Radioactive Waste Treatment Technologies and Environment

2007 ◽  
Author(s):  
Ja´n Horva´th ◽  
Dusan Krasny
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Treatment ◽  
Slovak Republic ◽  
Effective Management ◽  
Radioactive Waste Management ◽  
Near Surface ◽  
Treatment Technologies ◽  
Radioactive Waste Treatment

The radioactive waste treatment and conditioning are the most important steps in radioactive waste management. At the Slovak Electric, plc, a range of technologies are used for the processing of radioactive waste into a form suitable for disposal in near surface repository. These technologies operated by JAVYS, PLc. Nuclear and Decommissioning Company, PLc. Jaslovske´ Bohunice are described. Main accent is given to the Bohunice Radwaste Treatment and Conditioning Centre, Bituminization plant, Vitrification plant, and Near surface repository of radioactive waste in Mochovce and their operation. Conclusions to safe and effective management of radioactive waste in the Slovak Republic are presented.

Radioactive Waste Management Challenges and Progress in Iraq

2011 ◽  
Author(s):  
Fouad Al-Musawi ◽  
Emad S. Shamsaldin ◽  
John R. Cochran
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Treatment ◽  
Nuclear Research ◽  
Management Program ◽  
Nuclear Facilities ◽  
Radioactive Waste Management ◽  
The Government ◽  
Key Sites ◽  
Radioactive Waste Treatment

The government of Iraq, through the Ministry of Science and Technology (MoST) is decommissioning Iraq’s former nuclear facilities. The 18 former facilities at the Al-Tuwaitha Nuclear Research Center near Baghdad include partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. These 18 former facilities contain large numbers of silos and drums of uncharacterized radioactive waste and approximately 30 tanks that contain or did contain uncharacterized liquid radioactive wastes. Other key sites outside of Al Tuwaitha include facilities at Jesira (uranium processing and waste storage facility), Rashdiya (centrifuge facility) and Tarmiya (enrichment plant). The newly created Radioactive Waste Treatment Management Directorate (RWTMD) within MoST is responsible for Iraq’s centralized management of radioactive waste, including safe and secure disposal. In addition to being responsible for the uncharacterized wastes at Al Tuwaitha, the RWTMD will be responsible for future decommissioning wastes, approximately 900 disused sealed radioactive sources, and unknown quantities of NORM wastes from oil production in Iraq. This paper presents the challenges and progress that the RWTMD has made in setting-up a radioactive waste management program. The progress includes the establishment of a staffing structure, staff, participation in international training, rehabilitation of portions of the former Radioactive Waste Treatment Station at Al-Tuwaitha and the acquisition of equipment.

Systematical Approach to the Radioactive Waste Management in Slovak Republic

2001 ◽  
Author(s):  
Milan Breza
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Solid Waste ◽  
Waste Treatment ◽  
Slovak Republic ◽  
Storage Tanks ◽  
Waste Streams ◽  
And Storage ◽  
Radioactive Waste Treatment

Abstract The aim of this paper is to inform of the world’s specialists about the systematical approach to the radioactive waste management in Slovak Republic (Slovakia). In Slovakia are in operation six preassurized light water reactors at NPPs V-1, V-2 in Jaslovske Bohunice and reactors 2×440 MWe in NPP Mochovce at present. The installed elektro-capacity produced from these reactors is 2640 MWe total. The first experimental NPP in the former Czechoslovakia was NPP A-1. It had used natural uranium as a fuel and heavy water as a moderator and CO2 as a cooling medium. The installed preformance of this NPP A-1 was 150 MWe and was in operation since 1972 to 1977. After two technological incidents former Czechoslovak government have decided to take out of this NPP A-1 from operation. According to former Soviet projects concerning for costructions of the above mentioned NPP in Jaslovske Bohunice Slovakia, to these project didn’t belong the projects for constructions of the technological units for the radioactive waste treatment, expect of the evaporating plant for the contaminated water concetration and storage tanks for the evaporated concentrates storage and storage possibilities for the contaminated solid waste storage. A comparable complicated situation was at NPP A-1, because all type of the radioactive waste streams content gama, beta and alfa radioanuclides as well. The second technological incident at NPP A-1 (with the some portion of the cooling medium CO2 leaking form the reactor vessel out) caused contamination for the NPP A-1 operating spaces by alfa radionuclides and alfa radionuclides penetrated in all waste streams at storage tanks, pipelines, vessels, etc. as well. During the beginning of the 80’s were realized some states R and D tasks that solved the systematical approach to the radioactive waste treatment in former Czechoslovakia. The main aim of the first etap was solved the all problems connected for the radioactive waste, treatment that are formed during NPPs of the VVER-440 type operation. It was necessary to secure the production of the electro energie. The most seriously priority had the tasks, that solved of the evaporator concentrates and solid waste treatment, especially burnable, pretratment. Simultaneuosly were solved the problems connected with the proposals, designings and realisations of the disposals for the long term storage of the treated RAW in the Czech and Slovak regions. In this presentation I have tried to deliver main information, that give of the survey for RAW treatment and their long term safety storage at disposal system in Mochovec - Slovakia.

