Liquid Low-level Radioactive Waste Treatment by Membrane Processes

2012 ◽  
Vol 1475 ◽  
Author(s):  
Grazyna Zakrzewska-Trznadel ◽  
Marian Harasimowicz ◽  
Agnieszka Miskiewicz ◽  
Agnieszka Jaworska-Sobczak
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Treatment ◽  
Liquid Radioactive Waste ◽  
Liquid Waste ◽  
Membrane Distillation ◽  
Integrated System ◽  
Nuclear Chemistry ◽  
Radioactive Waste Management ◽  
Membrane Processes

ABSTRACTThe first step in the processing of low- and medium-level liquid radioactive waste is the reduction in the volume of liquid containing small concentrations of radionuclides. Various methods for concentration of radioactive waste have been studied and developed at the Institute of Nuclear Chemistry and Technology, including membrane processes. Reverse osmosis was implemented at the Radioactive Waste Management Plant. Other methods such as ultrafiltration, membrane distillation, adsorption and different integrated processes were studied in the scope of national and international projects.This paper presents the results of research performed at Institute of Nuclear Chemistry and Technology in Warsaw concerning radioactive liquid waste treatment and the programs of implementation of these methods at nuclear centers producing such wastes, as well as the plans for the utilization of the knowledge and experience and designs of schemes for radioactive waste management in future nuclear power industry. The integrated system developed on the basis of research will be a prototype for further implementation.

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.

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.

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.

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.

Sorption-Reagent Method in Liquid Radioactive Waste Management

2002 ◽  
Vol 713 ◽  
Author(s):  
Valentin A. Avramenko ◽  
Veniamin V. Zheleznov ◽  
Elena V. Kaplun ◽  
Dmitri V. Marinin ◽  
Tatiana A. Sokolnitskaya ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Reverse Osmosis ◽  
High Salinity ◽  
Liquid Radioactive Waste ◽  
Distribution Coefficients ◽  
Radioactive Waste Management ◽  
Combined Application ◽  
Multi Stage ◽  
Co Precipitation

ABSTRACTMethods of liquid radioactive waste (LRW) decontamination from radionuclides including their co-precipitation at specific conditions or adsorption on selective sorption materials are well known and extensively used in LRW management technologies. At the same time, it was shown in a number of papers that some forms of organic and inorganic ionexchangers react with solutions containing specific components that results in formation of virtually insoluble precipitates inside the sorbent matrix or on its surface. Here in some cases the sorbent selectivity to some radionuclides increases substantially.The sorption-reagent materials synthesized for decontamination purposes are the most highly selective in regard to such difficult to remove radionuclides as strontium-90 and cobalt-60. It was shown by comparative analysis of radionuclide removal efficiency by traditional selective sorbents and developed sorption-reagent materials that the latter have the highest distribution coefficients in systems too complex for “pure” sorption/ion-exchange decontamination. For example, the sorption-reagent materials have strontium distribution coefficients several dozens higher than those of commercially available sodium titanates and silicotitanates.The mechanism of radionuclide sorption on sorption-reagent materials of different types was studied. It was shown that this is a multi-stage process and the course of different stages of chemical reactions and sorption is determined by the parameters of medium from which radionuclides are sorbed. It was also shown that these materials application in liquid radioactive waste management enables one to develop simple technological setups combining the advantages of sorption and precipitation methods.One of the main fields of the sorption-reagent materials application can be decontamination of high-salinity radioactive waste formed whether as a result of ionexchanger filters regeneration in LRW management systems or in reverse osmosis installations. Use of sorption-reagent materials for high-salinity waste management enables one to reduce several ten-fold or even hundred-fold the volume of solid radioactive waste (SRW) to be sent for final disposal and, therefore, to decrease the cost of LRW management. The approach consisting in combined application of reverse-osmosis and sorption-reagent methods for LRW decontamination is suggested.

Low-Level Liquid Waste Treatment System Technical Design in China

2013 ◽  
Author(s):  
Juan Zhao
Keyword(s):  
Ion Exchange ◽  
Radioactive Waste ◽  
Waste Treatment ◽  
Fuel Cycle ◽  
Liquid Radioactive Waste ◽  
Liquid Waste ◽  
Spent Fuel ◽  
Nuclear Facilities ◽  
High Concentration ◽  
Low Level

Radioactive wastes are produced within the nuclear fuel cycle operations (uranium conversion and enrichment, fuel fabrication and spent fuel reprocessing). Evaporation is a proven method for the treatment of liquid radioactive waste providing both good decontamination and high concentration. Two technical designs of nuclear facilities for low-level liquid radioactive waste treatment are presented in the paper and the evaluation of both methods, as well. One method is two-stage evaporation, widely used in the People’s Republic of China’s nuclear facilities; another is two evaporator units and subsequently ion exchange, which is based on the experience gained from TIANWAN nuclear power plant. Primary evaporation and ion exchange ensure the treated waste water discharged to environment by controlling the condensate radioactivity, and secondary evaporation is to control concentrates in a limited salt concentration.

