in how to dispose of waste stored inside a permanently stopped nuclear power plant and waste generated as decommissioning process is increasing. KHNP CRI is conducting research on the advancement of plasma torch melting facilities for waste treatment generated during the plant decommissioning and operation period. Plasma torch melting facility is composed of various equipment such as a melting furnace (Melting chamber, Pyrolsis chamber), a torch, an exhaust system facility, a waste supply device, and other equipment. In demonstration test, concrete waste was put in a 200 L drum to check whether it can be pyrolyzed using a plasma torch melting facility. Reproducibility for waste treatment in the form of a 200 L drum and discharge of molten slag could be confirmed, the amount of concrete waste in 200 L Drum that could be treated according to power of plasma torch was confirmed. This demonstration test confirmed the field applicability and stability of plasma torch melting facility, and improved expectations for long-term operation.

In nuclear power plants, insulation is used to protect equipment and block heat. Insulation materials include asbestos, glass fiber, calcium silicate, etc. Various types and materials are used. This study aims to ensure volume reduction and disposal safety by applying plasma torch melting technology to insulation generated at operating and dismantling nuclear power plants. After the evaluation of characteristics by securing thermal insulation materials or similar materials in use at the operational and dismantling nuclear power plant. It is planned to perform pyrolysis and melting tests using the MW plasma torch melting facility owned by KHNP CRI Before the plasma test, check the thermal decomposition and melting characteristics (fluidity, etc.) of the insulation in a 1,600°C high-temperature furnace. The insulation is stored in a 200 L drum and injected into a plasma facility, and the drum and the insulation are to be pyrolyzed and melted by the high temperature inside the plasma torch melting furnace. Through this test, thermal decomposition and melting of the insulation, solidification/ stabilization method, maximum throughput, and exhaust characteristics are confirmed at a high temperature (1,600°C) of the plasma torch. Through this study, it is expected that the stable treatment and disposal of insulation generated from operating and dismantling nuclear power plants will be possible.

During the operation or decommission of nuclear facilities, a large amount of dry active waste and cable waste with various shape and material is generated. Most of these wastes have almost no radioactive contamination and can be disposed of by incineration, landfill, recycling, etc. under clearance regulation. For clearance of radioactive waste, it is necessary to verify the characteristics of radiological contamination and prove that it meets the criteria for clearance regulation. According to the domestic clearance regulation, if it is difficult to measure radioactivity of wastes due to their surface condition using direct or indirect measurement methods, representative samples should be collected and analyzed for radioactivity. When sampling, it is desirable to collect samples of about 1 kg that can represent waste contamination per 200 kg or per 1 m2, and the homogeneity of the samples also should be demonstrated. However, in the case of dry active wastes, it is very difficult to prove the homogeneity of the samples because of surface shapes and conditions of the wastes. In particular, considering cable waste generated during the decommission, it is hardly capable to prove the representativeness of the sample, even though the inner shell of the covering material and the copper wire are almost uncontaminated. In this study, we show the development of a treatment system that makes it easy to prove the representativeness of samples when disposing of dry active waste or cable waste generated in nuclear facilities. The treatment device is designed in such a way that it has different storage unit and cutting unit suitable for the material characteristics of each waste type (soft, hard and cable), and therefore optimizes the efficiency of the shredding or cutting process. In addition, it is expected that the work efficiency in the radioactive treatment site with a narrow area can also be improved by providing a moving part on the device.

자기공명영상(MRI) 장비의 조영제로 흔히 사용되는 가돌리늄(Gd)은 매우 안정된 상태로 하수처리과정에서 거의 제거되지 않고 수환경으로 유입된다고 알려져 있다. 따라서 본 연구에서는 세 가지의 공법으로 하수처리를 하는 부산 수영 하수처리장에서 채취한 하수 시료의 공정별 용존 희토류 원소의 제거율 및 수환경으로 배출되는 인위적 기원 Gd (Gdanth)의 배출량을 평가하고자 하였다. 용존 희토류 원소는 공정별 처리 단계에 따라 무거운 희토류 원소(Tb-Lu)에 비 해 가벼운 희토류 원소(La-Eu)에서 농도가 감소하는 경향을 보였다. 또한 일부 시료에서 나타난 음의(negative) Sm anomaly (<1)는 생물학적 제거 과정에서 Sm이 입자나 인산염과 흡착되어 함께 제거되었을 가능성을 시사한다. 모든 시 료에서 양의(positive) Gd anomaly (149±50, n=9)를 보였으며, 공정별로 측정된 Gd의 총 농도 중 Gdanth은 약 97% 이 상을 차지하는 것으로 나타났다. 이는 하수처리과정에서 Gdanth 이 거의 제거되지 않고 수영강 하류로 배출된다는 것을 의미한다. 일별 처리용량을 고려하여 각 공정에서 배출되는 Gdanth의 배출량은 259 mmol/day로 추정할 수 있다. 본 연 구의 결과는 하수처리장을 통해 수영만 연안으로 Gdanth이 지속적으로 배출될 것으로 예상되며, 향후 Gd의 중장기적인 관측이 필요함을 시사한다.

