Abstract:
본 발명은 제올라이트만을 이용한 염화염 폐기물(waste chloride salt)의 고정화 생성물 제조방법에 관한 것으로서, 보다 상세하게는 사용후 핵연료를 재처리하는 과정에서 발생하는 세슘(Cs), 스트론튬(Sr) 및 바륨(Ba) 등과 같은 알칼리 또는 알칼리 토금속족, 또는 세륨(Ce), 란타늄(La), 네오디늄(Nd), 이트륨(Y)과 같은 희토류계 방사성 핵종을 포함하는 염화염 폐기물과 제올라이트를 혼합하여 고정화 중간체를 제조하는 단계 및 상기 고정화 중간체를 Na계 소달라이트로 전이시키는 단계를 포함하는 제올라이트만을 이용한 염화염 폐기물의 고정화 생성물의 제조방법에 관한 것이다. 본 발명의 고정화 생성물은 보다 안정한 형태인 Na계 소달라이트로 되어 침출특성이 우수할 뿐만 아니라, 소달라이트로 전이를 시키는 과정에서 전이 촉진제 등을 첨가하지 않음으로써 그에 해당하는 양만큼의 최종 고화체(waste form)의 생성량을 줄임으로써 보다 효과적으로 염폐기물을 처리할 수 있게 한다. LiCl계 염폐기물, 제올라이트 NaA, 소달라이트, 고정화 생성물, 세슘, 스트론튬
Abstract:
PURPOSE: Provided are a process and an apparatus for cracking and decomposing a waste lubricant and generating hydrocarbon fuel gas having a low molecular weight, a low boiling point, and a high calorie by using electric arc. CONSTITUTION: The apparatus comprises: a storage container(10) to store the waste lubricant(11); a pump(15) to transfer the waste lubricant(11) from the storage container(10); a lower electrode stick(70) connected with the pump(15), which has a channel(75) to transfer the waste lubricant(11); an upper electrode stick(60) keeping a fixed interval(80) against the lower electrode stick(70), which generates the electric arc(90) with the lower electrode stick(70); a decomposing container(20) equipped with the upper and the lower electrode sticks(60)(70), which stores the waste lubricant effused to the interval(80) of the upper and the lower electrode sticks(60)(70), and has an outlet hole(21) to exhaust the hydrocarbon gas generated by the electric arc(90); a power supply and control means(50) to supply power to the electrode sticks(60)(70) and to control the power supply.
Abstract:
Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective layer and a fabrication method thereof. The nuclear fuel rod for fast reactors, that includes a surface treated metallic fuel slug and a cladding tube according to the present invention, has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the inter-diffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to an existing technique of using a functional material for preventing the inter-diffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors.
Abstract:
A solidification method of radioactive waste salt using a silica based inorganic material is provided to reduce the treatment volume of a final waste and to improve long-time treatment stability. A solidification method of radioactive waste salt using a silica based inorganic material includes the steps of: preparing the silica based inorganic material by heat-treating inorganic acids, a metallic mixture solved in water or alcohol, or a mixture thereof, and a tetraalkoxysilane compound; preparing a silica based reaction product by reacting the silica based inorganic material with the radioactive waste salt; and preparing silica concrete hardening material by mixing the silica based reaction product with the concrete hardening material.
Abstract:
A method for dechlorinating metal chlorides is provided to remove chlorine components from the metal chlorides effectively, by jetting activated brown gas to waste containing metal chlorides so as to transform the chlorine components contained in the waste into hydrogen chloride. A reactor(1) receives waste containing metal chlorides. A waste containing chlorine component is transformed into hydrogen chloride by jetting activated brown gas to the waste within the reactor. When the waste is contacted with the activated brown gas, the waste is preheated to a temperature of 400-1000°C to suppress the dispersion of dust. The hydrogen chloride is removed through a condenser(3), and remaining hydrogen chloride is neutralized with a caustic sodium liquid.
Abstract:
본 발명은 하기 화학식 1로 표시되는 칼릭스[4]아렌 디벤조 크라운에테르 화합물, 그의 제조방법 및 세슘 선택 이온교환체로서의 용도에 관한 것이다.
(상기 화학식 1에서 R 1 , R 2 및 n은 명세서에 정의한 바와 같다.) 상기 화학식 1의 칼릭스[4]아렌 디벤조 크라운에테르 화합물은 세슘이온(Cs + )을 선택적으로 우수하게 분리하는 작용을 하므로 방사성 폐기물을 처리할 때, 세슘 선택 이온교환체(selective ion exchanger)로 유용하게 사용될 수 있다.