Optimalisation by the Conditioning of Liquid and Solid Low- and Intermediate Radioactive Waste for Final Disposal in Slovakia

2003 ◽  
Author(s):  
Vladimir Remia´sˇ ◽  
Dusan Kra´sny
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Treatment ◽  
Fiber Reinforced Concrete ◽  
Radioactive Waste Management ◽  
Waste Package ◽  
Final Disposal ◽  
Whole Process ◽  
Waste Container ◽  
Radioactive Waste Treatment

The radioactive waste treatment and conditioning are the most important step in radioactive waste management. In Slovak Republic the waste treatment and conditioning are including in the “Strategy of Radioactive waste management”. According to this “Strategy..” all sorts of low- and intermediate radioactive waste have to be conditioned to the fiber reinforced concrete container, i.e. “waste package”, only acceptable form for disposal in surface repository in Mochovce. In spite of good design of “Strategy..., in whole process should be occur some difficulty or difference. In the Radioactive Waste Treatment and Conditioning Center in Jaslovske Bohunice, built in 1999, the German treatment and conditioning technology together with French design of waste container was engaged. Presented paper summarized the practices during about 3 years operational period of conditioning radwaste in Jaslovske Bohunice. Till the presented results was achieved the harmonization of conditioning technology, particularly the cementation, has been necessary to accomplish with selected waste package. This aim had been reached after 1 years testing and analyzing with main fixed-target to find suitable formulation for radioactive grouting. The specific experiences had been received after 3 years operational period, which could be use for improving of whole process. In next time, the effects of conditioning process should be done especially in connection to the final disposal namely in term of economical efficiency. Based on present practice the great allowance indicated in area of concentration limits exploitation.

Management of Institutional Radioactive Waste in Lithuania

2003 ◽  
Author(s):  
P. Poskas ◽  
J. E. Adomaitis ◽  
R. Kilda
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Former Soviet Union ◽  
Effective Control ◽  
Surface Barrier ◽  
Radioactive Waste Management ◽  
Near Surface ◽  
Interim Storage ◽  
Storage Facilities

The growing number of radionuclide applications in Lithuania is mirrored by increasing demands for efficient management of the associated radioactive waste. For the effective control of radioactive sources a national authorization system based on the international requirements and recommendations was introduced, which also includes keeping and maintaining the State Register of Sources of lonising Radiation and Occupational Exposure. The principal aim of the Lithuania’s Radioactive Waste Management Agency is to manage and dispose all radioactive waste transferred to it. Radioactive waste generated during the use of sources in non-power applications are managed according to the basic radioactive waste management principles and requirements set out in the Lithuanian legislation and regulations. The spent sealed sources and other institutional waste are transported to the storage facilities at Ignalina NPP. About 35,000 spent sealed sources in about 500 packages are expected until year 2010 at Ignalina NPP storage facilities. The existing disposal facility for radioactive waste from research, medicine and industry at Maisiagala was built in the early 1960’s according to a concept typical of those applied in the former Soviet Union at that time. SKB (Sweden) with participation of Lithuanian Energy Institute has performed assessment of the long-term safety of the existing facility. It was shown that the existing facility does not provide safe long-term storage of the waste already disposed in the facility. Two alternatives were defined to remedy the situation. A first alternative is the construction of a surface barrier and a second one is a retrieval solution, whereby the already stored waste will be retrieved for conditioning, characterisation and interim storage at Ignalina NPP. Facilities for the processing of the institutional radioactive waste are required before submittal to Ignalina NPP for storage, since the present facilities are inadequate. Feasibility study to establish a new central facility has been performed by SKB International Consultants (Sweden) with participation of Lithuanian Energy Institute. This study has identified the process applied and equipment needed for a new facility. Reference design and Preliminary Safety Assessment have also been performed. Plans for the interim storage and disposal of the institutional waste are described in the paper. The aspects of finging safe disposal solutions for spent sealed sources in a near surface repositories are also discussed.