본 연구는 국내의 성범죄자 심리치료프로그램 연구동향을 분석함으로써 향후 성범 죄자 심리치료프로그램을 올바르게 발전시키고 적용하기 위한 방향을 제시하기 위하 여 실시하였다. 이를 위해 최근 15년간 국가기관 주도하에 국내에서 개발한 각종 성범 죄자 심리치료프로그램들을 정리하여 그 이론적 근거가 되는 주요 모델들과 진행방식, 프로그램 내용 및 치료의 과정 등을 검토하였다. 분석을 위한 문헌자료의 포함 및 배 제기준과 절차에 따라 총 26편이 최종 분석대상으로 선정되었으며, 주요특징, 연구시 기, 관련부처, 성별, 연구대상, 형태, 진행자 구성, 집단크기, 운영회기, 회기당 운영시 간, 이론적 배경, 치료적 요인에 대한 분석을 실시하였다. 연구결과를 정리하여 민간 기관과의 연계 강화, 청소년을 대상으로 한 새로운 방식의 개입, 적절한 위험성 평가 에 따른 치료 제공, 특정한 요구도가 있는 성범죄자에 대한 개입 프로그램 개발, 프로 그램 효과에 대한 주기적 분석 등 권고안을 제시하였으며, 마지막으로 연구의 한계점 과 후속연구를 위한 제언에 대해 논의하였다.

본 연구는 코로나19 사태로 대면 접촉을 기피하는 가운데 심리치료가 필요한 고위 험 성폭력사범에 대해 비대면으로도 실시가 가능한 글쓰기가 성폭력사범 치료에 효과 적인지 확인하였다. 성폭력사범이 치료프로그램에 대해 느끼는 심리적 불편감을 줄임 으로써 이들의 낮은 프로그램 반응성을 조절하는 것이 가능한지 확인하기 위한 목적 으로 실험연구를 수행하였다. 전국 교정 심리치료센터에서 치료 중인 고위험 성폭력 사범 중 선발된 32명을 대상으로 55회기의 비대면 글쓰기 및 집단상담 치료를 진행하 였다. 그 결과, 비대면 글쓰기는 강간통념을 감소시키고, 사건 및 자서전적 기억을 다 루는 모듈에서 심리적 불편감을 완화하는 조절적인 역할을 함으로써 성폭력사범의 프 로그램 반응성을 증가시켰다. 본 연구의 결과는 길어지는 팬데믹 상황에서도 치료가 필수적인 성폭력 사범들에게 필요한 부분이 무엇인지를 시사하고 있다.

The frequent detection and occurrence of micropollutants (MPs) in aquatic ecosystems has raised public health concerns worldwide. In this study, the behavior of 50 MPs was investigated in three different domestic wastewater treatment plants (WWTPs). Furthermore, the Kruskal-Wallis test was used to assess the geographical and seasonal variation of MPs in the WWTPs. The results showed that the concentrations of 43 MPs ranged from less than 0.1 to 237.6 μg L-1, while other seven MPs including 17-ethynylestradiol, 17-estradiol, sulfathiazole, sulfamethazine, clofibric acid, simvastatin, and lovastatin were not detected in all WWTPs. Among the detected MPs, the pharmaceuticals such as metformin, acetaminophen, naproxen, and caffeine were prominent with maximum concentrations of 133.4, 237.6, 71.5, and 107.7 μg L-1, respectively. Most perfluorinated compounds and nitrosamines were found at trace levels of 1.2 to 55.3 ng L-1, while the concentration of corrosion inhibitors, preservatives (parabens), and endocrine disruptors ranged from less than 0.1 to 4310.8 ng L-1. Regardless of the type of biological treatment process such as MLE, A2O, and MBR, the majority of pharmaceuticals (except lincomycin, diclofenac, iopromide, and carbamazepine), parabens (except Methyl paraben), and endocrine disruptors were removed by more than 80%. However, the removal efficiencies of certain MPs such as atrazine, DEET, perfluorinated compounds (except PFHxA), nitrosamines, and corrosion inhibitors were relatively low or their concentration even increased after treatment. The results of statistical analysis reveal that there is no significant geographical difference in the removal efficacy of MPs, but there are temporal seasonal variations in all WWTPs.

