The number of dismantled nuclear facilities is increasing globally. Dismantling of nuclear facilities generates large amount of waste such as concrete, soil, and metal. Concrete waste accounts for 70% of the total amount of waste. Since hundreds of thousansds of tons of concrete waste generated, securing technology of reduction and recycling of waste is emerging as a very important issue. The objective of this study is to synthesize geopolymer using inorganic materials from cement fine powder in concrete waste. Dismantled concrete waste contains a large amount of calcium silicate hydrate(C-S-H), Ca(OH)2, SiO2, etc., which is an inorganic material required for the synthesis of geopolymer. SiO2 affects the compressive strength of the geopolymer and Ca(OH)2 affects the curing rate. A high concentration of alkali solution is used as an alkali activator, and alkali activator is necessary for the polymerzation reaction of metakaolinite. The experiment consists of three steps. The first step is to react with concrete waste and hydrochloric acid to extract ions. In the solid after filtration, SiO2 and Al2O3 are composed of 84.10%. It can be used instead of commercial SiO2 required for the synthesis of geopolymer. The second step is to add NaOH up to pH 10, impurities can be removed to extract Ca(OH)2 with high purity. The final step is to add NaOH up to pH 13, and Ca(OH)2 extraction. The alkali solution generated after the last reaction can be recycled into an alkali activator during the synthesis of the geopolymer. If dismantled concrete waste is recycled during geopolymer synthesized, the volume reduction rate of dismantled concrete waste is more than 50%. If you put the radioactive waste in the recycled solidification materials synthesis from concrete waste by dismantling of nuclear facilities, it is possible to reduce the amount of waste generated and disposal costs.

기후 변화의 가속화로 국내 제주 및 남부 지방을 중심으로 열대 및 아열대 작물의 재배 및 소비가 증가하는 추세이다.오크라는 식용적 가치가 있을 뿐만 아니라, 품종별 고유의 꼬 투리와 잎의 색은 관상적 가치가 있어 조경 식물로 많이 사용 되고 있다. 본 연구는 도심 내 옥상 온실에 관상식물인 오크 라를 도입하기 위해 피트모스와 펄라이트 비율에 따른 기초 종자 발아 및 육묘기 실험을 진행하였다. 피트모스와 펄라이 트 비율은 PT:PL=1:2, 1:1, 2:1, 4:1 네 가지로 조성하였다. 발 아율은 파종 후 7일차부터 다른 처리구에 비해 피트모스:펄라 이트=1:2의 처리구에서 가장 높았다. 파종 후 28일차와 70일 차에 줄기길이, 경경, 뿌리길이, 지상부와 지하부의 생체중과 건물중 그리고 엽면적은 피트모스:펄라이트=1:2 처리구에서 가장 높았다. 그러나, 파종 후 56일 이후부터 엽수는 피트모 스:펄라이트=1:2, 2:1, 4:1 처리구에서 감소하였다. 피트모스: 펄라이트=1:1, 2:1, 4:1 처리구에서 식물이 필요로 하는 피트 모스의 비율이 지나치게 높아 높은 피트모스 비율로 인하여 수분함수량이 과도하게 높아 식물이 고사한 것으로 판단된다. 따라서 오크라를 관상식물로 활용하기 위해서는 피트모스와 펄라이트를 1:2로 혼합한 배지가 가장 적합하다.

본 연구에서는 수확 후 저장 기간에 따른 절화 장미의 수명 변화를 알아보았다. 절화장미 ‘Antique Curl’을 수확 직후 4℃ 암조건의 저장고에서 0일(무처리), 1일, 3일, 5일, 7일간 보존 용액 처리 후 습식 저장하였다. 저장이 끝난 절화는 24℃ 실 내 광환경으로 옮겨 절화 보존제 유무 조건에서 절화수명을 조사하였다. 그 결과, 절화수명은 저장기간 3일차까지는 20일 전후로 높았으나, 5일차 이후 유의적으로 감소했다. 절화 보 존제는 절화수명 연장에 효과적이지는 않았으나 절화의 꽃목 굽음 현상을 완화시켰다. 엽록소 형광(Fv/Fm)은 저장 기간과 관계없이 0.78~0.82 수준으로 나타났으며 저장기간에 의한 광 생리 기능저하는 확인되지 않았다. 결과적으로 절화장미 ‘Antique Curl’의 상업적 저장 기한은 최대 5일로 확인되었다.

Although the effect of elevated carbon dioxide (CO2) on Phalaenopsis plant flowering, biomass, and photosynthesis has received intensive study, whether elevated CO2 affects plant requirements and sensitivity to potassium sulfate (SOP) during the reproductive growth stage remains unclear. To evaluate the combined effect of CO2 and SOP provision on crassulacean acid metabolism orchids, we cultivated Phalaenopsis Queen Beer ‘Mantefon’ under ambient and elevated CO2 treatments (≈ 400 or ≈ 720 μmol×mol-1, respectively) and four levels of SOP supply for 20 weeks after treatments (WAT): potassium and sulfate levels by 10.41 and 1.96 mmol·L-1 (SOP1), 5.98 and 0.90 mmol·L-1 (SOP2), 12.80 and 1.96 mmol·L-1 (SOP3), and 14.83 and 3.16 mmol·L-1 (SOP4), respectively. The number of floral buds and flowers decreased in the plants grown under elevated CO2 than in those grown under ambient CO2, regardless of the SOP level; however, the reduced production of floral buds and flowers did not affect the dry mass of shoot, root, and spike at 20 WAT. There were significant interactive effects of CO2 and SOP on root biomass accumulation and net CO2 uptake. The stimulation of biomass partitioning on the root, as a sink source, observed due to the uptake of elevated CO2 was improved under increased SOP supply. Under ambient CO2, the leaf critical SOP level was SOP1 for root and spike biomass accumulation. Plants grown under elevated CO2 were more sensitive to SOP treatments, with higher essential leaf levels of SOP.

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.

High level nuclear waste (HLW) is surely disposed in repository in safe by being separated from human life zone. Deep geological disposal method is one of the most potent disposal method. Deep geological repository is exposed to high pressure and groundwater saturation due to its depth over 500 m. And it is also exposed to high temperature and radiation by spent fuels. Thus, HLW repository suffers extremely complex thermo-hydro-mechanical-radioactive condition. Long-term integrity of repository should be verified because the expected lifetime of the repository is over 10,000 years. However, the integrity of monitoring sensors are not reach the endurance lifetime of the repository with present technology. And the disposal condition, thermo-hydro-mechanical-radioactive, should shorten the estimated lifetime of the monitoring sensors. Therefore, it is necessary to improve the long-term integrity of the monitoring sensors. Although long-term tests are required to identify the prolonged durability of monitoring sensors, accelerated tests can help curtail test period. Accelerated tests is classified into accelerated stress test and accelerated degradation test and their methodology and theories are investigated. Their tests are design and proceed by following process: 1) identify failure modes, 2) select accelerated stress parameter, 3) Determine stress level, 4) Determine testing time and number of specimens, 5) Define measurement paremeter and failure criteria, 6) Suggest measurement method and measurement duration. Literature reviews were conducted to identify the influence of the disposal conditions such as thermo-hydro-mechnical-radioactive on integrity of material and monitoring sensors. The investigated data reported in this paper will be utilized to verify the improvement of integrity of monitoring sensors.