The Sorption of Uranium and Technetium on Bentonite, Tuff and Granodiorite

1994 ◽  
Vol 353 ◽  
Author(s):  
G. M. N. Baston ◽  
J. A. Berry ◽  
M. Brownsword ◽  
M. M. Cowper ◽  
T. G. Heath ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Mathematical Modelling ◽  
Nuclear Microprobe ◽  
Mineral Surfaces ◽  
Geological Materials ◽  
Reducing Conditions ◽  
Geochemical Speciation ◽  
Preliminary Study ◽  
High Level ◽  
Hlw Repository

AbstractA combined experimental and modelling study of the sorption of uranium and technetium on geological materials has been carried out as part of the PNC programme to increase confidence in the performance assessment for a high-level radioactive waste (HLW) repository in Japan. Batch sorption experiments have been performed in order to study the sorption of uranium and technetium onto bentonite, tuff and granodiorite from both equilibrated seawater and de-ionised water under strongly-reducing and non-reducing conditions.A preliminary study of the sorption of uranium on mineral surfaces in granodiorite has also been undertaken using a nuclear microprobe.Mathematical modelling using the geochemical speciation program HARPHRQ in conjunction with the HATCHES database has been carried out in order to interpret the results of the sorption experiments.

The Effect of Temperature on the Sorption of Technetium, Uranium, Neptunium and Curium on Bentonite, Tuff and Granodiorite

1996 ◽  
Vol 465 ◽  
Author(s):  
G M N Baston ◽  
J A Berry ◽  
M Brownsword ◽  
T G Heath ◽  
D J Blett ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Mathematical Modelling ◽  
Performance Assessment ◽  
Room Temperature ◽  
Effect Of Temperature ◽  
Geological Materials ◽  
Reducing Conditions ◽  
Geochemical Speciation ◽  
Waste Repository ◽  
High Level

ABSTRACTA study of the sorption of the radioelements: technetium; uranium; neptunium; and curium onto geological materials has been carried out as part of the PNC programme to increase confidence in the performance assessment for a high-level radioactive waste repository in Japan. Batch sorption experiments have been performed in order to study the sorption of the radioelements onto bentonite, tuff and granodiorite from equilibrated de-ionised water under strongly-reducing conditions at both room temperature and at 60°C.Mathematical modelling using the geochemical speciation program HARPHRQ in conjunction with the HATCHES database has been undertaken in order to interpret the experimental results.

Effect of Redox Conditions on the Sorption of Plutonium onto Geological Materials

2002 ◽  
Vol 713 ◽  
Author(s):  
J.A. Berry ◽  
M. Brownsword ◽  
D.J. Ilett ◽  
C.M. Linklater ◽  
C. Mason ◽  
...  
Keyword(s):  
Experimental Design ◽  
Radioactive Waste ◽  
Performance Assessment ◽  
Geochemical Modelling ◽  
Redox Conditions ◽  
Radioactive Waste Repository ◽  
High Level Radioactive Waste ◽  
Geological Materials ◽  
Waste Repository ◽  
High Level

ABSTRACTThis paper presents the latest results from a programme of generic sorption studies undertaken to increase confidence in data underpinning the performance assessment for a potential high-level radioactive waste repository in Japan. The sorption of plutonium onto basalt and sandstone was studied as a function of redox conditions that ranged from strongly reducing to oxidising. Geochemical modelling was used to aid experimental design and the interpretation of results.

The Sorption of Polonium, Actinium and Protactinium Onto Geological Materials

1999 ◽  
Vol 556 ◽  
Author(s):  
G. M. N. Baston ◽  
J. A. Berry ◽  
M. Brownsword ◽  
T. G. Heath ◽  
D. J. Ilett ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Performance Assessment ◽  
Room Temperature ◽  
Radioactive Waste Repository ◽  
Geological Materials ◽  
Reducing Conditions ◽  
Chemical Modelling ◽  
Waste Repository

AbstractThis paper describes a combined experimental and modelling programme of generic sorption studies to increase confidence in the performance assessment for a potential highlevel radioactive waste repository in Japan. The sorption of polonium, actinium and protactinium onto geological materials has been investigated. Sorption of these radioelements onto bentonite, tuff and granodiorite from equilibrated de-ionised water was studied under reducing conditions at room temperature. In addition, the sorption of actinium and protactinium was investigated at 60°C. Thermodynamic chemical modelling was carried out to aid interpretation of the results.

