In this study, we compared the activity of dry active waste predicted using the generated waste data ... and that measured for the accepted waste in the disposal facility. ... For very low level waste, the measured activity was higher than the predicted activity for 137Cs, 90Sr
Waste(LILW) disposal facility, the calculation result by the GENII code was assessed using the RESRAD ... evaluation and analysis of the human intrusion scenario of the Gyeongju Low and Intermediate Level Radioactive
waste vitrification plant. ... were newly introduced to the high temperature filter(HTF) system in thelow- and intermediate-level radioactive ... not evidences of corrosion but the deposition of sodium, sulfur and silicacompounds volatilized from waste
Waste Management Corporation (KRMC) was performed to examine the contribution of each radiation source ... radiation shielding analysis for a Burnup-credit (BUC) cask designed under the management of Korea Radioactive
waste packages and disposal container, a buffer zone, and a concrete lining zone. ... 사일로를 다중방벽개념으로 고려하여 사일로를 구성하는 3개의 특성지역 (waste, buffer, concrete)으로 구분하여 해석하였고, EDZ는 사 일로 주변과 건설운영 터널 주변의 ... The model considers each silo as an engineered barrier system (EBS) consisting of a waste zone comprising
waste because of their high solubilities and the existence of anionic species in natural water. ... fission products 79Se and 99Tc have been considered as the major concern nuclides for the disposal of radioactive
본 연구에서는 사용후핵연료 회수성과 처분밀도를 향상시킨 새로운 CANDU 사용후핵 연료처분시스템의 열해석을 수행하였다. 제안된 CANDU 사용후핵연료 처분방식 에서는 사용후핵연료의 회수성을 향상시키기 위해 일정 기간 동안 터널에 자연대류를 이용하여 저장하며, 처분밀도 ..
본 연구에서는 KURT (KAERI 지하처분연구시설)를 포함한 지하연구시설에서 핵종 및 콜로이드 이동에 대 한 연구현황을 조사하였다. 화강암과 같은 결정질 암반층에 건설된 해외 지하연구시설들을 간략하게 소개하 고 비교하였다. 특히 Grimsel Test Site (GT..
waste repository was performed as a function of the pH and the ionic strength. ... bentonite colloid generated from Gyeongju bentonite which is a potential buffer material in a high-level radioactive