Prestudy of final disposal of long-lived low and intermediate level waste

Energy Technology Data Exchange (ETDEWEB)

Wiborgh, M [ed.; Kemakta Konsult AB., Stockholm (Sweden)

1995-01-01

The repository for long-lived low and intermediate level waste, SFL 3-5, is foreseen to be located adjacent to the deep repository for spent encapsulated fuel, SFL 2. The SFL 3-5 repository comprises of three repository parts which will be used for the different categories of waste. In this report the work performed within a pre-study of the SFL 3-5 repository concept is summarised. The aim was to make a first preliminary and simplified assessment of the near-field as a barrier to radionuclide dispersion. A major task has been to compile information on the waste foreseen to be disposed of in SFL 3-5. The waste comprises of; low and intermediate level waste from Studsvik, operational waste from the central interim storage for spent fuel, CLAB, and the encapsulation plant, decommissioning waste from these facilities, and core components and internal parts from the reactors. The total waste volume has been estimated to about 25000 m{sup 3}. The total activity content at repository closure is estimated to be about 1 {center_dot}10{sup 17} Bq in SFL 3-5. At repository closure the short-lived radionuclides, for example Co-60 and Fe-55, have decayed considerably and the activity is dominated by nickel isotopes in the metallic waste from the reactors, to be disposed of in SFL 5. However, other radionuclides may be more or equally important from a safety point of view, e.g cesium-isotopes and actinides which are found in largest amounts in the SFL 3 waste. A first evaluation of the long term performance or the SFL 3-5 repository has been made. A systematic methodology for scenario formulation was tested. The near-field release of contaminants was calculated for a selected number of radionuclides and chemo-toxic elements. The radionuclide release calculations revealed that Cs-137 and Ni-63 would dominate the annual release from all repository parts during the first 1000 years after repository closure and that Ni-59 would dominate at longer times.

Dicty_cDB: SFL482 [Dicty_cDB

Lifescience Database Archive (English)

Full Text Available SF (Link to library) SFL482 (Link to dictyBase) - - - Contig-U15494-1 SFL482P (Link... to Original site) SFL482F 434 SFL482Z 394 SFL482P 828 - - Show SFL482 Library SF (Link to library) Clone ID SFL482 (Link to dict...yBase) Atlas ID - NBRP ID - dictyBase ID - Link to Contig Contig-U15494-1 Original site URL http://dict...cftclww*qmcqmcp*qnrscfln*rtknr*nclqeatkrfkt ker*EIIQINVVININHFLLIKKK--- ---ICTHIEKMVQRLTYRRRLSYRTTSNATKIVKTP...KQQK DLKQKKDKKSSK*m Translated Amino Acid sequence (All Frames) Frame A: icthiekmvqrltyrrrlsyrttsnatkivktpgg

High sorption materials for SFL - A literature review

Energy Technology Data Exchange (ETDEWEB)

Krall, Lindsay [Svensk Kaernbraenslehantering AB, Stockholm (Sweden)

2012-05-15

This literature survey is part of a project called the SFL Concept Study, carried out at SKB during the years 2011 to 2013, which investigates possible repository concepts for long-lived, low and intermediate level waste. The addition of a high sorption material has been proposed as a means through which releases may be limited from the near-field. In the previous repository concept from 1999 (SFL 3-5), the transport of cationic nuclides was expected to be reduced by their adsorption to the cement, gravel, and bedrock, However, in the preliminary safety assessment of that previous concept, it was found that the key radionuclides are mainly anions. Thus, this literature survey has placed special emphasis on the adsorption of anions. Due to their high release and dose rates from the far field, Cl-36, Mo-93, C-14, and I-129 were of particular interest. Ion exchange and surface complexation are the main adsorption mechanisms. Ion exchange is theoretically reversible and involves the isomorphic substitution of either (a) cation(s) or anion(s) in a mineral structure. The ions exchanged do not need to have the same charge, but the exchange should be stoichiometric. Surface complexation is more dependent on pH, and the strength of the bond formed (and thus the reversibility of the reaction) is partially dependent on the type of complex formed. A material's adsorption mechanism and efficiency is a function of its structure and charge density, but it will also vary as a function of pH, the type and amount of competing ions, and the concentration of the solute in solution. A substantial body of work exists that investigates the application of materials that can remediate groundwater through the adsorptive removal of the contaminant(s). Application of such a function in the future SFL repository will differ from remediation applications in that the system will be more complex and heterogeneous than most of the contaminated waters studied, the adsorption processes must be

High sorption materials for SFL - A literature review

International Nuclear Information System (INIS)

Krall, Lindsay

2012-05-01

This literature survey is part of a project called the SFL Concept Study, carried out at SKB during the years 2011 to 2013, which investigates possible repository concepts for long-lived, low and intermediate level waste. The addition of a high sorption material has been proposed as a means through which releases may be limited from the near-field. In the previous repository concept from 1999 (SFL 3-5), the transport of cationic nuclides was expected to be reduced by their adsorption to the cement, gravel, and bedrock, However, in the preliminary safety assessment of that previous concept, it was found that the key radionuclides are mainly anions. Thus, this literature survey has placed special emphasis on the adsorption of anions. Due to their high release and dose rates from the far field, Cl-36, Mo-93, C-14, and I-129 were of particular interest. Ion exchange and surface complexation are the main adsorption mechanisms. Ion exchange is theoretically reversible and involves the isomorphic substitution of either (a) cation(s) or anion(s) in a mineral structure. The ions exchanged do not need to have the same charge, but the exchange should be stoichiometric. Surface complexation is more dependent on pH, and the strength of the bond formed (and thus the reversibility of the reaction) is partially dependent on the type of complex formed. A material's adsorption mechanism and efficiency is a function of its structure and charge density, but it will also vary as a function of pH, the type and amount of competing ions, and the concentration of the solute in solution. A substantial body of work exists that investigates the application of materials that can remediate groundwater through the adsorptive removal of the contaminant(s). Application of such a function in the future SFL repository will differ from remediation applications in that the system will be more complex and heterogeneous than most of the contaminated waters studied, the adsorption processes must be

Systemic Functional Linguistics (SFL as Sociolinguistic and Sociological Conception: Possibilities and Limits of Theoretical Framework

Directory of Open Access Journals (Sweden)

Mariia Rubtcova

2016-05-01

Full Text Available The paper aims at examining possibilities and limits of Systemic functional linguistics theoretical framework. Ideologically SFL concept was associated with the ideas of social justice and equality, the building of the society of equal opportunities through the educational system. The most interesting ideas arose when the SFL representatives thought about the development of English as a native language and were connected with the overcoming of class distinctions. The current version - genre-based approach – has serious limits. The desire of a genre-based approach to the systematization of genres carries a risk of cultural contradictions and conflict of cultures. However, the basic theoretical SFL principles are still in the stage of formation, as SFL researchers seek to avoid some rigidity of the classical institutional (genre approach, which is in contradiction with the principles of diversity. The founder M. Halliday offered ideas for the organization of a flexible approach based on International English that may become World Englishes, developing in order to adapt to the meanings of other cultures.  Therefore, an SFL approach still needs some alterations to spread outside the Western world and conform to the new culture for it. Besides, we can think about proposals of Halliday’s supporters to develop the own version of English for non-Western countries, considering its culture and mentality.

The Methodology of Investigation of Intercultural Rhetoric applied to SFL

Directory of Open Access Journals (Sweden)

David Heredero Zorzo

2016-12-01

Full Text Available Intercultural rhetoric is a discipline which studies written discourse among individuals from different cultures. It is a very strong field in the Anglo-Saxon scientific world, especially referring to English as a second language, but in Spanish as a foreign language it is not as prominent. Intercultural rhetoric has provided applied linguistics with important methods of investigation, thus applying this to SFL could introduce interesting new perspectives on the subject. In this paper, we present the methodology of investigation of intercultural rhetoric, which is based on the use of different types of corpora for analysing genders, and follows the precepts of tertium comparationis. In addition, it uses techniques of ethnographic investigation. The purpose of this paper is to show the applications of this methodology to SFL and to outline future investigations in the same field.

Comparative transcript profiling of Candida albicans and Candida dubliniensis identifies SFL2, a C. albicans gene required for virulence in a reconstituted epithelial infection model.

LENUS (Irish Health Repository)

Spiering, Martin J

2010-02-01

Candida albicans and Candida dubliniensis are closely related species displaying differences in virulence and genome content, therefore providing potential opportunities to identify novel C. albicans virulence genes. C. albicans gene arrays were used for comparative analysis of global gene expression in the two species in reconstituted human oral epithelium (RHE). C. albicans (SC5314) showed upregulation of hypha-specific and virulence genes within 30 min postinoculation, coinciding with rapid induction of filamentation and increased RHE damage. C. dubliniensis (CD36) showed no detectable upregulation of hypha-specific genes, grew as yeast, and caused limited RHE damage. Several genes absent or highly divergent in C. dubliniensis were upregulated in C. albicans. One such gene, SFL2 (orf19.3969), encoding a putative heat shock factor, was deleted in C. albicans. DeltaDeltasfl2 cells failed to filament under a range of hypha-inducing conditions and exhibited greatly reduced RHE damage, reversed by reintroduction of SFL2 into the DeltaDeltasfl2 strain. Moreover, SFL2 overexpression in C. albicans triggered hyphal morphogenesis. Although SFL2 deletion had no apparent effect on host survival in the murine model of systemic infection, DeltaDeltasfl2 strain-infected kidney tissues contained only yeast cells. These results suggest a role for SFL2 in morphogenesis and an indirect role in C. albicans pathogenesis in epithelial tissues.

Design and production of the KBS-3 repository

International Nuclear Information System (INIS)

Moren, Lena

2010-12-01

The report contains the common basis for a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility. The report presents the role of the Production reports within the safety report and their common purposes and objectives. An important part of the report is to present the background and sources to the principles to be applied in the design, the functions of the KBS-3 repository and the barrier functions the engineered barriers and rock. Further, the methodology to substantiate detailed design premises for the engineered barriers, underground openings and other parts of the KBS-3 repository is presented. The report also gives an overview of the KBS-3 system and its facilities and the production lines for the spent fuel, the engineered barriers and underground openings. Finally, an introduction to quality management, safety classification and their application is given

Design and production of the KBS-3 repository

Energy Technology Data Exchange (ETDEWEB)

Moren, Lena

2010-12-15

The report contains the common basis for a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility. The report presents the role of the Production reports within the safety report and their common purposes and objectives. An important part of the report is to present the background and sources to the principles to be applied in the design, the functions of the KBS-3 repository and the barrier functions the engineered barriers and rock. Further, the methodology to substantiate detailed design premises for the engineered barriers, underground openings and other parts of the KBS-3 repository is presented. The report also gives an overview of the KBS-3 system and its facilities and the production lines for the spent fuel, the engineered barriers and underground openings. Finally, an introduction to quality management, safety classification and their application is given

Global thermo-mechanical effects from a KBS-3 type repository

International Nuclear Information System (INIS)

Hakami, E.; Olofsson, Stig-Olof

1998-01-01

The objective of this study has been to identify the global thermo-mechanical effects in the bedrock hosting a nuclear waste repository. Numerical thermo-mechanical modeling using distinct element models was performed. The number of fracture zones, the heat intensity of the waste, the material properties of the rock mass and the boundary conditions of the models were varied. Different models for multi-level repositories were also analyzed and compared to the main single-level case. Further, the global influence from the excavation of repository tunnels and deposition holes was examined by introducing weaker rock mass material properties in the repository region of one model. The maximum compression stress obtained for the main model is 44 MPa and occurs at the repository level after about 100 years of deposition. Due to thermal expansion, the rock mass displaces upward, and the maximum heave at the ground surface after 1000 years is calculated to be 16 cm. In the area close to the ground surface the horizontal stresses reduce, causing the rock to yield in tension down to a depth of about 80 meters. The fracture zones show opening displacements at shallow depths and closing and shearing at the repository level. The maximum displacements are 0.3-2.5 cm for closing, 0.0-0.8 cm for opening and 0.2-2.2 cm for shearing. The resultant stresses and displacements depend in large part on the assumptions made concerning the heat intensity of the waste. In the main model, an initial heat intensity of 10 W/m 2 is assumed, which gives larger effects than the case with 6 W/m 2 . Another important input parameter for the analysis is the Young's modulus of the rock mass. In the main model, a value of 30 GPa is assumed. Higher values of Young's modulus give larger thermo-mechanical effects. All multi-level repository layouts give rise to higher temperatures than the single-level layout, causing the compressive stresses to increase more at the repository level. The multi

Thermo-mechanical effects from a KBS-3 type repository. Performance of pillars between repository tunnels

International Nuclear Information System (INIS)

Hakami, E.; Olofsson, Stig-Olof

2000-03-01

The aim of this study has been to investigate how the rock mass, in the near field of a KBS-3 type repository, will be affected by the excavation of tunnels and deposition holes and the thermal load from the deposited waste. The three-dimensional finite difference program FLAC 3D was used to perform numerical simulation of the rock mass behaviour. The rock mass was modelled as a homogeneous and isotropic continuum. The initial area heat intensity of the repository was assumed to be 10 W/m 2 in all models. The results show that in the middle of the pillar between the repository tunnels the temperature reaches a maximum of about 70 deg C after 55 years of deposition. The extent of areas where the rock is predicted to yield depends on the assumed quality of the rock mass and the initial in-situ stress field. The volume of yielded rock reaches a maximum after about 200 years after deposition. For a rock mass with internal friction angle of 45 deg and cohesion of 5 MPa (using a Mohr-Coulomb material model), the extent of yielded rock is limited to about 1.5 m behind the excavation periphery. The largest rock displacements are found in the tunnel floor at the upper part of the deposition holes. Tension and shear failure in the periphery of the excavations is predicted to occur during the rock excavation, with a depth extension depending on the magnitude and orientation of the in-situ stresses, as well as on the rock mass quality. Both the excavation effects and the then-no-mechanical effects are smallest when the major principal stress is oriented parallel with the deposition tunnels. The maximum convergence between tunnel walls was calculated to occur after 200 years and be about 9 mm, in the model assuming a rock mass with 5 MPa cohesion, 45 deg internal friction angle and maximum horizontal stress perpendicular to the tunnel. In this study confining effects from the buffer and backfill material was neglected. The effective stress concept was used in most of the models

Making research data repositories visible: the re3data.org Registry.

Directory of Open Access Journals (Sweden)

Heinz Pampel

Full Text Available Researchers require infrastructures that ensure a maximum of accessibility, stability and reliability to facilitate working with and sharing of research data. Such infrastructures are being increasingly summarized under the term Research Data Repositories (RDR. The project re3data.org-Registry of Research Data Repositories-has begun to index research data repositories in 2012 and offers researchers, funding organizations, libraries and publishers an overview of the heterogeneous research data repository landscape. In July 2013 re3data.org lists 400 research data repositories and counting. 288 of these are described in detail using the re3data.org vocabulary. Information icons help researchers to easily identify an adequate repository for the storage and reuse of their data. This article describes the heterogeneous RDR landscape and presents a typology of institutional, disciplinary, multidisciplinary and project-specific RDR. Further the article outlines the features of re3data.org, and shows how this registry helps to identify appropriate repositories for storage and search of research data.

Making research data repositories visible: the re3data.org Registry.

Science.gov (United States)

Pampel, Heinz; Vierkant, Paul; Scholze, Frank; Bertelmann, Roland; Kindling, Maxi; Klump, Jens; Goebelbecker, Hans-Jürgen; Gundlach, Jens; Schirmbacher, Peter; Dierolf, Uwe

2013-01-01

Researchers require infrastructures that ensure a maximum of accessibility, stability and reliability to facilitate working with and sharing of research data. Such infrastructures are being increasingly summarized under the term Research Data Repositories (RDR). The project re3data.org-Registry of Research Data Repositories-has begun to index research data repositories in 2012 and offers researchers, funding organizations, libraries and publishers an overview of the heterogeneous research data repository landscape. In July 2013 re3data.org lists 400 research data repositories and counting. 288 of these are described in detail using the re3data.org vocabulary. Information icons help researchers to easily identify an adequate repository for the storage and reuse of their data. This article describes the heterogeneous RDR landscape and presents a typology of institutional, disciplinary, multidisciplinary and project-specific RDR. Further the article outlines the features of re3data.org, and shows how this registry helps to identify appropriate repositories for storage and search of research data.

SFR 1 Vault Database

International Nuclear Information System (INIS)

Savage, David; Stenhouse, Mike

2002-04-01

SKB is carrying out a safety assessment of the operational SFR 1 repository under the auspices of the 'SAFE' (Safety Assessment of Final Repository for Radioactive Operational Waste) project. SKI in turn, is carrying out its own review of SFR 1. The work presented here is a compilation of physical and chemical data for the SFR 1 repository which will be used in radionuclide transport and assessment calculations by SKI. This compilation has focused on the repository itself (engineered barriers plus near-field rock). Data have been compiled for the following: Physical properties (porosity, hydraulic conductivity, bulk density, effective diffusivity); Sorption of radionuclides (on concrete, sand, bentonite, sand-bentonite, and rock); Radionuclide solubility. In addition, issues affecting gas generation at SFR I have been reviewed and placed in context with research conducted for the SFL 3-5 repository

National Radwaste Repository Mochovce

International Nuclear Information System (INIS)

2000-01-01

In this leaflet the National Radioactive Waste Repository in Mochovce (Repository) is described. The Mochovce National Radioactive Waste Repository is a surface multi-barrier type storage facility for solid and treated solidified radioactive wastes generated from the Slovak Republic nuclear power plants operation and decommissioning, research institutes, laboratories and hospitals. The Repository comprises a system of single- and double-row storage boxes. The first double-row is enclosed by a steel-structure building. The 18 x 6 x 5.5 m storage boxes are made of reinforced concrete. The wall thickness is 600 mm. Two-double-rows, i.e. 80 storage boxes were built as part of Stage I (1 row = 20 storage boxes). Each storage box has a storage capacity of 90 fibre concrete containers of 3.1 m 3 volume. The total storage capacity is 7200 containers with the overall storage volume of 22320 m 3

Photograms of a city: a didactic sequency to avanced level in SFL

Directory of Open Access Journals (Sweden)

Yanet Portes-Fernández

2016-10-01

Full Text Available The present work shows a designed proposal with the objective of contributing with the teaching learning process of Spanish as Foreign Language (SFL in Santiago of Cuba. It takes into consideration the relevance, practicality and impact of the audiovisual materials –but only those that are considered authentic materials- in education, with a particular emphasis on language classrooms. In this sense, it focuses on the utility of the aforementioned materials to deal with the cultural component, for which a didactic sequence has been elaborated of the short film Cuando vuelvo. The proposal is particularly targeted towards the advanced level.

Review of SFL 3-5 performance assessment

International Nuclear Information System (INIS)

Glynn, P.D.

2000-01-01

This 'performance assessment' report has 1) several logical flaws and 2) is not scientifically objective. There is a lot of good work done by individual SKB consultants. The problem is that the report does not consider all the available research that has been conducted, both by SKB consultants and by other scientists. The report only seems to select evidence/research pieces that fit preconceived notions supporting SKB's ultimate objectives. This is done rather poorly, which is why one can easily pick out inconsistencies and logical flaws

Design process for a repository - KBS-3 case

International Nuclear Information System (INIS)

Svemar, C.