Radiological Aspects of Liquid Radioactive Waste Management from Nuclear Power Plant Operation

2017 ◽  
pp. 34-38
Author(s):  
О. Кочетков ◽  
O. Kochetkov ◽  
Е. Иванов ◽  
E. Ivanov ◽  
Д. Шаров ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Liquid Radioactive Waste ◽  
Radiological Hazard ◽  
Treatment Technology ◽  
Radioactive Waste Management ◽  
Waste Characterization ◽  
Radioactive Waste Characterization ◽  
Treatment Technologies

Purpose: The prospects and scale of the further development of nuclear energy depend to a large extent on the solution of the radioactive waste management (RW) problem. Special attention is given to management of the liquid radioactive waste (LRW), which poses the main potential hazard to the public and the environment, since LRW storage can lead to leaks into the environment. The purpose of the paper is to examine the radiological aspects of LRW management from nuclear power plants (NPPs) operation and to study the influence of the list of radionuclides controlled in RW on the evaluation of the efficiency of LRW treatment technology and on the validity of radioactive waste characterization and classification. Material and methods: The work is based on analysis of public materials (scientific publications, legal documents, international standards, recommendations of international organizations) in the area of LRW treatment and conditioning technologies, and methods of radioactive waste characterization, including information about accepted lists of controlled radionuclides. Results: It is shown that an unreasonable reduction of the list of controlled radionuclides can lead to a significant underestimation of the radiological hazard of RW packages transferred for disposal. In order to optimize the volume of RW radiation control, the radionuclide vector technology was proposed. It is stated that the technology is not universal and its application in each specific case requires additional justification. It is shown that the correctness of accounting for the radiological characteristics of radioactive waste can significantly influence the evaluation of the efficiency of the radioactive waste treatment technology. A possible approach to determining the acceptability of LRW treatment technology based on the characteristics of the final products formed is suggested. Conclusions: There is no universal approach to solve the problems of LRW treatment at the moment. A survey of the characteristics of LRW (chemical, physical, radiation) accumulated and formed during the operation of NPP with various types of reactors (VVER, RBMK, BN) should be performed to determine the initial requirements for LRW treatment technologies. A comprehensive analysis of the efficiency of LRW treatment technologies at all Russian NPPs is of interest with taking into account radionuclides that determine the radiological hazard of radioactive waste after the final disposal.

Advancing the Use of IAEA Networks in Radioactive Waste Management: Past Successes, Present Challenges and Future Opportunities

2010 ◽  
Author(s):  
P. Degnan ◽  
I. Mele ◽  
P. Dinner ◽  
H. Monken-Fernandes ◽  
A. Morales Leon ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Management Practices ◽  
Fuel Cycle ◽  
Support Network ◽  
Radioactive Waste Management ◽  
Member States ◽  
Near Surface ◽  
Novel Technologies ◽  
Stage Of Development