본 연구에서는 참외과실의 수확후 식용왁스코팅처리가 과실품질 및 과골 갈변에 미치는 대사체의 변화를 분석하였다. 코코넛 오일과 밀랍 (9:1 w/w) 처리를 참외 과실표면에 코팅 후 실온 저장 7일후에 과실 품질, 에틸렌 발생량 및 호흡량을 조사하였다. 그 결과, 참외의 경도와 골갈변도는 식용코팅처리된 과실과 무처리군 사이에 유의한 차이는 없었다. 하지만, 과피색의 명도(L*), 순도(a*), 및 색상각(hue angle)은 식용왁스처리군이 무처리군에 비해 유의한 차이가 있었다. 이는 호흡량 및 에틸렌 발생량이 식용왁스처리에 의해 유의하게 낮아져 과피색이 유지된 것으로 생각된다. 식용왁스 처리에 의한 참외의 대사체 변화를 분석한 결과, gamma-aminobutyric acid, aspartate 그리고 myo-inositol 대사가 가장 유의적인 차이를 나타났으며, 특히 삼투보호제 역할을 하는 alanine, 가바(GABA)성분이 식용왁스코팅에 의해 증가하였다. 따라서, 식용왁스코팅처리는 호흡과 에틸렌 발생의 억제, 수분 스트레스 경감 등을 통해 참외의 선도 유지를 유도한 것으로 판단되며, 참외 과피색 변화 억제 등 상품성 향상에 활용될 수 있을 것으로 보인다.

다양한 산업 중에서 섬유 산업은 섬유 염색을 위해 가장 많은 양의 물을 사용하는데, 이는 여러 종류의 염료를 포 함한 폐수의 방대한 배출로 이어진다. 염료의 제거를 위한 방법에는 오존 처리, 흡착 등의 다양한 처리 방법이 존재한다. 하 지만 이러한 처리 방법은 폐수 재사용의 문제로 인해 처리 가격이 상승하기 때문에 성공적이지 못하다. 이에 대한 대안으로 막분리 공정이 폐수의 염료 처리를 위한 가장 적절한 기술로 보고되고 있다. 이때 사용되는 분리막은 고분자 분리막과 세라 믹 분리막으로 나눌 수 있다. 세라믹 분리막의 장점에는 세척의 용이함, 긴 수명, 내열성, 내화학성, 그리고 기계적 안정성이 있다. 세라믹 분리막은 다양한 원료로 만들 수 있으며, 점토, 제올라이트, 플라이 애시와 같은 천연 재료는 저렴하고 구하기 용이하다. 본 리뷰에서 폐수처리는 크게 한외여과(ultrafiltration), 정밀여과(microfiltration), 그리고 나노여과(nanofiltration) 세 가지 공정으로 나누어져 있다.

