The microbial ecology of land and water contaminated with radioactive waste: towards the development of bioremediation options for the nuclear industry

2012 ◽  
pp. 226-241 ◽  
Author(s):  
Andrea Geissler ◽  
Sonja Selenska-Pobell ◽  
Katherine Morris ◽  
Ian T. Burke ◽  
Francis R. Livens ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Microbial Ecology ◽  
Nuclear Industry

scholarly journals Management of Radioactive Waste Containing Graphite: Overview of Methods

Energies ◽  
2020 ◽  
Vol 13 (18) ◽  
pp. 4638
Author(s):  
Leon Fuks ◽  
Irena Herdzik-Koniecko ◽  
Katarzyna Kiegiel ◽  
Grazyna Zakrzewska-Koltuniewicz
Keyword(s):  
High Temperature ◽  
Radioactive Waste ◽  
Nuclear Power ◽  
Information Service ◽  
Nuclear Industry ◽  
Current Status ◽  
Triso Fuel ◽  
Irradiated Graphite ◽  
High Temperature Gas

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.

Waste Minimization by Melting–Recycling of Radioactive Metals: 20 Years Operation of the Melting Plant CARLA by Siempelkamp Nukleartechnik GmbH

2011 ◽  
Author(s):  
Ulrich Quade ◽  
Thomas Kluth
Keyword(s):  
Radioactive Waste ◽  
Nuclear Industry ◽  
Waste Minimization ◽  
Final Disposal ◽  
Long Period ◽  
The Future ◽  
The Status ◽  
Current Potential

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.

scholarly journals Management of radioactive waste from application of radioactive materials and small reactors in non-nuclear industries in Canada and the implications for their new application in the future

2021 ◽  
Vol 8 (6) ◽  
pp. 619-640
Author(s):  
George Sikun Xu ◽  
◽  
Nicholas Chan ◽  
Keyword(s):  
Radioactive Waste ◽  
Management Practices ◽  
Oil And Gas ◽  
Nuclear Reactions ◽  
Industrial Applications ◽  
Nuclear Industry ◽  
International Standards ◽  
Waste Streams ◽  
Energy Agency ◽  
Intermediate Level Radioactive Waste

<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>

Norwegian Support in Development of Regulations of Radioactive Waste Management in Central Asia-Threat Assessment

2010 ◽  
Author(s):  
Tamara Zhunussova ◽  
Malgorzata Sneve ◽  
Astrid Liland ◽  
Alexander Kim ◽  
Ulmas Mirsaidov ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Central Asia ◽  
Liquid Radioactive Waste ◽  
Management Strategies ◽  
Threat Assessment ◽  
Nuclear Industry ◽  
Industrial Complex ◽  
Radioactive Waste Management ◽  
Potential Health

In Central Asia (CA) the radioactive waste comes mainly from uranium mining and milling, nuclear weapon testing and nuclear power development and other ionizing sources. This waste was produced, to a greater extent, by the military-industrial complex and the uranium and non-uranium industry, and, to a lesser extent, by the nuclear industry and in the process of use of isotope products. Exploitation and mining of uranium and thorium deposits produce a large amount of solid and liquid radioactive waste, as well volatile contaminants which need a proper management. In Central Asia the wastes are mainly stored at the surface in large piles and represent a long-term potential health and environmental hazard. The process of remediating legacy sites of the past and reducing the threats is now getting under way, with the design and implementation of remediation activities, partly with international support. However, there is a significant lack in the regulatory basis for carrying out such remediation work, including a lack of relevant radiation and environmental safety norms and standards, licensing procedures and requirements for monitoring etc., as well as expertise to transform such a basis into practice. Accordingly, the objective of the proposed project is to assist the relevant regulatory authorities in Kazakhstan, Kirgizstan and Tajikistan to develop national robust and adequate regulations and procedures, taking into account the international guidance and Norwegian experience with regulatory support projects in Russia. Specific expected results in the project period include: a threat assessment report identifying priority areas for regulatory development, based on the status of current regulatory documents and the hazard presented by the different sites and facilities; development of national radioactive waste management strategies in each country; development of an enhanced regulatory framework for supervision of nuclear matters, and an enhanced safety culture.

Practical Implementation of National Clearance Levels at Dounreay

2003 ◽  
Author(s):  
Paul McClelland ◽  
Frank Dennis ◽  
Mark Liddiard
Keyword(s):  
Public Relations ◽  
Radioactive Waste ◽  
Waste Management ◽  
Radioactive Wastes ◽  
Nuclear Industry ◽  
Radioactive Waste Disposal ◽  
Radioactive Material ◽  
Practical Implementation ◽  
Nuclear Site ◽  
Regulatory Controls

Clearance is a very important part of any effective waste management strategy for both operating and decommissioning nuclear facilities. Radioactive waste disposal capacity is becoming an increasingly valuable resource and costs for disposal of radioactive wastes continue to dramatically rise. Considerable cost savings may be realised by efficient segregation of essentially non-radioactive material from radioactive wastes. The release of these materials from licensed nuclear sites for disposal, reuse or recycle without further regulatory controls is commonly referred to by the nuclear industry as “clearance”. Although much effort has been directed at establishing national clearance levels, below which, materials may be released without further regulatory controls, there is little practical guidance regarding implementation into local waste management programmes. Compliance with regulatory clearance limits is a relatively straightforward technical exercise involving appropriate management control and monitoring of the material. Whilst this is sufficient to avoid prosecution for breach of regulatory requirements, it is not sufficient to avoid a myriad of political and public relations land mines. When material is unconditionally released, unless additional attention is given to management of its future destination off-site, it may end up anywhere. The worst nightmare for a waste manager at a nuclear site is headlines in local and national newspapers such as, “RADIOACTIVE WASTE DISPOSED IN LOCAL MUNICIPAL LANDFILL,” or, “RADIOACTIVE WASTE USED AS CONSTRUCTION MATERIAL FOR CHILDRENS PLAYGROUND,” etc. Even if the material were released legally, the cost of recovering from such a situation is potentially very large, and such public relations disasters could threaten to end the clearance programme at the given site, if not nationally. This paper describes how national regulatory clearance levels have been implemented for the decommissioning of the Dounreay nuclear site in the far north of Scotland. It specifically focuses on the management of public relations aspects of clearance in order to limit the exposure to non-regulatory pressures and liabilities associated with clearance programmes from nuclear sites. The issues are put into context for uncontaminated wastes, trace contaminated wastes and management of contaminated land.