scholarly journals PREDICTION OF THE TECTONIC PROCESSES AT A SELECTED AREAS FOR DISPOSE RADIOACTIVE WASTE

2007 ◽  
Vol 1 ◽  
pp. 70
Author(s):  
Vladislav Morozov ◽  
Sergey Belov ◽  
Ilya Kolesnikov ◽  
Victor Tatarinov
Keyword(s):  
Radioactive Waste ◽  
Underground Water ◽  
Tectonic Block ◽  
Tectonic Processes ◽  
Time Space ◽  
Geodynamic Processes ◽  
Heated Debate ◽  
High Level ◽  
Geological Formations ◽  
Hlw Repository

The possibility of using deep geological formations to dispose of high-level radioactive waste (HLW) is a subject raising heated debate among scientists. In Russia, the idea of constructing HLW repository in the Niznekansky granitoid massif (NKM) in Krasnoyarsk area is widely discussed. To solve this problem we are elaborating a technology associated with time - space stability prediction of the geological environment, which is subject to geodynamic processes evolutionary effects. It is based on the prediction of isolation properties stability in a structural tectonic block of the Earth’s crust for a given time. The danger is in the possibility that the selected structural block may be broken by new tectonic faults or movements on a passive fault may be activated and thus underground water may penetrate to HLW containers. 

Study on Performance Assessment for HLW Repository in China

2009 ◽  
Author(s):  
Weiming Chen ◽  
Ju Wang ◽  
Rui Su ◽  
Yunfeng Li
Keyword(s):  
Radioactive Waste ◽  
Performance Assessment ◽  
Assessment Model ◽  
Design Parameters ◽  
Beishan Granite ◽  
High Level Radioactive Waste ◽  
High Level ◽  
Sensitive Parameters ◽  
Beishan Area ◽  
Hlw Repository

This paper presents the latest achievements of performance assessment (PA) for high level radioactive waste (HLW) repository in China. The first PA model, taking Beishan granite site as an example, is established with GoldSim and is verified by comparison with Japanese PA model. Then the behaviors of granite repository in Beishan area are simulated. The results from these simulations show that the engineered barrier is the most important part inside the repository, especially its bentonite plays a key role in the retardation of repository after the nuclide is released from the vitrified waste. Five sensitive parameters are identified and two design parameters are optimized. As a result, it has been proved that performance assessment model is a necessary tool to understand the behaviors of repository, to identify sensitive parameters, and to optimize design parameters.

Repository Site Characterization: Comparing International Experience

2009 ◽  
Author(s):  
Martin Goldsworthy ◽  
Till Popp ◽  
Knut Seidel ◽  
Johannes Bruns
Keyword(s):  
Radioactive Waste ◽  
Selection Process ◽  
International Experience ◽  
Geological Repository ◽  
Clay Cover ◽  
Under Construction ◽  
High Level ◽  
A Site ◽  
Hlw Repository ◽  
The Ideal

An important part of the work described here was a study of existing international experience in investigating deep geological repository sites. The objective of this study was to derive a basis for planning the content and extent of investigations which might be carried out in Germany in the future. Such investigations would be required in the course of a site selection process for a repository for HLW (high level radioactive waste). For this purpose information on suitable sites was gathered, mainly from literature sources. Suitable in this context meant two things. Firstly, the investigated site should be in rock similar to four being considered in Germany (salt, clay, crystalline and other hard rock under a clay cover). Secondly, the investigations carried out could reasonably be considered as being intended to lead to the use of the site as a repository. The investigation processes were presented, analysed and compared. The comparison was based on the quality and the intensity of the methods employed to obtain the information necessary for deciding between candidate repository sites in terms of safety and the feasibility of construction. In the final stage of the work the analysis and presentation method developed for the international sites was applied to the investigations already carried out at three German sites (Gorleben — a prospective HLW repository, Morsleben — an existing but now not operational repository for radioactive waste and Konrad — a repository currently under construction). The reported investigatory work was compared with the ideal investigations developed on the basis of the existing international experience.