1995-01-01

This paper deals with the design process for the Swedish (generic) repository design KBS-3. The repository may have a spiral access ramp, access shafts, or straight access ramps. Galleries lead from a central service area to a small spent fuel storage area, a larger main spent fuel storage area, and a disposal area for other nuclear waste. This, or any, design has to be planned through three stages of layout and design, viz. feasibility study, preliminary planning, and architectural design, followed by detailed planning, and then planning of excavation and construction. Decisions on final design have to wait until construction is imminent, and all the rock data are available. This means that different sections of the repository may be at different planning stages at any one time. In the last stage, the plan of the disposal holes depends on detailed coring results, because a hole will not be bored where there is a fracture. 3 refs., 1 tab., 3 figs

Global thermo-mechanical effects from a KBS-3 type repository. Summary report

International Nuclear Information System (INIS)

Hakami, E.; Olofsson, Stig-Olof; Hakami, H.; Israelsson, Jan

1998-04-01

The objective of this study has been to identify the global thermomechanical effects in the bedrock hosting a nuclear waste repository - i.e. the effects at large distances from the repository. Numerical thermomechanical modeling was performed in several steps, beginning with elastic continuum models and followed by distinct element models (3DEC), in which fracture zones are explicitly simulated. The number of fracture zones, the heat intensity of the waste, the material properties of the rock mass and the boundary conditions of the models were varied in different simulations. The results from the numerical modeling show that the principal stresses increase near the repository. The maximum stress obtained for the main model is 44 MPa and occurs at the repository level after about 100 years of deposition. Due to thermal expansion, the rock mass displaces upward, and the maximum heave at the ground surface after 1000 years is calculated to be 16 cm. In the area close to the ground surface, above the center of the repository, the horizontal stresses reduce, causing the rock to yield in tension down to a depth of about 80 m. In correspondence with the stress changes, the fracture zones show opening normal displacements at shallow depths and closing normal displacements and shearing at the repository level. The maximum displacements of the different fracture zones are 0.3-2.5 cm for closing, 0.0-0.8 cm for opening and 0.2-2.2 cm for shearing. Another important input parameter for the analysis is the Young's modulus of the rock mass. In the main model, a value of 30 GPa is assumed. Higher values of Young's modulus give larger thermo-mechanical effects. Other changes of the properties considered give minor changes of the rock mass behavior. All multi-level repository layouts give rise to higher temperatures than the single-level layout, causing the compressive stresses to increase more at the repository level. Fracture zone displacements caused by different layouts are

Spent nuclear fuel for disposal in the KBS-3 repository

Energy Technology Data Exchange (ETDEWEB)

Grahn, Per; Moren, Lena; Wiborgh, Maria

2010-12-15

The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility. The report provides input to the assessment of the long-term safety, SR-Site as well as to the operational safety report, SR-Operation. The report presents the spent fuel to be deposited, and the requirements on the handling and selection of fuel assemblies for encapsulation that follows from that it shall be deposited in the KBS-3 repository. An overview of the handling and a simulation of the encapsulation and the resulting canisters to be deposited are presented. Finally, the initial state of the encapsulated spent nuclear fuel is given. The initial state comprises the radionuclide inventory and other data required for the assessment of the long-term safety

Spent nuclear fuel for disposal in the KBS-3 repository

International Nuclear Information System (INIS)

Grahn, Per; Moren, Lena; Wiborgh, Maria

2010-12-01

The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility. The report provides input to the assessment of the long-term safety, SR-Site as well as to the operational safety report, SR-Operation. The report presents the spent fuel to be deposited, and the requirements on the handling and selection of fuel assemblies for encapsulation that follows from that it shall be deposited in the KBS-3 repository. An overview of the handling and a simulation of the encapsulation and the resulting canisters to be deposited are presented. Finally, the initial state of the encapsulated spent nuclear fuel is given. The initial state comprises the radionuclide inventory and other data required for the assessment of the long-term safety

Evaluation of colloid transport issues and recommendations for SKI performance assessments

Energy Technology Data Exchange (ETDEWEB)

Wickham, S. M.; Bennett, D. G.; Higgo, J. J. W. [Galson Sciences Ltd., Oakham (United Kingdom)

2000-08-01

The primary objective of this project was to develop recommendations to SKI for evaluating the potential significance of colloids in performance assessment (PA) studies by: Updating a previous review of the treatment of colloids in PA studies for radioactive waste repositories and to include information on PAs published in the period 1997-1999. We have reviewed sixteen PAs conducted in nine countries and have made the following observations: All PAs include colloid formation and colloid transport in their FEP list. Although some programmes have deferred consideration of colloidal radionuclide transport until further research has been performed, more recent PAs do account for the effects of colloids. PAs of disposal systems in which the waste canister is surrounded by a bentonite buffer do not consider the effect of colloids on the source term. These PAs assume that all colloids are filtered by the bentonite buffer and cannot escape from the near-field. PAs of disposal systems with no bentonite buffer have to account for mobilisation of radionuclides from the waste by colloids. The concentration of colloids that may form in the repository is a key uncertainty. Many PA programmes have modelled colloidal radionuclide transport in the geosphere using one-dimensional transport equations. No PA has included a comprehensive treatment of colloid transport using mechanistic modelling. Some PAs have not undertaken modelling of colloid transport in the geosphere, but have relied instead on arguments that such transport processes will be of low consequence to the performance of the disposal system. Five PAs have shown the effects of colloid transport through the geosphere to be potentially significant. For the disposal of spent nuclear fuel, SKB has developed the KBS-3 concept. For the disposal of long-lived low-level and intermediate-level radioactive waste, SKB has developed the SFL 3-5 concept. In the SFL 3-5 concept, waste is placed in underground disposal caverns and

Thermodynamic Properties of Magnesium Chloride Hydroxide Hydrate (Mg3Cl(OH)5:4H2O, Phase 5), and Its importance to Nuclear Waste Isolation in Geological Repositories in Salt Formations

Science.gov (United States)

Xiong, Y.; Deng, H.; Nemer, M. B.; Johnsen, S.

2009-12-01

MgO (bulk, pure MgO corresponding to the mineral periclase) is the only engineered barrier certified by the Environmental Protection Agency for emplacement in the Waste Isolation Pilot Plant (WIPP) in the US, and an Mg(OH)2-based engineered barrier (bulk, pure Mg(OH)2 corresponding to brucite) is to be employed in the Asse repository in Germany. Both the WIPP and the Asse are located in salt formations. The WIPP is a U.S. Department of Energy geological repository being used for the permanent disposal of defense-related transuranic waste (TRU waste). The repository is 655 m below the surface, and is situated in the Salado Formation, a Permian salt bed mainly composed of halite, and of lesser amounts of polyhalite, anhydrite, gypsum, magnesite, clays and quartz. The WIPP Generic Weep Brine (GWB), a Na-Mg-Cl dominated brine, is associated with the Salado Formation. The previous vendor for MgO for the WIPP was Premier Chemicals and the current vendor is Martin Marietta Materials. Experimental studies of both Premier MgO and Martin Marietta MgO with the GWB at SNL indicate the formation of magnesium chloride hydroxide hydrate, Mg3Cl(OH)5:4H2O, termed as phase 5. However, this important phase is lacking in the existing thermodynamic database. In this study, the solubility constant of phase 5 is determined from a series of solubility experiments in MgCl2-NaCl solutions. The solubility constant at 25 oC for the following reaction, Mg3Cl(OH)5:4H2O + 5H+ = 3Mg2+ + 9H2O(l) + Cl- is recommended as 43.21±0.33 (2σ) based on the Specific Interaction Theory (SIT) model for extrapolation to infinite dilution. The log K obtained via the Pitzer equations is identical to the above value within the quoted uncertainty. The Gibbs free energy and enthalpy of formation for phase 5 at 25 oC are derived as -3384±2 (2σ) kJ mol-1 and -3896±6 (2σ) kJ mol-1, respectively. The standard entropy and heat capacity of phase 5 at 25 oC are estimated as 393±20 J mol-1 K-1 and 374±19 J mol-1 K

re3data.org - a global registry of research data repositories

Science.gov (United States)

Pampel, Heinz; Vierkant, Paul; Elger, Kirsten; Bertelmann, Roland; Witt, Michael; Schirmbacher, Peter; Rücknagel, Jessika; Kindling, Maxi; Scholze, Frank; Ulrich, Robert

2016-04-01

re3data.org - the registry of research data repositories lists over 1,400 research data repositories from all over the world making it the largest and most comprehensive online catalog of research data repositories on the web. The registry is a valuable tool for researchers, funding organizations, publishers and libraries. re3data.org provides detailed information about research data repositories, and its distinctive icons help researchers to easily identify relevant repositories for accessing and depositing data sets [1]. Funding agencies, like the European Commission [2] and research institutions like the University of Bielefeld [3] already recommend the use of re3data.org in their guidelines and policies. Several publishers and journals like Copernicus Publications, PeerJ, and Nature's Scientific Data recommend re3data.org in their editorial policies as a tool for the easy identification of appropriate data repositories to store research data. Project partners in re3data.org are the Library and Information Services department (LIS) of the GFZ German Research Centre for Geosciences, the Computer and Media Service at the Humboldt-Universität zu Berlin, the Purdue University Libraries and the KIT Library at the Karlsruhe Institute of Technology (KIT). After its fusion with the U.S. American DataBib in 2014, re3data.org continues as a service of DataCite from 2016 on. DataCite is the international organization for the registration of Digital Object Identifiers (DOI) for research data and aims to improve their citation. The poster describes the current status and the future plans of re3data.org. [1] Pampel H, et al. (2013) Making Research Data Repositories Visible: The re3data.org Registry. PLoS ONE 8(11): e78080. doi:10.1371/journal.pone.0078080. [2] European Commission (2015): Guidelines on Open Access to Scientific Publications and Research Data in Horizon 2020. Available: http://ec.europa.eu/research/participants/data/ref/h2020/grants_manual/hi/oa_pilot/h2020-hi

Which User of technology? Perspectivising the UTAUT model by application of the SFL language Pronoun System towards a systems perspective of technology acceptance and use

Directory of Open Access Journals (Sweden)

Cheryl Marie Cordeiro

2018-04-01

Full Text Available This study applies systemic functional linguistics (SFL as complementary framework of analysis of technology acceptance models (TAMs. The purpose is to bridge research methodology language in international business (IB studies and engineering management science. Currently TAMs and its consolidated version, the Unified Theory of Acceptance and Use of Technology (UTAUT provides for a typology of one user in one context scenario. The need for the UTAUT model to account for multiple users in multiple work contexts in a single framework of analysis was foregrounded in the study of the workflow processes of a remote services business model of a European founded multinational business enterprise (MBE with regards to its (i intra-firm improvements in managing remote services cases, and its (ii extra-firm selling of life cycle management remote services contracts. The Enterprise has global operations in over 100 countries, of which this study focused on its European operations of improving the quality of remote services for the marine industry. Through an application of SFL unto UTAUT, this study illustrates how multiple users in multiple contexts can be analysed simultaneously, and whose behaviours can be accounted for in a single framework of analysis. The combined SFL UTAUT model addresses the initial statisticity of the UTAUT model, whilst at the same time, expands upon current theoretical perspectives of technology use and acceptance that can be applied in practice.

10 CFR 960.5-2-3 - Meteorology.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Meteorology. 960.5-2-3 Section 960.5-2-3 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Preclosure Guidelines Preclosure Radiological Safety § 960.5-2-3 Meteorology. (a) Qualifying...

Integrated management system for radioactive waste repositories (SGI3R)

International Nuclear Information System (INIS)

Silva, Fabio; Tello, Cledola Cassia Oliveira de

2009-01-01

The implantation of a repository for radioactive wastes is a multidisciplinary project that needs specialists of different areas of knowledge, interaction with public and private institutions, data and information related to radioactive wastes, geology, technology etc. All the activities must be in accordance with norms, requirements and procedures, including national and international legislation. The maintenance of the waste inventory records is an important regulatory requirement and must be available even after the closure of the repository. CDTN - Center of Nuclear Technology Development - is coordinating the Project for the construction of the national repository to dispose the low -and intermediate-level wastes. In order to consolidate all information that will come from this Project, it is being developed and implanted in CDTN a manager system of database, called Integrated Management System for Radioactive Waste Repositories (SGI3R), which will also manage all data from previous work carried out in Brazil and around the world about this subject. The proposal is to build a structure of modules, having as base eight modules: inventory, site selection, types of repository, technology, partners, legislation, communication and documents. The SGI3R running comprises the data processing (inclusion, update and exclusion), integration, standardization, and consistency among the processes. The SGI3R will give support to the stages of this Project, which will allow the preservation of all the available information, preventing duplication of efforts and additional costs, improving, in this way, the Project planning and execution. Additionally the SGI3R will make possible the information access to all stakeholders. (author)

Evaluation of colloid transport issues and recommendations for SKI performance assessments

International Nuclear Information System (INIS)

Wickham, S. M.; Bennett, D. G.; Higgo, J. J. W.

2000-08-01

The primary objective of this project was to develop recommendations to SKI for evaluating the potential significance of colloids in performance assessment (PA) studies by: Updating a previous review of the treatment of colloids in PA studies for radioactive waste repositories and to include information on PAs published in the period 1997-1999. We have reviewed sixteen PAs conducted in nine countries and have made the following observations: All PAs include colloid formation and colloid transport in their FEP list. Although some programmes have deferred consideration of colloidal radionuclide transport until further research has been performed, more recent PAs do account for the effects of colloids. PAs of disposal systems in which the waste canister is surrounded by a bentonite buffer do not consider the effect of colloids on the source term. These PAs assume that all colloids are filtered by the bentonite buffer and cannot escape from the near-field. PAs of disposal systems with no bentonite buffer have to account for mobilisation of radionuclides from the waste by colloids. The concentration of colloids that may form in the repository is a key uncertainty. Many PA programmes have modelled colloidal radionuclide transport in the geosphere using one-dimensional transport equations. No PA has included a comprehensive treatment of colloid transport using mechanistic modelling. Some PAs have not undertaken modelling of colloid transport in the geosphere, but have relied instead on arguments that such transport processes will be of low consequence to the performance of the disposal system. Five PAs have shown the effects of colloid transport through the geosphere to be potentially significant. For the disposal of spent nuclear fuel, SKB has developed the KBS-3 concept. For the disposal of long-lived low-level and intermediate-level radioactive waste, SKB has developed the SFL 3-5 concept. In the SFL 3-5 concept, waste is placed in underground disposal caverns and

General construction requirements for the deep repository in the KBS-3 system

International Nuclear Information System (INIS)

2002-10-01

The KBS-3 systems includes equipment and plants for transport of spent nuclear fuels and encapsulated spent fuels, central intermediate storage, encapsulation and deep geologic disposal. The requirements in this document concern the repository and have been put together in view of the tasks of designing, constructing and building the repository. The report presents: A general review of existing design plans; Laws and regulations relevant for the design of the repository; How the regulations have been broken down to functional demands and dimensioning requirements for the repository; How the site conditions influence the design, and how the layout of the different parts of the repository interact; Relations between the functions of the repository, the safety and the design; A foundation for developing construction plans for the repository. The requirements will be collected in a database that will develop as new knowledge is collected

Integration of the tricarboxylic acid (TCA) cycle with cAMP signaling and Sfl2 pathways in the regulation of CO2 sensing and hyphal development in Candida albicans.

Science.gov (United States)

Tao, Li; Zhang, Yulong; Fan, Shuru; Nobile, Clarissa J; Guan, Guobo; Huang, Guanghua

2017-08-01

Morphological transitions and metabolic regulation are critical for the human fungal pathogen Candida albicans to adapt to the changing host environment. In this study, we generated a library of central metabolic pathway mutants in the tricarboxylic acid (TCA) cycle, and investigated the functional consequences of these gene deletions on C. albicans biology. Inactivation of the TCA cycle impairs the ability of C. albicans to utilize non-fermentable carbon sources and dramatically attenuates cell growth rates under several culture conditions. By integrating the Ras1-cAMP signaling pathway and the heat shock factor-type transcription regulator Sfl2, we found that the TCA cycle plays fundamental roles in the regulation of CO2 sensing and hyphal development. The TCA cycle and cAMP signaling pathways coordinately regulate hyphal growth through the molecular linkers ATP and CO2. Inactivation of the TCA cycle leads to lowered intracellular ATP and cAMP levels and thus affects the activation of the Ras1-regulated cAMP signaling pathway. In turn, the Ras1-cAMP signaling pathway controls the TCA cycle through both Efg1- and Sfl2-mediated transcriptional regulation in response to elevated CO2 levels. The protein kinase A (PKA) catalytic subunit Tpk1, but not Tpk2, may play a major role in this regulation. Sfl2 specifically binds to several TCA cycle and hypha-associated genes under high CO2 conditions. Global transcriptional profiling experiments indicate that Sfl2 is indeed required for the gene expression changes occurring in response to these elevated CO2 levels. Our study reveals the regulatory role of the TCA cycle in CO2 sensing and hyphal development and establishes a novel link between the TCA cycle and Ras1-cAMP signaling pathways.

Integration of the tricarboxylic acid (TCA cycle with cAMP signaling and Sfl2 pathways in the regulation of CO2 sensing and hyphal development in Candida albicans.

Directory of Open Access Journals (Sweden)

Li Tao

2017-08-01

Full Text Available Morphological transitions and metabolic regulation are critical for the human fungal pathogen Candida albicans to adapt to the changing host environment. In this study, we generated a library of central metabolic pathway mutants in the tricarboxylic acid (TCA cycle, and investigated the functional consequences of these gene deletions on C. albicans biology. Inactivation of the TCA cycle impairs the ability of C. albicans to utilize non-fermentable carbon sources and dramatically attenuates cell growth rates under several culture conditions. By integrating the Ras1-cAMP signaling pathway and the heat shock factor-type transcription regulator Sfl2, we found that the TCA cycle plays fundamental roles in the regulation of CO2 sensing and hyphal development. The TCA cycle and cAMP signaling pathways coordinately regulate hyphal growth through the molecular linkers ATP and CO2. Inactivation of the TCA cycle leads to lowered intracellular ATP and cAMP levels and thus affects the activation of the Ras1-regulated cAMP signaling pathway. In turn, the Ras1-cAMP signaling pathway controls the TCA cycle through both Efg1- and Sfl2-mediated transcriptional regulation in response to elevated CO2 levels. The protein kinase A (PKA catalytic subunit Tpk1, but not Tpk2, may play a major role in this regulation. Sfl2 specifically binds to several TCA cycle and hypha-associated genes under high CO2 conditions. Global transcriptional profiling experiments indicate that Sfl2 is indeed required for the gene expression changes occurring in response to these elevated CO2 levels. Our study reveals the regulatory role of the TCA cycle in CO2 sensing and hyphal development and establishes a novel link between the TCA cycle and Ras1-cAMP signaling pathways.

Estimated quantities of residual materials in a KBS-3H repository at Olkiluoto

Energy Technology Data Exchange (ETDEWEB)

Hagros, Annika (Sannio and Riekkola OY (Finland))

2008-12-15

The quantities of residual materials in a KBS-3H type repository have been estimated in this report. The repository is assumed to be constructed at Olkiluoto in Eurajoki, Western Finland. Both the total quantities of the materials introduced into the repository and the quantities of materials that remain in the repository after closure have been calculated. The calculations are largely based on a similar work regarding the material quantities in the Finnish KBS-3V repository and the main goal has been to identify the differences between the KBS-3H and KBS-3V repositories with respect to the type and quantities of residual materials. As the design of the KBS-3H repository is not final yet, the results are only preliminary. Several alternative designs were assumed in the calculations, resulting in different total quantities of materials. The design alternatives that had the greatest effect on the total material quantities were the two different tunnel backfill options, bentonite-crushed rock and Friedland clay. If Friedland clay is used instead of a bentonite-crushed rock mixture, the total quantity of pyrite remaining in the repository is 20 times larger and the quantities of organic materials and gypsum are also increased significantly. The other design alternatives did not have a substantial effect on the total material quantities. The remaining quantity of cement can be reduced by some 20% by selecting the silica grouting alternative in the sealing of the rock mass and low-pH cement in the shotcreting of the repository, instead of using the ordinary cement alternatives. If the total quantity of steel should be minimised, the use of the DAWE design alternative would be better than the Basic Design, although the total reduction would be less than 10%. The main difference between the different drift end plug alternatives is related to the total remaining quantity of silica, which is some 80% smaller if the rock plug is used instead of the LHHP (Low Heat High

Estimated quantities of residual materials in a KBS-3H repository at Olkiluoto

International Nuclear Information System (INIS)

Hagros, Annika

2008-12-01

The quantities of residual materials in a KBS-3H type repository have been estimated in this report. The repository is assumed to be constructed at Olkiluoto in Eurajoki, Western Finland. Both the total quantities of the materials introduced into the repository and the quantities of materials that remain in the repository after closure have been calculated. The calculations are largely based on a similar work regarding the material quantities in the Finnish KBS-3V repository and the main goal has been to identify the differences between the KBS-3H and KBS-3V repositories with respect to the type and quantities of residual materials. As the design of the KBS-3H repository is not final yet, the results are only preliminary. Several alternative designs were assumed in the calculations, resulting in different total quantities of materials. The design alternatives that had the greatest effect on the total material quantities were the two different tunnel backfill options, bentonite-crushed rock and Friedland clay. If Friedland clay is used instead of a bentonite-crushed rock mixture, the total quantity of pyrite remaining in the repository is 20 times larger and the quantities of organic materials and gypsum are also increased significantly. The other design alternatives did not have a substantial effect on the total material quantities. The remaining quantity of cement can be reduced by some 20% by selecting the silica grouting alternative in the sealing of the rock mass and low-pH cement in the shotcreting of the repository, instead of using the ordinary cement alternatives. If the total quantity of steel should be minimised, the use of the DAWE design alternative would be better than the Basic Design, although the total reduction would be less than 10%. The main difference between the different drift end plug alternatives is related to the total remaining quantity of silica, which is some 80% smaller if the rock plug is used instead of the LHHP (Low Heat High

Radioactive waste repository study

International Nuclear Information System (INIS)

1978-11-01

This is the first part of a report of a preliminary study for Atomic Energy of Canada Limited. It considers the requirements for an underground waste repository for the disposal of wastes produced by the Canadian Nuclear Fuel Program. The following topics are discussed with reference to the repository: 1) underground layout, 2) cost estimates, 3) waste handling, 4) retrievability, decommissioning, sealing and monitoring, and 5) research and design engineering requirements. (author)

Design information verification (DIV) of closed geological repositories (SAGOR activity 3c)

International Nuclear Information System (INIS)

Myatt, J.

