Calculated Reduction of the Residual Adsorbent Mass Requiring Long-Term Storage in Radioactive Waste Processing by Magnetic Separation

2007 ◽  
Vol 160 (3) ◽  
pp. 352-360
Author(s):  
James H. P. Watson ◽  
Patrick Foss-Smith ◽  
Ray Lidzey
Keyword(s):  
Radioactive Waste ◽  
Magnetic Separation ◽  
Waste Processing ◽  
Long Term Storage ◽  
Term Storage

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.

Decommissioning and Dismantling Solution Development for Volodarsky Civil Nuclear Fleet Support Ship

2009 ◽  
Author(s):  
Konstantin N. Koulikov ◽  
Rinat A. Nizamutdinov ◽  
Andrey N. Abramov ◽  
Anatoly I. Tsubanikov
Keyword(s):  
Radioactive Waste ◽  
Radiation Safety ◽  
Pollution Source ◽  
Long Term Storage ◽  
Murmansk Region ◽  
State Corporation ◽  
Solid Radioactive Waste ◽  
Federal Special Purpose Program ◽  
Term Storage

Having about 200 tons of solid radioactive waste aboard, the Volodarskiy Floating Technical Base (FTB) is a potential radiation pollution source for the Murmansk region and Kola Bay, as her long-term berthing negatively affects the hull structures. Thereby, Atomflot collaborated with ANO Aspect-Konversia and JSC NIPTB Onega within the frameworks of Federal Special-purpose Program “Assurance of Nuclear and Radiation Safety for 2008 and for the period up to 2015” and developed the Volodarskiy FTB dismantling concept. In 2008 in the course of development of the Volodarskiy FTB dismantling concept the following works were carried out: 1) vessel condition survey, including SRW radiological analysis; 2) feasibility study of the Volodarskiy FTB dismantling alternatives. In this regard the following alternatives were analyzed: – formation of the package assembly in the form of vessel’s undivided hull for durable storage in the Saida long-term storage facility (LTSF); - formation of individual SRW package assemblies for durable storage in the Saida LTSF; - comprehensive recycling of all solid radioactive waste by disposal in protective containers. 3) selection and approval of the dismantling alternative. The alternative of formation of individual SRW package assemblies for durable storage in the Saida LTSF was selected by the Rosatom State Corporation. In this case the works will be performed on a step-by-step basis at the Atomflot enterprise and SRE Nerpa. The conceptual dismantling technology was developed for the selected Volodarskiy FTB dismantling option. The proceedings contain description of options, analysis procedure and proposal for further study of mentioned challenge.

Cementitious Materials for Radioactive Waste Management Within IAEA Coordinated Research Project

2011 ◽  
Author(s):  
Zoran Drace ◽  
Michael I. Ojovan
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Cementitious Materials ◽  
Radioactive Waste Management ◽  
Long Term Storage ◽  
Waste Immobilization ◽  
Materials Used ◽  
Cementitious Systems ◽  
Term Storage

The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in 2007 [1, 2]. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste management system with various purposes and included waste packages, wasteforms and backfills as well as investigation of interactions and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods of production of cementitious materials for: immobilization into wasteform, backfills and containers; (vi) conditions envisaged in the disposal environment for packages (physical and chemical conditions, temperature variations, groundwater, radiation fields); (vii) testing and nondestructive monitoring techniques for quality assurance of cementitious materials; (viii) waste acceptance criteria for waste packages, waste forms and backfills; transport, long term storage and disposal requirements; and finally (ix) modelling or simulation of long term behaviours of cementations materials used for packaging, waste immobilization and backfilling, especially in the post-closure phase. The CRP has gathered overall 26 research organizations from 22 Member States aiming to share their research and practices on the use of cementitious materials [2]. The main research outcomes of the CRP were summarized in a summary report currently under preparation to be published by IAEA. The generic topical sections covered by report are: a) conventional cementitious systems; b) novel cementitious materials and technologies; c) testing and waste acceptance criteria; and d) modelling long term behaviour. These themes as well as all contributions of participating organizations were further developed in the individual reports to be presented in the IAEA publication. The CRP facilitated the exchange of information and research co-operation in resolving similar problems between different institutions and contributed towards improving waste management practices, their efficiency and general enhancement of safety.

