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.

An overview of research activities on cementitious materials for radioactive waste management

2012 ◽  
Vol 1475 ◽  
Author(s):  
Zoran Drace ◽  
Irena Mele ◽  
Michael I. Ojovan ◽  
R. O. Abdel Rahman
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Management Practices ◽  
Fuel Cycle ◽  
Large Body ◽  
Cementitious Materials ◽  
Radioactive Waste Management ◽  
Research Activities

ABSTRACTAn overview is given on research activities on cementitious materials for radioactive waste management systems based on the IAEA Coordinated Research Project (CRP) held in 2007-2010. It has been joined by 26 research organizations from 22 countries which shared their research and practical activities on use of cementitious materials for various barrier purposes. The CRP has initially formulated the research topics considered within four specific streams: A) Conventional cementitious systems; B) Novel cementitious materials and technologies; C) Testing and waste acceptance criteria; and D) Modelling long term behaviour.The CRP has analysed both barrier functions and interactions envisaged between various components with focus on predisposal stage of waste management. Cementation processes have achieved a high degree of acceptance and many processes are now regarded as technically mature. A large body of information is currently available on proven waste conditioning technologies although novel approaches are continuing to be devised.Most of the existing technologies have been developed for conditioning of large amounts of operational radioactive waste from nuclear power plants and other nuclear fuel cycle facilities. However new waste streams including those resulting from legacy and decommissioning activities required improved material performance and technologies.The most important outcome of CRP was the exchange of information and research co-operation between different institutions and has contributed towards general enhancement of safety by improving waste management practices and their efficiency. The paper presents the most important results and trends revealed by CRP participants. The research contributions of participating organizations will be published as country contributions in a forthcoming IAEA technical publication.

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 Radioactive Waste Management of Fusion Power Plants

10.5772/35045 ◽  
2012 ◽  
Author(s):  
Luigi Di ◽  
Laila El-Guebaly ◽  
Boris Kolbasov ◽  
Vincent Massaut ◽  
Massimo Zucchetti
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Power Plants ◽  
Radioactive Waste Management ◽  
Fusion Power

Optimization of Concrete Container Composition in Radioactive Waste Management

1985 ◽  
Vol 50 ◽  
Author(s):  
I. B. Plecas ◽  
Li. L. Mihajlovic ◽  
A. M. Kostadinovic
Keyword(s):  
Mechanical Properties ◽  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Leakage Rate ◽  
Intermediate Level ◽  
Radioactive Waste Management ◽  
Intermediate Level Radioactive Waste

AbstractIn this paper an optimization of concrete container composition, used for storing low and intermediate level radioactive waste from nuclear power plants in Yugoslavia, is presented.Mechanical properties 37−52 MPa, permeability 1.07. 10−13 - 1.50. 10−11cm2 and leakage rate 3.66. 10−6 - 1.77. 10−4 cm/d for concrete made of commercial materials, were tested.

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.

Generic Design Assessment of Long-Term Spent Fuel Storage for New Reactors in the UK

2011 ◽  
Author(s):  
D. Watson ◽  
I. Streatfield ◽  
C. Grundy ◽  
S. Price-Water ◽  
D. Glazbrook ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Assessment Process ◽  
Spent Fuel ◽  
Radioactive Waste Management ◽  
Design Assessment ◽  
Safety Issues ◽  
The Uk ◽  
Generic Design

In the UK the Office for Nuclear Regulation and the Environment Agency developed the Generic Design Assessment process in response to a request from the UK Government. The process allows the regulators to jointly assess new nuclear reactor designs, in advance of any site-specific proposals to build a nuclear power station. Two reactor types are currently being assessed within Generic Design Assessment: • AREVA and Electricite´ de France’s UK EPR®; • Westinghouse Electric Company’s AP1000®. This paper will present the outcome of the assessment of radioactive waste management within the Generic Design Assessment process. One aspect of particular interest is the management of spent fuel from proposed new reactors as the assessment is based on an assumption that it will be sent for disposal. Therefore the paper will specifically consider the management of spent fuel and how this affects the regulatory decisions. The paper will look at four aspects. The first of these is to give a short overview of the Generic Design Assessment process. This will be followed by a summary of the Generic Design Assessment Radioactive Waste Management assessment on the acceptability of: • The types of waste and spent fuel. • The plans for conditioning of the wastes. • The safety issues associated with short-term storage. • The safety issues associated with long-term storage. • The issues associated with the disposal of the wastes. • The safety issues associated with decommissioning the reactors. The third aspect will be to look at the work commissioned by the Office of Nuclear Regulation in support of the Generic Design Assessment of radioactive waste management and how this has affected the regulatory decisions. This work has looked at the long-term stability of spent fuel in storage and the potential faults associated with the storage and handling of the spent fuel. The paper will end with the main conclusions of the radioactive waste management assessment within Generic Design Assessment. Looking at how storage of spent fuel can affect transport, disposal and decommissioning and how work by licensees could alter these conclusions.

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.

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