Solid Radioactive Waste Management Facility Design for Managing Candu® 600 MW Nuclear Generating Station Retube/Refurbishment Waste Streams

2007 ◽  
Author(s):  
N. Pontikakis ◽  
D. Scott ◽  
J. Hopkins ◽  
V. Bajaj ◽  
L. Nosella
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Atomic Energy ◽  
Waste Streams ◽  
Design Features ◽  
Main Design ◽  
Design Activities ◽  
Solid Radioactive Waste ◽  
Waste Handling ◽  
Canada Limited

The main design features of the retube canisters, waste handling equipment and waste containers designed by Atomic Energy of Canada Limited (AECL®) and implemented in support of the retube/refurbishment activities for CANDU 600 MW nuclear generating stations are described in this paper. The retube/refurbishment waste characterization and the waste management principles, which form the basis of the design activities are also briefly outlined.

Towards Solving the Problems of the Solid Radioactive Wastes From Decommissioned Soviet-Designed Nuclear Submarines

2007 ◽  
Author(s):  
Bjo̸rn Borgaas ◽  
Ingar Amundsen ◽  
Ole Reistadt
Keyword(s):  
Radioactive Waste ◽  
Nuclear Safety ◽  
Long Term Storage ◽  
Bilateral Agreement ◽  
Solid Radioactive Waste ◽  
The Individual ◽  
Waste Handling ◽  
Term Storage ◽  
Shipyard Workers

This paper describes the cooperation and inspection arrangements for verifying the dismantlement of non-strategic Russian submarines, including waste handling, in accordance with the provisions given in the bilateral agreement between the Governments of Russia and Norway and the Norwegian Plan of Action for Nuclear Safety. The main concerns during the project implementation are nuclear safety, the individual safety of workers and the safe and secure handling of radioactive and toxic wastes. Based on data provided by the shipyard on individual exposure, one dismantlement project results in average in an effective dose for shipyard workers between 1,1 and 1,9 mSv, depending on the scope of the work for each worker. The main conclusion is that the present handling of solid radioactive waste is not optimal as such waste now is being put into the reactor compartments without the possibility for adequate control, including the retrieval for repacking or transfer to adequate storage facilities, after the reactor compartments have been placed in the long term storage facility in Saida Bay. Today there is no repository in Northwest-Russia for defence-related radioactive waste.

Radioactive Waste Management in Lebanon

2010 ◽  
Author(s):  
Muzna Assi
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Atomic Energy Commission ◽  
Atomic Energy ◽  
Technical Cooperation ◽  
Energy Agency ◽  
Research Fields ◽  
Reference Number ◽  
Orphan Sources ◽  
Radioactive Sources

The disused sealed radioactive sources including orphan sources in Lebanon, along with the growing industry of sealed radioactive sources in medical, industrial and research fields have posed a serious problem for authorities as well as users due to the lack of a national store for disused radioactive sources. Assistance from the International Atomic Energy Agency (IAEA) was requested to condition and store disused radium needles and tubes present at two facilities. The mission took place on July 25, 2001 and was organized by the IAEA in cooperation with the Lebanese Atomic Energy Commission (LAEC). Other disused radioactive sources were kept in the facilities till a safer and securer solution is provided; however orphan sources, found mainly during export control, were brought and stored temporarily in LAEC. The necessity of a safe and secure store became a must. Prior to October 2005, there was no clear legal basis for establishing such store for disused radioactive sources, until the ministerial decree no 15512 dated October 19, 2005 (related to the implementation of decree-law no 105/83) was issued which clearly stated that “The LAEC shall, in cooperation with the Ministry of Public Health, establish a practical mechanism for safe disposal of radioactive waste”. Following this, the work on inventory of disused sealed sources along with collecting orphan sources and placing them temporarily in LAEC was legally supported. Moreover, several missions were planned to repatriate category I and II sources, one of which was completed specifically in August 2009; other missions are being worked on. In 2008, a national technical cooperation project with the IAEA was launched. Under the Technical Cooperation (TC) project with reference number LEB3002, the project was entitled “Assistance in the establishment of a safe temporary national storage at the LAECfor orphan sources and radioactive waste” which cycle is 2009–2011. Under this project, a national store for radioactive sources in the third basement of LAEC is being established. The area is being reconstructed currently and will be equipped when ready under LEB3002 project. Along with this, a system for sealed disused sources management has been prepared, part of which is applied now and the rest will be applied upon the establishment of the store. This paper will cover the inventory collection process, the study for the establishment of this store, the present and prospective waste management system, and the waste acceptance criteria.