New Sorbents and Technologies for Liquid Radioactive Waste Management

1996 ◽  
Vol 465 ◽  
Author(s):  
D. V. Marinin ◽  
V. A. Avramenko ◽  
V.Yu. Glushchenko ◽  
V.l. Sergienko ◽  
V. A. Vasilevskiy ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Reactors ◽  
Liquid Radioactive Waste ◽  
Single Stage ◽  
Major Portion ◽  
Radioactive Waste Management ◽  
Selective Sorbent ◽  
Polluted Waters

ABSTRACTThe possibilities for using various technologies for liquid radioactive waste (LRW) management were considered. Technologies based on the application of sorbents highly selective to radionuclides were shown to have good prospects. Possible ways of increasing selective sorbent efficiency in cleaning radionuclide-polluted waters of various types were examined. The results of studying new high-selective sorbents produced in the Institute of Chemistry FEDRAS are given. The use of these sorbents enables one to treat LRW of various types in a single stage. The results of testing a sorption filter installation for management of LRW produced during operation, repair and disposal of nuclear reactors are presented. Use of this installation resolves a major portion of LRW disposal problems.

scholarly journals Scientifi c and Design Aspects of Liquid Radioactive Waste Vitrifi cation from Nuclear Power Plants with WWER-1200 Reactor Units

2020 ◽  
Vol 11 (2) ◽  
pp. 56-65
Author(s):  
V. T. Sorokin ◽  
◽  
D. I. Pavlov ◽  
V. A. Kashcheev ◽  
N. D. Musatov ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Bottom Sediment ◽  
Nuclear Power ◽  
Power Plants ◽  
Liquid Radioactive Waste ◽  
State System ◽  
Radioactive Waste Management ◽  
Industrial Use ◽  
State Of Art

The article presents a comparison of technologies for liquid radioactive waste bottom sediment processing from NPPs with WWER-1200 reactor units. Vitrifi cation and cementing methods were compared based on the state of art in the development of the Unifi ed State System for Radioactive Waste Management, as well as engineering and design study of various processing methods. The research demonstrates that industrial use of the vitrifi cation method can be seen as a promising one when it comes to the processing of liquid radioactive waste from NPPs and radiochemical plants.

scholarly journals Study of Radioactive Waste Management of Nuclear Power Plant: Prospect of Rooppur Nuclear Power Plant

2020 ◽  
pp. 69-79
Author(s):  
Iftekhar Ahmed ◽  
Hriday Dhar Joni ◽  
Hridita Nowrin Pranti
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Liquid Waste ◽  
Main Concern ◽  
Radioactive Waste Management ◽  
Radiation Level ◽  
Near Surface

The nuclear power plant is required to supply a substantial amount of electricity for a densely populated country like Bangladesh. The government of Bangladesh has attached to a commitment to implement the Rooppur Nuclear Power Plant, and so Bangladesh will be the 33rd nuclear power-producing country after the successful construction of this plant. Bangladesh has planned to construct two power units (Rooppur-1 & Rooppur-2) with a capacity of 1200 MW, each of and is expected to go into operation in 2023. Russian Rosatom State Atomic Energy Corporation is constructing this nuclear power plant, which is the generation-3+ VVER-1200 model. But the main concern is how a third world country like Bangladesh can handle the tons of radioactive waste of RNNP. Radioactive waste i.e., a variety of solids, liquids, and gases which are produced during the generation of nuclear energy in a nuclear reactor. Depending on activity content, solid and liquid waste are disposed of in near-surface or deep geological facilities, and gaseous waste is dissolved by following some filtering process. If not properly disposed of or recycled, irradiation from radioactive waste will cause major problems for the environment. Various stages should be required for the removal of a tremendous amount of radioactive waste in a cost-effective way. This paper mainly delineates the proximate of radioactive waste management of RNNP and gives an account of (1) Radioactivity and radiation level, (2) Classification, (3) Treatment of solid, liquid and gaseous radioactive waste, (4) Reprocessing and packaging, (5) Storage and (6) Disposal.

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