RUCAS (Recycling-Underlying Computational Dose Assessment System), a dose assessment program based on the RESRAD-RECYCLE framework, is designed to evaluate dose for recycling scenarios of radioactive waste in metals and concrete. To confirm the validity of the recycling scenarios provided by RUCAS, comparative evaluations will be conducted with RESRAD-RECYCLE for metal radioactive waste recycling scenarios and with MicroShield® for concrete radioactive waste recycling scenarios. In the evaluation of metal recycling scenarios without shielding, RUCAS showed similar results when compared to both MicroShield® and RESRAD-RECYCLE. This validates the function of dose assessments using RUCAS for metal recycling scenarios. However, when shielding was present, RUCAS produced results that were comparable to MicroShield®, but differed from those of RESRAD-RECYCLE. The underestimation of dose values up to 1.66E+08 times difference by RESRAD-RECYCLE could potentially decrease reliability and safety in evaluated doses, further emphasizing the importance of RUCAS. Because validation is also necessary for the expanded calculation capabilities resulting from methodological changes of RUCAS (i.e., various radiation source geometries), based on prior validations, it was determined that additional validations are required for different radiation source materials and shielding conditions. In case where the radiation source and shielding materials were identical, RUCAS and MicroShield® produced similar results according to both the Kalos et al. (1974) and Lin and Jiang (1996) methodologies. This demonstrates that the that differences in methodology are inconsequential when considering the same source and shielding materials. However, when the atomic number of the radiation source materials was larger than that of shielding material (HZ-LZ condition), RUCAS obtained results similar to MicroShield® only for the Kalos et al. (1974) methodology. While Lin and Jiang (1996) methodology yield higher results than MicroShield®. Lastly, in case where the atomic number of the radiation source material was smaller than that of the shielding material (LZ-HZ condition,) both methodologies yielded results comparable to MicroShield®. In conclusion, the validity of RUCAS’s shielding calculations has been verified, confirming improvements in dose assessment compared to RESRAD-RECYCLE. Additionally, we observed that shielding effectiveness calculations differ depending on the methodology of build-up effect. If the validity of these methodologies is confirmed, it is expected that selecting the most advantageous methodology for each condition will enable more rational dose assessments. Consequently, in future research, we plan to evaluate the validity of Lin and Jiang (1996) methodology using particle transport codes based on the Monte Carlo method, such as MCNP and Geant 4, rather than MicroShield®.

Decontamination and Dismantlement (D&D) are of great interest to owner of decommissioning as a large number of old nuclear facilities around the world are either shutdown or soon to be decommissioned. D&D are key steps in the decommissioning of nuclear power plants (NPPs). These activities typically generate a significant volume of radioactively contaminated waste. However, as much as 90% or more of this waste is lightly contaminated metal and concrete that could potentially be cleared for recycle or beneficial reuse, rather than disposed of as radioactive waste. The objective of this study is to provide reference for the application of current technologies to cost-effectively reduce the volume of radioactive waste associated with decommissioning, through review of experiences with decontamination of NPPs materials for unrestricted release, recycle or reuse, Also, highlights the importance of ongoing efforts to harmonize regulations and standards for radioactive waste management globally to enable reuse and recycle of valuable materials generated during decommissioning. The presented results in the balance of this study are organized to align with the sequence of operations for executing reuse or recycle of material for a decommissioning project. Concrete from buildings has most commonly been used for backfill of voids onsite, while metal has most commonly been melted or cleared into the conventional scrap recycling industry. Copper and lead, commonly found in cables and shielding, have high residual value and are thus highly desirable for recycling. Steel and stainless steel, while not inherently valuable, are present in many large components, such that decontamination for recycling can be cost-effective compared to disposal as radioactive waste. The decontamination techniques range from simple, inexpensive methods to complex, aggressive methods, each with advantages in various scenarios and limitations in others. Treatment often involves the sequential application of two or more decontamination techniques (e.g., chemical decontamination followed by abrasive blasting). Strategies for the characterization of materials for recycling include analyzing material in place before dismantlement, analyzing removed samples before or after dismantlement, and evaluating bulk material removed after dismantlement. If clearance and recycling are permitted, metals can be released to the conventional scrap recycling market, and concrete rubble can be used as backfill material onsite. In general, successful reuse/recycle projects require consideration of reuse/recycling objectives and implementation of associated planning activities early in the decommissioning process. The practicality of reuse/recycle depends on a number of high level (country and region-specific) and component level (material and case specific) factors. Since this information is useful to those responsible for planning or implementing the decommissioning of nuclear facilities, it is expected that it will be of great help especially to those in charge of decommissioning plan and managers in charge of decommissioning projects.

