35 Years of Incineration in Studsvik: Lessons Learned and Recent Modifications and Improvements

Author(s):  
Maria Lindberg ◽  
Joakim Lo¨vstrand ◽  
Karin von Kronhelm

Since the incinerator in Studsvik was taken into operation in 1976 it has been operating at a level of 350–500 tonnes per year. The incinerator treats waste from both the nuclear industry and from other sectors generating radioactive waste such as hospitals, research companies/facilities and academic institutions. The incineration facility has been upgraded several times during its lifetime. The upgrades includes, change of off gas treatment as well as new control systems and currently the commissioning of a sister pyrolysis plant. Several new waste streams have also been approved for treatment in the last few years.

2021 ◽  
Vol 8 (6) ◽  
pp. 619-640
Author(s):  
George Sikun Xu ◽  
◽  
Nicholas Chan ◽  

<abstract> <p>A large number of artificial-origin radionuclides from irradiation in small reactors and/or nuclear reactions in accelerators are currently used in non-nuclear industries such as education, oil and gas, consumer merchandise, research, and medicine. Radioactive wastes from the use of these radionuclides in non-nuclear industries include expired sealed radioactive sources, biological materials, radionuclide-containing chemicals, contaminated equipment, and very small quantities of used nuclear fuel. Although being less challenging and complex than nuclear energy production and research waste streams, these wastes are subject to the common nuclear regulations by the Canadian Nuclear Safety Commission, and are managed following domestic and international standards and guidelines made by the Canadian Standards Association, International Atomic Energy Agency, and International Organization for Standardization. Management practices used in the nuclear industry in Canada are commonly applied to the non-nuclear industry radioactive waste streams, such as waste handling, treatment, packaging, storage, transportation, clearance and exemptions, and disposal. The half-lives of radionuclides in non‑nuclear applications range from hours to thousands of years, and their activities in non-nuclear industrial applications can be as low as their clearance level or as high as the upper limits for intermediate level radioactive waste. Waste containing only short half-life radionuclides is placed in temporary storage to allow decay, and then is cleared and disposed of through non-radioactive waste routes. Non‑clearable waste materials are treated, consolidated, and managed along with radioactive waste generated from the nuclear industries at designated radioactive waste management sites.</p> </abstract>


Author(s):  
Pierre Cnapelinckx ◽  
Fanny Castillo

Projects Decommissioning of nuclear installations constitutes an important challenge and shall prove to the public that the whole nuclear life cycle is fully mastered by the nuclear industry. When ceasing operation, nuclear installations owners and operators are looking for solutions in order to assess and keep decommissioning costs at a reasonable level, to fully characterize waste streams (in particular radiological inventories of difficult-to-measure radionuclides) and to reduce personnel exposure during the decommissioning activities taking into account several project, site and country specific constraints. In response to this need, Tractebel Engineering has developed IDEA (Integrated DEcommissioning Application), an integrated set of computer tools, to support the engineering activities to be carried out in the frame of a decommissioning project. IDEA provides optimized solutions from an economical, environmental, social and safety perspective. IDEA is based on the integration of the following computer tools: LLWAA-DECOM, VISIMODELLER/VISIPLAN and DBS. The LLWAA-DECOM module has been developed for the radiological characterization of contaminated systems and equipment. The module constitutes a specific part of more general software that was originally developed to characterize NPP radioactive waste streams in order to assist the Operators when declaring the radiological inventory of critical nuclides, in particular difficult-to-measure radionuclides, to the Authorities. In the case of LLWAA-DECOM, deposited activities inside contaminated equipment (piping, tanks, heat exchangers ...) and scaling factors between nuclides, at any given time of the decommissioning time schedule, are calculated on the basis of physical characteristics of the systems and of operational parameters of the nuclear power plant. The VISIMODELLER tool, a user friendly CAD interface developed to ease the introduction of lay-out areas in a software named VISIPLAN. VISIPLAN is a 3D dose rate assessment tool for ALARA work planning, developed by the Belgian Nuclear Research Centre SCK•CEN. The DBS computer tool has been developed to manage the different kinds of activities that are part of the general time schedule of a decommissioning project. For each activity, when relevant, algorithms allow to estimate, on the basis of local inputs, radiological exposures of the operators (collective and individual doses), production of primary, secondary and tertiary waste and their characterization, production of conditioned waste, release of effluents, ... and enable the calculation and the presentation (histograms) of the global results for all activities together. Based on design and operating data from the Nuclear Power Plant to be dismantled and on the specificities of the country regarding radioactive waste management and disposal routes, IDEA will enable to prepare and manage a decommissioning project, in a sustainable way, leading to a greenfield or a reuse of the nuclear site after decommissioning of the plant. Moreover thanks to the characterization and definition of the optimal waste treatment and conditioning techniques, IDEA contributes to the long term safe management of the radioactive waste.


