Low-Level Waste Disposition in D&D: A Systems Engineered Approach

2003 ◽  
Author(s):  
Robert E. Prince ◽  
Dennis P. Ferrigno ◽  
Mark Kirshe
Keyword(s):  
Waste Management ◽  
Complex Systems ◽  
Nuclear Power ◽  
Research Reactor ◽  
Power Reactor ◽  
Lessons Learned ◽  
Nuclear Facilities ◽  
Nuclear Power Reactor ◽  
Waste Production ◽  
Key Factor

When approaching the decontamination and decommissioning (D&D) of a nuclear facility, the key elements of the project are the characterization, dismantlement execution, and the waste management (assay, packaging, transportation, and disposal) tasks. Waste management generally accounts for 40 to 45% of the total cost of the decommissioning project. This paper addresses an effective approach, based on demonstrated experience, to manage the dispostion alternatives for the decommissioning of waste materials. A systems engineered approach will minimize waste production and maximize efficiencies in the decommissioning schedule and offsite waste disposal. A key factor in this approach is to understand the disposal options and the staging criteria permitted within the specific applicable regulatory environment governing the decommissioning. For research reactor, nuclear power reactor, and other nuclear facilities involving complex systems, structures, and components, the key criteria and methodology of this systematic approach are applicable. Duratek has decommissioned numerous power reactor, research reactor, and industrial production facilities involving numerous complex systems and components. This paper focuses on the systems engineered approach, including applicable standards, waste streams, disposition alternatives, waste management methodologies, and lessons learned, for such decommissioning projects.

scholarly journals Decommissioning: a problem or a challenge?

2004 ◽  
Vol 19 (2) ◽  
pp. 65-73
Author(s):  
Irena Mele
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Waste Management ◽  
Nuclear Power ◽  
Research Reactor ◽  
Management Programme ◽  
Financial Resources ◽  
Uranium Mine ◽  
Nuclear Facility ◽  
Nuclear Facilities

With the ageing of nuclear facilities or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. To avoid such problems, future liailities should be thoroughly estimated in drawing up the decommissioning and waste management programme for each nuclear facility in time, and financial provisions for implementing such programme should be provided. In this paper a presentation of current decommissioning experience in Slovenia is given. The main problems and difficulties in decommissioning of the Zirovski Vrh Uranium Mine are exposed and the lesson learned from this case is presented. The preparation of the decommissioning programme for the Nuclear Power Plant Krsko is also described, and the situation at the TRIGA research reactor is briefly discussed.

Belgian Regulatory Framework for Decontamination and Decommissioning: Lessons Learned and New Initiatives

2013 ◽  
Author(s):  
Joris Creemers ◽  
Gilles Hermans ◽  
Virginie Schrayen ◽  
Frederik Van Wonterghem ◽  
An Wertelaers ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Regulatory Framework ◽  
Lessons Learned ◽  
Nuclear Facilities ◽  
Nuclear Power Reactor ◽  
Fuel Fabrication ◽  
Periodic Safety ◽  
Final Shutdown

Belgium can rely on significant experience in the field of decontamination and decommissioning of nuclear facilities. Several projects are ongoing and include research reactors (BR3, Thetis), uranium and MOX fuel fabrication plants (FBFC International, Belgonucleaire), fuel reprocessing facilities (Eurochemic) and radwaste processing facilities (Belgoprocess). Additional projects are expected in the coming years with the planned final shutdown of the oldest nuclear power reactor units. Two national authorities are involved in the decontamination and decommissioning process of nuclear facilities. The FANC (together with its subsidiary Bel V) is concerned for all matters related to nuclear safety and radiation protection, while NIRAS/ONDRAF is concerned for all matters related to radioactive waste and fuel management and financial provisions. These attributions ensure that all safety and material concerns are addressed and that both the licensees and the national authorities bear their own responsibilities. They rely on an existing regulatory framework covering both the procedural and the technical aspects of the decontamination and decommissioning activities. However, opportunities for regulatory improvement were raised after some recent events in Belgium, among which the bankruptcy of a nuclear company producing radioisotopes, involving numerous additional interested parties in a complex judiciary context. Amendments in the current regulations are considered to increase the prerogatives of the authorities regarding the management of radioactive waste by a licensee, the transfer of an operating license from an operator to another, and the general decommissioning strategy of a facility. Furthermore, a dedicated “waste and decommissioning” working group within WENRA defined new reference levels applying to the decontamination and decommissioning of nuclear facilities. Belgium committed to include these requirements explicitly in its national legislation, even though most of them were already included in the existing decommissioning authorizations. Amendments will cover the safety provisions inherent to the decontamination and decommissioning phase, such as the decommissioning strategy, the qualification of techniques, the experience feedback valorization, the periodic safety reviews, the radioactive waste management, or the final characterization of the sites. Additionally, requirements regarding the authorization process will be detailed, such as the content of the licensee’s application file or the structure of the safety report covering the decontamination and decommissioning phase. These changes will contribute to a more secure regulatory framework for all interested parties.

SANICRO 71

Alloy Digest ◽  
1965 ◽  
Vol 14 (12) ◽  
Keyword(s):  
Nuclear Power ◽  
Elevated Temperatures ◽  
Power Reactor ◽  
Base Alloy ◽  
Heat Treating ◽  
Good Resistance ◽  
Nuclear Power Reactor ◽  
Temperature Performance ◽  
Resistance To Stress ◽  
Nickel Base

Abstract Sanicro 71 is a nickel-base alloy having good resistance to stress-corrosion, oxidation and creep at elevated temperatures. It is recommended for nuclear power reactor heat exchanger tubes, aircraft turbojet engines and for equipment in the textile, plastic, and chemical industries. This datasheet provides information on composition, physical properties, hardness, elasticity, and tensile properties. It also includes information on high temperature performance and corrosion resistance as well as forming, heat treating, machining, joining, and surface treatment. Filing Code: Ni-108. Producer or source: Sandvik.

Visualization of Supercritical Carbondioxide Pseudo-Boiling Inside a Rectangular Channel

2001 ◽  
Author(s):  
K. Sakurai ◽  
H. S. Ko ◽  
K. Okamoto ◽  
H. Madarame
Keyword(s):  
Forced Convection ◽  
Supercritical Fluids ◽  
Nuclear Power ◽  
Power Reactor ◽  
Rectangular Channel ◽  
Visual Observation ◽  
Next Generation ◽  
Nuclear Power Reactor

Abstract The characteristics of the supercritical fluids should be precisely investigated for the next generation nuclear power reactor, i.e., Super-critical water Cooled Reactor (SCR). There are few experiments for visual observation especially in forced convection, because of the difficulty of the experiment.

On the Shape of Stress Corrosion Cracks in Water-Cooled Nuclear Power Reactor Piping

2013 ◽  
Vol 50 (30) ◽  
pp. 27-39 ◽  
Author(s):  
S.-K. Lee ◽  
D. Kramer ◽  
D. D. Macdonald
Keyword(s):  
Stress Corrosion ◽  
Nuclear Power ◽  
Power Reactor ◽  
Nuclear Power Reactor
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