영국에서는 지난 수년간 소년범죄의 지속적 감소경향에 따라 소년수용기관에 수용 중인 인원수가 급격히 줄어들게 되었으며, 소년사법시스템의 성과 역시 긍정적으로 평가되고 있다. 그러나 수용인원 감소에 따른 수용기관 감축, 정부 재정지원 축소 경 향, 시설 내에서의 폭력, 자해 증가, 시설 출원 후의 높아지는 재범률 등은 보다 큰 문제로 제기되고 있으며, 시설에 수용 중인 범죄소년들이 갖고 있는 결손가정, 약물 오남용, 음주, 세대적 실업, 피학대 경험, 정신건강 문제, 폭력조직 가담, 교육실패 등 과 같은 공통적인 배경들은 보다 복잡한 사회문제로 부각되고 있는 실정이다. 영국 정 부는 이를 해결하기 위해 교육과 복지를 소년수용기관의 중점과제로 설정하고, 범죄 위험가능성을 높이는 근본적 위험요인들을 해결하기 위한 서비스 확충 및 제고를 위 한 노력에 힘을 기울이고 있다. 최근 영국 정부는 재범방지에 초점을 맞춘 소년사법정책을 펴고 있고, 이를 위해서 소년범죄예방 및 신속한 개입을 위한 효율적, 효과적인 소년사법 행정을 추구, 소년의 특성에 맞는 지원 절차 및 방식을 재정비하는 데에 노력하고 있다. 우리 한국은 물질의 풍요, 인터넷의 발달 등으로 인간의 정신적, 신체적 성장속도가 빨라지고 있고 범죄의 저연령화, 잔혹화 등이 문제되고 있으므로, 현행법상 형사 미성 년자의 연령을 낮추어 현실을 반영하자는 목소리가 커지고 있으며, 강력범죄로 검거 된 소년이 가벼운 처분을 받는 경우가 많아 현행법이 오히려 재범의 위험성을 키우고 범죄예방의 효과를 약화시킨다는 지적이 있다. 이에 대하여 「특정강력범죄의 처벌에 관한 특례법」 제2조의 특정강력범죄를 범한 경우에는 소년부 보호사건의 심리대상에서 제외하고, 형사미성년자의 연령을 12세 미 만으로 조정함으로써 소년범죄의 처벌 및 예방을 강화하려는 소년법 일부개정법률안 이 입법발의 되어 있다. 하지만 소년범죄의 예방 및 재범방지를 위해서는 소년범죄 전반에 대한 증거기반 형사정책에 입각한 실태조사와 원인진단이 필요하며, 현행 공식통계상 소년범죄의 흉 포화, 저연령화 및 증가에 대한 증거나 반증을 찾기 어려운 실정이다. 따라서 본 연구에서는 한국과 영국의 소년사범 교정처우제도를 살펴보고, 우리 소 년사범들의 재범을 예방하고 재사회화를 위한 한국의 소년사법 교정처우제도의 개선 방안을 제안해 보고자 한다. 이에 따른 대안으로 이 연구에서는 첫째, 영국의 소년수 용시설(YOI, Young Offender Institution)을 기반으로 한 ‘소년회복학교’설립, 둘 째, 메타버스를 활용한 정보교육 및 취업 프로그램의 개발, 셋째, 재범방지를 위한 지 역사회와 연계한 멘토-멘티 자원봉사기구인 ‘소년안전협의회’의 구축, 넷째, 지방자치 단체와 보건복지부 청년사회서비스사업을 활용한 정신･신체 건강 프로그램의 개발을 제안해 보았다.

Acute cholangitis is a clinical syndrome characterized by fever, jaundice, and abdominal pain that develops as a result of stasis and infection in the biliary tract. It can be a life-threatening condition if it is not recognized early. Patients with severe cholangitis may present with hypotension, and mental status changes. The most frequent causes of acute cholangitis are biliary calculi, benign biliary stricture, and malignancy. The most common pathogens isolated are gram-negative bacteria (Escherichia coli , followed by Klebsiella species and Enterobacter species). A diagnosis of acute cholangitis requires evidence of systemic inflammation, cholestasis, and imaging with biliary obstruction. Imaging studies may consist of ultrasound, computed tomography, magnetic resonance cholangiopancreatography, and/or endoscopic ultrasound. The mainstay of treatment consists of fluid resuscitation, antibiotics, and biliary drainage. Penicillin/β-lactamase, third-generation cephalosporin, or carbapenem are all acceptable choices for first-line treatment. In patients with severe cholangitis, biliary drainage should be performed within 24 hours. Patients with severe acute cholangitis require urgent (within 24 hours) biliary decompression. Endoscopic retrograde cholangiopancreatography remains the preferred modality for biliary drainage. In conclusion, acute cholangitis is mostly treatable when recognized and treated early. Recognizing and initiating early treatment leads to markedly decreased patient morbidity and mortality.

Conventional wastewater treatment plants (WWTPs) do not fully remove micropollutants. Enhanced treatment of sewage effluents is being considered or implemented in some countries to minimize the discharge of problematic micropollutants from WWTPs. Representative enhanced sewage treatment technologies for micropollutant removal were reviewed, including their current status of research and development. Advanced oxidation processes (AOPs) such as ozonation and UV/H2O2 and adsorption processes using powdered (PAC) and granular activated carbon (GAC) were mainly discussed with focusing on process principles for the micropollutant removal, effect of process operation and water matrix factors, and technical and economic feasibility. Pilot- and full-scale studies have shown that ozonation, PAC, and GAC can achieve significant elimination of various micropollutants at economically feasible costs(0.16-0.29 €/m3). Considering the current status of domestic WWTPs, ozonation and PAC were found to be the most feasible options for the enhanced sewage effluent treatment. Although ozonation and PAC are all mature technologies, a range of technical aspects should be considered for their successful application, such as energy consumption, CO2 emission, byproduct or waste generation, and ease of system construction/operation/maintenance. More feasibility studies considering domestic wastewater characteristics and WWTP conditions are required to apply ozonation or PAC/GAC adsorption process to enhance sewage effluent treatment in Korea.