The pyroprocessing of spent nuclear fuel generates LiCl-KCl eutectic waste salt containing radioactive ... It is necessary to develop a simple process for the treatment of LiCl-KCl eutectic waste in a hot-cell ... simplify the existing separation and solidification process of rare earth nuclides in LiCl-KCl eutectic waste
For the removal of cesium (Cs) from high radioactive/high salt-laden liquid waste, this study synthesized ... liquid waste with high efficiency. ... It is proved that this composite adsorbent can remove rapidly Cs contained in high radioactive/high salt-laden
waste disposal. ... waste disposal project as well as other structures and underground openings. ... on the study, this monitoring system is potentially applicable to long term monitoring systems for radioactive
as well as the waste management organization. ... Korea’s disposal fee for LILW is higher than other countries’ fee, which is a burden to waste generators
waste volume and to recycle resource materials. ... This paper is about recovery of residual LiCl-KCl eutectic salts in radioactive rare earth precipitates ... pyrochemical process of spent nuclear fuels, recovery of LiCl-KCl eutectic salts is needed to reduce radioactive
Securing the radiological safety is a prerequisite for the safe management of the naturally occurring radioactive ... Here, we assess the environmental impact of the NORM waste disposal with respect to the major domestic ... are performed using the characteristics of the representative domestic NORM wastes including flying
with Barium (Ba) impregnated 4A zeolite (BaA) from high-radioactive seawater waste (HSW). ... This study investigated the removal of Sr, which was one of the high radioactive nuclides, by adsorption ... Also, BaA-Sr adsorption was more excellent removal capacity of Sr in the seawater waste than distilled
본 연구에서는 방사성폐기물 처분장이 건설운영되고, 폐쇄 후 제도적 관리기간이 끝나게 되어 그 곳에 처분장이 존재한다 는 사실과 위해(hazard)의 정도가 잊혀 지면서 무의식적인(inadvertent) 처분장 인간침입이 일어날 경우 이를 어떻게 평가할 것인지에 대해 기..
concentration), 33 m (most probably radioactivity concentration), and 57 m (maximum radioactivity concentration ... did not vary with facility size (except 5 5 2 m size) due to the self-shielding of decontamination waste ... separation distances without cover soil for a 50 50 2 m size facility were evaluated as 14 m (minimum radioactivity
waste from a submerged transportation cask in the sea. ... transportation risk assessment code, and no research has been conducted to evaluate the release rate of radioactive
본 연구에서는 열분해잔사유(Pyrolysis Fuel Oil, PFO)를 이용한 Pitch계 활성탄소섬유를 제조하였다. 제조한 Pitch안정화 섬유의 탄화 및 활성화 온도를 850, 880, 900 ℃로 달리하여 각각 다른 샘플의 기공형성에 대한 영향을 알아보기 위해 ..
waste disposal facility. ... underground silo structure was the first stage of erecting the Gyeongju low-and-intermediate-level radioactive ... silo structure, 25 and 50 m in diameter and height, respectively, consists of cylindrical (for storing waste
waste from nuclear facilities. ... 전처리법으로 판단된다. 55Fe and 63Ni are key factors in deciding the proper handling of the decommissioning of radioactive ... For determining beta emitting radionuclides, the dismantled waste samples should be completely decomposed
soil waste stored for more than 10 years. ... for the electrokinetic remediation experiment to increase removal efficiency of Cs and Co from the radioactive
Chemical wastes containing small amounts of uranium can not be disposed of them after treatment as an ... industrial waste, because the uranium concentration in the final dry cake exceeds the exemption level
The cemented and paraffin wastes form which are incorporated the concentrated wastes, the cemented waste ... More hydrogen() gas was generated in the decontamination paper waste than in the other wastes, and the ... was generated in the cemented waste form incorporated a spent ion-exchange resin than in the other wastes