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.

Fundamental R&D Work on Methods for State Monitoring of Transport and Storage Containers for Spent Fuel and Heat-Generating High-Level Radioactive Waste on Prolonged Intermediate Storage

2017 ◽  
Author(s):  
Daniel Fiß ◽  
Sebastian Schmidt ◽  
Sebastian Reinicke ◽  
Alexander Kratzsch
Keyword(s):  
Applied Sciences ◽  
Radioactive Waste ◽  
Storage Period ◽  
Material Behavior ◽  
Spent Fuel ◽  
Radiation Emission ◽  
Storage Container ◽  
University Of Applied Sciences ◽  
Intermediate Storage

The continuing search for a long-term storage for highly-active nuclear waste in Germany requires a prolonged intermediate storage period of spent fuel in dry storage casks at the power plant sites. Currently, it is not sufficiently clear if there might be a loss of integrity of the fuel rods within such long periods, e.g. due to rising pressure from gaseous products of nuclear decay. Regarding a final evaluation, extrapolative modelling of the radiochemical and thermomechanical material behavior is challenging and not suitable for predictions on the condition of storage container inventory after the intermediate storage period. Therefore, it is of public interest to find measurement principles or methods which can provide information about the condition of the storage container inventory. In line with a cooperative project (project partners: Technical University Dresden, Zittau/Görlitz University of Applied Sciences) different measurement principles and methods (radiation emission, muon transmission, thermography, acoustical spectrometry) for non-invasive condition monitoring of the storage container inventory in case of prolonged intermediate storage are going to be investigated and evaluated. The results shall help to determine suitable methods for the identification of both changes of the spent fuel and inner container structure over long periods without opening the container and would be a significant contribution for the long-term safety of intermediately stored highly radioactive waste. Furthermore, suitable methods would provide information about the transport and conditioning ability of the waste before transfer to the repository. This paper deals with the content of the subproject of Zittau/Görlitz University of Applied Sciences as well as with the approach for project realization. A further main part of this paper is the development of experimental infrastructure to support the investigations.

scholarly journals SiLiF Neutron Counters to Monitor Nuclear Materials in the MICADO Project

Sensors ◽  
2021 ◽  
Vol 21 (8) ◽  
pp. 2630
Author(s):  
Luigi Cosentino ◽  
Quentin Ducasse ◽  
Martina Giuffrida ◽  
Sergio Lo Meo ◽  
Fabio Longhitano ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Detector Response ◽  
Nuclear Materials ◽  
Spent Fuel ◽  
Neutron Detectors ◽  
Intermediate Level Radioactive Waste ◽  
Eu Project ◽  
Interim Storage ◽  
Waste Drums

In the framework of the MICADO (Measurement and Instrumentation for Cleaning And Decommissioning Operations) European Union (EU) project, aimed at the full digitization of low- and intermediate-level radioactive waste management, a set of 32 solid state thermal neutron detectors named SiLiF has been built and characterized. MICADO encompasses a complete active and passive characterization of the radwaste drums with neutrons and gamma rays, followed by a longer-term monitoring phase. The SiLiF detectors are suitable for the monitoring of nuclear materials and can be used around radioactive waste drums possibly containing small quantities of actinides, as well as around spent fuel casks in interim storage or during transportation. Suitable polyethylene moderators can be exploited to better shape the detector response to the expected neutron spectrum, according to Monte Carlo simulations that were performed. These detectors were extensively tested with an AmBe neutron source, and the results show a quite uniform and reproducible behavior.