1998-02-01

then said to be 'closed' and this report addresses the DIV issues of this post closure phase. Following an introduction in section 1 the DIV requirements are described in section 2. Here, in section 2.1, the physical characteristics which make repositories different from any other type of safeguarded facility are highlighted. Of special significance is the fact that it is hidden underground and covert activities may prove to be very difficult to detect. The tools available for DIV are described in section 3 where it is pointed out that the only useful standard tool is visual observation. This will not be sufficient to maintain reliable safeguards and will have to be supplemented by one or more of the techniques new to safeguards described in section 3.2. They include: a) Ground penetrating radar - to enable the concrete seal plugs to be tested to see if they have been tampered with. b) Passive seismic monitoring - to monitor evidence of undeclared underground activity in the vicinity of the repository. Newly developing mining techniques may, however, make this ineffective. c) Active seismic monitoring - to provide evidence of new, undeclared, underground tunnels. A proven technique for oil surveys but one which will have to be proven in this application where finer detail is being sought. d) Satellite observations - to look for evidence of underground tunnelling from evidence of aboveground activities, within say 10 km of the periphery of the repository's emplacement areas, such as the sinking and use of mine shafts, the disposal of waste material, and the suspicious movement of vehicles. The general DIV requirements are discussed in section 4. In section 4.2, it is pointed out how important it is to consider how the closed repository will be safeguarded even before construction starts. Its location relative to other features can make safeguarding it more or less difficult and expensive. Old and current mine-workings adjacent to the repository may be a particular

An evaluation of repository-induced disturbances for a KBS-3 type repository

Energy Technology Data Exchange (ETDEWEB)

Savage, D.; McLeod, R.; McEwen, T. [QuantiSci, Melton Mowbray (United Kingdom)

1998-03-01

This report considers the potential physical and chemical perturbations caused by the excavation, operation and backfilling and sealing of a KBS-3 type repository for spent fuel in Sweden. Parts of the underground excavations are likely to remain open to the atmosphere for up to several decades. Time-dependent changes to the chemical environment and the properties of the geological formation will be occurring as well as the initial disturbance of construction and subsequent changes after backfilling. In addition, this report also discusses issues that arise from the co-disposal of spent fuel and intermediate level waste. The processes which are likely to act during each stage of a repository from construction through to backfilling and sealing have been reviewed and the degree to which these processes are understood and represented within the performance assessment is discussed. The areas of particular interest are: The coupling of thermal, hydrogeological and mechanical processes with particular reference to the development of the near-field; Understanding the transient process of re-saturation with particular reference to the buffer material surrounding the waste canisters, including chemical changes to the material; The impact of accidental events during the construction and operational phases of work and their possible consequence on the long term performance of the repository; Chemical issues relating to the co-disposal of spent fuel and intermediate level wastes within a single facility. When consideration of transient processes and coupling is discussed, it is apparent that numerical tools and a complete understanding to provide quantitative information is lacking. The importance of the engineered barrier system within the performance assessment for spent fuel disposal is recognised and the emphasis is placed on the understanding of the coupled processes in the evolution in the near-field of the geosphere 45 refs, 4 fig, 2 tabs

An evaluation of repository-induced disturbances for a KBS-3 type repository

International Nuclear Information System (INIS)

Savage, D.; McLeod, R.; McEwen, T.

1998-03-01

This report considers the potential physical and chemical perturbations caused by the excavation, operation and backfilling and sealing of a KBS-3 type repository for spent fuel in Sweden. Parts of the underground excavations are likely to remain open to the atmosphere for up to several decades. Time-dependent changes to the chemical environment and the properties of the geological formation will be occurring as well as the initial disturbance of construction and subsequent changes after backfilling. In addition, this report also discusses issues that arise from the co-disposal of spent fuel and intermediate level waste. The processes which are likely to act during each stage of a repository from construction through to backfilling and sealing have been reviewed and the degree to which these processes are understood and represented within the performance assessment is discussed. The areas of particular interest are: The coupling of thermal, hydrogeological and mechanical processes with particular reference to the development of the near-field; Understanding the transient process of re-saturation with particular reference to the buffer material surrounding the waste canisters, including chemical changes to the material; The impact of accidental events during the construction and operational phases of work and their possible consequence on the long term performance of the repository; Chemical issues relating to the co-disposal of spent fuel and intermediate level wastes within a single facility. When consideration of transient processes and coupling is discussed, it is apparent that numerical tools and a complete understanding to provide quantitative information is lacking. The importance of the engineered barrier system within the performance assessment for spent fuel disposal is recognised and the emphasis is placed on the understanding of the coupled processes in the evolution in the near-field of the geosphere

Repository seal materials performance for a SALT Repository Project 5-year code/model development plan: Draft

International Nuclear Information System (INIS)

1987-06-01

This document describes an integrated laboratory testing and model development effort for the seal system for a high-level nuclear waste repository in salt. The testing and modeling efforts are designed to determine seal material response in the repository environment, to provide models of seal system components for performance assessment, and to assist in the development of seal system designs. A code/model development and performance analysis program will be performed to predict the short- and long-term response of seal materials and seal components. The results from these analyses will be used to support the material testing activities on this contract and to support performance assessment activities that are conducted in other parts of the Salt Repository Project (SRP). 48 refs., 15 figs., 4 tabs

Prototype Repository. Tracer dilution tests during operation phase, test campaign 3

Energy Technology Data Exchange (ETDEWEB)

Harrstroem, Johan; Andersson, Peter (Geosigma AB (Sweden))

2010-05-15

The Prototype Repository project is focused on testing and demonstrating the function of the SKB deep repository system. The third tracer dilution campaign during the Prototype Repository operation period was performed in January 2010. The purpose was to estimate the groundwater flows and hydraulic gradients in the boreholes vicinity and will function as a reference for comparison with results from modeling and prior assumptions. The test campaign consisted of tracer dilution tests in 13 different borehole sections. Each test consisted of approximately 15-55 min tracer injection time and about 1-3 days dilution test time depending on the transmissivity of the test section. The data interpretation also included estimates of the local hydraulic gradients in the vicinity of the borehole sections

Radiological risks due to intrusion into a deep bedrock repository

International Nuclear Information System (INIS)

Nordlinder, S.; Bergstroem, U.; Edlund, O.

1999-01-01

The Swedish concept for disposal of high-level waste is a deep (500 m) bedrock repository (SFL) protected by multiple barriers that isolate the waste from the environment for such a long time that the physical decay will cause a substantial reduction of the radioactivity. The aim of concentration and isolation of high-level waste is to reduce the radiation risk. Intrusion in the repository may introduce a small residual risk to individuals. A risk analysis was performed comprising dose assessment and probabilities of occurrence. Intrusions may be considered to take place either due to conscious actions or by actions without any knowledge about the repository. For conscious intrusion it may be assumed that there will be enough knowledge to manage the radiation situation in a professional manner. Several reasons for making inadvertent intrusion are possible. Independently of the purpose, the most probable initial way of coming into contact with the radioactive material is by deep drilling. Examples of causes for drilling could be general scientific purposes or exploitation of geothermal energy. Dose assessments were made for intrusion due to inclined drilling directly into a canister, and drilling near an initially malfunctioning canister from which radionuclides have leaked into the groundwater. For the former case, external pathways were considered due to exposure from a core of the canister with fuel and contaminated bore dust. The most common drilling method is with water flushing for removal of bore dust, which will not cause any substantial transfer of radionuclides to air. For the second case, it was assumed that there was a well in the vicinity. The only pathway considered was therefore consumption of water because it dominates the exposure. The highest dose rates to man were, as expected, obtained by drilling into the canister. Dose rates decrease with time after closure. During the first time the relatively short-lived radionuclides Cs-137 and Sr-90 give

SUBSURFACE REPOSITORY INTEGRATED CONTROL SYSTEM DESIGN

International Nuclear Information System (INIS)

Randle, D.C.

2000-01-01

, controlled, and interfaced (Section 6.2). (3) Develop a preliminary design for the overall Subsurface Repository Integrated Control System functional architecture and graphically depict the operational features of this design through a series of control system functional block diagrams (Section 6.2). (4) Develop a physical architecture that presents a viable yet preliminary physical implementation for the Subsurface Repository Integrated Control System functional architecture (Section 6.3). (5) Develop an initial concept for an overall subsurface data communications network that can be used to integrate the various control systems comprising the Subsurface Repository Integrated Control System (Section 6.4). (6) Develop a preliminary central control room design for the Subsurface Repository Integrated Control System (Section 6.5). (7) Identify and discuss the general safety-related issues and design strategies with respect to development of the Subsurface Repository Integrated Control System (Section 6.6). (8) Discuss plans for the Subsurface Repository Integrated Control System's response to off-normal operations (Section 6.7). (9) Discuss plans and strategies for developing software for the Subsurface Repository Integrated Control System (Section 6.8)

Salt repository sealing materials development program: 5-year work plan

International Nuclear Information System (INIS)

Myers, L.B.

1986-06-01

This plan covers 5 years (fiscal years 1986 through 1990) of work in the repository sealing materials program to support design decisions and licensing activities for a salt repository. The plan covers a development activity, not a research activity. There are firm deliverables as the end points of each part of the work. The major deliverables are: development plans for code development and materials testing; seal system components models; seal system performance specifications; seal materials specifications; and seal materials properties ''handbook.'' The work described in this plan is divided into three general tasks as follows: mathematical modeling; materials studies (salt, cementitious materials, and earthen materials); and large-scale testing. Each of the sections presents an overview, status, planned activities, and summary of program milestones. This plan will be the starting point for preparing the development plans described above, but is subject to change if preparation of the work plan indicates that a different approach or sequence is preferable to achieve the ultimate goal, i.e., support of design and licensing

Thermal analyses of KBS-3H type repository

International Nuclear Information System (INIS)

Ikonen, K.

2003-12-01

This report contains the temperature dimensioning of the KBS-3H type nuclear fuel repository, where the fuel canisters are disposed at horizontal position in the horizontal tunnels according to the preliminary SKB (Swedish Nuclear Fuel and Waste Management Co) and Posiva plan. The maximum temperature on the canister surface is limited to the design temperature of +100 deg C. However, due to uncertainties in thermal analysis parameters (like scattering in rock conductivity) the allowable calculated maximum canister temperature is set to 90 deg C causing a safety margin of 10 deg C. The allowable temperature is controlled by adjusting the space between adjacent canisters, adjacent tunnels and the distance between separate panels of the repository and the pre-cooling time affecting power of the canisters. With reasonable canister and tunnel spacing the maximum temperature 90 deg C is achieved with an initial canister power of 1700 W. It became apparent that the temperature of canister surfaces can be determined by superposing analytic line heat source models much more efficiently than by numerical analysis, if the analytic model is first verified and calibrated by numerical analysis. This was done by comparing the surface temperatures of the central canister in a single infinite canister queue calculated numerically and analytically. In addition, the results from SKB analysis were used for comparison and for confirming the calculation procedure. For the Olkiluoto repository a reference case of one panel having 1500 canisters was analysed. The canisters are disposed in a rectangular geometry in a certain order. The calculation was performed separately for both Olkiluoto BWR canisters and Loviisa PWR canisters. The result was the minimum allowable spacing between canisters. (orig.)

Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 5, Part B: Chapter 8, Sections 8.3.1.5 through 8.3.1.17

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-01

This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the SOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules.

Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 5, Part B: Chapter 8, Sections 8.3.1.5 through 8.3.1.17

International Nuclear Information System (INIS)

1988-12-01

This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the SOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules

Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 8, Part B: Chapter 8, Sections 8.3.5 through 8.3.5.20

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-01

This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 68 figs., 102 tabs.

Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 8, Part B: Chapter 8, Sections 8.3.5 through 8.3.5.20

International Nuclear Information System (INIS)

1988-12-01

This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 68 figs., 102 tabs

SR 97: Post-closure safety for a KBS 3 type deep repository for spent nuclear fuel

International Nuclear Information System (INIS)

Hedin, A.; Kautsky, U.

2000-03-01

Prior to coming site investigations for siting of a deep repository for spent nuclear fuel, SKB has carried out the long-term safety assessment SR 97, requested by the Swedish Government. The repository is of the KBS-3 type, where the fuel is placed in isolating copper canisters with a high-strength cast iron insert. The canisters are surrounded by bentonite clay in individual deposition holes at a depth of 500 m in granitic bedrock. The future evolution of the repository system is analysed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings, including climate, persist. The four other scenarios show the evolution if the repository contains a few initially defective canisters, in the event of climate change, in the event of earthquakes, and in the event of future inadvertent human intrusion. The principal conclusion of the assessment is that the prospects of building a safe deep repository for spent nuclear fuel in Swedish granitic bedrock are very good. (author)

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Evolution report

International Nuclear Information System (INIS)

Smith, P.; Johnson, L.; Snellman, M.; Pastina, B.; Gribi, P.

2007-12-01

The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. KBS-3H and KBS-3V are the two design alternatives of the KBS-3 method. Posiva and SKB have conducted a joint research, demonstration and development (RD and D) programme in 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to the reference alternative KBS-3V. The overall objectives of the present phase covering the period 2004-2007, have been to demonstrate that the horizontal deposition alternative is technically feasible and to demonstrate that it fulfils the same long-term safety requirements as KBS-3V. The safety studies conducted as part of this programme include a safety assessment of a preliminary design of a KBS-3H repository for spent nuclear fuel located about 400 m underground at the Olkiluoto site, which is the proposed site for a spent fuel repository in Finland. In the KBS-3H design alternative, each canister, with a surrounding layer of bentonite clay, is pre-packaged in a perforated steel cylinder prior to emplacement in the deposition drift; the entire assembly is called the supercontainer. Several supercontainers are positioned along parallel, 100 - 300 m long deposition drifts, which are sealed following waste emplacement using drift end plugs. Bentonite distance blocks separate the supercontainers, one from another, along the drift. Steel compartment plugs can be used to seal off drift sections with higher inflow, thus isolating the different compartments within the drift. The present report describes the repository evolution in successive time frames, including key uncertainties. The description of evolution starts with the initial conditions at the time of emplacement of the first canisters. The repository evolves through an early, transient phase to a state where evolution is far slower. Particular attention is given to describing the transient phase, since this is where most of the

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Evolution report

International Nuclear Information System (INIS)

Smith, Paul; Johnson, Lawrence; Snellman, Margit; Pastina, Barbara; Gribi, Peter

2008-01-01

The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. KBS-3H and KBS-3V are the two design alternatives of the KBS-3 method. Posiva and SKB have conducted a joint research, demonstration and development (RDandD) programme in 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to the reference alternative KBS-3V. The overall objectives of the present phase covering the period 2004-2007, have been to demonstrate that the horizontal deposition alternative is technically feasible and to demonstrate that it fulfils the same long-term safety requirements as KBS-3V. The safety studies conducted as part of this programme include a safety assessment of a preliminary design of a KBS-3H repository for spent nuclear fuel located about 400 m underground at the Olkiluoto site, which is the proposed site for a spent fuel repository in Finland. In the KBS-3H design alternative, each canister, with a surrounding layer of bentonite clay, is pre-packaged in a perforated steel cylinder prior to emplacement in the deposition drift; the entire assembly is called the supercontainer. Several supercontainers are positioned along parallel, 100-300 m long deposition drifts, which are sealed following waste emplacement using drift end plugs. Bentonite distance blocks separate the supercontainers, one from another, along the drift. Steel compartment plugs can be used to seal off drift sections with higher inflow, thus isolating the different compartments within the drift. The present report describes the repository evolution in successive time frames, including key uncertainties. The description of evolution starts with the initial conditions at the time of emplacement of the first canisters. The repository evolves through an early, transient phase to a state where evolution is far slower. Particular attention is given to describing the transient phase, since this is where most of the

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Evolution report

Energy Technology Data Exchange (ETDEWEB)

Smith, Paul; Johnson, Lawrence; Snellman, Margit; Pastina, Barbara; Gribi, Peter

2008-01-15

The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. KBS-3H and KBS-3V are the two design alternatives of the KBS-3 method. Posiva and SKB have conducted a joint research, demonstration and development (RDandD) programme in 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to the reference alternative KBS-3V. The overall objectives of the present phase covering the period 2004-2007, have been to demonstrate that the horizontal deposition alternative is technically feasible and to demonstrate that it fulfils the same long-term safety requirements as KBS-3V. The safety studies conducted as part of this programme include a safety assessment of a preliminary design of a KBS-3H repository for spent nuclear fuel located about 400 m underground at the Olkiluoto site, which is the proposed site for a spent fuel repository in Finland. In the KBS-3H design alternative, each canister, with a surrounding layer of bentonite clay, is pre-packaged in a perforated steel cylinder prior to emplacement in the deposition drift; the entire assembly is called the supercontainer. Several supercontainers are positioned along parallel, 100-300 m long deposition drifts, which are sealed following waste emplacement using drift end plugs. Bentonite distance blocks separate the supercontainers, one from another, along the drift. Steel compartment plugs can be used to seal off drift sections with higher inflow, thus isolating the different compartments within the drift. The present report describes the repository evolution in successive time frames, including key uncertainties. The description of evolution starts with the initial conditions at the time of emplacement of the first canisters. The repository evolves through an early, transient phase to a state where evolution is far slower. Particular attention is given to describing the transient phase, since this is where most of the

Source terms; isolation and radiological consequences of carbon-14 waste in the Swedish SFR repository

International Nuclear Information System (INIS)

Hesboel, R.; Puigdomenech, I.; Evans, S.

1990-01-01

The source term, isolation capacity, and long-term radiological exposure of 14 C from the Swedish underground repository for low and intermediate level waste (SFR) is assessed. The prospective amount of 14 C in the repository is assumed to be 5 TBq. Spent ion exchange resins will be the dominant source of 14 C. The pore water in the concrete repository is expected to maintain a pH of >10.5 for a period of at least 10 6 y. The cement matrix of the repository will retain most of the 14 CO 3 2- initially present. Bacterial production of CO 2 and CH 4 from degradation of ion-exchange resins and bitumen may contribute to 14 C release to the biosphere. However, CH 4 contributes only to a small extent to the overall carbon loss from freshwater ecosystems. The individual doses to local and regional individuals peaked with 5x10 -3 and regional individuals peaked with 5x10 -3 and 8x10 -4 μSv y -1 respectively at about 2.4x10 4 years. A total leakage of 8.4 GBq of 14 C from the repository will cause a total collective dose commitment of 1.1 manSv or 130 manSv TBq -1 . (authors)

Active Exploration of Large 3D Model Repositories.