As the number of aging nuclear power plants increases, the market for dismantling nuclear power plants is growing rapidly. About 40% of the cost of dismantling nuclear power plants is the waste treatment cost incurred during the dismantling process, of which concrete waste accounts for a significant portion of the total waste. Securing technology for reducing and recycling concrete waste is very important not only in terms of economy but also in terms of environment. The objective is to synthesize geopolymer using inorganic materials from cement fine powder in concrete waste. Cement fine powder in concrete waste has a large amount of inorganic elements necessary for filing materials for radioactive waste treatment such as CaO and SiO2. In particular, Ca(OH)2 is synthesized by extracting Ca2+ from concrete waste. It can be used as an alkali activator to synthesize geopolymer. The mortar from crushed concrete was used as a source of calcium. The first step is to react with concrete waste and hydrochloric acid to extract ions. The second step is to react with NaOH and synthesize Ca(OH)2. The product was divided into two stages according to the reaction method and order. The first and second products were washed and dried, and then XRD and XRF were performed. The second product was matched only Ca(OH)2 and CaCO3 at the XRD peak. In the case of XRF, it was analyzed to have a purity of 67.80–78.73%. Synthesis of geopolymer by recycling materials extracted from concrete waste can reduce disposal costs and improve the utilization rate of disposal sites.

In this study, an aerosol process was introduced to produce CaCO3. The possibility of producing CaCO3 by the aerosol process was evaluated. The characteristics of CaCO3 prepared by the aerosol process were also evaluated. In the CaCO3 prepared in this study, as the heat treatment proceeded, the calcite phase disappeared. The portlandite phase and the lime phase were formed by the heat treatment. Even if the CO2 component is removed from the calcite phase, there is a possibility that the converted CO2 component could be adsorbed into the Ca component to form a calcite phase again. Therefore, in order to remove the calcite phase, carbon components should be removed first. The lime phase was formed when CO2 was removed from the calcite phase, while the portlandite phase was formed by the introducing of H2O to the lime phase. Therefore, the order in which each phase formed could be in the order of calcite, lime, and portlandite. The reason for the simultaneous presence of the portlandite phase and the lime phase is that the hydroxyl group (OH−) introduced by H2O was not removed completely due to low temperature and/or insufficient heating time. When the sufficient temperature (900°C) and heating time (60 min) were applied, the hydroxyl group (OH−) was removed to transform into lime phase. Since the precursor contained the hydrogen component, it could be possible that the moisture (H2O) and/or the hydroxyl group (OH−) were introduced during the heat treatment process.

원자력발전소 해체 시 발생하는 금속폐기물은 폐기물 중에서 많은 비중을 차지하고 있다. 본 연구에서는 국내 자체처분 규제 요건 및 국내 기관별 자체처분현황을 조사하였다. 실제 원자력발전소 해체 시 발생되는 금속폐기물의 자체처분을 위하여 RESRAD-RECYCLE 코드를 이용하였으며 26가지 시나리오에 대한 선량평가를 수행하였다. 평가결과는 원자력발전소 해 체 시 자체처분 및 재활용에 관한 사전자료로서 활용가치가 있을 것으로 사료된다. 추후 자체처분을 통한 처분비용 저감효 과 연구가 추가로 가능할 것으로 판단된다.