An Overview of the Draft of ‘Nuclear Materials and Radioactive Waste Management Act’

2013 ◽  
Author(s):  
Huan Lin ◽  
Tai-Wei Lan ◽  
Min-Tsang Chang ◽  
Wuu-Kune Cheng
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Public Involvement ◽  
Nuclear Materials ◽  
Regulatory Body ◽  
Nuclear Facilities ◽  
Radioactive Waste Management ◽  
Regulatory Capacity ◽  
Concept Of Information ◽  
The Impact

The “Nuclear Materials and Radioactive Waste Management Act” (NMRWMA) in Taiwan has been in use since 2002. To promote further administrative efficiency and improve regulatory capacity, an amendment of the act has been initiated by the Atomic Energy Council (AEC). It is now being reviewed by outside experts and related communities so as to include the best understanding of risk management factors. For the future decommissioning challenges of nuclear facilities, the act is also being amended to comply with the regulatory requirements of the decommissioning mandates. Currently the Taiwan government is conducting government reorganization, and AEC will be reformed but will remain as an independent regulatory body. AEC will then be capable of improving the regulatory capacity for facilitating licensing and inspection, ensuring operational safety, environmental protection and public involvement, and giving a more flexible administrative discretion, such as expending the margin of penalty. The amendment is also required to provide a formal legal basis for the Nuclear Backend Fund, and to mandate the waste producers to take responsibility for any final debt repayment. In addition, this amendment promotes measures to prevent accidents or emergencies concerning radioactive materials and facilities and procedures to reduce the impact and effect of any unexpected events. Furthermore, this amendment intends to implement the concept of information transparency and public participation so as to meet the public needs. Finally, radioactive waste final disposal tasks have to be completed by waste producers under the supervision of the AEC.

Current Status of the Radioactive Waste Management Programme in Spain

2007 ◽  
Author(s):  
Jorge Lang-Lenton Leo´n ◽  
Emilio Garcia Neri
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Management Programme ◽  
Current Status ◽  
Spent Fuel ◽  
Radioactive Waste Management ◽  
Set Up ◽  
Intermediate Storage ◽  
Term Management

Since 1984, ENRESA is responsible of the radioactive waste management and the decommissioning of nuclear installations in Spain. The major recent challenge has been the approval of the Sixth General Radioactive Waste Plan (GRWP) as “master plan” of the activities to be performed by ENRESA. Regarding the LILW programme, the El Cabril LILW disposal facility will be described highlighting the most relevant events especially focused on optimizing the existing capacity and the start-up of a purpose–built disposal area for VLLW. Concerning the HLW programme, two aspects may be distinguished in the direct management of spent fuel: temporary storage and long-term management. In this regards, a major challenge has been the decision adopted by the Spanish Government to set up a Interministerial Committee for the establishment of the criteria that must be met by the site of the Centralized Intermediate Storage (CTS) facility as the first and necessary step for the process. Also the developments of the long-term management programme will be presented in the frame of the ENRESA’s R&D programme. Finally, in the field of decommissioning they will be presented the PIMIC project at the CIEMAT centre and the activities in course for the decommissioning of Jose´ Cabrera NPP.

Optimization Features in Management of Salaspils Research Reactor Decommissioning Waste

2003 ◽  
Author(s):  
A. Dreimanis
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Research Reactor ◽  
Optimal Solution ◽  
Environmental Safety ◽  
Radioactive Waste Disposal ◽  
Disposal Site ◽  
Radioactive Waste Management ◽  
Safety Control ◽  
Simplified Approach