Science.gov (United States)

Gao, Lin; Cao, Yan-Pei; Lai, Yu-Kun; Huang, Hao-Zhi; Kobbelt, Leif; Hu, Shi-Min

2015-12-01

With broader availability of large-scale 3D model repositories, the need for efficient and effective exploration becomes more and more urgent. Existing model retrieval techniques do not scale well with the size of the database since often a large number of very similar objects are returned for a query, and the possibilities to refine the search are quite limited. We propose an interactive approach where the user feeds an active learning procedure by labeling either entire models or parts of them as "like" or "dislike" such that the system can automatically update an active set of recommended models. To provide an intuitive user interface, candidate models are presented based on their estimated relevance for the current query. From the methodological point of view, our main contribution is to exploit not only the similarity between a query and the database models but also the similarities among the database models themselves. We achieve this by an offline pre-processing stage, where global and local shape descriptors are computed for each model and a sparse distance metric is derived that can be evaluated efficiently even for very large databases. We demonstrate the effectiveness of our method by interactively exploring a repository containing over 100 K models.

3D numerical modelling of the thermal state of deep geological nuclear waste repositories

Science.gov (United States)

Butov, R. A.; Drobyshevsky, N. I.; Moiseenko, E. V.; Tokarev, Yu. N.

2017-09-01

One of the important aspects of the high-level radioactive waste (HLW) disposal in deep geological repositories is ensuring the integrity of the engineered barriers which is, among other phenomena, considerably influenced by the thermal loads. As the HLW produce significant amount of heat, the design of the repository should maintain the balance between the cost-effectiveness of the construction and the sufficiency of the safety margins, including those imposed on the thermal conditions of the barriers. The 3D finite-element computer code FENIA was developed as a tool for simulation of thermal processes in deep geological repositories. Further the models for mechanical phenomena and groundwater hydraulics will be added resulting in a fully coupled thermo-hydro-mechanical (THM) solution. The long-term simulations of the thermal state were performed for two possible layouts of the repository. One was based on the proposed project of Russian repository, and another features larger HLW amount within the same space. The obtained results describe the spatial and temporal evolution of the temperature filed inside the repository and in the surrounding rock for 3500 years. These results show that practically all generated heat was ultimately absorbed by the host rock without any significant temperature increase. Still in the short time span even in case of smaller amount of the HLW the temperature maximum exceeds 100 °C, and for larger amount of the HLW the local temperature remains above 100 °C for considerable time. Thus, the substantiation of the long-term stability of the repository would require an extensive study of the materials properties and behaviour in order to remove the excessive conservatism from the simulations and to reduce the uncertainty of the input data.

Metadata for 3D Models. How to search in 3D Model repositories?

OpenAIRE

Boeykens, Stefan; Bogani, Elena

2008-01-01

In architectural education and practice, students, teachers and architects increasingly rely on online repositories with architectural information. This includes product model data, exemplary architectural projects and technical documentation, in a wide variety of formats. Unfortunately, the major part of this architectural content exists in individual repositories and they are not accessible to geographically distributed professionals and students who require them. Some of them are freely ac...

Radionuclide transport from near-surface repository for radioactive waste - The unsaturated zone approach

Energy Technology Data Exchange (ETDEWEB)

Jakimaviciute-Maseliene, V. [Vilnius University (Lithuania); Mazeika, J. [Nature Research Centre (Lithuania); Motiejunas, S. [Radioactive Waste Management Agency (Lithuania)

2014-07-01

About 100 000 m{sup 3} of solid conditioned Low and Intermediate Level Waste (LILW), generated during operation and decommissioning of the Ignalina nuclear power plant (INPP), are to be disposed of in a near-surface repository (NSR) - a 'hill'-type repository with reinforced concrete vaults and with engineered and natural barriers. The northeastern Lithuania and the environment of the INPP in particular were recognized as the areas most suitable for a near-surface repository (Stabatiske Site). The engineered barriers of the repository consist of concrete cells surrounded by clay-based material of low permeability with about the same isolating capacity in all directions. The clay materials must be effectively compactable so that required hydraulic conductivity is reached. The Lithuanian Triassic clay turned out to be sufficiently rich in smectites and was proposed as main candidate for sealing of the repository. When the concrete vaults are filled, the repository cover will be constructed. The surface of the mound will be planted with grass. In this study a computer code FEFLOW 5.0 was applied for simulating the transport of the most mobile radionuclides ({sup 3}H, {sup 14}C, {sup 59}Ni and {sup 94}Nb) with moisture through an unsaturated vault of the near-surface repository in Stabatiske Site. The HYDRUS-1D analysis was used to assess the radionuclide transport in the repository and to estimate initial activity concentrations of radionuclides transported from the cemented waste matrix. Radionuclide release from the vault in the unsaturated conditions after closure of the repository and consequent contaminant plume transport has been assessed taking into account site-specific natural and engineering conditions and based on a normal evolution scenario. The highest peak radionuclide activity concentrations were estimated applying the FEFLOW code. The highest value of {sup 14}C activity concentration(about 1.3x10{sup 8} Bq/m{sup 3}) at the groundwater table

Reference design description for a geologic repository. Revision 02

International Nuclear Information System (INIS)

1999-01-01

This Reference Design Description explains the current design for a potential geologic repository that may be located at Yucca Mountain in Nevada. It describes the proposed design for a surface facility, subsurface repository, and waste packaging; it also presents the current design of the key engineering systems for the final four phases: operations, monitoring, closure, and postclosure. In addition, this Reference Design Description reviews the expected long-term performance of the potential repository. In accordance with current law, this design does not include an interim storage option. This document has six major sections. Section 1 describes the physical layout of the proposed repository. The second section describes the 4-phase evolution of the development of the proposed repository. Section 3 describes the reception of waste from offsite locations. The fourth section details the various systems that will package the waste and move it below ground as well as safety monitoring and closure. Section 5 describes the systems (both physical and analytical) that ensure continued safety after closure. The final section offers design options that may be adopted to increase the margin of safety

Assessment of a KBS-3 nuclear waste repository as a plane of weakness

Energy Technology Data Exchange (ETDEWEB)

Loennqvist, Margareta; Kristensson, Ola; Faelth, Billy (Clay Technology AB, Lund (Sweden))

2010-06-15

normal- and shear stresses recorded in horizontal planes in a Mw 6.2 model. The results indicate that even with a system of tunnels the rock mass have a high stability. Including tunnels with 40 m spacing at a location far from any fault edge, gives a FoS reduction from 4 to 3.5. Reducing the tunnel spacing down to 20 m gives a FoS of 2. In the earthquake model the earthquake is simulated using conservative assumptions (small rupture area, high fault slip velocity, large fault slip), which means that the stability evaluation here is conservative. In order to study the stability against sheeting, a model with a number of fractures at different depths (10 m, 20 m, 30 m, 40 m, 50 m, 75 m, 100 m and 400 m) is subjected to a large horizontal stress increase. In order to provoke sheeting in the fractures, the model's upper boundary simulates a curved ground surface, and all fractures are parallel with the ground surface. All fractures have zero tensile strength. After completed compression, sheeting is observed in all fractures down to 100 m depth. In the fracture at 400 m depth, the normal effective stress has been reduced from 6.5 to 6.0 MPa (about 8%). Thus, this fracture is still subjected to compressive stress. Given the conservative model assumptions (large horizontal compression, fractures at all depths parallel with the curved ground surface and zero fracture tensile strength), it can be concluded that there is no risk of sheeting failure at the projected repository depth (about 500 m). Since the rock mass will be subjected to vertical compression at all times at this depth, a system of tunnels will not give any increased risk of sheeting. Based on the schematic and conservative modelling approaches applied here, it is concluded that, given the current repository layout with 40 m deposition tunnel spacing, the repository will not act as a plane of weakness. It is also concluded that a reduction of the tunnel spacing to 20-30 m will not increase the risk of

Assessment of a KBS-3 nuclear waste repository as a plane of weakness

International Nuclear Information System (INIS)

Loennqvist, Margareta; Kristensson, Ola; Faelth, Billy

2010-06-01

stresses recorded in horizontal planes in a Mw 6.2 model. The results indicate that even with a system of tunnels the rock mass have a high stability. Including tunnels with 40 m spacing at a location far from any fault edge, gives a FoS reduction from 4 to 3.5. Reducing the tunnel spacing down to 20 m gives a FoS of 2. In the earthquake model the earthquake is simulated using conservative assumptions (small rupture area, high fault slip velocity, large fault slip), which means that the stability evaluation here is conservative. In order to study the stability against sheeting, a model with a number of fractures at different depths (10 m, 20 m, 30 m, 40 m, 50 m, 75 m, 100 m and 400 m) is subjected to a large horizontal stress increase. In order to provoke sheeting in the fractures, the model's upper boundary simulates a curved ground surface, and all fractures are parallel with the ground surface. All fractures have zero tensile strength. After completed compression, sheeting is observed in all fractures down to 100 m depth. In the fracture at 400 m depth, the normal effective stress has been reduced from 6.5 to 6.0 MPa (about 8%). Thus, this fracture is still subjected to compressive stress. Given the conservative model assumptions (large horizontal compression, fractures at all depths parallel with the curved ground surface and zero fracture tensile strength), it can be concluded that there is no risk of sheeting failure at the projected repository depth (about 500 m). Since the rock mass will be subjected to vertical compression at all times at this depth, a system of tunnels will not give any increased risk of sheeting. Based on the schematic and conservative modelling approaches applied here, it is concluded that, given the current repository layout with 40 m deposition tunnel spacing, the repository will not act as a plane of weakness. It is also concluded that a reduction of the tunnel spacing to 20-30 m will not increase the risk of shearing or sheeting at the

Rock support for nuclear waste repositories

International Nuclear Information System (INIS)

Abramson, L.W.; Schmidt, B.

1984-01-01

The design of rock support for underground nuclear waste repositories requires consideration of special construction and operation requirements, and of the adverse environmental conditions in which some of the support is placed. While repository layouts resemble mines, design, construction and operation are subject to quality assurance and public scrutiny similar to what is experienced for nuclear power plants. Exploration, design, construction and operation go through phases of review and licensing by government agencies as repositories evolve. This paper discusses (1) the various stages of repository development; (2) the environment that supports must be designed for; (3) the environmental effects on support materials; and (4) alternative types of repository rock support

Representation of an open repository in groundwater flow models

International Nuclear Information System (INIS)

Painter, Scott; Sun, Alexander

2005-08-01

The effect of repository tunnels on groundwater flow has been identified as a potential issue for the nuclear waste repository being considered by SKB for a fractured granite formation in Sweden. In particular, the following pre-closure and post-closure processes have been identified as being important: inflows into open tunnels as functions of estimated grouting efficiencies, drawdown of the water table in the vicinity of the repository, upcoming of saline water, 'turnover' of surface water in the upper bedrock, and resaturation of backfilled tunnels following repository closure. The representation of repository tunnels within groundwater models is addressed in this report. The primary focus is on far-field flow that is modeled with a continuum porous medium approximation. Of particular interest are the consequences of the tunnel representation on the transient response of the groundwater system to repository operations and repository closure, as well as modeling issues such as how the water-table free surface and the coupling to near-surface hydrogeology should be handled. The overall objectives are to understand the consequences of current representations and to identify appropriate approximations for representing open tunnels in future groundwater modeling studies. The following conclusions can be drawn from the results of the simulations: 1. Two-phase flow may be induced in the vicinity of repository tunnels during repository pre-closure operations, but the formation of a two-phase flow region will not significantly affect far-field flow or inflows into tunnels. 2. The water table will be drawn down to the repository horizon and tunnel inflows will reach a steady-state value within about 5 years. 3. Steady-state inflows at the repository edge are estimated to be about 250 m 3 /year per meter of tunnel. Inflows will be greater during the transient de-watering period and less for tunnel locations closer to the repository center. 4. Significant amounts of water

Representation of an open repository in groundwater flow models

Energy Technology Data Exchange (ETDEWEB)

Painter, Scott; Sun, Alexander [Southwest Research Inst., San Antonio, TX (United States). Center for Nuclear Waste Regulatory Analyses

2005-08-01

The effect of repository tunnels on groundwater flow has been identified as a potential issue for the nuclear waste repository being considered by SKB for a fractured granite formation in Sweden. In particular, the following pre-closure and post-closure processes have been identified as being important: inflows into open tunnels as functions of estimated grouting efficiencies, drawdown of the water table in the vicinity of the repository, upcoming of saline water, 'turnover' of surface water in the upper bedrock, and resaturation of backfilled tunnels following repository closure. The representation of repository tunnels within groundwater models is addressed in this report. The primary focus is on far-field flow that is modeled with a continuum porous medium approximation. Of particular interest are the consequences of the tunnel representation on the transient response of the groundwater system to repository operations and repository closure, as well as modeling issues such as how the water-table free surface and the coupling to near-surface hydrogeology should be handled. The overall objectives are to understand the consequences of current representations and to identify appropriate approximations for representing open tunnels in future groundwater modeling studies. The following conclusions can be drawn from the results of the simulations: 1. Two-phase flow may be induced in the vicinity of repository tunnels during repository pre-closure operations, but the formation of a two-phase flow region will not significantly affect far-field flow or inflows into tunnels. 2. The water table will be drawn down to the repository horizon and tunnel inflows will reach a steady-state value within about 5 years. 3. Steady-state inflows at the repository edge are estimated to be about 250 m{sup 3}/year per meter of tunnel. Inflows will be greater during the transient de-watering period and less for tunnel locations closer to the repository center. 4. Significant

SUBSURFACE REPOSITORY INTEGRATED CONTROL SYSTEM DESIGN

International Nuclear Information System (INIS)

C.J. Fernado

1998-01-01

that present preliminary concepts for integrating the diverse set of control systems to be used within the subsurface repository facility (Presented in Section 7.3). (5) Develop initial concepts for an overall subsurface data communication system that can be used to integrate critical and data-intensive control systems (Presented in Section 7.4). (6) Discuss technology trends and control system design issues (Presented in Section 7.5)

SUBSURFACE REPOSITORY INTEGRATED CONTROL SYSTEM DESIGN

Energy Technology Data Exchange (ETDEWEB)

C.J. Fernado

1998-09-17

present preliminary concepts for integrating the diverse set of control systems to be used within the subsurface repository facility (Presented in Section 7.3). (5) Develop initial concepts for an overall subsurface data communication system that can be used to integrate critical and data-intensive control systems (Presented in Section 7.4). (6) Discuss technology trends and control system design issues (Presented in Section 7.5).

Czech Republic. Dukovany repository

International Nuclear Information System (INIS)

2001-01-01

Full text: The repository at the Dukovany site is a structure located above the land surface. It consists of two double-rows of reinforced concrete vaults. Each double-row has dimensions 38x160x6 meters and contains 2x28 vaults. The internal dimensions of each vault are 18x6x5.4 meters. The repository serves for reactor wastes from the Dukovany and Temelin nuclear power plants (NPPs). Its capacity is 55,000 m 3 or 130,000 drums. The repository is a fully engineered facility with multiple barriers. The first engineered barrier is the waste form (in the case of waste from the Dukovany NPP, the waste form is mainly bitumen, but concrete and glass are also considered as suitable solidification products). The second barrier is the container (a 200 litre steel drum or a HIC container), whereas the third consists of cut-off reinforced concrete walls with asphalt-based hydro-insulation. The fourth barrier is a cap which should protect the vaults against infiltration of rainwater and should serve also as an intrusion and erosion barrier. The fifth barrier is a drainage system around the repository which is composed of layers of gravel and sand. The void space in drums around the waste is filled with specially composed grout. Such waste packages are emplaced into the disposal vault, which is covered by pre-fabricated panels. Thereafter, joints between the panels are sealed and a provisional coverage added; the final cover, however, will be constructed only over the whole row of 28 vaults, until all vaults are filled with waste. The final cover will encompass the following components: reinforced concrete pre-fabricated panels (500 mm); cement overcoat (30 mm); insulation foil; concrete layer for cap levelling (5-150 mm); layer of asphalto-propylene concrete (150 mm); soil (450 mm); geotextile foil with topsoil (top surface vegetation). (author)

Radioactive waste repository study

International Nuclear Information System (INIS)

1978-11-01

This is the second part of a report of a preliminary study for AECL. It considers the requirements for an underground waste repository for the disposal of wastes produced by the Canadian Nuclear Fuel Program. The following topics are discussed with reference to the repository: 1) geotechnical assessment, 2) hydrogeology and waste containment, 3) thermal loading and 4) rock mechanics. (author)

Decision-Making Risks Concerning the Construction of the Goiania Waste Repository

International Nuclear Information System (INIS)

Paschoa, A.S.; Rozental, J.J.; Tranjan Filho, A.

2001-01-01

As it is well known, an accident with a teletherapy source made of 137 CsCl with an initial activity of 59 TBq occurred in Goiania, in September of 1987. This paper will discuss the decision-making process, and the struggle that followed the decision to build the final repository for the remnants of the Goiania accident. The Goiania final repository was built as planned. The two subsurface structures under the grassy artificial hills hold the overall volume of the remnants of the Goiania accident. The near hill holds 5x10 3 m3 of stabilized wastes without radioactivity, or with very low radioactivity. The far hill holds the remaining 6.5x10 3 m 3 of stabilized wastes with low and medium radioactivity. The central part of each subsurface hill has been shielded by wastes with less and less radioactivity. The overall fenced area occupies 1.85x10 5 m 2 . The external radiation levels are similar to the surrounding background, and much lower than those found in the Brazilian areas of high natural radioactivity. The site is permanently monitored by independent institutions, including Brazilian universities, and national and international organizations. As it was mentioned earlier, the final repository was build to last for at least 400 years. Although the initial decision to adopt a too conservative decontamination criterion in the case of the Goiania accident was bound to produce excessive amount of waste; such decision proved, retrospectively, not to be bad because the excess low radioactive waste produced was used as extra shielding material in final repository. The technical decision-maker should not abandon risk estimates, but should be aware that credibility is the main basis to achieve acceptability of a decision by the general public. Risk perception should be regarded as only a first step towards what may be called knowledge, or comprehension of risk estimates, but risk perception by the general public is still an open issue. The problem of a fixed, or near

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Complementary evaluations of safety

International Nuclear Information System (INIS)

Neall, Fiona; Pastina, Barbara; Snellman, Margit; Smith, Paul; Gribi, P.; Johnson, Lawrence

2008-12-01

The KBS-3H design is a variant of the more general KBS-3 method for the geological disposal of spent nuclear fuel in Finland and Sweden. In the KBS-3H design, multiple assemblies containing spent fuel are emplaced horizontally in parallel, approximately 300 m long, slightly inclined deposition drifts. The copper canisters, each with a surrounding layer of bentonite clay, are placed in perforated steel shells prior to deposition in the drifts; the assembly is called the 'supercontainer'. The other KBS-3 variant is the KBS-3V design, in which the copper canisters are emplaced vertically in individual deposition holes surrounded by bentonite clay but without steel supercontainer shells. SKB and Posiva have conducted a Research, Development and Demonstration programme over the period 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to KBS-3V. As part of this programme, the long-term safety of a KBS-3H repository has been assessed in the KBS-3H safety studies. In order to focus the safety studies, the Olkiluoto site in the municipality of Eurajoki, which is the proposed site for a spent fuel repository in Finland, was used as a hypothetical site for a KBS-3H repository. The present report is part of a portfolio of reports discussing the long-term safety of the KBS-3H repository. The overall outcome of the KBS-3H safety studies is documented in the summary report, 'Safety assessment for a KBS-3H repository for spent nuclear fuel at Olkiluoto'. The purpose and scope of the KBS-3H complementary evaluations of safety report is provided in Posiva's Safety Case Plan, which is based on Regulatory Guide YVL 8.4 and on international guidelines on complementary lines of argument to long-term safety that are considered an important element of a post-closure safety case for geological repositories. Complementary evaluations of safety require the use of evaluations, evidence and qualitative supporting arguments that lie outside the

National waste terminal storage conceptual reference repository description

International Nuclear Information System (INIS)

Odgers, I.L.; Collings, J.L.

1981-01-01

The conceptual reference repository description (CRRD) discusses, from a conceptual engineering standpoint, the structures, systems, equipment, and operations necessary to: (1) receive unreprocessed spent fuel assemblies in standard casks; (2) unload these assemblies; (3) place them in canisters; (4) transport the canisters to underground storage locations in the salt dome; and (5) place the canisters in terminal storage. The CRRD also elaborates on the concepts for retrieval and recovery of the spent fuel after burial and describes the development of the shafts and the underground areas, as well as the supporting operational utility and administrative features of the repository

Food entries in a large allergy data repository.