Doses Forming Paths of External Irradiation of Personnel on Radioactive Waste Disposal Facilities

2003 ◽  
Author(s):  
T. V. Yakimenco ◽  
T. I. Paramonova ◽  
V. A. Smirnov
Keyword(s):  
Radioactive Waste ◽  
Fuel Cycle ◽  
Pollution Prevention ◽  
Radioactive Waste Disposal ◽  
External Irradiation ◽  
Long Term Storage ◽  
Average Activity ◽  
Term Storage ◽  
Centralized System

The centralized system of radioactive waste management formed beyond of a nuclear fuel cycle exist in Russia. In territory of Russian Federation 16 regional specialized combines (SO) “Radon” are located, the majority of them is entered into operation in the first half 60th years. The specialized combines “Radon” are carrying out centralized collection, RW transportation, processing, localization and long-term storage of RW low and average activity, delivery service of new sources of ionizing radiation to users, take part in liquidation of radioactive contamination of served territory, carry out an nature-conservative measures of pollution prevention of the environment fromradioactive substances and ensuring radiation safety of population. For years of their existence total number of the personnel has made hundreds person. In most cases the personnel of combines are under a radiation control since time of introduction of objects in operation, about 40 years.

Improving the Durability of Protective Materials Based on Inorganic Binders when Exposed to Short-Wave Radiation

2015 ◽  
Vol 725-726 ◽  
pp. 391-395 ◽  
Author(s):  
Oleg Makarevich ◽  
Olga Smirnova
Keyword(s):  
Radioactive Waste ◽  
Portland Cement ◽  
Short Wave ◽  
Wave Radiation ◽  
Optimal Composition ◽  
Short Wave Radiation ◽  
Long Term Storage ◽  
Term Storage

The concretes and mortars based on the Portland cement are able to perform the functions of the protective and durable materials for the disposal and long term storage of radioactive waste. It has investigated the influence of fineness of the carbon-containing component and the type of the water-reducing polycarboxylate-based admixtures on the properties of protective concrete of the recommended optimal composition.

scholarly journals Microscopic and spectroscopic bioassociation study of uranium(VI) with an archaeal Halobacterium isolate

PLoS ONE ◽  
2022 ◽  
Vol 17 (1) ◽  
pp. e0262275
Author(s):  
Stephan Hilpmann ◽  
Miriam Bader ◽  
Robin Steudtner ◽  
Katharina Müller ◽  
Thorsten Stumpf ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Rock Salt ◽  
Luminescence Spectroscopy ◽  
Spectroscopic Techniques ◽  
High Level Radioactive Waste ◽  
Long Term Storage ◽  
High Level ◽  
The Impact ◽  
Term Storage

The safe disposal of high-level radioactive waste in a deep geological repository is a huge social and technical challenge. So far, one of the less considered factors needed for a long-term risk assessment, is the impact of microorganisms occurring in the different host rocks. Even under the harsh conditions of salt formations different bacterial and archaeal species were found, e. g. Halobacterium sp. GP5 1–1, which has been isolated from a German rock salt sample. The interactions of this archaeon with uranium(VI), one of the radionuclides of major concern for the long-term storage of high-level radioactive waste, were investigated. Different spectroscopic techniques, as well as microscopy, were used to examine the occurring mechanisms on a molecular level leading to a more profound process understanding. Batch experiments with different uranium(VI) concentrations showed that the interaction is not only a simple, but a more complex combination of different processes. With the help of in situ attenuated total reflection Fourier-transform infrared spectroscopy the association of uranium(VI) onto carboxylate groups was verified. In addition, time-resolved laser-induced luminescence spectroscopy revealed the formation of phosphate and carboxylate species within the cell pellets as a function of the uranium(VI) concentration and incubation time. The association behavior differs from another very closely related halophilic archaeon, especially with regard to uranium(VI) concentrations. This clearly demonstrates the importance of studying the interactions of different, at first sight very similar, microorganisms with uranium(VI). This work provides new insights into the microbe-uranium(VI) interactions at highly saline conditions relevant to the long-term storage of radioactive waste in rock salt.

The Long-Term Storage of Radioactive Waste and Spent Fuel: Safety and Policy Considerations

2007 ◽  
Author(s):  
J. Rowat ◽  
P. Metcalf
Keyword(s):  
Radioactive Waste ◽  
Position Paper ◽  
Spent Fuel ◽  
Management Options ◽  
Institutional Control ◽  
Long Term Storage ◽  
Security Costs ◽  
Term Storage

Storage is a necessary step in the overall management of radioactive waste. In recent years, due to the unavailability of disposal facilities, storage facilities intended originally as temporary, have had their lifetimes extended and consideration has been given, in some countries, to the use of long term storage (LTS) as a management option. In 2003, the IAEA published a position paper titled “The Long Term Storage of Radioactive Waste: Safety and Sustainability”. The position paper, which written for a non-specialist audience, focused on seven key factors for safety and sustainability of LTS, namely: safety, maintenance/institutional control, retrieval, security, costs, community attitudes and retention of information. The Agency is preparing a follow-up report to the position paper that elaborates in a more technical manner upon the issues raised in the position paper and issues important for implementation of LTS. It also provides some discussion of the reasons for implementing a LTS option and contrasts LTS with aspects of other management options. The present paper provides an overview of the draft follow-up report.

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