scholarly journals High level waste characterization in support of low level waste certification. I. HLW supernate radionuclide characterization

1994 ◽  
Author(s):  
M.E. Jamison ◽  
P.D. d`Entremont ◽  
J.S. Clemmons ◽  
C.E. Bess ◽  
D.F. Brown
Keyword(s):  
High Level Waste ◽  
Waste Characterization ◽  
Low Level ◽  
High Level

High-level Waste, Low-level Logic

1994 ◽  
Vol 50 (6) ◽  
pp. 40-45
Author(s):  
Kristin Shrader-Frechette
Keyword(s):  
High Level Waste ◽  
Low Level ◽  
High Level

Models and Strategies for Blending Nuclear Wastes to Minimize Immobilized Waste Volume

1995 ◽  
Vol 412 ◽  
Author(s):  
M. Hoza
Keyword(s):  
High Level Waste ◽  
Nuclear Wastes ◽  
Low Level ◽  
Wide Variability ◽  
Stable Glass ◽  
High Level ◽  
Tank Waste

AbstractHanford tank waste will be separated into high-level and low-level portions; each portion will then be vitrified to produce a stable glass form for disposal. Because of the wide variability in the tank waste compositions, blending is being considered as a way to reduce the number of distinct compositions that must be vitrified and to minimize the resultant volume of vitrified waste.This paper discusses several approaches to blending and models developed to formulate blends for each approach. The models produce optimized blends which minimize the volume of glass required such that all composition and property constraints on the glass are satisfied. The paper will discuss several blending strategies, and will provide the results of calculations comparing the approaches and strategies. Finally, an overall strategy for retrieving, blending, and vitrifying Hanford tank waste will be briefly discussed.Results of the calculations for high-level waste show that an effective blending strategy can greatly reduce the volume of glass required to immobilize the waste.

scholarly journals A Transport Code for Radiocolloid Migration: With an Assessment of an Actual Low-Level Waste Site

1984 ◽  
Vol 44 ◽  
Author(s):  
Bryan J. Travis ◽  
H. E. Nuttall
Keyword(s):  
High Level Waste ◽  
Waste Site ◽  
Low Level ◽  
Transport Code ◽  
Experimental Laboratory ◽  
Rapid Transport ◽  
High Level ◽  
Waste Repositories ◽  
Low Level Radioactive Waste

AbstractRecently, there is increased concern that radiocolloids may act as a rapid transport mechanism for the release of radionuclides from high-level waste repositories. The role of colloids is, however, controversial because the necessary data and assessment methodology have been limited. To quantitatively assess the role of colloids, the TRACR3D transport code has been enhanced by the addition of the population balance equations. The code was tested against the experimental laboratory column data of Avogadro et al. Next a low-level radioactive waste site was investigated to explore whether colloid migration could account for the unusually rapid transport of plutonium and americium observed. The nature and modeling of radiocolloids are discussed along with site simulation results from the TRACR3D code.

Treatment and Disposal of the Radioactive Graphite Waste

2010 ◽  
Author(s):  
Lifang Tian ◽  
Mingfen Wen ◽  
Jing Chen
Keyword(s):  
Radioactive Waste ◽  
Radioactive Contamination ◽  
Carbon Material ◽  
Advanced Technology ◽  
High Level Waste ◽  
Graphite Material ◽  
Low Level ◽  
Radioactive Graphite ◽  
High Level ◽  
Low Level Radioactive Waste

A large number of nuclear reactors with graphite as moderator and reflector material are facing to be decommissioned now or later, and the radioactive graphite waste is a large part of the involved wastes. In addition, high temperature gas-cooled reactors being developed rapidly use a large quantity of graphite material (up to 95%) in the nuclear fuel elements, besides graphite material as their moderator and reflector material in the reactor cores. Therefore, it is very critical to manage these graphite wastes from the decommissioned and being decommissioned reactors. The part with low-level radioactive contamination that could not be reused now, may be disposed of as solid waste to reduce its volume, and the possibility of its being retrieved and reused in the future with advanced technology should be considered. The other graphite waste with high-level radioactive contamination requires much more consideration. Due to several factors, such as its large quantity, a lack of available disposal sites and public acceptance, it may not be disposed of directly in the repository any more. An option may be the transformation of the high-level radioactive graphite waste into low-level radioactive waste through physical and chemical processes. The current technologies involve, e.g., thermal treatment to release 36Cl, capture of the 14C from the gases of incineration of carbon material and decomposition of carbon dioxide into solid carbon. After these treatments the carbon material might be decontaminated and separated as low-level radioactive waste and a small amount of residual high-level waste could be disposed of ultimately. In order to achieve a sustainable development of graphite material, the maximum utility and the minimal disposal of radioactive graphite should be considered in the management of radioactive graphite waste. It is urgent to explore new technologies for decontaminating and recycling radioactive graphite.

The Belgian R&D Feasibility Programme on the Geological Disposal of High-Level and Long-Lived Radioactive Waste

2013 ◽  
Author(s):  
Philippe Van Marcke ◽  
William Wacquier
Keyword(s):  
Radioactive Waste ◽  
High Level Waste ◽  
Reference Solution ◽  
Conceptual Level ◽  
Geological Disposal ◽  
Low Level ◽  
High Level ◽  
Term Management

ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, considers geological disposal in poorly indurated clay as the reference solution for the long-term management of high-level waste (HLW) and intermediate and low level waste, long-lived (ILLW-LL). The disposal concept entails the post-conditioning of the waste in disposal packages and the subsequent disposal of these packages in an underground repository. The R&D feasibility programme on geological disposal aims at demonstrating, at a conceptual level, that the proposed disposal system can be constructed, operated and closed.

Technologies for the containment, immobilization, and disposal of radioactive wastes

1989 ◽  
Vol 16 (4) ◽  
pp. 444-458 ◽  
Author(s):  
J. C. Tait ◽  
P. J. Hayward ◽  
J. S. Devgun
Keyword(s):  
Electrical Power ◽  
Radioactive Wastes ◽  
Radioactive Isotopes ◽  
High Level Waste ◽  
Technical Aspects ◽  
Geological Disposal ◽  
Low Level ◽  
High Level ◽  
Nuclear Fuel Waste ◽  
Canada Limited

Atomic Energy of Canada Limited is developing methods for the management and safe disposal of radioactive wastes. These wastes range from the highly radioactive (high-level) UO2 fuel arising from the nuclear generation of electrical power to the low- and intermediate-level wastes arising from research in various Canadian institutions using radioactive isotopes. This paper reviews the current research programs on materials and processes for the immobilization and containment of UO2 fuel wastes and the technical aspects of programs demonstrating the various technologies needed for implementing a disposal program for low-level wastes. Key words: waste management, radioactive, nuclear fuel waste, high-level waste, low-level waste, disposal, immobilization, glass, containment, siting, land burial, geological disposal.

The Buffering Mechanisms in Leaching of Composites of Cement with Radioactive Waste

1982 ◽  
Vol 15 ◽  
Author(s):  
Mary W. Barnes ◽  
Della M. Roy
Keyword(s):  
Radioactive Waste ◽  
High Level Waste ◽  
Low Level ◽  
High Level

Composites of cement and radioactive waste are being used for disposal of low level waste and may be used for high level waste. It is important to be able to predict their behavior in case of intrusion of leaching waters. The purpose of this paper is to determine the mechanisms of leaching of the cement and how the presence of radioactive waste components affects these mechanisms in composites.

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