Science.gov (United States)

Plasek, Joseph M; Goss, Foster R; Lai, Kenneth H; Lau, Jason J; Seger, Diane L; Blumenthal, Kimberly G; Wickner, Paige G; Slight, Sarah P; Chang, Frank Y; Topaz, Maxim; Bates, David W; Zhou, Li

2016-04-01

Accurate food adverse sensitivity documentation in electronic health records (EHRs) is crucial to patient safety. This study examined, encoded, and grouped foods that caused any adverse sensitivity in a large allergy repository using natural language processing and standard terminologies. Using the Medical Text Extraction, Reasoning, and Mapping System (MTERMS), we processed both structured and free-text entries stored in an enterprise-wide allergy repository (Partners' Enterprise-wide Allergy Repository), normalized diverse food allergen terms into concepts, and encoded these concepts using the Systematized Nomenclature of Medicine - Clinical Terms (SNOMED-CT) and Unique Ingredient Identifiers (UNII) terminologies. Concept coverage also was assessed for these two terminologies. We further categorized allergen concepts into groups and calculated the frequencies of these concepts by group. Finally, we conducted an external validation of MTERMS's performance when identifying food allergen terms, using a randomized sample from a different institution. We identified 158 552 food allergen records (2140 unique terms) in the Partners repository, corresponding to 672 food allergen concepts. High-frequency groups included shellfish (19.3%), fruits or vegetables (18.4%), dairy (9.0%), peanuts (8.5%), tree nuts (8.5%), eggs (6.0%), grains (5.1%), and additives (4.7%). Ambiguous, generic concepts such as "nuts" and "seafood" accounted for 8.8% of the records. SNOMED-CT covered more concepts than UNII in terms of exact (81.7% vs 68.0%) and partial (14.3% vs 9.7%) matches. Adverse sensitivities to food are diverse, and existing standard terminologies have gaps in their coverage of the breadth of allergy concepts. New strategies are needed to represent and standardize food adverse sensitivity concepts, to improve documentation in EHRs. © The Author 2015. Published by Oxford University Press on behalf of the American Medical Informatics Association. All rights reserved. For

Monitoring system specifications: retrieval of surf from a salt repository

International Nuclear Information System (INIS)

1980-01-01

The task of developing specifications for a reference monitoring system determined by repository environmental conditions, retrieval operations, and federal regulatory criteria is discussed. The monitoring system specified in this report is capable of measuring (1) package position and orientation, (2) vault deformation, (3) brine accumulation, (4) spent fuel dissolution, (5) temperature, (6) nuclear radiation, and (7) package condition with sufficient accuracy to provide data input to a general risk assessment model. In order to define a monitoring system which can provide probabilistic data on radiological risk to operating personnel and the general public for a salt mine repository, the following information is required: (1) a complete design of the salt SURF repository including inventory, density and waste package design details; (2) probalistic failure rate data on containment integrity of the SURF waste package; (3) probabilistic failure rate data on the monitoring system components

Postclosure risks of alternative SRP nuclear waste forms in geologic repositories

International Nuclear Information System (INIS)

Cheung, H.; Edwards, L.; Harvey, T.; Revelli, M.

1982-05-01

The postclosure risk of REFERENCE and ALTERNATIVE waste forms for the defense high-level waste at the Savannah River Plant (SRP) were compared by analyses with a computer code, MISER, written to study the effects of repository features in a probabilistic framework. MISER traces radionuclide flows through a network of stream tubes from the repository to risk-sensitive points. Uncertainties in waste form, package properties, and geotechnical data are accounted for with Monte Carlo techniques. Our results show: (1) for generic layered-salt and basalt repositories, the difference in performance between the two waste forms is insignificant; (2) where the doses are sensitive to uncertainties in leaching rates, the doses are orders of magnitude below background; (3) disruptive events contribute only slightly to the risk of a layered-salt repository; (4) simple design alterations have strong effects on near field doses; (5) great care should be exercised in selecting the location at which repository risks are to be measured, calculated, or regulated

Preliminary design of the repository. Stage 2

International Nuclear Information System (INIS)

Saanio, T.; Kirkkomaeki, T.; Keto, P.; Kukkola, T.; Raiko, H.

2007-04-01

, investigations in ONKALO and investigations during the excavation and operation of the repository. The repository is planned so that technical development can be flexibly utilized. The total volume of the repository is approximately 1.3 million m 3 . The maximum open volume at any one time is around 0.6 million m 3 , because the repository is excavated and backfilled in stages. The repository is divided into the controlled area and the uncontrolled area. Canisters are always handled and lowered to the deposition hole in the controlled area. The excavation and construction of new tunnels and the backfilling of the tunnels is carried out in the uncontrolled area. Extensive material transfers, such as transfers of broken rock and backfilling materials are conducted in the access tunnel. Separate ventilation systems are provided for the controlled and the uncontrolled area. (orig.)

Preliminary design of the repository, stage 2

International Nuclear Information System (INIS)

Saanio, T.; Kirkkomaeki, T.; Keto, P.; Kukkola, T.; Raiko, H.

2007-01-01

, investigations in ONKALO and investigations during the excavation and operation of the repository. The repository is planned so that technical development can be flexibly utilized. The total volume of the repository is approximately 1.3 million m3. The maximum open volume at any one time is around 0.6 million m3, because the repository is excavated and backfilled in stages. The repository is divided into the controlled area and the uncontrolled area. Canisters are always handled and lowered to the deposition hole in the controlled area. The excavation and construction of new tunnels and the backfilling of the tunnels is carried out in the uncontrolled area. Extensive material transfers, such as transfers of broken rock and backfilling materials are conducted in the access tunnel. Separate ventilation systems are provided for the controlled and the uncontrolled area. (orig.)

Monitored Geologic Repository Project Description Document

International Nuclear Information System (INIS)

Curry, P. M.

2001-01-01

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (YMP 2000a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M and O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6)

Monitored Geologic Repository Project Description Document

International Nuclear Information System (INIS)

Curry, P.

2000-01-01

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (CRWMS M and O 2000b) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) engineering design basis in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The engineering design basis documented in the PDD is to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the engineering design basis from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the engineering design basis captured in the SDDs and the design requirements captured in U.S. Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M and O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 2-1, the MGR Architecture (Section 4.1),the Engineering Design Bases (Section 5), and the Controlled Project Assumptions (Section 6)

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Complementary evaluations of safety

Energy Technology Data Exchange (ETDEWEB)

Neall, Fiona; Pastina, Barbara; Snellman, Margit; Smith, Paul; Gribi, P.; Johnson, Lawrence

2008-12-15

The KBS-3H design is a variant of the more general KBS-3 method for the geological disposal of spent nuclear fuel in Finland and Sweden. In the KBS-3H design, multiple assemblies containing spent fuel are emplaced horizontally in parallel, approximately 300 m long, slightly inclined deposition drifts. The copper canisters, each with a surrounding layer of bentonite clay, are placed in perforated steel shells prior to deposition in the drifts; the assembly is called the 'supercontainer'. The other KBS-3 variant is the KBS-3V design, in which the copper canisters are emplaced vertically in individual deposition holes surrounded by bentonite clay but without steel supercontainer shells. SKB and Posiva have conducted a Research, Development and Demonstration programme over the period 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to KBS-3V. As part of this programme, the long-term safety of a KBS-3H repository has been assessed in the KBS-3H safety studies. In order to focus the safety studies, the Olkiluoto site in the municipality of Eurajoki, which is the proposed site for a spent fuel repository in Finland, was used as a hypothetical site for a KBS-3H repository. The present report is part of a portfolio of reports discussing the long-term safety of the KBS-3H repository. The overall outcome of the KBS-3H safety studies is documented in the summary report, 'Safety assessment for a KBS-3H repository for spent nuclear fuel at Olkiluoto'. The purpose and scope of the KBS-3H complementary evaluations of safety report is provided in Posiva's Safety Case Plan, which is based on Regulatory Guide YVL 8.4 and on international guidelines on complementary lines of argument to long-term safety that are considered an important element of a post-closure safety case for geological repositories. Complementary evaluations of safety require the use of evaluations, evidence and qualitative supporting arguments

NWTS conceptual reference repository description (CRRD). Volume 1. Summary

International Nuclear Information System (INIS)

1981-05-01

This report is a Conceptual Reference Repository Description (CRRD) for the terminal storage of spent, unreprocessed fuel assemblies and low-level transuranic waste. It is based on the following three previously prepared conceptual design reports: National Waste Terminal Storage in a Bedded Salt Formation for Spent Unreprocessed Fuel (NWTS-R2), prepared by Kaiser Engineers; National Waste Terminal Storage Repository Number 1 (NWTS-R1), prepared by Stearns-Roger; Spent Fuel Receiving and Packaging Facility Conceptual Design, prepared by Rockwell Hanford Operations and Kaiser Engineers. The CRRD is not itself a conceptual design report, but combines the key features of the above three reports into a description of a reference repository. This description is to be used as a basis for the preparation of a preliminary information report for the repositories. The CRRD discusses from a conceptual engineering standpoint the structures, systems, equipment, and operations necessary to (1) receive unreprocessed spent fuel assemblies via standard shipping casks, (2) offload these assemblies, (3) place the assemblies in canisters, (4) transport the canisters to underground storage locations in the salt dome, and (5) place these canisters in terminal storage. The CRRD also elaborates on the concepts for the retrieval and recovery of the spent fuel after burial; describes the development of the shafts and the underground areas,as well as the supporting operational utility and administrative features of the repository; and discusses the impacts on the reference repository of (1) changes in the waste package concept, (2) dry receiving and dry temporary storage of waste, (3) terminal storage of reprocessing waste, and (4) alternative underground development schemes

Decision-Making Risks Concerning the Construction of the Goiania Waste Repository

Energy Technology Data Exchange (ETDEWEB)

Paschoa, A.S. [Pontificia Univ. Catolica, Rio de Janeiro (Brazil); Rozental, J.J. [Ministry of Environment (Israel); Tranjan Filho, A. [Comissao Nacional de Energia Nuclear (CNEN) (Brazil)

2001-07-01

As it is well known, an accident with a teletherapy source made of {sup 137}CsCl with an initial activity of 59 TBq occurred in Goiania, in September of 1987. This paper will discuss the decision-making process, and the struggle that followed the decision to build the final repository for the remnants of the Goiania accident. The Goiania final repository was built as planned. The two subsurface structures under the grassy artificial hills hold the overall volume of the remnants of the Goiania accident. The near hill holds 5x10{sup 3} m3 of stabilized wastes without radioactivity, or with very low radioactivity. The far hill holds the remaining 6.5x10{sup 3} m{sup 3} of stabilized wastes with low and medium radioactivity. The central part of each subsurface hill has been shielded by wastes with less and less radioactivity. The overall fenced area occupies 1.85x10{sup 5} m{sup 2}. The external radiation levels are similar to the surrounding background, and much lower than those found in the Brazilian areas of high natural radioactivity. The site is permanently monitored by independent institutions, including Brazilian universities, and national and international organizations. As it was mentioned earlier, the final repository was build to last for at least 400 years. Although the initial decision to adopt a too conservative decontamination criterion in the case of the Goiania accident was bound to produce excessive amount of waste; such decision proved, retrospectively, not to be bad because the excess low radioactive waste produced was used as extra shielding material in final repository. The technical decision-maker should not abandon risk estimates, but should be aware that credibility is the main basis to achieve acceptability of a decision by the general public. Risk perception should be regarded as only a first step towards what may be called knowledge, or comprehension of risk estimates, but risk perception by the general public is still an open issue. The

Numerical modelling of fracture displacements due to thermal load from a KBS-3 repository

Energy Technology Data Exchange (ETDEWEB)

Hakami, Eva; Olofsson, Stig-Olof [Itasca Geomekanik AB, Stockholm (Sweden)

2002-01-01

The objective of the project has been to estimate the largest shear displacements that could be expected on a pre-existing fracture located in the repository area, due to the heat release from the deposited waste. Two-dimensional numerical analyses using the 'Universal Distinct Element Code' (UDEC) have been performed. The UDEC models represent a vertical cross section of a KBS-3 type repository with a large planar fracture intersecting a deposition hole at the repository centre. The extension, dip and mechanical properties of the fracture were changed in different models to evaluate the influence of these parameters on fracture shear displacements. The fracture was modelled using a Coulomb slip criterion with no cohesion and no dilation. The rock mass surrounding the fracture was modelled as a homogeneous, isotropic and elastic material, with a Young's modulus of 40 GPa. The initial heat release per unit repository area was assumed to be 8W/m{sup 2} (total power/total repository area). The shear displacements occur due to the thermal expansion of the rock surrounding the heat generating canisters. The rock mass is almost free to expand vertically, but is constrained horizontally, which gives a temperature-induced addition of shear stresses in the plane of the fracture. The shear movement of the fracture therefore follows the temperature development in the surrounding rock and the maximum shear displacement develops about 200 years after the waste deposition. Altogether, twenty cases are analysed. The maximum shear displacement, which occurs at the fracture centre, amounts to 0.2-13.8 cm depending on the fracture parameters. Among the analysed cases, the largest shear values, about 13 cm, was calculated for the cases with about 700 m long fractures with a shear stiffness of 0.005 GPa/m. Also, for large fractures with a higher shear stiffness of 5 GPa/m, but with a low friction angle (15 deg), the shear displacement reaches similar magnitudes, about

Information about activity, status and radiation conditions of Republic radioactive waste repository

International Nuclear Information System (INIS)

Saidumarov, P.

2000-01-01

All radioactive wastes in the Republic of Uzbekistan are stored in the Republic Radioactive Waste Repository in Parkent district of Tashkent region. In the facility there are 2 tanks for solid radioactive waste, each of 800 m 3 , one of them is full, second is in operation; 2 tanks for liquid radioactive waste each tank of 200 m 3 , both of them are empty; 6 storages, each of 3 m 3 all of them are empty; 3 storages for spent radioactive sources, one of them is full, 2 of them are in operation; 4 storages for high level radioactive waste, each storage of 3.5 m 3 , one of them is in operation, 3 are empty; one sealed storage containing 135 m 3 of concrete blocks with waste from electronic industry. According to conclusions of a few competent examinations RRWR does not cause damage to the environment. Geographic location and technical conditions of the repository are satisfactory. Low deposition of underground water (62 m) excludes penetration of radioisotopes. There were no radiation accidents during the repository operation

Design aspects of the alpha repository. II. Conceptual layouts of underground storage facilities

International Nuclear Information System (INIS)

Grams, W.H.

1975-01-01

Five conceptual repository layouts are presented: linear repository, 1 panel; bow tie repository, 2 panels; maltese cross repository, 4 panels; snowflake repository; 5 panels, and sash window repository, 8 panels. The layouts are compared with respect to excavation requirements, haulage distances, ventilation flow path designs, and safety features

Safety analysis of the VLJ repository

International Nuclear Information System (INIS)

Vieno, T.; Nordman, H.

1991-05-01

The VLJ repository is an underground disposal facility for the low and medium level waste generated at the Olkiluoto nuclear power plant. The repository is located within 1 km from TVO I and TVO II (2 x 710 MWe) BWR's on the Olkiluoto island at the west coast of Finland. It contains two rock silos excavated at the depth of 60...100 meters in the bedrock. Low level waste will be disposed of in a shotcreted rock silo. For bituminized medium level waste, a separate silo of reinforced concrete has been built inside the shotcreted rock silo. The post-closure safety analysis has been done for the Final Safety Analysis Report (FSAR) of the VLJ repository. In addition to the normal evolution scenario, several disturbed evolution and accident scenarios have been analysed. In the reference scenario, radio-nuclides are assumed to be released from the bituminized waste within 500 years, the concrete silo is assumed to gradually disintegrate and finally to collapse at 5 000 years, all concrete in the silo is assumed to be also chemically depleted within 6 000 years, and all the seals of the repository are assumed to deteriorate within 12 000 years. The ability of alone natural barriers to restrict the release of radionuclides into the biosphere has been evaluated by means of scenarios where the degradation of engineered barriers has been assumed to take place at a still faster rate. In one of the disturbed evolution scenarios it has been assumed that the concrete silo for medium level waste is severely impaired immediately after sealing of the repository. Effects of gas generation and consequences of human intrusion have been evaluated, too. The results of the safety analysis show that radiation doses of any significance are caused only if a well is bored in the vicinity of the repository or if the groundwater discharge spot is inhabited and used for cultivation. In the reference scenario the maximum expectation value of the individual dose rate is 0.3 mSv/a

Learning Object Repositories

Science.gov (United States)

Lehman, Rosemary

2007-01-01

This chapter looks at the development and nature of learning objects, meta-tagging standards and taxonomies, learning object repositories, learning object repository characteristics, and types of learning object repositories, with type examples. (Contains 1 table.)

Information base for waste repository design. Volume 5. Decommissioning of underground facilities. Technical report

International Nuclear Information System (INIS)

Giuffre, M.S.; Plum, R.L.; Koplik, C.M.; Talbot, R.

1979-03-01

This report is Volume 5 of a seven volume document on nuclear waste repository design issues. This report discusses the requirements for decommissioning a deep underground facility for the disposal of radioactive waste. The techniques for sealing the mined excavations are presented and an information base on potential backfill materials is provided. Possible requirements for monitoring the site are discussed. The performance requirements for backfill materials are outlined. The advantages and disadvantages of each sealing method are stated

Implementation of smoke-free legislation in Malaysia: are adolescents protected from respiratory health effects?

Science.gov (United States)

Zulkifli, Aziemah; Abidin, Najihah Zainol; Abidin, Emilia Zainal; Hashim, Zailina; Rahman, Anita Abd; Rasdi, Irniza; Syed Ismail, Sharifah Norkhadijah; Semple, Sean

2014-01-01

This study aimed to examine the relationship between respiratory health of Malaysian adolescents with secondhand smoke (SHS) exposure and smoke-free legislation (SFL) implementation. A total of 898 students from 21 schools across comprehensive- and partial-SFL states were recruited. SHS exposures and respiratory symptoms were assessed via questionnaire. Prenatal and postnatal SHS exposure information was obtained from parental-completed questionnaire. The prevalence of respiratory symptoms was: 11.9% ever wheeze, 5.6% current wheeze, 22.3% exercise-induced wheeze, 12.4% nocturnal cough, and 13.1% self-reported asthma. SHS exposure was most frequently reported in restaurants. Hierarchical logistic regression indicates living in a comprehensive-SFL state was not associated with a lower risk of reporting asthma symptoms. SHS exposure in public transport was linked to increased risk for wheeze (Adjusted Odds Ratio (AOR) 16.6; 95%confidence interval (CI), 2.69-101.7) and current wheezing (AOR 24.6; 95%CI, 3.53-171.8). Adolescents continue to be exposed to SHS in a range of public venues in both comprehensive- and partial-SFL states. Respiratory symptoms are common among those reporting SHS exposure on public transportation. Non-compliance with SFL appears to be frequent in many venues across Malaysia and enforcement should be given priority in order to reduce exposure.

Reduction of repository heat load using advanced fuel cycles

International Nuclear Information System (INIS)

Preston, Jeff; Miller, L.F.

2008-01-01

With the geologic repository at Yucca Mountain already nearing capacity full before opening, advanced fuel cycles that introduce reprocessing, fast reactors, and temporary storage sites have the potential to allow the repository to support the current reactor fleet and future expansion. An uncertainty analysis methodology that combines Monte Carlo distribution sampling, reactor physics data simulation, and neural network interpolation methods enable investigation into the factor reduction of heat capacity by using the hybrid fuel cycle. Using a Super PRISM fast reactor with a conversion ratio of 0.75, burn ups reach up to 200 MWd/t that decrease the plutonium inventory by about 5 metric tons every 12 years. Using the long burn up allows the footprint of 1 single core loading of FR fuel to have an integral decay heat of about 2.5x10 5 MW*yr over a 1500 year period that replaces the footprint of about 6 full core loadings of LWR fuel for the number of years required to fuel the FR, which have an integral decay heat of about.3 MW*yr for the same time integral. This results in an increase of a factor of 4 in repository support capacity from implementing a single fast reactor in an equilibrium cycle. (authors)

Repository Rodeo Redux

CERN Document Server

Anez, Melissa; Donohue, Tim; Fyson, Will; Simko, Tibor; Wilcox, David

2017-01-01

You’ve got more repository questions and we’ve got more answers! Last year’s Repository Rodeo panel was a huge success, so we’re taking the show on the road to Brisbane for OR2017. Join representatives from the DSpace, Eprints, Fedora, Hydra, and Islandora communities as we (briefly) explain what each of our repositories actually does. We'll also talk about the directions of our respective technical and community developments, and related to the conference theme of Open: Innovation Knowledge Repositories, offer brief observations about the latest, most promising and/or most surprising innovations in our space. This panel will be a great opportunity for newcomers to Open Repositories to get a crash course on the major repository options and meet representatives from each of their communities. After a brief presentation from each representative, we'll open the session up for questions from the audience.