Since 2001 the International Atomic Energy Agency has championed the concept and use of Networks to advance radioactive waste management across the globe. At the present time there are four Networks managed on behalf of Member States by the IAEA and a fifth one is currently being implemented. The scopes of interest covered by the Networks encompass near-surface and deep geological disposal, the decommissioning of nuclear facilities, the environmental remediation of sites contaminated with radioactive materials and the characterisation of low- and intermediate-level radioactive wastes. To date over 100 organisations from more than 40 Member States are involved in the Networks. Many of these Network participants generously donate resources, time and effort to support Network activities, while others with nascent or otherwise less well developed programmes are still in the process of acquiring experience, capabilities and know-how. Regardless of the stage of development, all Network participants share in the mutual benefits that arise from improved communications with sister organisations and the sharing of experience and knowledge. The universal Goal of the Networks is the promotion of methods and technologies that will enhance the safety and sustainability of radioactive waste management practices and facilities. This Goal is being achieved through continuous improvements in communication and knowledge sharing between Network participants and the provision of enhanced opportunities for training, involvement in demonstration projects and the development of novel technologies and methodologies. We recognise that interdisciplinary understanding and the coordination of efforts at key interfaces at the back-end of the fuel cycle are critical aspects for achieving the Network Goal efficiently and effectively. Consequently, the IAEA Networks that will be operational by the end of 2010 are themselves are being molded into an organic “Network of Networks” where the use of new electronic media and the possibilities presented by enhanced communication channels will be exploited. Here we provide an overview of the IAEA Networks in radioactive waste management and present a new tool that is under development, an internet-based portal for enhanced communications and the provision of improved training opportunities.

Development of Joint Regulatory Guidance on the Management of Higher Activity Radioactive Wastes on Nuclear Licensed Sites

2009 ◽  
Author(s):  
Mick Bacon ◽  
Doug Ilett ◽  
Andy Whittall
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Health And Safety ◽  
Radioactive Wastes ◽  
Dissemination And Implementation ◽  
Radioactive Waste Management ◽  
Near Surface ◽  
Better Regulation ◽  
Interim Storage

In 2006 the UK Governments response to recommendations by its Committee on Radioactive Waste Management (CoRWM) established, in England and Wales, that geological disposal, supported by safe and secure interim storage, is the preferred route for the long-term management of higher-activity radioactive waste (i.e. that which is not suitable for near-surface disposal). It also gave the responsibility for delivering the programme for a deep geological repository to the Nuclear Decommissioning Authority (NDA). The Scottish Government has a policy of long term, near site, near surface safe and secure interim storage. To support the open and transparent approach promised by Government, the Health and Safety Executive (HSE), the Environment Agency and the Scottish Environment Protection Agency (SEPA) are developing joint guidance on the management of higher-activity radioactive waste to explain regulatory objectives in securing safe and secure interim storage and the associated management of radioactive wastes. The guidance comes in two parts: • Guidance on the regulatory process; • Technical guidance modules. The guidance promotes a cradle to grave approach to radioactive waste management and by aligning the regulatory interests of environmental and safety regulators it delivers one of the Government’s “Better Regulation” objectives. This paper describes the process by which the joint guidance was produced with particular emphasis on stakeholder engagement. It describes the key features of the guidance, including the concept of the radioactive waste management case (RWMC). Finally the problems encountered with dissemination and implementation are discussed together with measures taken by the regulators to improve these aspects.

Creation of system of final isolation (disposal) of radioactive waste in the Russian Federation

MRS Advances ◽  
2020 ◽  
Vol 5 (5-6) ◽  
pp. 275-282 ◽  
Author(s):  
Vsevolod Igin ◽  
Victor Krasilnikov
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Disposal ◽  
Russian Federation ◽  
Radioactive Waste Disposal ◽  
High Level Waste ◽  
Federal State ◽  
Radioactive Waste Management ◽  
Near Surface ◽  
High Level

Abstract:The paper provides generic overview of legal and regulatory framework of radioactive waste management activities held in Russian Federation and national operator responsibilities and accomplishments. It gives a short description of waste classification scheme used and plans for radioactive waste disposal. In particular the paper provides information on the plans of the FEDERAL STATE UNITARY ENTERPRISE "National operator for radioactive waste management" to construct and operate several near-surface disposal facilities for low and intermediate level waste with total capacity up to 550 000 cubic meter. The paper also provides detailed information on the steps of high-level waste disposal program including site-selection, construction phase of the underground research laboratory (URL) near the city of Zheleznogorsk, Krasnoyarsk Region and research program after the construction of the URL. The paper also describes Russian system and state policy in the field of RW management and gives recommendations for future implementers.

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