Since warm mix asphalt (WMA) was introduced in early 2000, many of these pavements were built more than 10 years ago. Therefore, the WMA recycling research is important and necessary. However, the recycling issue of WMA has lagged behind other researches such as moisture sensitivity and long-term performance of WMA. If the aged WMA is incorporated into the asphalt mixes, the mixing and compaction temperatures of the mixtures are expected to decrease by the warm additives. The effect of warm additive after in-service period needs to be evaluated to see if the aged WMA can be used in asphalt pavements. The main objective of this study was to evaluate the properties of recycled asphalt binders containing long-term aged (LTA) WMA binders through Superpave asphalt binder tests. The WMA binders were manufactured with two wax additives, LEADCAP and Sasobit, and artificially aged using rolling thin film oven (RTFO) and pressure aging vessel (PAV) procedures. The aged WMA binders were recycled at 15% and 30%. The viscosity properties for the binders in the original state, the rutting properties in the original state and after RTFO aging, the fatigue cracking properties at intermediate temperature after RTFO+PAV aging methods, and the low temperature cracking properties after RTFO+PAV procedures were evaluated. The following conclusions were drawn for the materials used in this study: (1) Although the addition of LTA into virgin binder increased the binder’s viscosity, the binders containing wax additives had significantly lower viscosities compared with the unmodified binders at all recycling content (0, 15, and 30%). (2) Even though the binder with wax experienced the aging processes, the wax additive within recycled binder was effective to decrease the binder viscosity at almost the same degree, provided with the actual amount of wax in recycled binders. (3) The binders containing wax additive had higher G*/sin δvalues than control binders at each recycling content. It means that the wax additive still plays an important role in increasing rutting resistance, even though the additive was aged within asphalt binder. (4) From the DSR test at intermediate temperature, it appears that the higher recycling content seemed to have negative effects on resistance to fatigue cracking, regardless of the wax additive. (5) The recycled WMA binders at 30% recycling content were observed to have significantly lower resistance on low temperature cracking (measured by the BBR test). It is recommended that the WMA be recycled in a lower contents in cold regions.

탈기/무산소조, 삼중반응조, 경사판침전조, 막분리조에서 경사판침전조에서 탈기/무산소조로 1Q의 내부반송과 삼중반응조로 0.3~0.5Q의 30분 마다 교대반송을 하였다. 교대반송시 NaOH를 주입하여 탈질원을 제공하였다. TN 유입 농도는 30.1mg/L에서 4.7mg/L로 제거되었으며, 처리수의 NH3-N의 평균농도는 0.5mg/L로 처리되어 대부분 질산화가 이루어졌다. NO3-N은 2.1mg/L로 무산소/탈기, 삼중반응조 및 침전조가 모두 하부로 연결되어 무산소조의 역할이 크게 증가하여 나타난 것으로 판단된다. NaOH(2,000mg/L)를 34mL/min으로 주입한 결과 반송수 상징액의 CODMn 농도는 24.7(19.9~31.0)mg/L로 탈질원이 형성되었음을 알 수 있었다.

탈기/무산소조, 삼중반응조, 경사판침전조, 막분리조에서 2, 3단계에 침전조 하부에 경사판을 설치하였고, 위어의 높이를 증가시켰다. 1단계에서 침전조와 막분리조의 MLSS 차이는 1,800mg/L 정도이며, 2, 3단계에서는 1,300mg/L로 막분리조의 MLSS 농도가 낮아졌다. 경사판침전조에서 막분리조로 이송되는 위어의 단면적이 증가함에 따라 유속이 느려지고, 막분리조로 이동하는 유속인 ULd과의 합이 낮아져 유량이 감소하는 것을 알 수 있다. 위어의 높이를 증가시키거나 단면적을 증가시키면 막분리조의 MLSS의 농축을 낮출 수 있고 경사판침전조의 MLSS 농도를 고농도로 유지 할 수 있어 분리막의 오염을 낮출 수 있다. 처리수의 H3-N의 평균농도는 0.5mg/L로 처리되어 대부분 질산화가 이루어졌다.

