Six Years Operation Experience With the Cilva Incinerator for Radioactive Waste Treatment

2001 ◽  
Author(s):  
Jan Deckers ◽  
Paul Luycx
Keyword(s):  
Radioactive Waste ◽  
Waste Treatment ◽  
Mission Statement ◽  
Liquid Waste ◽  
Volume Reduction ◽  
Research Centre ◽  
Air Pollution Control ◽  
Nuclear Facilities ◽  
Gas Cleaning ◽  
Set Up

Abstract Since the very beginning of nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. An experimental furnace “Evence Coppée” was built in 1960 for treatment of LLW produced by the Belgian Research Centre (CEN.SCK). Regulatory this furnace has been modified, improved and equipped with additional installations to obtain better combustion conditions and a more efficient gas cleaning system. Based on the 35 years of experience gained by the operation of the “Evence Coppée”, a new industrial nuclear incineration installation was set into operation in May 1995, as a part of the Belgian Centralised Treatment/Conditioning Facility CILVA. Up to the end of 2000, the CILVA incinerator has burnt 703 tons of solid waste and 343 tons of liquid waste. This paper describes the type of waste and the allowable radioactivity, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the operation experience, capacity, volume reduction, chemical and radiological emissions and maintenance. The most important changes which improved safety, reliability and capacity are also mentioned. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialised in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste.

Thermal Treatment of Historical Radioactive Solid and Liquid Waste Into the CILVA Incinerator

2007 ◽  
Author(s):  
Jan Deckers ◽  
Ludo Mols
Keyword(s):  
Radioactive Waste ◽  
Solid Waste ◽  
Mission Statement ◽  
Organic Liquid ◽  
Liquid Waste ◽  
Volume Reduction ◽  
Air Pollution Control ◽  
Nuclear Facilities ◽  
Set Up ◽  
Exchange Resins

Since the very beginning of the nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. Based on the 35 years experience gained by the operation of the old incinerator, a new industrial incineration plant started nuclear operation in May 1995, as a part of the Belgian Centralized Treatment/Conditioning Facility named CILVA. Up to the end of 2006, the CILVA incinerator has burnt 1660 tonne of solid waste and 419 tonne of liquid waste. This paper describes the type and allowable radioactivity of the waste, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the treatment of several hundreds of tonne historical waste from former reprocessing activities such as alpha suspected solid waste, aqueous and organic liquid waste and spent ion exchange resins. The capacity, volume reduction, chemical and radiological emissions are also evaluated. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialized in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste.

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.

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.

Experience of Clean-Up Activities and Feedback to Future D&D Projects: Japan Power Demonstration Reactor Decommissioning Project

2001 ◽  
Author(s):  
Satoshi Yanagihara ◽  
Mitsuo Tachibana ◽  
Taro Shimada ◽  
Takenori Sukegawa ◽  
Kunio Shiraishi
Keyword(s):  
Radioactive Waste ◽  
Waste Treatment ◽  
Nuclear Facilities ◽  
Radioactive Materials ◽  
Treatment Policy ◽  
Regulatory Systems ◽  
Building Surfaces ◽  
Radiological Characterization ◽  
Radioactive Waste Treatment

Abstract In the Japan Power Demonstration Reactor (JPDR) decommissioning project, the procedure for clean-up activities was specially studied for harmonization with radioactive waste treatment policy in Japan; it consisted of several components such as survey of the facility operational history, radiological characterization of building surfaces, decontamination and final survey of radioactivities. After confirming that there was no significant radioactivity in the facilities in the final step of the procedure, buildings were demolished in consideration of treatment of wastes as non-radioactive materials. The JPDR decommissioning project was completed by March 1996 with no serious problems, which showed that the procedure was rational, and that the experiences are useful for planning of future decommissioning activities. The dismantling and clean-up activities were reviewed, and the experiences are excepted to contribute to establishing standard and regulatory systems on decommissioning nuclear facilities.