Management of decommissioning waste is considered as complex task of seeking for optimal solution in the environment of various competing technical, safety and socio-economical factors. If from the formal mathematics viewpoint it is a multi-parameter optimization task, then for real conditions simplified approach for such problem should be applied. We propose to decompose this task into the set of optimization analysis for particular steps, and then in each step it is easier to find optimum. For the real case of management of radioactive waste arising from dismantling and decommissioning of Salaspils Research Reactor (SRR) we consider following main optimization steps: 1) the choice of the decommissioning concept — among three elaborated versions — with estimation of the foreseen radioactive waste amount for disposal, recycling and free release, taking into account also potential exposures and financial resources; 2) establishment of national radioactive waste management agency “RAPA” Ltd., ensuring common administration and maintenance of the shutdown SRR and radioactive waste (RW) disposal site — RAPA manages some decommissioning activities of SRR and shall actively participate together with envisaged decommissioning operator in this process also in future, but in all stages will keep full responsibility of waste management; 3) optimization of radioactive waste transportation: i) organizational aspects (packing, transportation time, schedule, route, etc.), ii) environmental safety control; 4) optimization arrangement of space for radioactive waste disposal: i) choice of the best strategy to ensure a new space, ii) optimization of the vault size — to be able accommodate decommissioning waste without being oversized; 5) strategy of treatment, conditioning and packing of solid decommissioning waste; 6) optimization of liquid decommissioning waste management — its conditioning together with the solid radioactive waste; 7) socio-economical optimization features: i) existing infrastructure for RW disposal, ii) financial compensation for local municipality, iii) international cooperation, technical and financial assistance by EU, IAEA, Sweden. The proposed optimization features used in the developing of Concept for radioactive waste management in Latvia for the period 2003–2010 (which corresponds to the approved decommissioning period of SRR) supplement existing separate optimization aspects of decommissioning waste management and could be considered as simplified integral set of factors for elaboration of optimal strategy for decommissioning waste management.

Dry Storage of Spent Research Reactor Fuel in Castor BR3® Casks at Belgoprocess in Belgium

2001 ◽  
Author(s):  
Marnix Braeckeveldt ◽  
Luc Ooms ◽  
Gustaaf Geenen
Keyword(s):  
Radioactive Waste ◽  
Nuclear Research ◽  
High Level Waste ◽  
Spent Fuel ◽  
Fuel Rods ◽  
Dry Storage ◽  
Nuclear Site ◽  
Test Reactor ◽  
Intermediate Storage ◽  
High Level

Abstract The BR3 reactor (10.5 MWe) at the Nuclear Research Center SCK•CEN was the first PWR plant installed in Europe and has been shut down in 1987. The BR3 reactor is from 1989 in a decommissioning stage and most of the spent fuel is presently still stored in the deactivation pool of the BR3 plant and has to be evacuated. The BR3 was used as a test-reactor for new fuel types and assemblies (Mixed Oxide (MOX) fuel, fuel rods containing burnable poison (Gd2O3) and other types of fuels). Some fuel rods, having undergone a destructive analysis, are stored in different laboratories at the SCK•CEN. In total, the BR3 spent fuel comprises the equivalent of almost 200 fuel assemblies corresponding to some 5000 fuel rods. Beside the spent BR3 fuel, a limited number of spent fuel rods, with equivalent characteristics as the BR3 fuel but irradiated in research reactors outside Belgium and stored in other buildings at the SCK•CEN nuclear site, were added to the inventory of spent fuel to be evacuated. Various options such as reprocessing and intermediate storage awaiting final disposal were evaluated against criteria as available techniques, safety, waste production and overall costs. Finally the option of an AFR (away-from-reactor) intermediate dry storage of the BR3 and other spent fuel in seven CASTOR BR3® casks was adopted. As the SCK•CEN declared this spent fuel as radioactive waste, NIRAS/ONDRAF, the Belgian radioactive waste management agency became directly involved and the decision was taken to construct a small building at the Belgoprocess nuclear site for storing the CASTOR BR3® casks. Loading at the SCK•CEN followed by transport to Belgoprocess and storage is scheduled to take place at the end of 2001. The CASTOR BR3® cask weighing some 25 tonnes, consists of a monolithic body and has two independent lids with metal seals guaranteeing the long term leak-tightness of the cask. The CASTOR BR3® cask is designed for transport and the intermediate storage of at least 50 years. Although a defect of the leaktightness of a CASTOR BR3® cask is very unlikely to occur, an intervention scenario had to be developed. As no pool is present at the Belgoprocess nuclear site to unload the fuel, an innovative procedure is developed that consists of transferring the basket, containing the spent fuel, into another CASTOR BR3® cask. This operation can be performed in the hot cell of the existing storage building for high level waste at the Belgoprocess site.