NAGRA - Sites for geological repositories - Technical safety factors: Suggestions for stage 3

International Nuclear Information System (INIS)

2015-01-01

This comprehensive brochure published by the Swiss National Cooperative for the Disposal of Radioactive Waste (NAGRA) examines the six sites for repositories for nuclear wastes in Switzerland which have been proposed in Stage 1 of the program concerning nuclear waste repositories. Three of these sites are proposed for both highly radioactive wastes as well as for low and medium-active wastes, the other three for low and medium-active wastes only. The evaluation of the sites is discussed. The sites are to be further evaluated in Stage 2 of the program. The work to be done in the further stages involved in the selection of the final site (or sites) is described. Along with definition of the regions where deep repositories could possibly be built, suggestions for the placing of the facilities required on the surface are discussed. Geological requirements on the repositories and safety-relevant characteristics of the various site options are discussed. The results of the assessments made are presented in tabular form. Maps and geological cross-sections of all the suggested areas are included

Environmental issues of repository licensing: an evaluation of a hypothetical high-level radioactive waste repository

International Nuclear Information System (INIS)

Owen, J.L.; McGinnis, J.T.; Harper, C.M.; Battelle Columbus Labs., OH)

1982-01-01

This paper presents results of an environmental assessment conducted under the direction of the Office of Nuclear Waste Isolation as part of the National Waste Terminal Storage program. The study defined a range of potential environmental effects of constructing, operating, decommissioning, and long-term isolation of a nuclear waste repository. The analytical methodology used to determine potential environmental effects required definition of a hypothetical environmental setting and repository. Potentially applicable regulatory requirements were identified and were used as guidelines to evaluate permitting feasibility. The environmental effects of repository development were analyzed for the two major time periods of concern: short term (the period of construction, operation, and decommissioning) and long term (the isolation period after decommissioning). As a result of this analysis, major environmental uncertainties and issues were identified. 11 references, 5 figures

EEI/UWASTE oversight of the DOE Repository Program by the Repository Information Exchange Team

International Nuclear Information System (INIS)

Henkel, C.J.; Supko, E.M.; Schwartz, M.H.

1993-01-01

The Utility Nuclear Waste and Transportation Program of the Edison Electric Institute (EEI/UWASTE) has conducted reviews of the US DOE's repository program through its Repository Information Exchange Team (RIET or Team). Eight such reviews have been conducted since 1985 covering topics that include repository program management and control; repository schedule; repository budget; quality assurance; site characterization; repository licensing; environmental issues; and institutional and public information activities. The utility industry has used these repository program reviews as a forum for providing DOE's Office of Civilian Radioactive Waste Management (OCRWM) with comments on the direction of the repository program, advice for future actions regarding quality assurance activities and repository licensing, and suggestions for management and control of the Repository Program. The most significant recommendations made by the utility industry through the RIET are discussed along with any subsequent action by OCRWM in response to or subsequent to utility industry recommendations. The process used by the RIET to develop its recommendations to OCRWM regarding the repository program is also discussed

Socioeconomic impacts of repositories

International Nuclear Information System (INIS)

Thomas, J.K.; Hamm, R.R.; Murdock, S.H.

1983-01-01

Federal and state decision makers, community leaders, and residents must know how communities will be changed by the impacts of a high-level nuclear waste repository. This chapter identifies the factors affecting an assessment of socioeconomic impacts and the types of impacts (economic, demographic, fiscal, community service, and social) likely to occur as a result of repository development. Each of these types can be divided into standard (those which typically results from any large-scale development) and special impact categories (those which result from the fact that radioactive materials will be handled). 3 tables

Siting regions for deep geological repositories. Why just here?

International Nuclear Information System (INIS)

Rieser, A.

2009-09-01

This report helps to the popularization of the Nagra works accomplished for the management and disposal of the radioactive wastes in Switzerland. The programme for management and disposal of the radioactive wastes are extensively determined by regulations. Protection of mankind and environment is the primary objective. The basic storage process is considered as having been solved. The question addressed in the report is where the facility has to be built; the site selection procedure includes five steps: 1) according to their type the wastes have to be allocated to two different repositories: for low- and intermediate-level wastes (L/ILW), and for high-level and alpha-toxic wastes (HLW); 2) the safety concept for both repositories and the requirements on the geology have to be determined; 3) large suitable geological-tectonic zones must be found where repositories could be built; 4) in these geological zones a suitable host rock has to be identified; 5) the most important spatial geological conditions of the host rock (minimum depth with respect to surface erosion, maximum depth in terms of engineering requirements, lateral extent) have to be identified. Based on these criteria, three suitable siting regions for a HLW repository were found in the North of Switzerland. The preferred host rock is Opalinus clay because of its very low permeability; it is therefore an excellent barrier against nuclide transport. In the three proposed siting regions, Opalinus clay is present in sufficient volumes at a suitable depth. For a L/ILW repository six different possible siting regions were identified, five in Northern Switzerland and one in Central Switzerland. In the three siting regions found for a possible HLW repository, it would also be possible to built a combined repository for both HLW and L/ILW wastes

How many geologic repositories will be needed

International Nuclear Information System (INIS)

Evans, T.J.; Halstead, R.J.

1987-01-01

DOE's postponement of site-specific work on the second repository program had rekindled debate over the number of geologic repositories needed for disposal of high level radioactive waste. The multiple repository approach grew out of the March, 1979 IRG report, which recommended co-disposal of civilian and defense HLW in a system of regional repositories. The multiple repository approach was adopted by DOE, and incorporated in the Nuclear Waste Policy Act passed by Congress in December, 1982. Since the late 1970's, the slower than anticipated growth of the nuclear power industry has substantially reduced earlier estimates of the amount of civilian spent fuel which will require geologic disposal. Reactors currently in operation (78.5 GWe) and reactors in the construction pipeline (28 GWe) are expected to discharge about 103,200 MTU of spent fuel by the year 2036, assuming no increase in fuel burnup rate. By the year 2020, defense high level radioactive wastes equivalent to as much as 27,000 MTU could require geologic disposal. Small amounts of high level waste from other sources will also require geologic disposal. Total disposal requirements appear to be less than 140,000 MTU. The five sites nominated for the first repository, as well as hypothetical sites in granite, the host rock under primary consideration for the second repository, all appear capable of accommodating up to 140,000 MTU

Report of the Task Force on the MRS/repository interface

International Nuclear Information System (INIS)

1986-02-01

In April 1985, the DOE established an MRS/repository interface task force to analyze the cost and schedule impacts of implementing an integrated waste-management system on the repository and the MRS facility. The intended end products of the study were preliminary conceptual designs of repository and MRS facilities, cost and schedule estimates, and other analyses that would advance the definition of the role and function of the MRS facility, support the preparation of the MRS proposal to Congress, and serve as a source of baseline data for further studies of the integrated waste-management system. From the general overall objectives, specific equations were developed to guide the task-force effort, e.g., What would the surface facilities at the repository look like and cost with an MRS facility in the system. In order to address these questions, five scenarios were defined and analyzed. (A number of other scenarios and associated issues were also explored to a lesser extent.) These five scenarios are as follows. Scenario 1: reference case (no MRS facility). Scenario 2: MRS facility with overpacking of both spent fuel and defense high-level waste. Scenario 3: MRS facility with overpacking of spent fuel only (defense-waste overpacking at the repository). Scenario 4: MRS facility with all overpacking at the repository. Scenario 5: MRS facility with all overpacking at the repository and western fuel shipped directly to the repository. It is apparent that, with such a limited set of scenarios, determination of the optimum system was not an objective of this study. Furthermore, time constraints limited the level of detail to which facility designs could be developed; this level can best be characterized as ''preconceptual.'' These limitations are, however, compatible with the intent of the study, which was to make general comparisons between the several systems on an internally consistent basis

Knowledge, attitude and perception of second-hand smoke and factors promoting smoking in Malaysian adolescents.

Science.gov (United States)

Abidin, N Zainol; Zulkifli, A; Abidin, E Zainal; Rasdi, I; Ismail, S N Syed; Rahman, A Abd; Hashim, Z; Semple, S

2014-07-01

To identify the relationship between knowledge, attitude and perception regarding environmental tobacco smoke (ETS) and smoking among Malaysian adolescents living in states with complete or partial smoke-free legislation (SFL). A total of 898 respondents aged 13-14 years were randomly selected from 21 secondary schools. The Malay version of the modified Global Youth Tobacco Survey questionnaire was used. Hierarchical logistic regression was performed in examining predictors of smoking attempt among adolescents. Participants exposed to ETS >5 h/day were more likely to have smoked compared to those exposed to ETS smoking attempts (OR 1.95, 95%CI 1.10-3.43) compared to living in a state with complete SFL. Negative attitudes and perceptions towards smoking and ETS exposure were linked to lower smoking attempts in states with complete SFL. Adolescents with limited ETS exposure who lived in a state with complete SFL were less likely to attempt smoking compared to those exposed more regularly to ETS and living in a state with partial SFL. Preventing adolescents from becoming smokers is the key to reducing national prevalence rates in smoking. There is a need to implement comprehensive smoke-free legislation nationally across Malaysia.

Analysis of computational vulnerabilities in digital repositories

Directory of Open Access Journals (Sweden)

Valdete Fernandes Belarmino

2015-04-01

Full Text Available Objective. Demonstrates the results of research that aimed to analyze the computational vulnerabilities of digital directories in public Universities. Argues the relevance of information in contemporary societies like an invaluable resource, emphasizing scientific information as an essential element to constitute scientific progress. Characterizes the emergence of Digital Repositories and highlights its use in academic environment to preserve, promote, disseminate and encourage the scientific production. Describes the main software for the construction of digital repositories. Method. The investigation identified and analyzed the vulnerabilities that are exposed the digital repositories using Penetration Testing running. Discriminating the levels of risk and the types of vulnerabilities. Results. From a sample of 30 repositories, we could examine 20, identified that: 5% of the repositories have critical vulnerabilities, 85% high, 25% medium and 100% lowers. Conclusions. Which demonstrates the necessity to adapt actions for these environments that promote informational security to minimizing the incidence of external and / or internal systems attacks.Abstract Grey Text – use bold for subheadings when needed.

Developing design premises for a KBS-3V repository based on results from the safety assessment - 16027

International Nuclear Information System (INIS)

Andersson, Johan; Hedin, Allan

2009-01-01

As a part of the planned license application for a final repository for spent nuclear fuel the Swedish Nuclear Fuel and Waste Management Co. (SKB), has developed design premises from a long term safety aspect of a KBS-3V repository for spent nuclear fuel. The purpose is to provide requirements from a long term safety aspect, to form the basis for the development of the reference design of the repository and to justify that design. Design premises typically concern specification on what mechanical loads the barriers must withstand, restrictions on the composition of barrier materials or acceptance criteria for the various underground excavations. These design constraints, if all fulfilled by the actual design, should form a good basis for demonstrating repository safety. The justification for these design premises is derived from SKB's most recent safety assessment SR-Can complemented by a few additional analyses. Some of the design premises may be modified in future stages of SKB's program, as a result of analyses based on more detailed site data and a more developed understanding of processes of importance for long-term safety. (authors)

Towards Interoperable Preservation Repositories: TIPR

Directory of Open Access Journals (Sweden)

Priscilla Caplan

2010-07-01

Full Text Available Towards Interoperable Preservation Repositories (TIPR is a project funded by the Institute of Museum and Library Services to create and test a Repository eXchange Package (RXP. The package will make it possible to transfer complex digital objects between dissimilar preservation repositories.  For reasons of redundancy, succession planning and software migration, repositories must be able to exchange copies of archival information packages with each other. Every different repository application, however, describes and structures its archival packages differently. Therefore each system produces dissemination packages that are rarely understandable or usable as submission packages by other repositories. The RXP is an answer to that mismatch. Other solutions for transferring packages between repositories focus either on transfers between repositories of the same type, such as DSpace-to-DSpace transfers, or on processes that rely on central translation services.  Rather than build translators between many dissimilar repository types, the TIPR project has defined a standards-based package of metadata files that can act as an intermediary information package, the RXP, a lingua franca all repositories can read and write.

Repository simulation model: Final report

International Nuclear Information System (INIS)

1988-03-01

This report documents the application of computer simulation for the design analysis of the nuclear waste repository's waste handling and packaging operations. The Salt Repository Simulation Model was used to evaluate design alternatives during the conceptual design phase of the Salt Repository Project. Code development and verification was performed by the Office of Nuclear Waste Isolation (ONWL). The focus of this report is to relate the experience gained during the development and application of the Salt Repository Simulation Model to future repository design phases. Design of the repository's waste handling and packaging systems will require sophisticated analysis tools to evaluate complex operational and logistical design alternatives. Selection of these design alternatives in the Advanced Conceptual Design (ACD) and License Application Design (LAD) phases must be supported by analysis to demonstrate that the repository design will cost effectively meet DOE's mandated emplacement schedule and that uncertainties in the performance of the repository's systems have been objectively evaluated. Computer simulation of repository operations will provide future repository designers with data and insights that no other analytical form of analysis can provide. 6 refs., 10 figs

Compilation of data for radionuclide transport analysis

International Nuclear Information System (INIS)

2001-11-01

This report is one of the supporting documents to the updated safety assessment (project SAFE) of the Swedish repository for low and intermediate level waste, SFR 1. A number of calculation cases for quantitative analysis of radionuclide release and dose to man are defined based on the expected evolution of the repository, geosphere and biosphere in the Base Scenario and other scenarios selected. The data required by the selected near field, geosphere and biosphere models are given and the values selected for the calculations are compiled in tables. The main sources for the selected values of the migration parameters in the repository and geosphere models are the safety assessment of a deep repository for spent fuel, SR 97, and the preliminary safety assessment of a repository for long-lived, low- and intermediate level waste, SFL 3-5. For the biosphere models, both site-specific data and generic values of the parameters are selected. The applicability of the selected parameter values is discussed and the uncertainty is qualitatively addressed for data to the repository and geosphere migration models. Parameter values selected for these models are in general pessimistic in order not to underestimate the radionuclide release rates. It is judged that this approach combined with the selected calculation cases will illustrate the effects of uncertainties in processes and events that affects the evolution of the system as well as in quantitative data that describes this. The biosphere model allows for probabilistic calculations and the uncertainty in input data are quantified by giving minimum, maximum and mean values as well as the type of probability distribution function

Compilation of data for radionuclide transport analysis

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-11-01

This report is one of the supporting documents to the updated safety assessment (project SAFE) of the Swedish repository for low and intermediate level waste, SFR 1. A number of calculation cases for quantitative analysis of radionuclide release and dose to man are defined based on the expected evolution of the repository, geosphere and biosphere in the Base Scenario and other scenarios selected. The data required by the selected near field, geosphere and biosphere models are given and the values selected for the calculations are compiled in tables. The main sources for the selected values of the migration parameters in the repository and geosphere models are the safety assessment of a deep repository for spent fuel, SR 97, and the preliminary safety assessment of a repository for long-lived, low- and intermediate level waste, SFL 3-5. For the biosphere models, both site-specific data and generic values of the parameters are selected. The applicability of the selected parameter values is discussed and the uncertainty is qualitatively addressed for data to the repository and geosphere migration models. Parameter values selected for these models are in general pessimistic in order not to underestimate the radionuclide release rates. It is judged that this approach combined with the selected calculation cases will illustrate the effects of uncertainties in processes and events that affects the evolution of the system as well as in quantitative data that describes this. The biosphere model allows for probabilistic calculations and the uncertainty in input data are quantified by giving minimum, maximum and mean values as well as the type of probability distribution function.

The Vital Role of Free Access in Supporting Digital Repositories

African Journals Online (AJOL)

pc

2018-03-05

Mar 5, 2018 ... the scientific research forward, stressing that the free access to the scientific .... links in the digital repositories for the scientific journals publishers not to mention .... psychology, physics and encryption. Moreover, repositories.

Flammable gas production in Land 2 and Land 3/4 radioactive waste repositories

International Nuclear Information System (INIS)

1988-02-01

Geological, radiolytic and microbiological sources of gas are considered in relation to Land 2 and Land 3/4 type radioactive waste repositories. Geological sources are potentially the most troublesome and it is concluded that site investigation work should be designed to detect gas trap structures, reservoir lithologies or source rocks. Known source and reservoir lithologies should not be considered as suitable for the siting of waste repositories. Radiolytic and microbiological sources will depend on waste characteristics. A detailed review of the literature on radiolytic gas generation is presented and conclusions from this work indicate that water in waste and matrix should be kept to a minimum. Similarly, the level of radioactivity stored in each waste container should be kept to the minimum compatible with the storage design. Microbiological gas sources will be reduced by maintaining the cellulose content of the waste at a minimum. It is suggested that the removal of organics from the waste stream would be beneficial in terms of potential gas production. (author)

Combination of 2D/3D ligand-based similarity search in rapid virtual screening from multimillion compound repositories. Selection and biological evaluation of potential PDE4 and PDE5 inhibitors.

Science.gov (United States)

Dobi, Krisztina; Hajdú, István; Flachner, Beáta; Fabó, Gabriella; Szaszkó, Mária; Bognár, Melinda; Magyar, Csaba; Simon, István; Szisz, Dániel; Lőrincz, Zsolt; Cseh, Sándor; Dormán, György

2014-05-28

Rapid in silico selection of target focused libraries from commercial repositories is an attractive and cost effective approach. If structures of active compounds are available rapid 2D similarity search can be performed on multimillion compound databases but the generated library requires further focusing by various 2D/3D chemoinformatics tools. We report here a combination of the 2D approach with a ligand-based 3D method (Screen3D) which applies flexible matching to align reference and target compounds in a dynamic manner and thus to assess their structural and conformational similarity. In the first case study we compared the 2D and 3D similarity scores on an existing dataset derived from the biological evaluation of a PDE5 focused library. Based on the obtained similarity metrices a fusion score was proposed. The fusion score was applied to refine the 2D similarity search in a second case study where we aimed at selecting and evaluating a PDE4B focused library. The application of this fused 2D/3D similarity measure led to an increase of the hit rate from 8.5% (1st round, 47% inhibition at 10 µM) to 28.5% (2nd round at 50% inhibition at 10 µM) and the best two hits had 53 nM inhibitory activities.

High level radioactive waste repositories. Task 3. Review of underground handling and emplacement. 1. Executive summary

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

A review is presented of proposals for transport, handling and emplacement of high-level radioactive waste in an underground repository appropriate to the U.K. context, with particular reference to waste block size and configuration; self-shielded or partially-shielded block; stages of disposal; transport by road/rail to repository site; handling techniques within repository; emplacement in vertical holes or horizontal tunnels; repository access by adit, incline or shaft; conventional and radiological safety; costs; and major areas of uncertainty requiring research or development.

Repositories; Repositorios

Energy Technology Data Exchange (ETDEWEB)

Freire, Carolina Braccini; Tello, Cledola Cassia Oliveira de [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mails: cbf@cdtn.br; tellocc@cdtn.br

2007-11-15

The use of the nuclear energy is increasing in all areas. Then the radioactive waste management is in continuous development to comply the national and international established requirements. The final objective is to assure that it will not have any contamination of the public or the environmental, and that the exposition doses will be lower than the radiological protection limits. The multi barrier concept for the repository is internationally recognized. Among the repository types, the most used are: near surface, geological formations and of deposition in rock cavities. This article explains the concept and the types of repository and gives some examples of them. (author)

Safety Assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto

International Nuclear Information System (INIS)

Smith, P.; Neall, F.; Snellman, M.; Pastina, B.; Hjerpe, T.; Nordman, H.; Johnson, L.