Involvement of ANDRAD in Endorsement of Decommissioning Documentation of Nuclear Facilities in Romania

2009 ◽  
Author(s):  
Marin Dinca
Keyword(s):  
Radioactive Waste ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Waste Treatment ◽  
Competent Authority ◽  
Regulatory Body ◽  
Nuclear Facilities ◽  
National Agency ◽  
Waste Storage ◽  
Safe Management

National Agency for Radioactive Waste — ANDRAD — is in Romania, by law, the competent authority for the disposal administration of spent nuclear fuel and radioactive waste and for the coordination of the predisposal management of spent nuclear fuel and radioactive waste, inclusive decommissioning of nuclear facilities. Government Ordinance (GO) No. 11/January 30, 2003 and Government Decision (GD) No. 1601/December 23, 2003 established the ANDRAD’s foundation and organization. In accordance with GO No. 11/2003, republished, on the safe management of the radioactive waste, ANDRAD has the responsibility to endorse the decommissioning documentation issued by the main radioactive waste generators (nuclear installations and other major radiological installations: radioactive waste treatment plants, radioactive waste storage facilities, post irradiation examination laboratories, centres for radioisotopes production etc.). ANDRAD receives for endorsement some of the documentation for decommissioning that is provided by enforced norms for each type of nuclear facility. There are presented the nuclear facilities that must have decommissioning documentation endorsed by ANDRAD, the type of documents submitted by license holder to ANDRAD and the procedure of endorsement in relation with the regulatory body (CNCAN) approval of the decommissioning documents.

Radioactive Waste Treatment From Mo-99 Production Facility in the Netherlands

2001 ◽  
Author(s):  
Rozé M. Van Kleef ◽  
Klaas A. Duijves
Keyword(s):  
The Netherlands ◽  
Radioactive Waste ◽  
Waste Treatment ◽  
Liquid Waste ◽  
Nuclear Research ◽  
Production Cycle ◽  
Production Facility ◽  
Waste Management Concept ◽  
Interim Storage ◽  
Radioactive Waste Treatment

Abstract In Petten, the Netherlands, a Molybdenum Production Facility (MPF) has been realised since 1994 by the Nuclear Research and Consultancy Group (NRG) in close co-operation with Mallinckrodt, a company that produces isotopes for medical applications at the same site. The facility is operated by Mallinckrodt personnel under the license of NRG. At this moment the facility has a weekly production rate of 0,4 PBq (10,500 Ci). The management of the radioactive waste treatment, developed by Mallinckrodt, NRG and COVRA, has been one of the key issues during the development of the production facility. COVRA is the Central Organisation for Radioactive Waste in the Netherlands and responsible for the execution of the radwaste policy of the Dutch government. For solid and liquid low level waste (LLW) the existing route at COVRA was available. For the handling of solid and liquid intermediate level waste (ILW) from the MPF, a new system for transport, interim storage and treatment had to be developed. Therefore the Mo-waste project was established in 1994. This project included the following issues: • development, construction and operation of a filling and packaging station for liquid waste at the production site, • design, engineering, fabrication and testing of Type A-transport containers for both the solid and liquid ILW, • modification of transport vehicle, • design and realisation of interim storage and treatment facilities for both the solid and liquid ILW at the COVRA site. At this moment the completed facilities have successfully undergone the hot testing phase. The experiences achieved confirmed the rightness of the choice to integrate the COVRA waste management concept in the Molybdenum production cycle.

Photocatalytic and Photochemical Degradation of Liquid Waste Containing EDTA

2011 ◽  
Author(s):  
C. Lepeytre ◽  
C. Lavaud ◽  
G. Serve
Keyword(s):  
Radioactive Waste ◽  
Waste Treatment ◽  
Process Development ◽  
Degradation Products ◽  
Liquid Waste ◽  
Degradation Process ◽  
Decontamination Factor ◽  
Photochemical Degradation ◽  
Degradation Degree ◽  
Radioactive Waste Treatment

