Fusion reactor radioactive materials and national waste management regulations

2004 ◽  
Vol 329-333 ◽  
pp. 1653-1658
Author(s):  
Massimo Zucchetti ◽  
Andrea Ciampichetti
2007 ◽  
pp. 69-79 ◽  
Author(s):  
S. Rosanvallon ◽  
O. Gastaldi ◽  
L. Di Pace ◽  
R. Pampin ◽  
G. Marbach

2007 ◽  
Vol 82 (15-24) ◽  
pp. 2850-2855 ◽  
Author(s):  
T. Hayashi ◽  
R. Kasada ◽  
K. Tobita ◽  
S. Nishio ◽  
T. Sawai ◽  
...  

2019 ◽  
Vol 24 ◽  
pp. 53
Author(s):  
A. Savidou ◽  
E. Ntalla ◽  
A. Chanousis

The Radioactive Materials Management Laboratory (RMML) was established in July 2013. The RMML is the sole laboratory in the country that holds the know-how in all the fields of radioactive waste management and decommissioning of nuclear facilities.The challenge for the Laboratory is the prospect of development of the Centralized Infrastructure of the country for Radioactive Waste at the NCSR D.


2000 ◽  
Vol 283-287 ◽  
pp. 1473-1477 ◽  
Author(s):  
Paolo Rocco ◽  
Massimo Zucchetti

Author(s):  
Vladan Ljubenov ◽  
Ernst Warnecke ◽  
Mark Hannan

This paper presents a summary of the recent, ongoing and planned safety related IAEA activities on planning, implementation and termination of decommissioning. Work related to the “Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management” and to the development of the international safety standards for decommissioning of facilities using radioactive materials is described. The IAEA activities on the technical assistance to the Member States in the development and review of decommissioning plans through national and international Technical Cooperation Programme projects and through other projects (FaSa project, R2D2P Project, decommissioning of the Iraq former nuclear complex) are presented. Recently established IAEA peer review services on decommissioning are addressed, as well as the international decommissioning forum.


Author(s):  
J. J. Balkey ◽  
S. S. Ramsey ◽  
R. E. Wieneke

Los Alamos National Laboratory (LANL) is one of two design laboratories in the United States Department of Energy’s (DOE) weapons complex, with over 60 years of experience in handling radioactive materials and, consequently, in radioactive waste management. The focus for actinide research and development is the Plutonium Facility, which has been in operation since 1978. The Nuclear Materials Technology (NMT) Division is responsible for operating the Plutonium Facility. It has a dedicated group of personnel who manage radioactive and hazardous waste, and address environmental regulations. Waste from operations with radioactive materials inside glovebox lines in the Plutonium Facility is packaged for disposal in the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. This waste is subject to a prescriptive certification program and is expensive to dispose of. Because the Plutonium Facility generates approximately 140 cubic meters of transuranic (TRU) waste each year, this significant financial burden effectively reduces the funds available to conduct research. To cut waste disposal costs, the NMT Division is making a considerable effort to identify and fund implementation of treatment and size-reduction processes. This study looks at both the effectiveness and probability of successful implementation. The waste management group’s waste minimization specialist has used waste generation information to identify the two largest TRU waste streams: combustible solids would benefit from size reduction, and nonactinide metals can be decontaminated. To reduce the size of combustible solids (polyethylene bottles and rubber hose), an industrial-model granulator, which was purchased for the head end of a molten salt oxidation process, is being adapted. This waste stream can be reduced by about 30% without affecting the ability to perform nuclear material assay. For glovebox decontamination, electrolytic decontamination techniques previously developed will also work on metals (tubing, tools, and equipment). Reducing the TRU levels to low-level contamination will allow onsite disposal, significantly reducing disposal costs (by approximately an order of magnitude). Several other technologies that were developed to address environmental regulatory concerns will also result in modest waste minimization and are in various states of installation and testing; they are vitrification for aqueous TRU waste, pyrolysis for the destruction of mixed waste, and distillation and recycle for nitric acid and trichloroethylene. The successful implementation and coordination of waste minimization and treatment technologies is resulting in cost savings from waste reduction and avoidance for the NMT Division.


Author(s):  
E. Ruedl ◽  
P. Schiller

The low Z metal aluminium is a potential matrix material for the first wall in fusion reactors. A drawback in the application of A1 is the rel= atively high amount of He produced in it under fusion reactor conditions. Knowledge about the behaviour of He during irradiation and deformation in Al, especially near the surface, is therefore important.Using the TEM we have studied Al disks of 3 mm diameter and 0.2 mm thickness, which were perforated at the centre by double jet polishing. These disks were bombarded at∽200°C to various doses with α-particles, impinging at any angle and energy up to 1.5 MeV at both surfaces. The details of the irradiations are described in Ref.1. Subsequent observation indicated that in such specimens uniformly distributed He-bubbles are formed near the surface in a layer several μm thick (Fig.1).After bombardment the disks were deformed at 20°C during observation by means of a tensile device in a Philips EM 300 microscope.


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