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.

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.

scholarly journals ANALYSIS OF NATIONAL ACTIVITY FOR EXECUTING THE JOINT CONVENTION ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT

2016 ◽  
Vol 11 (5) ◽  
pp. 5-11
Author(s):  
A. I. Sobolev ◽  
I. V. Syreyshchikov
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Russian Federation ◽  
Spent Fuel ◽  
Fuel Management ◽  
Radioactive Waste Management ◽  
National Report ◽  
Safe Management ◽  
National Activity ◽  
The Russian Federation

Analysis of the results of the activity of the State Atomic Energy Corporation "Rosatom" and the Federal Service for Ecological, Technological and Nuclear Supervision for preparing the Russian Federation reports at meetings of the contracting parties to fulfil the obligations arising from the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was performed.The main content of the report refers to the fourth national report of the Russian Federation submitted to the IAEA in May 2015. The main results of the activity for the formation of a unified state system for RW management were considered. Analysis of the questions of the Member States of the Joint Convention to the content of the national report was performed. A review of the activities of the FSUE "RosRAO" in terms of solving the basic problems for the safe management of radioactive waste was presented.

Incineration of Spent Ion Exchange Resins in a Triphasic Mixture at Belgoprocess

2001 ◽  
Author(s):  
Jan Deckers ◽  
Paul Luycx
Keyword(s):  
Ion Exchange ◽  
Radioactive Waste ◽  
Calorific Value ◽  
Ion Exchange Resins ◽  
Nuclear Facilities ◽  
National Agency ◽  
Gas Treatment ◽  
Waste Production ◽  
Combustible Wastes ◽  
Exchange Resins

Abstract Up to 1998, spent ion exchange resins have been fed to the incinerator in combination with various other solid combustible wastes at Belgoprocess. However, thanks to sustained efforts to reduce radioactive waste production in all nuclear facilities in Belgium, the annual production of solid combustible waste is now much too small to allow this practice to be continued. Since the incinerator at Belgoprocess is not capable of treating spent ion exchange resins as such, it was decided to adopt the use of foam as a carrier to feed the resins to the incinerator. The mixture is a pseudohomogeneous charged foam, ensuring easy handling and allowing incineration in the existing furnace, while a number of additives may be included, such as oil to increase the calorific value of the mixture and accelerate combustion. The first incineration campaign of spent ion exchange resins in a triphasic foam mixture, in conjunction with other liquid and solid combustible wastes, will be started in January 2000. The foam, comprising 70% by weight of resins, 29% by weight of water and 1% by weight of surfactant will be pulverized in the incinerator through an injection lance, at a feed rate of 40 to 100 kg/h. The incinerator and associated off-gas treatment system can be operated at standard conditions. Belgoprocess is the subsidiary of the Belgian national agency for the management of radioactive waste, known by its Dutch and French acronyms, NIRAS and ONDRAF respectively. The company ensures the treatment, conditioning and interim storage of nearly all radioactive waste produced in Belgium.

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.

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.

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.

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