2007-12-01

The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. KBS-3H and KBS-3V are the two design alternatives of the KBS-3 spent fuel disposal method. Posiva and SKB have conducted a joint research, demonstration and development (RD and D) programme in 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to the reference alternative KBS-3V. The overall objectives of the present phase covering the period 2004-2007 have been to demonstrate that the horizontal deposition alternative is technically feasible and to demonstrate that it fulfils the same long-term safety requirements as KBS-3V. The safety studies conducted as part of this programme include a safety assessment of a preliminary design of a KBS-3H repository for spent nuclear fuel located about 400 m underground at the Olkiluoto site, which is the proposed site for a spent fuel repository in Finland. This safety assessment is summarised in the present report. The scientific basis of the safety assessment includes around 30 years of scientific R and D and technical development in the Swedish and Finnish KBS-3V programmes. Much of this scientific basis is directly applicable to KBS-3H. This has allowed the KBS-3H safety studies to focus on those issues that are unique to this design alternative, identified in a systematic difference analysis of KBS-3H and KBS-3V. This difference analysis has shown that the key differences in the evolution and performance of KBS-3H and KBS-3V relate mainly to the engineered barrier system and to the impact of local variations in the rate of groundwater inflow on buffer saturation along the KBS-3H deposition drifts. No features or processes specific to KBS-3H have been identified that could lead to a loss or substantial degradation of the safety functions of the engineered barriers over a million year time frame. Radionuclide release from the repository near field in the event of

CCDC 1433704: Experimental Crystal Structure Determination : 5-(3-(4-chlorophenyl)-3-oxo-1-phenylpropyl)-5-methylfuran-2(5H)-one

KAUST Repository

Guo, Hao; Xing, Fen; Du, Guang-Fen; Huang, Kuo-Wei; Dai, Bin; He, Lin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

An innovative 3-D numerical modelling procedure for simulating repository-scale excavations in rock - SAFETI

Energy Technology Data Exchange (ETDEWEB)

Young, R. P.; Collins, D.; Hazzard, J.; Heath, A. [Department of Earth Sciences, Liverpool University, 4 Brownlow street, UK-0 L69 3GP Liverpool (United Kingdom); Pettitt, W.; Baker, C. [Applied Seismology Consultants LTD, 10 Belmont, Shropshire, UK-S41 ITE Shrewsbury (United Kingdom); Billaux, D.; Cundall, P.; Potyondy, D.; Dedecker, F. [Itasca Consultants S.A., Centre Scientifique A. Moiroux, 64, chemin des Mouilles, F69130 Ecully (France); Svemar, C. [Svensk Karnbranslemantering AB, SKB, Aspo Hard Rock Laboratory, PL 300, S-57295 Figeholm (Sweden); Lebon, P. [ANDRA, Parc de la Croix Blanche, 7, rue Jean Monnet, F-92298 Chatenay-Malabry (France)

2004-07-01

This paper presents current results from work performed within the European Commission project SAFETI. The main objective of SAFETI is to develop and test an innovative 3D numerical modelling procedure that will enable the 3-D simulation of nuclear waste repositories in rock. The modelling code is called AC/DC (Adaptive Continuum/ Dis-Continuum) and is partially based on Itasca Consulting Group's Particle Flow Code (PFC). Results are presented from the laboratory validation study where algorithms and procedures have been developed and tested to allow accurate 'Models for Rock' to be produced. Preliminary results are also presented on the use of AC/DC with parallel processors and adaptive logic. During the final year of the project a detailed model of the Prototype Repository Experiment at SKB's Hard Rock Laboratory will be produced using up to 128 processors on the parallel super computing facility at Liverpool University. (authors)

Repository-analog experiments of nuclear waste leaching and migration

International Nuclear Information System (INIS)

Seitz, M.G.

1982-01-01

The potential for radionuclide migration from a breached nuclear-waste repository depends on the leaching and subsequent interaction of the leached radionuclides with materials in the groundwater flow path. An attempt is made to consider all interactions using experiments that integrate repository materials. Results of a repository-analog experiment using borosilicate glass, fissured granite, and flowing water suggest: (1) plutonium was immobile possibly because of its low solubility; (2) caesium migrated down slowly because of sorption; and (3) neptunium remained oxidized even in water of low oxidation potential. By summing the effects of all interactions, not just sorption, the repository-analog experiment produced radionuclide migration that could be expected from a breached repository. (author)

Logistics characterization for regional spent fuel repositories concept

International Nuclear Information System (INIS)

Joy, D.S.; Hudson, B.J.; Anthony, M.W.

1980-08-01

This report summarizes a study of logistics considerations for a four-region repository system for spent fuel disposal. The logistics considerations include: (1) yearly receipt and emplacement; (2) inventory; (3) away-from-reactor (AFR) storage; (4) nuclear capacity growth effects; (5) entire lifetime of reactors served by repository operations; (6) proportions of pressurized-water-reactor (PWR)/boiling-water-reactor (BWR) fuel; (7) proportions of rail and truck shipments; (8) shipping cask fleet requirements; (9) number of annual shipments; (10) mode (rail/truck) and cost of shipment; and (11) initial year for shipment to maintain full core reserve. The nation was divided into Northeast, North Central, Southern, and Western regions for evaluation purposes. Repository logistics were analyzed in each region based on three different capacity projections. For the Southern region, results for seven salt dome sites are presented. The Western region results cover four potential sites. The North Central and Northeastern regions results are not presented on a site specific basis. Conclusions are drawn based on the results. The methodology assumptions and references used in the logistics analysis are described for the convenience of the reader

Stream-simulation experiments for waste-repository investigations

International Nuclear Information System (INIS)

Seitz, M.G.

1980-01-01

The potential for radionuclide migration by groundwater flow from a breached-water repository depends on the leaching process and on chemical changes that might occur as the radionuclide moves away from the repository. Therefore, migration involves the interactions of leached species with (1) the waste and canister, (2) the engineered barrier, and (3) the geologic materials surrounding the repository. Rather than attempt to synthesize each species and study it individually, another approach is to integrate all species and interactions using stream-simulation experiments. Interactions identified in these studies can then be investigated in detail in simpler experiments

Final repository for spent nuclear fuel in granite - the KBS-3V concept in Sweden and Finland

International Nuclear Information System (INIS)

Pettersson, Stig; Loennerberg, Bengt

2008-01-01

Both Sweden and Finland has advanced plans for design, construction and operation of the final repositories for direct disposal of spent nuclear fuel. Both countries have the same type of host rock - granite. They are also investigating alternative concept for disposal, vertical or horizontal disposal of the canisters with encapsulated spent nuclear fuel, normally called KBS-3V or the KBS-3H disposal concept. The development of the KBS-3V concept started around 1980 and is the reference method for both SKB in Sweden and Posiva in Finland. However, extensive development work is ongoing since 2001 with KBS-3H in order to bring that concept to the same maturity as KBS-3V. This presentation deals with the design and operation of the KBS-3V based on the work done within Sweden and SKB but the development is Finland is identical and it is a close cooperation between SKB in Sweden and Posiva in Finland. In Sweden, the site investigation for location of the repository has been concentrated on two sites, in the Oskarshamn area, about 350 km south of Stockholm, and the Forsmark area, about 180 km north of Stockholm. For information it can be mentioned that Finland plans to locate their repository in the vicinity of the Olkiluoto nuclear power plant site, about 300 km north of Helsinki. The site investigation is completed and the selection of site is scheduled to mid 2009 and sending in the application for location and construction of the repository is scheduled to end 2009. After receiving all necessary permits, construction time and commissioning will take about 7 to 8 years and operation is expected to start about 2020. The KBS-3 system is based on a multi barrier concept and the work with compiling the design requirements for the underground part of the deep repository has been ongoing for some time within the SKB organisation. Today the design requirements for the underground part are documented in a big number of reports that has been produced by specialists and working

NAGRA - Sites for geological repositories - Geological surveys for stage 3

International Nuclear Information System (INIS)

2014-01-01

This brochure published by the Swiss National Cooperative for the Disposal of Radioactive Waste (NAGRA) examines the aims involved in the selection of sites for deep geological repositories for nuclear wastes in Switzerland. Various methods involved in their implementation are described. These include 3D-seismology, deep probe drillings, shallow drillings as well as field studies, gravimetric measurements and the study of the electrical properties of the ground and rock involved. These factors are discussed in detail. Maps are presented of the locations that are to be surveyed and details of the selected perimeters are shown. Also, the layout of a sample drilling site is presented. A timescale for the various surveys and work to be done is presented

Impact of retrievability of repository design

International Nuclear Information System (INIS)

Heijdra, J.J.; Gaag, J. v.d.; Prij, J.

1995-01-01

In this paper the impact of the retrievability on the design of the repository will be handled. Retrievability of radioactive waste from a repository in geological formations has received increasing attention during recent years. It is obvious that this retrievability will have consequences in terms of mining engineering, safety and cost. The purpose of the present study is to evaluate cost consequences by comparing two extreme options for retrievable storage. (author). 6 refs., 3 figs

Project JADE. Long-term function and safety. Comparison of repository systems

International Nuclear Information System (INIS)

Birgersson, Lars; Pers, K.; Wiborgh, M.

2001-12-01

A comparison of the KBS-3 V(ertical deposition), KBS-3 H(orizontal deposition) and MLH repository systems with regard to the long-term repository performance and the radionuclide migration is presented in the report. Several differences between the repository systems have been identified. The differences are mainly related to the: distance between canister and backfilled tunnels, excavated rock volumes, deposition hole direction. The overall conclusion is that the differences are in general quite small with regard to the repository function and safety. None of the differences are of such importance for the long-term repository performance and radionuclide migration that they discriminate any of the repository systems. The differences between the two KBS-3 systems are small. Based on this study, there is no reason to change from the reference system KBS-3 V to KBS-3 H. MLH has the potential to be a very robust system, especially in a long-term perspective. However, the MLH system will require extensive research, development, and analysis before it will be as confident as the reference repository system, KBS-3 V. Although the MLH and KBS-3 H systems are in some ways favourable compared to the reference system KBS-3 V, the overall conclusion is that the KBS-3 V system is still a very attractive system. A major advantage with KBS-3 V is that it is by far the most investigated and developed system. The JADE-project was initiated in 1996, and the main part of the study was carried out during 1997 and 1998. The JADE study is consequently based on presumptions that were valid a few years ago. Some of these presumptions have been modified since then. The new presumptions are however not judged to change the overall conclusions

Managing and Evaluating Digital Repositories

Science.gov (United States)

Zuccala, Alesia; Oppenheim, Charles; Dhiensa, Rajveen

2008-01-01

Introduction: We examine the role of the digital repository manager, discuss the future of repository management and evaluation and suggest that library and information science schools develop new repository management curricula. Method: Face-to-face interviews were carried out with managers of five different types of repositories and a Web-based…

Repository simulation tests

International Nuclear Information System (INIS)

Wicks, G.G.; Bibler, N.E.; Jantzen, C.M.; Plodinec, M.J.

1984-01-01

The repository simulation experiments described in this paper are designed to assess the performance of SRP waste glass under the most realistic repository conditions that can be obtained in the laboratory. These tests simulate the repository environment as closely as possible and introduce systematically the variability of the geology, groundwater chemistry, and waste package components during the leaching of the waste glass. The tests evaluate waste form performance under site-specific conditions, which differ for each of the geologic repositories under consideration. Data from these experiments will aid in the development of a realistic source term that can describe the release of radionuclides from SRP waste glass as a component of proposed waste packages. Hence, this information can be useful to optimize waste package design for SRP waste glass and to provide data for predicting long-term performance and subsequent conformance to regulations. The repository simulation tests also help to bridge the gap in interpreting results derived from tests performed under the control of the laboratory to the uncertainity and variability of field tests. In these experiments, site-specific repository components and conditions are emphasized and only the site specific materials contact the waste forms. An important feature of these tests is that both actual and simulated waste glasses are tested identically. 7 figures, 2 tables

The repository ecology an approach to understanding repository and service interactions

CERN Document Server

CERN. Geneva; Hagemann, Melissa

2007-01-01

An increasing number of university institutions and other organisations are deciding to deploy repositories and a growing number of formal and informal distributed services are supporting or capitalising on the information these repositories provide. Despite reasonably well understood technical architectures, early majority adopters may struggle to articulate their place within the actualities of a wider information environment. The idea of a repository ecology provides developers and administrators with a useful way of articulating and analysing their place in the information environment, and the technical and organisational interactions they have, or are developing, with other parts of such an environment. This presentation will provide an overview of the concept of a repository ecology and examine some examples from the domains of scholarly communications and elearning.

CCDC 838941: Experimental Crystal Structure Determination : 3,3,3',3'-Tetramethyl-5,5'-dinitro-2,2',3,3'-tetrahydro-1,1'-spirobi[indene]-6,6'-diol dichloromethane solvate

KAUST Repository

Ma, Xiaohua; Swaidan, R.; Belmabkhout, Youssef; Zhu, Yihan; Litwiller, E.; Jouiad, M.; Pinnau, I.; Han, Yu

2013-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Coupling fuel cycles with repositories: how repository institutional choices may impact fuel cycle design

International Nuclear Information System (INIS)

Forsberg, C.; Miller, W.F.

2013-01-01

The historical repository siting strategy in the United States has been a top-down approach driven by federal government decision making but it has been a failure. This policy has led to dispatching fuel cycle facilities in different states. The U.S. government is now considering an alternative repository siting strategy based on voluntary agreements with state governments. If that occurs, state governments become key decision makers. They have different priorities. Those priorities may change the characteristics of the repository and the fuel cycle. State government priorities, when considering hosting a repository, are safety, financial incentives and jobs. It follows that states will demand that a repository be the center of the back end of the fuel cycle as a condition of hosting it. For example, states will push for collocation of transportation services, safeguards training, and navy/private SNF (Spent Nuclear Fuel) inspection at the repository site. Such activities would more than double local employment relative to what was planned for the Yucca Mountain-type repository. States may demand (1) the right to take future title of the SNF so if recycle became economic the reprocessing plant would be built at the repository site and (2) the right of a certain fraction of the repository capacity for foreign SNF. That would open the future option of leasing of fuel to foreign utilities with disposal of the SNF in the repository but with the state-government condition that the front-end fuel-cycle enrichment and fuel fabrication facilities be located in that state

Definition of the waste package environment for a repository located in salt

International Nuclear Information System (INIS)

Clark, D.E.; Bradley, D.J.

1983-01-01

The expected environmental conditions for emplaced waste packages in a salt repository are simulated in the materials testing program to evaluate performance. Synthetic brines, based on the analyses of actual brines (both intrusion and inclusion), are used for corrosion and leach testing. Elevated temperatures (to 150 0 C) and radiation fields of up to 10 3 rad/h are employed as conservative conditions to bracket expected performance and provide data for worst case scenarios. Obtaining a precise definition of the waste package environment in a salt repository and its change with time is closely tied to detailed site characterization of the candidate salt repository horizon. It is expected that field testing can augment some of the materials testing currently under way and can provide increased confidence in the predicted site-specific near-field conditions. 17 references, 5 figures, 1 table

[The final situation in the Turkey "Stent for Life" project].

Science.gov (United States)

Ertaş, Gökhan; Kozan, Omer; Değertekin, Muzaffer; Kervan, Umit; Aksoy, Mehmet; Koç, Orhan; Göktekin, Omer

2012-09-01

The Stent for Life (SFL) project's main mission is to increase the use of primary percutaneous coronary intervention (PCI) in more than 70% of all acute ST segment elevation myocardial infarction (STEMI) patients. Previous to the SFL project, thrombolysis was the dominant reperfusion strategy since a low percentage of acute STEMI patients had access to primary PCI in our country. In this study, we present the main barriers of access to primary PCI in the centers that were involved with the SFL project. Patients with acute STEMI admitted to the centers that were involved in the SFL project between 2009 and 2011 were included in the analysis. Since the inception of the SFL project, the primary PCI rate has reached over 90% in SFL pilot cities. In the last 5 years, the number of ambulances and emergency stations has increased. Since the collaboration with 112 Emergency Service, a great majority of cases were reached via the emergency medical system. The mean door-to-balloon time for the pilot cities was 54.72±43.66 minutes. After three years of the SFL project, primary PCI has emerged as the preferred reperfusion strategy for patients with STEMI in pilot cities.

Development of the design and reliability analysis of a seabed repository system

International Nuclear Information System (INIS)

1987-06-01

This study examines the seabed repository scheme proposed in 1979 for the long term disposal of heat generating radio-active waste and develops it to a standard sufficient to compare its reliability with the drilled emplacement and penetrator schemes. The reinforced concrete repositories contain 324 waste canisters and weigh 982 tonnes fully loaded in water. The repositories are transported up to 6000 km to the disposal area by a special purpose ship and lowered 5.5 km to the seabed on six braided nylon ropes by traction winches. Reliability of the seabed repository system, measured in terms of accidents per year involving loss of one or more canisters, was comparable with the other systems. (author)

Comparison of different SFL design alternatives

International Nuclear Information System (INIS)

Ivars Neretnieks, Ivars; Moreno, Luis

2013-04-01

Four different design options for a repository for long-lived nuclear waste from the future dismantling of the nuclear power plants have been compared. The time scales considered range up to 100,000 years. The repository is to be located at about 500 m depth in granitic rock. The vault can be a tunnel about 200 m long and on the order of 15 X 15 meters, in which the waste is surrounded by either a hydraulic cage, a concrete buffer or a bentonite buffer about 2 m thick. A fourth option is to make a silo, called Supersilo, about as high as wide, surrounded by both concrete and bentonite. In order to compare potential release rates of radionuclides from the waste to the seeping water in the rock a number of simple models have been devised. Some of these models allow the water flow rates through vaults to be assessed under various conditions and configurations. Other models are used to calculate the uptake by molecular diffusion to the water in the rock that seeps past the vaults. Moreover other models are used to calculate the rate of transport of nuclides by diffusion and flow through the buffer and waste. The decay of the nuclides during their passage from the waste to the flowing water through and past the vaults is accounted for. Many nuclides of interest decay considerably in the buffer. The mathematical form of the models is made so simple that essentially hand calculations can be used to explore the strength of different barriers and design options. The simple models are validated against more complex coupled models accounting for simultaneously competing processes. The more complex models are solved by numerical methods. The toolbox of simple models is used to calculate the strength of the barriers in the different design options under various conditions. Examples of activity releases of three nuclides with different sorption characteristics and half-lives are presented. It is found that a hydraulic cage is not a good option as it promotes the release of

Comparison of different SFL design alternatives

Energy Technology Data Exchange (ETDEWEB)

Ivars Neretnieks, Ivars [Chemima AB, Taeby (Sweden); Moreno, Luis [LMQuimica, Vaarby (Sweden)

2013-04-15

Four different design options for a repository for long-lived nuclear waste from the future dismantling of the nuclear power plants have been compared. The time scales considered range up to 100,000 years. The repository is to be located at about 500 m depth in granitic rock. The vault can be a tunnel about 200 m long and on the order of 15 X 15 meters, in which the waste is surrounded by either a hydraulic cage, a concrete buffer or a bentonite buffer about 2 m thick. A fourth option is to make a silo, called Supersilo, about as high as wide, surrounded by both concrete and bentonite. In order to compare potential release rates of radionuclides from the waste to the seeping water in the rock a number of simple models have been devised. Some of these models allow the water flow rates through vaults to be assessed under various conditions and configurations. Other models are used to calculate the uptake by molecular diffusion to the water in the rock that seeps past the vaults. Moreover other models are used to calculate the rate of transport of nuclides by diffusion and flow through the buffer and waste. The decay of the nuclides during their passage from the waste to the flowing water through and past the vaults is accounted for. Many nuclides of interest decay considerably in the buffer. The mathematical form of the models is made so simple that essentially hand calculations can be used to explore the strength of different barriers and design options. The simple models are validated against more complex coupled models accounting for simultaneously competing processes. The more complex models are solved by numerical methods. The toolbox of simple models is used to calculate the strength of the barriers in the different design options under various conditions. Examples of activity releases of three nuclides with different sorption characteristics and half-lives are presented. It is found that a hydraulic cage is not a good option as it promotes the release of

Finite element code FENIA verification and application for 3D modelling of thermal state of radioactive waste deep geological repository

Science.gov (United States)

Butov, R. A.; Drobyshevsky, N. I.; Moiseenko, E. V.; Tokarev, U. N.