2021 ◽  
Author(s):  
Sidnei Guerreiro Da Silva ◽  
Andre Athayde Gonçalves ◽  
William Albuquerque Da Silva ◽  
Rafael Di Lorenzo Filho

Abstract The characteristics of Pre-Salt carbonate reservoirs demand downhole chemical injection to prevent scale, asphaltene, and wax deposits, besides the need of H2S scavenger, and MEG, normally injected at Xmas tree (WCT). The poor performance of injection systems installed in Santos Basin, together with production risks associated to the lack of chemical injection, led the project team to re-evaluate design requirements, such as chemical products characteristics, production systems equipments, umbilicals, and chemical injection valves. In addition, umbilical failures are being observed in other deep-water fields, related to subsea control systems functions. This paper focuses on Company operational experience and lessons learned related to umbilicals and downhole chemical injection.


Author(s):  
Kenneth R. Butts ◽  
Ravi Rangan ◽  
Mark Jennings ◽  
Gail Cheng

Model-based product development methodologies are becoming more widely used by developers of automotive embedded control systems. This paper presents a model repository intended to provide configuration management, reuse, and sharing infrastructure in support of this trend. An initial set of repository requirements is presented and then augmented with lessons-learned from a pilot realization of the system. This pilot realization is discussed with respect to implementation and application. A repository data model is also described.


Author(s):  
Jan Deckers ◽  
Rik Vanbrabant ◽  
Ronald Womack ◽  
Mark Shuey

Abstract Worldwide a great deal of the low and medium radioactive waste inventory is mixed with hazardous wastes and different non-combustibles. The path to treating these wastes historically has been to sort combustibles from non-combustibles and process them separately through incineration, supercompaction, cementation or other encapsulating technologies. Special attention has to be taken due to the presence of hazardous constituents. The cost and health physics exposure for sorting these types of mixed wastes and treating the separated streams in specialized infrastructure is not optimal and leaves a great potential for further optimization. After several years of development, a commercially available high temperature treatment system has been developed and installed that treats heterogeneous low-level radioactive waste. High temperature plasma processing and unique torch design and operating features make it feasible to achieve a volume reduced, permanent, high integrity waste form while eliminating the personnel exposure and cost associated with sorting, characterizing and handling. Plasma technology can also be used to recondition previous conditioned waste packages that don’t meet any longer the present acceptance criteria for final disposal. Plasma treatment can result in many cases in a substantial volume reduction, lowering the final disposal costs. This paper covers the unique plasma centrifugal treatment principles and history. It also explains the roles of international partners that blend plasma, off gas treatment and nuclear expertise into one “best developed and available technology” (BDAT) for the treatment of problematic wastes.


Energies ◽  
2020 ◽  
Vol 13 (18) ◽  
pp. 4638
Author(s):  
Leon Fuks ◽  
Irena Herdzik-Koniecko ◽  
Katarzyna Kiegiel ◽  
Grazyna Zakrzewska-Koltuniewicz

Since the beginning of the nuclear industry, graphite has been widely used as a moderator and reflector of neutrons in nuclear power reactors. Some reactors are relatively old and have already been shut down. As a result, a large amount of irradiated graphite has been generated. Although several thousand papers in the International Nuclear Information Service (INIS) database have discussed the management of radioactive waste containing graphite, knowledge of this problem is not common. The aim of the paper is to present the current status of the methods used in different countries to manage graphite-containing radioactive waste. Attention has been paid to the methods of handling spent TRISO fuel after its discharge from high-temperature gas-cooled reactors (HTGR) reactors.


Author(s):  
Ulrich Quade ◽  
Thomas Kluth

Since more than 20 years the company Siempelkamp is deeply involved in the field of melting and recycling of radioactively contaminated metals from operation and decommissioning of nuclear installations across Europe. The experience of this long period shows clearly that only a combination of recycling inside the nuclear industry and release for reuse outside the nuclear market will generate the optimum results for the minimisation of radioactive waste volume. Final disposal volume is becoming more and more the status of an own resource within our nuclear business and should be handled very carefully in the future. The paper gives a compact overview about the impressive results of melting treatment, the current potential of the melting plant CARLA and about further developments.


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