State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants

Abstract Minimizing the volume of radioactive waste generated during dismantling of nuclear power plants is a matter of great importance. In Japan waste forms buried in shallow burial disposal facility as low level radioactive waste (LLW) must be solidified by cement with adequate strength and must extend no harmful openings. The authors have developed an improved method to minimize radioactive waste volume by utilizing radioactive concrete and metal for mortar to fill openings in waste forms. Performance of a method to pre-place large sized metal or concrete waste and to fill mortar using small sized metal or concrete was tested. It was seen that the improved method substantially increases the filling ratio, thereby decreasing the numbers of waste containers.

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Planning of Large-Scale In-Situ Gas Generation Experiment in Korean Radioactive Waste Repository

ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management, Volume 1 ◽

10.1115/icem2010-40020 ◽

2010 ◽

Cited By ~ 2

Author(s):

Juyoul Kim ◽

Sukhoon Kim ◽

Jin Beak Park ◽

Sunjoung Lee

Keyword(s):

Radioactive Waste ◽

Nuclear Power ◽

Power Plants ◽

Nuclear Power Plants ◽

Large Scale ◽

Radioactive Waste Disposal ◽

Gas Generation ◽

Radioactive Waste Repository ◽

Waste Repository

In the Korean LILW (Low- and Intermediate-Level radioactive Waste) repository at Gyeongju city, the degradation of organic wastes and the corrosion of metallic wastes and steel containers would be important processes that affect repository geochemistry, speciation and transport of radionuclides during the lifetime of a radioactive waste disposal facility. Gas is generated in association with these processes and has the potential threat to pressurize the repository, which can promote the transport of groundwater and gas, and consequently radionuclide transport. Microbial activity plays an important role in organic degradation, corrosion and gas generation through the mediation of reduction-oxidation reactions. The Korean research project on gas generation is being performed by Korea Radioactive Waste Management Corporation (hereafter referred to as “KRMC”). A full-scale in-situ experiment will form a central part of the project, where gas generation in real radioactive low-level maintenance waste from nuclear power plants will be done as an in-depth study during ten years at least. In order to examine gas generation issues from an LILW repository which is being constructed and will be completed by the end of December, 2012, two large-scale facilities for the gas generation experiment will be established, each equipped with a concrete container carrying on 16 drums of 200 L and 9 drums of 320 L of LILW from Korean nuclear power plants. Each container will be enclosed within a gas-tight and acid-proof steel tank. The experiment facility will be fully filled with ground water that provides representative geochemical conditions and microbial inoculation in the near field of repository. In the experiment, the design includes long-term monitoring and analyses for the rate and composition of gas generated, and aqueous geochemistry and microbe populations present at various locations through on-line analyzers and manual periodical sampling. A main schedule for establishing the experiment facility is as follows: Completion of the detailed design until the second quarter of the year 2010; Completion of the manufacture and on-site installation until the second quarter of the year 2011; Start of the operation and monitoring from the third quarter of the year 2011.

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Carbon-14 in Low-level Radioactive Waste From Two Nuclear Power Plants

Health Physics ◽

10.1097/00004032-198601000-00004 ◽

1986 ◽

Vol 50 (1) ◽

pp. 57-64 ◽

Cited By ~ 14

Author(s):

J. E. Martin

Keyword(s):

Radioactive Waste ◽

Nuclear Power ◽

Power Plants ◽

Nuclear Power Plants ◽

Low Level ◽

Carbon 14 ◽

Low Level Radioactive Waste

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Optimization of Concrete Container Composition in Radioactive Waste Management

MRS Proceedings ◽

10.1557/proc-50-469 ◽

1985 ◽

Vol 50 ◽

Author(s):

I. B. Plecas ◽

Li. L. Mihajlovic ◽

A. M. Kostadinovic

Keyword(s):

Mechanical Properties ◽

Radioactive Waste ◽

Waste Management ◽

Nuclear Power ◽

Power Plants ◽

Nuclear Power Plants ◽

Leakage Rate ◽

Intermediate Level ◽

Radioactive Waste Management ◽

Intermediate Level Radioactive Waste

AbstractIn this paper an optimization of concrete container composition, used for storing low and intermediate level radioactive waste from nuclear power plants in Yugoslavia, is presented.Mechanical properties 37−52 MPa, permeability 1.07. 10−13 - 1.50. 10−11cm2 and leakage rate 3.66. 10−6 - 1.77. 10−4 cm/d for concrete made of commercial materials, were tested.

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