Systematical Approach to the Radioactive Waste Management in Slovak Republic

Author(s):  
Milan Breza

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.

Author(s):  
Ja´n Horva´th ◽  
Dusan Krasny

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.


2021 ◽  
Vol 11 (9) ◽  
pp. 3939
Author(s):  
Krzysztof Pikoń ◽  
Nikolina Poranek ◽  
Adrian Czajkowski ◽  
Beata Łaźniewska-Piekarczyk

The purpose of the study presented in this text is to show the influence of COVID-19 on waste management systems and circular economy stream, and their impact on circular economy, particularly the economic impact of the pandemic on the waste management sector, impact on circular economy objectives’ implementation as well as additional challenges like the need for hygienization of waste streams during different implementation efforts, such as changes in the municipal solid waste market and different waste processes of their disposal. Additionally, some methods—such as thermal treatment—which seemed to be not fully aligned with the circular economy approach have advantages not taken into account before. Incineration of higher volume of waste affects the waste structure and will change some of the circular economy objectives. The analysis was carried out on the example of the Polish market.


Author(s):  
Fouad Al-Musawi ◽  
Emad S. Shamsaldin ◽  
John R. Cochran

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.


Author(s):  
Yuri Pokhitonov ◽  
Dennis Kelley

Large amounts of liquid radioactive waste have existed in the U.S. and Russia since the 1950’s as a result of the Cold War. Comprehensive action to treat and dispose of waste products has been lacking due to insufficient funding, ineffective technologies or no proven technologies, low priority by governments among others. Today the U.S. and Russian governments seek new, more reliable methods to treat liquid waste, in particular the legacy waste streams. A primary objective of waste generators and regulators is to find economical and proven technologies that can provide long-term stability for repository storage. In 2001, the V.G. Khlopin Radium Institute (Khlopin), St. Petersburg, Russia, and Pacific Nuclear Solutions (PNS), Indianapolis, Indiana, began extensive research and test programs to determine the validity of polymer technology for the absorption and immobilization of standard and complex waste streams. Over 60 liquid compositions have been tested including extensive irradiation tests to verify polymer stability and possible degradation. With conclusive scientific evidence of the polymer’s effectiveness in treating liquid waste, both parties have decided to enter the Russian market and offer the solidification technology to nuclear sites for waste treatment and disposal. In conjunction with these efforts, the U.S. Department of Energy (DOE) will join Khlopin and PNS to explore opportunities for direct application of the polymers at predetermined sites and to conduct research for new product development. Under DOE’s “Initiatives for Proliferation Prevention” (IPP) program, funding will be provided to the Russian participants over a three year period to implement the program plan. This paper will present updated details of U.S. DOE’s IPP program, the project structure and its objectives both short and long-term, polymer tests and plications for LLW, ILW and HLW, and new product development initiatives.


Author(s):  
Vladimir Remia´sˇ ◽  
Dusan Kra´sny

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.


2004 ◽  
Vol 19 (2) ◽  
pp. 59-64
Author(s):  
Josef Neubauer

At the Austrian Research Centers Seibersdorf, there are several facilities in stalled for treatment of waste of low and intermediate radioactivity level (radwaste). A separate company within Centers, Nuclear Engineering Seibersdorf, has been formed recently, acting as a centralized facility for treatment, conditioning and storing of such waste within the country. The relevant treatment technology is applied depending on the waste category. In total about 6900 m3 of solid waste of low and intermediate radioactivity level originating from Austria was treated in the period between 1976 and 2002. Presently, there exists no final repository for radwaste in Austria. A study is under way to identify the structure for a long term storage facility.


2009 ◽  
Vol 27 (4) ◽  
pp. 354-361 ◽  
Author(s):  
Alireza Mesdaghinia ◽  
Kazem Naddafi ◽  
Amir Hossein Mahvi ◽  
Reza Saeedi

The waste management practices in primary healthcare centres of Iran were investigated in the present study. A total of 120 primary healthcare centres located across the country were selected using the cluster sampling method and the current situation of healthcare waste management was determined through field investigation. The quantities of solid waste and wastewater generation per outpatient were found to be 60 g outpatient—1 day—1 and 26 L outpatient—1 day— 1, respectively. In all of the facilities, sharp objects were separated almost completely, but separation of other types of hazardous healthcare solid waste was only done in 25% of the centres. The separated hazardous solid waste materials were treated by incineration, temporary incineration and open burning methods in 32.5, 8.3 and 42.5% of the healthcare centres, respectively. In 16.7% of the centres the hazardous solid wastes were disposed of without any treatment. These results indicate that the management of waste materials in primary healthcare centres in Iran faced some problems. Staff training and awareness, separation of healthcare solid waste, establishment of the autoclave method for healthcare solid waste treatment and construction of septic tanks and disinfection units in the centres that were without access to a sewer system are the major measures that are suggested for improvement of the waste management practices.


2021 ◽  
pp. 130282
Author(s):  
Jay R.S. Doorga ◽  
Soonil D.D.V. Rughooputh ◽  
Sum Yue Chung ◽  
Alexis McGivern

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