A radionuclide outlier identification and correlation analysis on low- and intermediate-level radioactive waste

2021 ◽  
Vol 151 ◽  
pp. 107947
Author(s):  
Sung-Chan Jang ◽  
Hyunjong Woo ◽  
Jeong-Guk Kim ◽  
Dong-Ju Lee ◽  
Il-Sik Kang ◽  
...  
Author(s):  
JooWan Park ◽  
Chang-Lak Kim ◽  
Jin Beak Park ◽  
Eun Yong Lee ◽  
Youn Myoung Lee ◽  
...  

An integrated safety assessment system to be used for evaluation of near-surface disposal concept has been developed within the framework of safety assessment methodology taken for low- and intermediate-level radioactive waste disposal in Korea. It is to provide an evaluation of the safety of the disposal system in a clear, comprehensive and well-documented manner, and to integrate the results into a defensible package showing reasonable assurance of compliance with regulatory requirements for licensing application. This system is made up of two key components, a system-level safety assessment code and an input database/quality assurance module for safety assessment, which both are interfaced with each other.


Author(s):  
M. Sokcic-Kostic ◽  
F. Langer ◽  
R. Schultheis

Low and intermediate level radioactive waste must be sorted and treated before it can be sent to radioactive waste storage. The waste must fulfil an extensive amount of acceptance criteria (WAC) to guarantee a safe storage period. NUKEM Technologies has a broad experience with the building and management of radioactive waste treatment facilities and has developed methods and equipment to produce the waste packages and to gather all the required information.


Author(s):  
Hyun-Jun Jo ◽  
Cheon-Woo Kim ◽  
Tae-Won Hwang

The Ulchin Vitrification Facility (UVF), to be used for the vitirification of low- and intermediate-level radioactive waste (LILW) generated by nuclear power plants (NPPs), is the world’s first commercial facility using Cold Crucible Induction Melter (CCIM) technology. The construction of the facility was begun in 2005 and was completed in 2007. From December 2007 to September 2009, all key performance tests, such as the system functional test, the cold test, the hot test, and the real waste test, were successfully carried out. The UVF commenced commercial operation in October 2009 for the vitrification of radioactive waste.


Author(s):  
Young-Ki Kim ◽  
Kwang-Hoon Koh ◽  
Sang-Sun Lee ◽  
Gi-Won Choi ◽  
Byung-Sik Lee ◽  
...  

The underground waste repository site is located at Gyeongju and is selected for the disposal of all the Low- and Intermediate-Level Radioactive Waste (LILW). Its operation is scheduled in the beginning of 2009. The repository, with a disposal capacity of 800,000 drums, will be constructed in granite bedrock near the seashore at the Gyeongju site. The repository will be constructed in phases to reach its final capacity of 800,000 drums. In the first phase of construction, the repository will have a capacity to dispose of 100,000 drums. The first phase of the repository design consists of an access shaft, a construction tunnel, an operating tunnel, an unloading tunnel, and six (6) silos. The silos are located at 80 to 130 meters below Mean Sea Level (MSL), in bedrock. Each silo is 24.8m in diameter and 52.4m in height. The silo will be reinforced with shotcrete, rockbolts and concrete lining for rock supports, and the lining will also act as an engineered barrier to limit radioactive nuclide release after closure. After serving its intended function the repository will be backfilled and sealed. The primary objective of backfilling and sealing is to prevent ground-water flow into the silos through the tunnel system and to prevent inadvertent intrusion into the repository after closure.


1994 ◽  
Vol 353 ◽  
Author(s):  
A. V. Chambers

AbstractIt is currently proposed to site the UK repository for intermediate-level radioactive waste (ILW) underground at a depth of several hundred metres, and to use a cementitious backfill to fill spaces between disposal packages within the repository vaults. Flow of water through the repository could be concentrated within cracks that may form in the backfill. This paper describes the CRACK and CRACK2 computer programs. These are used to predict radionuclide release via cracks, and radionuclide distributions within the vault. The programs are applied to an assessment of the release of inventory- and solubility-limited radionuclides from hypothetical ILW vaults. Calculations are reported for different densities of cracking, and for different repository designs, and the dominant modes of transport within cracks in repository vaults are discussed.


Sign in / Sign up

Export Citation Format

Share Document