AMS Measurement of 59Ni at China Institute of Atomic Energy

Radiocarbon ◽  
2013 ◽  
Vol 55 (2) ◽  
pp. 302-307 ◽  
Author(s):  
Ming He ◽  
Xiangdong Ruan ◽  
Wei Wang ◽  
Liang Dou ◽  
Lingbo Xie ◽  
...  
Keyword(s):  
Mass Spectrometry ◽  
Radioactive Waste ◽  
Waste Management ◽  
Accelerator Mass Spectrometry ◽  
Detection System ◽  
Atomic Energy ◽  
Detection Sensitivity ◽  
Research Fields ◽  
Laboratory Reference ◽  
Reference Samples

The long-lived radioisotope 59Ni is of interest in various research fields including neutron dosimetry, radioactive waste management, and astrophysics. In order to achieve the sensitivity required for such applications, the technique of accelerator mass spectrometry (AMS) 59Ni measurement has been developed at the AMS facility at China Institute of Atomic Energy (CIAE). Based on the AE-Q3D detection system in the CIAE AMS facility, the interference in 59Ni counting from the isobar 59Co has been reduced by a factor of 8 × 106. A series of laboratory reference samples and a blank sample were measured to check the performance of 59Ni measurement. A detection sensitivity of about 5 × 10−13 (59Ni/Ni) has been obtained.

Radioactive Waste and Spent Fuel Management in Argentina

2012 ◽  
Vol 1475 ◽  
Author(s):  
Elvira Rosa Maset
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Environmental Remediation ◽  
Power Plants ◽  
Fuel Cycle ◽  
Atomic Energy Commission ◽  
Atomic Energy ◽  
Spent Fuel ◽  
Radioactive Waste Management ◽  
Management Regime

ABSTRACTSince its creation in 1950, the Argentine Atomic Energy Commission (CNEA), has worked on the development of applications for the peaceful use of nuclear energy. They include, among others, research and development activities in basic and nuclear technology areas, the operation of important facilities for the production of radioisotopes and the performance of tasks in connection with the nuclear fuel cycle, mining and uranium processing activities, manufacturing of fuel elements, production of heavy water and the operation of two nuclear power plants. Also demonstrating reprocessing programs have been developed.As a result of the above mentioned activities performed in the nuclear field by private and public entities, various types of radioactive waste have been and are produced during operation and maintenance of facilities and plants, and will be produced in their future decommissioning. CNEA is also responsible for the environmental remediation of the closed uranium mining and milling facilities and for the management of disused sealed sources from medical and industrial applications.Activities concerning radioactive waste management are carried on according not only to Nuclear Regulatory Authority requirements and International Atomic Energy Agency recommendations, but also to the national legal framework.The Law Nº 25.018, "Radioactive Waste Management Regime“(1998), created the National Program for Radioactive Waste Management (PNGRR), as part of CNEA organization.

Radioactive Waste Characterization and Tracking System at the French Atomic Energy Commission

2013 ◽  
Author(s):  
Hervé Lamotte ◽  
Luc Torreblanca ◽  
Suzel Vilarel
Keyword(s):  
Information System ◽  
Radioactive Waste ◽  
Waste Management ◽  
Waste Treatment ◽  
Solid Waste Management ◽  
Tracking System ◽  
Atomic Energy Commission ◽  
Atomic Energy ◽  
New Information ◽  
Before And After

CARAIBES is the traceability information system in radioactive solid waste management of the French Atomic Energy Commission, (CEA). Initially developed for the reprocessing facility of low and intermediate level waste of the centre of Cadarache, it has been gradually enhanced to manage very low level waste and the facilities of the centres of Saclay and Fontenay-aux-Roses. This software is directly connectable to characterization equipment as X-Ray measurement, gamma spectrometric measurement and/or neutronic measurement. After 15 years of operation, a new information system should replace it in 2014. This new CARAIBES V2 will make the functional and technical improvements resulting from the CARAIBES feedback but will also allow to manage all produced and/or treated waste in the Atomic Energy Commission and to ensure the traceability of waste and waste treatment before and after its packaging. From the analysis of the processes, waste management was described as an iterative process where, in every step, the facility in charge of a waste will apply a treatment to it (packaging, association or division) and will characterize it in order to evacuate it towards the next facility. Associated with a strongly customizable information system, this process allows the management of all kind of radioactive waste, including radioactive liquids. The final objectives are: to share a unique software and only one database for all CEA’s facilities involved in radioactive waste management, to be able to track the radioactive waste through all steps of its process, to meet the user’s needs as well as the regulatory requirements.

Systematical Approach to the Radioactive Waste Management in Slovak Republic

2001 ◽  
Author(s):  
Milan Breza
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Solid Waste ◽  
Waste Treatment ◽  
Slovak Republic ◽  
Storage Tanks ◽  
Waste Streams ◽  
And Storage ◽  
Radioactive Waste Treatment

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.

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