Characterization of Glass Melts Containing Simulated Low and Intermediate Level Radioactive Waste

2006 ◽  
Vol 43 (3) ◽  
pp. 148-151
Keyword(s):  
Radioactive Waste ◽  
Intermediate Level ◽  
Glass Melts ◽  
Intermediate Level Radioactive Waste

scholarly journals SiLiF Neutron Counters to Monitor Nuclear Materials in the MICADO Project

Sensors ◽  
2021 ◽  
Vol 21 (8) ◽  
pp. 2630
Author(s):  
Luigi Cosentino ◽  
Quentin Ducasse ◽  
Martina Giuffrida ◽  
Sergio Lo Meo ◽  
Fabio Longhitano ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Detector Response ◽  
Nuclear Materials ◽  
Spent Fuel ◽  
Neutron Detectors ◽  
Intermediate Level Radioactive Waste ◽  
Eu Project ◽  
Interim Storage ◽  
Waste Drums

In the framework of the MICADO (Measurement and Instrumentation for Cleaning And Decommissioning Operations) European Union (EU) project, aimed at the full digitization of low- and intermediate-level radioactive waste management, a set of 32 solid state thermal neutron detectors named SiLiF has been built and characterized. MICADO encompasses a complete active and passive characterization of the radwaste drums with neutrons and gamma rays, followed by a longer-term monitoring phase. The SiLiF detectors are suitable for the monitoring of nuclear materials and can be used around radioactive waste drums possibly containing small quantities of actinides, as well as around spent fuel casks in interim storage or during transportation. Suitable polyethylene moderators can be exploited to better shape the detector response to the expected neutron spectrum, according to Monte Carlo simulations that were performed. These detectors were extensively tested with an AmBe neutron source, and the results show a quite uniform and reproducible behavior.

scholarly journals Qualification of the activities measured by gamma spectrometry on unitary items of intermediate-level radioactive waste from particle accelerators

2021 ◽  
Vol 167 ◽  
pp. 109431
Author(s):  
Patrycja Dyrcz ◽  
Thomas Frosio ◽  
Nabil Menaa ◽  
Matteo Magistris ◽  
Chris Theis
Keyword(s):  
Radioactive Waste ◽  
Gamma Spectrometry ◽  
Intermediate Level ◽  
Particle Accelerators ◽  
Intermediate Level Radioactive Waste

An Integrated Safety Assessment System for Near-Surface Disposal of Low- and Intermediate-Level Radioactive Waste in Korea

2003 ◽  
Author(s):  
JooWan Park ◽  
Chang-Lak Kim ◽  
Jin Beak Park ◽  
Eun Yong Lee ◽  
Youn Myoung Lee ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Safety Assessment ◽  
Assessment System ◽  
Intermediate Level ◽  
Radioactive Waste Disposal ◽  
System Level ◽  
Assessment Methodology ◽  
Regulatory Requirements ◽  
Near Surface ◽  
Intermediate Level Radioactive Waste

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.

Measurement Methodology for Fulfilling of Waste Acceptance Criteria for Low and Intermediate Level Radioactive Waste in Storages

2011 ◽  
Author(s):  
M. Sokcic-Kostic ◽  
F. Langer ◽  
R. Schultheis
Keyword(s):  
Radioactive Waste ◽  
Waste Treatment ◽  
Storage Period ◽  
Intermediate Level ◽  
Acceptance Criteria ◽  
Waste Storage ◽  
Measurement Methodology ◽  
Treatment Facilities ◽  
Intermediate Level Radioactive Waste ◽  
Radioactive Waste Storage

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.

Commercialization Project of Ulchin Vitrification

2010 ◽  
Author(s):  
Hyun-Jun Jo ◽  
Cheon-Woo Kim ◽  
Tae-Won Hwang
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Cold Test ◽  
Intermediate Level ◽  
Performance Tests ◽  
Cold Crucible ◽  
Commercial Operation ◽  
Intermediate Level Radioactive Waste ◽  
Hot Test

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.

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 ◽  
...  
Keyword(s):  
Correlation Analysis ◽  
Radioactive Waste ◽  
Intermediate Level ◽  
Outlier Identification ◽  
Intermediate Level Radioactive Waste

The Korean Final Repository for Low- and Intermediate-Level Radioactive Waste

2007 ◽  
Author(s):  
Young-Ki Kim ◽  
Kwang-Hoon Koh ◽  
Sang-Sun Lee ◽  
Gi-Won Choi ◽  
Byung-Sik Lee ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Primary Objective ◽  
Intermediate Level ◽  
Concrete Lining ◽  
Radioactive Nuclide ◽  
Ground Water Flow ◽  
Intermediate Level Radioactive Waste ◽  
In The Beginning ◽  
Rock Supports ◽  
Tunnel System

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.

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