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.

Decommissioning Activities for Salaspils Research Reactor

2011 ◽  
Author(s):  
A. Abramenkovs ◽  
J. Malnacs
Keyword(s):  
Radioactive Waste ◽  
Research Reactor ◽  
Legal Aspects ◽  
Radioactive Wastes ◽  
Measurement Equipment ◽  
Radiation Measurement ◽  
Spent Fuel ◽  
Nuclear Facility ◽  
Radioactive Materials ◽  
Conceptual Study

In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor (SRR). The reactor is out of operation since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und Umwelttechnik GmbH at 1998–1999. The Latvian government decided to start the direct dismantling to “green field” in October 26, 1999. The upgrade of decommissioning and dismantling plan was performed in 2003–2004 years, which change the main goal of decommissioning to the “brown field”. The paper deals with the SRR decommissioning experience during 1999–2010. The main decommissioning stages are discussed including spent fuel and radioactive wastes management. The legal aspects and procedures for decommissioning of SRR are described in the paper. It was found, that the involvement of stakeholders at the early stages significantly promotes the decommissioning of nuclear facility. Radioactive waste management’s main efforts were devoted to collecting and conditioning of “historical” radioactive wastes from different storages outside and inside of reactor hall. All radioactive materials (more than 96 tons) were conditioned in concrete containers for disposal in the radioactive wastes repository “Radons” at Baldone site. The dismantling of contaminated and activated components of SRR systems is discussed in paper. The cementation of dismantled radioactive wastes in concrete containers is discussed. Infrastructure of SRR, including personal protective and radiation measurement equipment, for decommissioning purposes was upgraded significantly. Additional attention was devoted to the free release measurement’s technique. The certified laboratory was installed for supporting of all decommissioning activities. All non-radioactive equipments and materials outside of reactor buildings were released for clearance and dismantled for reusing or conventional disposing. Weakly contaminated materials from reactor hall were collected, decontaminated and removed for clearance measurements.

Operational Programs for National Radioactive Waste and Spent Fuel Management Programme in Slovenia

2007 ◽  
Author(s):  
Nadja Zˇeleznik ◽  
Metka Kralj ◽  
Irena Mele
Keyword(s):  
Radioactive Waste ◽  
Management Programme ◽  
Spent Fuel ◽  
Fuel Management ◽  
Nuclear Facilities ◽  
National Agency ◽  
National Programme ◽  
Action Programme ◽  
Operational Activities ◽  
Technical Solutions

The first separate National Radioactive Waste and Spent Fuel Management Programme (National Programme) was prepared in Slovenia in 2005 as a supplementary part of the National Environmental Action Programme and was adopted in February 2006 by the Slovenian Parliament. The new National Programme includes all topics being relevant for the management of the radioactive waste and spent fuel which are produced in Slovenia, from the legislation and identification of different waste streams, to the management of radioactive waste and spent fuel, the decommissioning of nuclear facilities and management of (TE)NORM in the near future from 2006 up to the 2015. The National Programme identified the existing and possible future problems and proposed the technical solutions and action plans for two distinctive periods: 2006–2009 and 2010–2015. According to the requirement of Act on Protection against Ionising Radiation and Nuclear Safety the national Agency for Radwaste Management (ARAO) prepared the operational programmes for the four year period with technical details on implementation of the National programme. ARAO gained the detailed plans of different involved holders and proposed 9 operational programmes with aims, measures, individual organizations in charge, expenses and resources for each of the programmes. The Operational programmes were already reviewed by the Ministry of Environment and Physical Planning and are under acceptance. The orientation of the radioactive waste management according to the National Programme and operational activities within additional limitations based on the strategical decisions of Slovenian Government is presented in the paper.

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.

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