The decontamination factor of liquid waste containing 60Co is generally weak. This is due to the presence of complexant molecules. For instance, complexation of EDTA with 60Co decreases efficiency of radioactive waste treatment. The aim of this study was to degrade EDTA in H2O and CO2 and to concentrate free 60Co in order to increase decontamination factor. A first test of radioactive waste treatment by photocatalysis was allowed to increase decontamination factor (60Co) from 16 to 196 with a device requiring to be improved. The present work concerns the first step of the degradation process development with a more powerful device. These first experiments were leaded to follow the only EDTA oxidation. EDTA degradation was carried out by the following Advanced Oxidation Processes (AOP): UV/H2O2 (photochemistry); UV/TiO2 (photocatalysis); UV/TiO2/H2O2. A specific reactor was achieved for this study. The wavelength used was 254 nm (UVC). The photocatalytic degradation of EDTA was carried out with Degussa P-25 titanium dioxide (TiO2), which is a semiconductor photocatalyst. The degradation degree of EDTA and the intermediate products were monitored by TOC and ionic chromatography methods. The effects of various parameters such as pH and the quantity of H2O2 were studied. This allows us to conclude that basic pH slows down EDTA degradation. The study showed that UV/H2O2 process was the most effective treatment process under acid conditions. The rate of EDTA degradation was very high and reached 95% in 120 minutes. The presence of glyoxilic, oxalic, glycolic and formic acids was detected as degradation products. Among the intermediates produced by photochemistry, NO3− ions presence informed of the amine degradations. These results highlighted faster EDTA degradation by photochemistry than photocatalysis.

The Removal, Transportation and Final Treatment and Conditioning of the THETIS Research Reactor Spent Fuel of the University of Ghent (Belgium) Achieved in 2010

2011 ◽  
Author(s):  
Hubert Thierens ◽  
Myriam Monsieurs ◽  
Vincent De pooter ◽  
Luc Noynaert ◽  
Patrick Maris ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Research Reactor ◽  
Storage Period ◽  
Disposal Site ◽  
Research Centre ◽  
Nuclear Materials ◽  
Spent Fuel ◽  
Nuclear Facilities ◽  
Enriched Uranium ◽  
Intermediate Storage

The THETIS research reactor on the site of the Nuclear Sciences Institute of the Ghent University has been in operation from 1967 until December 2003. This light-water moderated graphite-reflected low-enriched uranium pool-type reactor has been used for various purposes e.g. the production of radio-isotopes and activation analyses. During the first years its core power was 15 kW. In the early ’70, a core enlargement allowed for operation at typically 150 kW, while the maximum was allowed to be 250 kW. The fuel was 5% enriched uranium cladded with AISI304L stainless steel, with graphite plugs at both ends of the tubes. In order to decommission the reactor, the spent fuel and other nuclear materials present had to be removed from the reactor site. Ghent University entrusted SCK·CEN, the Belgian Nuclear Research Centre, with the study of the further management of the spent fuel. Various options such as reprocessing, intermediate storage awaiting final disposal were investigated. However the characteristics and the small amount of spent fuel (84.64 kg of UO2) made these solutions very expensive. In the meantime ONDRAF/NIRAS, the Belgian radioactive waste management agency, was developing together with Belgoprocess, a solution for final conditioning in 400 liter drums and further intermediate storage of the spent fuel in its nuclear facilities at the BELGOPROCESS site in Dessel. This conditioned waste is foreseen to enter the future geological disposal site after the intermediate storage period only after 2050. Finally SCK·CEN recommended this solution for the back-end of the THETIS spent fuel and Ghent University declared this spent fuel as radioactive waste. Once the feasibility for conditioning and storage was demonstrated, further actions were taken in order to unload the spent fuel out of the reactor and to transport it to the PAMELA-installation at the Belgoprocess site in Dessel. Finally after receiving all necessary licensing authorisations from the FANC/AFCN, the Belgian nuclear safety authority, the operations started at the reactor site beginning of 2010 and the spent fuel was placed into the intermediate storage building after conditioning at the Belgoprocess site at the end of 2010. The paper will focus on: - the inventarisation and characterization of the spent fuel and other nuclear materials; - the operations at Ghent University and Belgoprocess sites; - the conclusions drawn from the operations.

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.

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