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

2011 ◽  
Author(s):  
Maria Lindberg ◽  
Joakim Lo¨vstrand ◽  
Karin von Kronhelm
Keyword(s):  
Radioactive Waste ◽  
Control Systems ◽  
Lessons Learned ◽  
Nuclear Industry ◽  
Academic Institutions ◽  
Waste Streams ◽  
Gas Treatment

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.

Treatment of Spent Ion Exchange Resins in Nuclear Industry

2017 ◽  
Vol 6 (3) ◽  
pp. 42-47
Author(s):  
А. Строкин ◽  
A. Strokin ◽  
А. Валов ◽  
A. Valov
Keyword(s):  
Ion Exchange ◽  
Radioactive Waste ◽  
Cost Reduction ◽  
Liquid Radioactive Waste ◽  
Nuclear Industry ◽  
Ion Exchange Resins ◽  
Domestic Technology ◽  
Exchange Resins ◽  
And Storage

This work is devoted to development of domestic technology for ion exchange resins treatment (conditioning) in the nuclear industry. In the work has been carried out the analysis of a number of domestic technologies applied to treatment of liquid radioactive waste for the purpose of their knots use for developed technological chain’s cost reduction. The analysis of perspective foreign technologies which are already used for ion exchange resins conditioning has been carried out as well. According to analysis report has been proposed the domestic technology for ion exchange resins conditioning with application of polymeric binding. The resulting experimental conditioned matrix obtained with this technology meets the modern requirements imposed to the final product of treatment, is convenient during the transporting and storage, at the same time it is close to foreign samples on key parameters.

Simulation and Analysis: The Dose Distribution of KBS-3 Spent Nuclear Fuel Canister by MCNP

2010 ◽  
Author(s):  
Bo Yang ◽  
He-xi Wu ◽  
Yi-bao Liu
Keyword(s):  
Cast Iron ◽  
Radioactive Waste ◽  
Nuclear Fuel ◽  
Nuclear Power ◽  
Power Plants ◽  
Spent Nuclear Fuel ◽  
Ductile Cast Iron ◽  
Nuclear Industry ◽  
Spent Fuel ◽  
High Level

With the sustained and rapid development of the nuclear power plants, the spent fuel which is produced by the nuclear power plants will be rapidly rising. Spent fuel is High-level radioactive waste and should be disposed safely, which is important for the environment of land, public safety and health of the nuclear industry, the major issues of sustainable development and it is also necessary part for the nuclear industry activities. It is important to study and resolve the high-level radioactive waste repository problem. Spent nuclear fuel is an important component in the radioactive waste, The KBS-3 canister for geological disposal of spent nuclear fuel in Sweden consists of a ductile cast iron insert and a copper shielding. The ductile cast iron insert provides the mechanical strength whereas the copper protects the canister from corrosion. The canister inserts material were referred to as I24, I25 and I26, Spent nuclear fuel make the repository in high radiant intensity. The radiation analysis of canister insert is important in canister transport, the dose analysis of repository and groundwater radiolysis. Groundwater radiolysis, which produces oxidants (H2O2 and O2), will break the deep repository for spent nuclear fuel. The dose distribution of canister surface with different kinds of canister inserts (I24, I25 and I26) is calculated by MCNP (Ref. 1). Analysing the calculation results, we offer a reference for selecting canister inserts material.

Utilization of coal fly ash in solidification of liquid radioactive waste from research reactor

2014 ◽  
Vol 32 (5) ◽  
pp. 366-370 ◽  
Author(s):  
Ahmet Erdal Osmanlioglu
Keyword(s):  
Fly Ash ◽  
Radioactive Waste ◽  
Research Reactor ◽  
Coal Fly Ash ◽  
Solidification Process ◽  
Nuclear Industry ◽  
Radioactive Isotopes ◽  
Environmental Implications ◽  
Near Surface ◽  
Waste Sludge

In this study, the potential utilization of fly ash was investigated as an additive in solidification process of radioactive waste sludge from research reactor. Coal formations include various percentages of natural radioactive elements; therefore, coal fly ash includes various levels of radioactivity. For this reason, fly ashes have to be evaluated for potential environmental implications in case of further usage in any construction material. But for use in solidification of radioactive sludge, the radiological effects of fly ash are in the range of radioactive waste management limits. The results show that fly ash has a strong fixing capacity for radioactive isotopes. Specimens with addition of 5–15% fly ash to concrete was observed to be sufficient to achieve the target compressive strength of 20 MPa required for near-surface disposal. An optimum mixture comprising 15% fly ash, 35% cement, and 50% radioactive waste sludge could provide the solidification required for long-term storage and disposal. The codisposal of radioactive fly ash with radioactive sludge by solidification decreases the usage of cement in solidification process. By this method, radioactive fly ash can become a valuable additive instead of industrial waste. This study supports the utilization of fly ash in industry and the solidification of radioactive waste in the nuclear industry.

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