large amount of effluent water would be produced from low temperature coal catalytic gasification (LTCCG) developed by ENN Co, Ltd, which located at Langfang, Hebei Province. Many phenol homologous compounds and a large amount of other organic compounds were contained in this effluent water, but the overall concentration of the organic compounds was not very high (CODCr value was about several thousands mg/L). Too high cost would occur if treating it with a traditional liquid-liquid extraction process, and it was a waste of resources if the effluent water was directly purified with biochemical technology. In this paper, a decontaminating and recycling technique was developed for an effluent water, and a two-step technique includes flocculation-recycling and ion exchange adsorption-elution processes. By this two-step process, the CODCr value of the final outlet water was decreased to meet the related national standards, and at least 90% of the organics in the effluent water could be recovered.

Ocean discharge of sewage sludge, which started in the year of 1993 in Korea, was stopped in the beginning of 2012, Landfill of sewage sludge was also prohibited in 2003 owing to public acceptance of the lanfill sites, and partially reopened in 2007 due to the necessity of organic component in sludge to produce methane gas. Sludge recycle ratio will increase in sewage sludge treatment by volume reduction and drying, and then recycle of the thermal energy as fuel in power plant and also material as raw material of cement. Several drying processes are compared with reasoning and an appropriate drying sequence is suggested.

고농도 유기질 폐수처리를 위해 전기화학적 방법의 사용에 있어 관심이 고조되고 있다. 전기화학적 방법의 기술은 음식물폐수 및 공업적 폐수 문제를 해결하는데 이상적 처리 방법이다. 다른 화학적 처리 방법과는 다르게 전기화학적 처리장치는 2차 폐수의 부피를 증가시키지 않고 용수와 유기질 비료로 재활용한다. 전기화학적 방법은 전해부상장치를 무기화학적 약품과 병행하여 더욱 효과적으로 음식물 폐수를 처리한다. 이 연구는 2차 처리로 초음파와 오존처리로 탈색, COD와 BOD가 격감함으로 용수 및 유기질 비료로 활용하도록 실험하였다.

The waste substrate from sawdust based cultivation of Heicium erinaceum was reused. This process was conducted three times. Even when the waste substrate was reused at three times, the yield of fruiting bodies was equal to that of fresh medium. However, the yield of the 1st-waste substrate was the best of all waste substrate media and the yields of waste substrate media deceased with recycling times. The yield of the 1st or the 2nd waste substrate medium increased by 1.3-1.4 times compared with that of the fresh medium. The content of low molecular α-glucan and β-glucan of the 1st or the 2nd waste substrate medium increased and C-N ratio of the 1st or the 2nd waste substrate medium decreased. These results suggest that low molecular glucan and N sources contribute to increasing fruiting bodies. It was clear that the 1st and the 2nd waste substrate were useful for the cultivation material of Heicium erinaceum.

서울시내 도로 유지보수 4개 현장에서 수집된 재령 및 물리적 특성이 서로 다른 폐아스팔트를 폼드 아스팔트 공법을 사용하여 기층용 혼합물을 제작하였다. 혼합물은 구재와 신재의 비율을 서로 달리하여 제작하였으며 구재 비율 변화에 따른 성능을 실내시험을 실시하여 분석하였다. 실내시험은 마샬안정도, 간접인장강도, 회목탄성계수, 크리프 시험 및 휠 트레킹 시험을 실시하였으며 시험 결과는 재생가열 아스팔트 혼합물 시험 결과와 상호 비교하였다. 비교 결과, 재생 폼드 아스팔트 혼합물은 소성변형 및 온도 변화에 대한 저항성은 재생 가열 아스팔트 혼합물에 비하여 동등하거나 우수한 것으로 나타났다. 한편 재생 폼드 아스팔트 혼합물의 건조시 간접인장강도는 재생 가열 아스팔트 혼합물에 비하여 낮게 측정되었으며 습윤시에는 구재의 비율과 관계없이 모두 간접인장강도가 낮게 나타나서 습윤 조건에서는 취약한 것으로 발견되었다.