Application of Formal Knowledge Engineering Approaches to Develop a Design Catalogue for a Japanese HLW Repository

2009 ◽  
Vol 1193 ◽  
Author(s):  
Masaaki Matsumoto ◽  
Osamu Sato ◽  
Hiroo Okubo ◽  
Hitoshi Makino ◽  
Yasuhiro Ochi ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Boundary Conditions ◽  
Design Process ◽  
Knowledge Engineering ◽  
Companion Paper ◽  
Formal Knowledge ◽  
Innovative Solutions ◽  
Advanced Knowledge ◽  
High Level ◽  
Hlw Repository

AbstractThe volunteer siting of disposal facilities for vitrified high-level radioactive waste (HLW) and TRU waste in Japan results in a particular need for flexibility to allow repositories to be tailored to specific sites. Instead of a single reference concept, a “catalogue” of designs for individual repository components is being developed, which can then be combined to form optimum solutions for particular site boundary conditions. As highlighted in a companion paper – Makino et al: Supporting Development of Practical Designs for a Japanese HLW Repository –, which puts the repository design process in the context of the Japanese HLW programme, the complexity of this work justifies use of advanced Knowledge Engineering approaches. In this paper three components are described – development of the knowledge base, assessing tacit system understanding and production of innovative solutions to resolve conflicts between requirements.

Sorption of Plutonium and Americium on Repository, Backfill and Geological Materials Relevant to The JNFL Low-Level Radioactive Waste Repository at Rokkasho-Mura

1994 ◽  
Vol 353 ◽  
Author(s):  
G M N Baston ◽  
J A Berry ◽  
M Brownsword ◽  
T G Heath ◽  
C J Tweed ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Sorption Behaviour ◽  
Radioactive Waste Repository ◽  
Geological Materials ◽  
Low Level ◽  
Anion Exchange Resins ◽  
Geochemical Speciation ◽  
Waste Repository ◽  
Exchange Resins ◽  
Low Level Radioactive Waste

AbstractAn integrated programme of batch sorption experiments and mathematical modelling has been carried out to study the sorption of plutonium and americium on a series of repository, backfill and geological materials relevant to the JNFL low-level radioactive waste repository at Rokkasho-Mura.The sorption of plutonium and americium on samples of concrete, mortar, sand/bentonite, tuff, sandstone and cover soil has been investigated. In addition, specimens of bitumen, cation and anion exchange resins, and polyester were chemically degraded. The resulting degradation product solutions, alongside solutions of humic and iso-saccharinic acids were used to study the effects on plutonium sorption onto concrete, sand/bentonite and sandstone.The sorption behaviour of plutonium and americium has been modelled using the geochemical speciation program HARPHRQ in conjunction with the HATCHES database.

Hydrolysis of trivalent plutonium and solubility of Pu(OH)3(am) under electrolytic reducing conditions

2016 ◽  
Vol 45 (48) ◽  
pp. 19449-19457 ◽  
Author(s):  
Hye-Ryun Cho ◽  
Young-Sang Youn ◽  
Euo Chang Jung ◽  
Wansik Cha
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Safety Assessment ◽  
Radioactive Waste Disposal ◽  
Reducing Conditions ◽  
System P ◽  
High Level ◽  
Hydrolysis Of

This paper focusses on the determination of the thermodynamic data of Pu(iii) hydrolysis, which are important for a long-term safety assessment of high-level radioactive waste disposal in a deep geological system.

Degradation of phosphatic waste forms incorporating long-lived radioactive isotopes

2001 ◽  
Vol 65 (5) ◽  
pp. 589-601 ◽  
Author(s):  
D. Read ◽  
C. T. Williams
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Radioactive Waste Disposal ◽  
Radioactive Isotopes ◽  
Long Term Stability ◽  
Waste Forms ◽  
Trivalent Actinides ◽  
High Level ◽  
Hlw Repository

AbstractThis paper provides a brief perspective on synthetic, phosphate-based waste forms for high level radioactive waste (HLW). Evidence in support of their long-term stability is then discussed by reference to the degradation of natural monazites with emphasis on the fate of released uranium, thorium and the rare earths (REE). It is apparent that the REE can be mobilized and fractionated at temperatures anticipated in a HLW repository (∼200°C). This provides an indication of the likely fate of the trivalent actinides (Am(III), Cm(III)) if incorporated in similar matrices. Thorium, though released on alteration of monazite, tends to re-concentrate locally in secondary, microcrystalline phases. In relative terms, U is readily removed from monazites. Although it can be re-concentrated in alteration products, the potential exists for substantial loss of U to groundwater. The findings of this research have important implications for the performance of radioactive waste disposal systems where there is a clear need for improved chemical data to describe the precipitation-dissolution of phosphate phases. It is concluded that monazite-like ceramics designed for the containment of HLW will retain tetravalent actinides but may release uranium in response to natural degradative processes.

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