2017-11-01

The verification of the FENIA finite element code on some problems and an example of its application are presented in the paper. The code is being developing for 3D modelling of thermal, mechanical and hydrodynamical (THM) problems related to the functioning of deep geological repositories. Verification of the code for two analytical problems has been performed. The first one is point heat source with exponential heat decrease, the second one - linear heat source with similar behavior. Analytical solutions have been obtained by the authors. The problems have been chosen because they reflect the processes influencing the thermal state of deep geological repository of radioactive waste. Verification was performed for several meshes with different resolution. Good convergence between analytical and numerical solutions was achieved. The application of the FENIA code is illustrated by 3D modelling of thermal state of a prototypic deep geological repository of radioactive waste. The repository is designed for disposal of radioactive waste in a rock at depth of several hundred meters with no intention of later retrieval. Vitrified radioactive waste is placed in the containers, which are placed in vertical boreholes. The residual decay heat of radioactive waste leads to containers, engineered safety barriers and host rock heating. Maximum temperatures and corresponding times of their establishment have been determined.

Discrete fracture network modelling of a KBS-3H repository at Olkiluoto

Energy Technology Data Exchange (ETDEWEB)

Lanyon, G.W. (Fracture Systems Ltd, St Ives (United Kingdom)); Marschall, P. (Nagra, Wettingen (Switzerland))

2008-06-15

This report presents Discrete Fracture Network (DFN) models of groundwater flow around a KBS-3H repository situated at Olkiluoto. The study was performed in support of the Safety Case for the KBS-3H Concept, being jointly studied by SKB and Posiva. As part of the preliminary assessment of long term safety of a KBS-3H repository, a Process Report and an Evolution Report (evolution of the disposal system from the emplacement of the first canister to the long term) are being produced. In the course of the task definition the project team identified the need for complementary modelling studies aimed at increasing insight into the hydrodynamic evolution of the disposal system after waste emplacement. In particular, the following issues were identified as requiring input from hydrodynamic models: Probability of high inflow points which may cause buffer erosion. Time transients of inflows after construction of deposition drifts. Interference between deposition drifts and transport tunnels. The DFN models represent the fault and fracture system in the planned repository volume at Olkiluoto. In particular, they represent the hydro geologically significant features. The types of hydrogeological features included in the models are: Major Fracture Zones (MFZs). Local Fracture Zones (LFZs) and associated water conducting features (LFZ-WCFs). Water Conducting Features in the background rock (BR-WCFs). These feature types are derived from the current geological and hydrogeological interpretations developed by Posiva. Several model variants were developed during the study and these variants were used for geometric simulations of the WCF network around the deposition drifts. A simple layout adaptation scheme has been applied to the network models to derive statistics for performance measures relating to the deposition drifts, compartments, plugs and super-containers. A single fracture transient flow model was developed to provide insight to transient flow behaviour around

Discrete fracture network modelling of a KBS-3H repository at Olkiluoto

International Nuclear Information System (INIS)

Lanyon, G.W.; Marschall, P.

2008-06-01

This report presents Discrete Fracture Network (DFN) models of groundwater flow around a KBS-3H repository situated at Olkiluoto. The study was performed in support of the Safety Case for the KBS-3H Concept, being jointly studied by SKB and Posiva. As part of the preliminary assessment of long term safety of a KBS-3H repository, a Process Report and an Evolution Report (evolution of the disposal system from the emplacement of the first canister to the long term) are being produced. In the course of the task definition the project team identified the need for complementary modelling studies aimed at increasing insight into the hydrodynamic evolution of the disposal system after waste emplacement. In particular, the following issues were identified as requiring input from hydrodynamic models: Probability of high inflow points which may cause buffer erosion. Time transients of inflows after construction of deposition drifts. Interference between deposition drifts and transport tunnels. The DFN models represent the fault and fracture system in the planned repository volume at Olkiluoto. In particular, they represent the hydro geologically significant features. The types of hydrogeological features included in the models are: Major Fracture Zones (MFZs). Local Fracture Zones (LFZs) and associated water conducting features (LFZ-WCFs). Water Conducting Features in the background rock (BR-WCFs). These feature types are derived from the current geological and hydrogeological interpretations developed by Posiva. Several model variants were developed during the study and these variants were used for geometric simulations of the WCF network around the deposition drifts. A simple layout adaptation scheme has been applied to the network models to derive statistics for performance measures relating to the deposition drifts, compartments, plugs and super-containers. A single fracture transient flow model was developed to provide insight to transient flow behaviour around

The repository ecology: an approach to understanding repository and service interactions

CERN Multimedia

CERN. Geneva

2007-01-01

An increasing number of university institutions and other organisations are deciding to deploy repositories and a growing number of formal and informal distributed services are supporting or capitalising on the information these repositories provide. Despite reasonably well understood technical architectures, early majority adopters may struggle to articulate their place within the actualities of a wider information environment. The idea of a repository ecology provides developers and administrators with a useful way of articulating and analysing their place in the information environment, and the technical and organisational interactions they have, or are developing, with other parts of such an environment. This presentation will provide an overview of the concept of a repository ecology and examine some examples from the domains of scholarly communications and elearning. View John Robertson's biography

Status of Proposed Repository for Latin-American Spent Fuel

Energy Technology Data Exchange (ETDEWEB)

Ferrada, J.J.

2004-10-04

This report compiles preliminary information that supports the premise that a repository is needed in Latin America and analyzes the nuclear situation (mainly in Argentina and Brazil) in terms of nuclear capabilities, inventories, and regional spent-fuel repositories. The report is based on several sources and summarizes (1) the nuclear capabilities in Latin America and establishes the framework for the need of a permanent repository, (2) the International Atomic Energy Agency (IAEA) approach for a regional spent-fuel repository and describes the support that international institutions are lending to this issue, (3) the current situation in Argentina in order to analyze the Argentinean willingness to find a location for a deep geological repository, and (4) the issues involved in selecting a location for the repository and identifies a potential location. This report then draws conclusions based on an analysis of this information. The focus of this report is mainly on spent fuel and does not elaborate on other radiological waste sources.

Implementation of the Brazilian national repository

International Nuclear Information System (INIS)

Tello, Cledola Cassia Oliveira de

2013-01-01

Ionizing radiation in Brazil is used in electricity generation, medicine, industry, agriculture and for research and development purposes. All these activities can generate radioactive waste. At this point, in Brazil, the use of nuclear energy and radioisotopes justifies the construction of a national repository for radioactive wastes of low and intermediate-level. According to Federal Law No. 10308, Brazilian National Commission for Nuclear Energy (CNEN) is responsible for designing and constructing the intermediate and final storages for radioactive wastes. Additionally, a restriction on the construction of Angra 3 is that the repository is under construction until its operation start, attaining some requirements of the Brazilian Environmental Regulator (IBAMA). The RBMN Project (Repository for Low and Intermediate-Level Radioactive Wastes) aims at the implantation of a National Repository for disposal of low and intermediate-level of radiation wastes. This Project has some aspects that are unique in the Brazilian context, especially referring to the time between its construction and the end of its institutional period. This time is about 360 years, when the area will be released for unrestricted uses. It means that the Repository must be safe and secure for more than three hundred years, which is longer than half of the whole of Brazilian history. This aspect is very new for the Brazilian people, bringing a new dimension to public acceptance. Another point is this will be the first repository in South America, bringing a real challenge for the continent. The current status of the Project is summarized. (author)

Main organic materials in a repository for high level radioactive waste

International Nuclear Information System (INIS)

Hallbeck, Lotta; Grive, Mireia; Gaona, Xavier; Duro, Lara; Bruno, Jordi

2007-11-01

, although the presence of aromatic compounds and PAHs in groundwater is not desirable by itself, they are of no consequence for the long-term performance of the repository. 5. Detergents and lubricants. The same reasoning as for fuels and engine emissions can be applied in this case. The amount of detergents should be minimized, although in the amounts that they are expected to occur, no important impact is foreseen. 6. Materials from human activities. Among them, the ones having potentially a more important effect are fibres from clothes, due to the presence of cellulose, and therefore it is recommended to minimise human-related wastes, although no large amounts of these materials are expected to be present after the repository closure. The effects that organic substances can have in the repository will always depend on the amounts present in the repository after closure. The estimated average concentrations are below 1.7x10 -4 kg/m 3 (0.17 mg/L) of hydrocarbons in the deposition tunnels and less than 8.4x10 -4 kg/m 3 (0.84 mg/L) of carbohydrates, assuming a total saturation in the pore water and an even distribution of the organic materials. This should be compared to the organic material found in groundwater at natural circumstances. At 500 m depth the DOC (dissolved organic carbon) content usually are approximately 0.5.2 mg/L. Three processes are deemed to have the largest possible impact on the performance of the repository: i) Increase of the reducing capacity and decrease of the redox potential in the short-term, and increased rate of depletion of the oxygen trapped during the repository operation stage. ii) Increase in the complexing capacity of the groundwater due to the presence of organic complexants, which is expected to be a process of more relevance in the long-term. Many organic molecules with complexing capacity, such as short organic acids like acetate are, however, oxidised as a consequence of microbial metabolism. The acetate concentration in ground water

Main organic materials in a repository for high level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Hallbeck, Lotta [Vita vegrandis, Hindaas (Sweden); Grive, Mireia; Gaona, Xavier; Duro, Lara; Bruno, Jordi [Enviros Consulting, Valldoreix, Barcelona (Spain)

2007-11-15

, although the presence of aromatic compounds and PAHs in groundwater is not desirable by itself, they are of no consequence for the long-term performance of the repository. 5. Detergents and lubricants. The same reasoning as for fuels and engine emissions can be applied in this case. The amount of detergents should be minimized, although in the amounts that they are expected to occur, no important impact is foreseen. 6. Materials from human activities. Among them, the ones having potentially a more important effect are fibres from clothes, due to the presence of cellulose, and therefore it is recommended to minimise human-related wastes, although no large amounts of these materials are expected to be present after the repository closure. The effects that organic substances can have in the repository will always depend on the amounts present in the repository after closure. The estimated average concentrations are below 1.7x10{sup -4} kg/m{sup 3} (0.17 mg/L) of hydrocarbons in the deposition tunnels and less than 8.4x10{sup -4} kg/m{sup 3} (0.84 mg/L) of carbohydrates, assuming a total saturation in the pore water and an even distribution of the organic materials. This should be compared to the organic material found in groundwater at natural circumstances. At 500 m depth the DOC (dissolved organic carbon) content usually are approximately 0.5.2 mg/L. Three processes are deemed to have the largest possible impact on the performance of the repository: i) Increase of the reducing capacity and decrease of the redox potential in the short-term, and increased rate of depletion of the oxygen trapped during the repository operation stage. ii) Increase in the complexing capacity of the groundwater due to the presence of organic complexants, which is expected to be a process of more relevance in the long-term. Many organic molecules with complexing capacity, such as short organic acids like acetate are, however, oxidised as a consequence of microbial metabolism. The acetate

CCDC 866713: Experimental Crystal Structure Determination : catena-(bis(mu~12~-5,5',5''-(1,3,5-benzenetriyltris(methyleneoxy))-tris(1,3-benzenedicarboxylato))-hexa-aqua-hexa-cobalt)

KAUST Repository

Eubank, J.F.; Nouar, F.; Luebke, Ryan; Cairns, Amy; Wojtas, L.; Al Kordi, Mohamed; Bousquet, T.; Hight, M.R.; Eckert, J.; Embs, J.P.; Georgiev, P.A.; Eddaoudi, Mohamed

2013-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Nuclear waste repository in basalt: preconceptual design guidelines

International Nuclear Information System (INIS)

1979-06-01

The development of the basalt waste isolation program parallels the growing need for permanent, environmentally safe, and secure means to store nuclear wastes. The repository will be located within the Columbia Plateau basalt formations where these ends can be met and radiological waste can be stored. These wastes will be stored such that the wastes may be retrieved from storage for a period after placement. After the retrieval period, the storage locations will be prepared for terminal storage. The terminal storage requirements will include decommissioning provisions. The facility boundaries will encompass no more than several square miles of land which will be above a subsurface area where the geologic makeup is primarily deep basaltic rock. The repository will receive, from an encapsulation site(s), nuclear waste in the form of canisters (not more than 18.5 feet x 16 inches in diameter) and containers (55-gallon drums). Canisters will contain spent fuel (after an interim 5-year storage period), solidified high-level wastes (HLW), or intermediate-level wastes (ILW). The containers (drums) will package the low-level transuranic wastes (LL-TRU). The storage capacity of the repository will be expanded in a time-phased program which will require that subsurface development (repository expansion) be conducted concurrently with waste storage operations. The repository will be designed to store the nuclear waste generated within the predictable future and to allow for reasonable expansion. The development and assurance of safe waste isolation is of paramount importance. All activities will be dedicated to the protection of public health and the environment. The repository will be licensed by the US Nuclear Regulatory Commission (NRC). Extensive efforts will be made to assure selection of a suitable site which will provide adequate isolation

Nuclear waste repository in basalt: preconceptual design guidelines

Energy Technology Data Exchange (ETDEWEB)

1979-06-01

The development of the basalt waste isolation program parallels the growing need for permanent, environmentally safe, and secure means to store nuclear wastes. The repository will be located within the Columbia Plateau basalt formations where these ends can be met and radiological waste can be stored. These wastes will be stored such that the wastes may be retrieved from storage for a period after placement. After the retrieval period, the storage locations will be prepared for terminal storage. The terminal storage requirements will include decommissioning provisions. The facility boundaries will encompass no more than several square miles of land which will be above a subsurface area where the geologic makeup is primarily deep basaltic rock. The repository will receive, from an encapsulation site(s), nuclear waste in the form of canisters (not more than 18.5 feet x 16 inches in diameter) and containers (55-gallon drums). Canisters will contain spent fuel (after an interim 5-year storage period), solidified high-level wastes (HLW), or intermediate-level wastes (ILW). The containers (drums) will package the low-level transuranic wastes (LL-TRU). The storage capacity of the repository will be expanded in a time-phased program which will require that subsurface development (repository expansion) be conducted concurrently with waste storage operations. The repository will be designed to store the nuclear waste generated within the predictable future and to allow for reasonable expansion. The development and assurance of safe waste isolation is of paramount importance. All activities will be dedicated to the protection of public health and the environment. The repository will be licensed by the US Nuclear Regulatory Commission (NRC). Extensive efforts will be made to assure selection of a suitable site which will provide adequate isolation.

Safety functions and safety function indicators - key elements in SKB'S methodology for assessing long-term safety of a KBS-3 repository

International Nuclear Information System (INIS)

Hedin, A.

2008-01-01

The application of so called safety function indicators in SKB safety assessment of a KBS-3 repository for spent nuclear fuel is presented. Isolation and retardation are the two main safety functions of the KBS-3 concept. In order to quantitatively evaluate safety on a sub-system level, these functions need to be differentiated, associated with quantitative measures and, where possible, with quantitative criteria relating to the fulfillment of the safety functions. A safety function is defined as a role through which a repository component contributes to safety. A safety function indicator is a measurable or calculable property of a repository component that allows quantitative evaluation of a safety function. A safety function indicator criterion is a quantitative limit such that if the criterion is fulfilled, the corresponding safety function is upheld. The safety functions and their associated indicators and criteria developed for the KBS-3 repository are primarily related to the isolating potential and to physical states of the canister and the clay buffer surrounding the canister. They are thus not directly related to release rates of radionuclides. The paper also describes how the concepts introduced i) aid in focussing the assessment on critical, safety related issues, ii) provide a framework for the accounting of safety throughout the different time frames of the assessment and iii) provide key information in the selection of scenarios for the safety assessment. (author)

Salt repository design approach

International Nuclear Information System (INIS)

Matthews, S.C.

1983-01-01

This paper presents a summary discussion of the approaches that have been and will be taken in design of repository facilities for use with disposal of radioactive wastes in salt formations. Since specific sites have yet to be identified, the discussion is at a general level, supplemented with illustrative examples where appropriate. 5 references, 1 figure

Repository operational criteria analysis

International Nuclear Information System (INIS)

Hageman, J.P.; Chowdhury, A.H.

1992-08-01

The objective of the ''Repository Operational Criteria (ROC) Feasibility Studies'' (or ROC task) was to conduct comprehensive and integrated analyses of repository design, construction, and operations criteria in 10 CFR Part 60 regulations, considering the interfaces and impacts of any potential changes to those regulations. The study addresses regulatory criteria related to the preclosure aspects of the geologic repository. The study task developed regulatory concepts or potential repository operational criteria (PROC) based on analysis of a repository's safety functions and other regulations for similar facilities. These regulatory concepts or PROC were used as a basis to assess the sufficiency and adequacy of the current criteria in 10 CFR Part 60. Where the regulatory concepts were same as current operational criteria, these criteria were referenced. The operations criteria referenced or the PROC developed are given in this report. Detailed analyses used to develop the regulatory concepts and any necessary PROC for those regulations that may require a minor change are also presented. The results of the ROC task showed a need for further analysis and possible major rule change related to the design bases of a geologic repository operations area, siting, and radiological emergency planning

Consortial routes to effective repositories

OpenAIRE

Moyle, M.; Proudfoot, R.

2009-01-01

A consortial approach to the establishment of repository services can help a group of Higher Education Institutions (HEIs) to share costs, share technology and share expertise. Consortial repository work can tap into existing structures, or it can involve new groupings of institutions with a common interest in exploring repository development. This Briefing Paper outlines some of the potential benefits of collaborative repository activity, and highlights some of the technical and organisation...

Reference Design Description for a Geologic Repository

International Nuclear Information System (INIS)

2000-01-01

of the waste materials will result in fission products that pose a minimal radiological hazard to the public afterward. For example, after 100 years, the relative hazard from the waste fission products will have diminished approximately 90 percent. After 1,000 years, the hazard will have diminished 99 percent, and after 10,000 years it will have diminished 99.9 percent. The resulting radiological hazard after 10,000 years is minimal, being of the same order of magnitude as that posed by 0.2 percent uranium ore, which is equivalent to that which was used to originally produce the nuclear fuel. Because developing such a repository is extremely complex, the design will move forward in three stages: Site Recommendation, License Application, and Construction. This document presents the design as it will be submitted in the Site Recommendation Consideration Report; the design will be updated as the design process moves forward. As more cost-effective solutions, technical advancements, or changes to requirements occur, the design may evolve. The U.S. Department of Energy's (DOE) Office of Civilian Radioactive Waste Management is developing a system that includes this potential repository. This waste management system integrates acceptance, transportation, storage, and disposal of spent nuclear fuel and high-level radioactive waste. Acceptance and transportation will be handled by regional servicing contractors under contract to the DOE. The U.S. Nuclear Regulatory Commission will conduct an in-depth and thorough licensing review to determine the acceptability of the proposed waste management system. Eight sections of this document follow. Section 2 discusses the design requirements for the proposed repository. Section 3 describes the physical layout of the proposed repository. Section 4 describes the evolutionary phases of the development of the proposed repository. Section 5 describes the receipt of waste. Section 6 details the various systems that will package the waste

Repository design

Energy Technology Data Exchange (ETDEWEB)

John, C M

1982-01-01

Various technical issues of radioactive waste design are addressed in this paper. Two approaches to repository design considered herein are: (1) design to minimize the disturbance of the hot rock; and (2) designs that intentionally modify the hot rock to insure better containment of the wastes. The latter designs range from construction of a highly impermeable barrier around a spherical cavern to creating a matrix of tunnels and boreholes to form a cage within which the hydraulic pressure is nearly constant. Examples of these design alternatives are described in some detail. It is concluded that proposed designs for repositories illustrate that performance criteria considered acceptable for such facilities can be met by appropriate site selection and repository engineering. With these technically feasible design concepts, it is also felt that socioeconomic and institutional issues can be better resolved. (BLM)

CCDC 866712: Experimental Crystal Structure Determination : catena-(bis(mu~12~-5,5',5''-(1,3,5-benzenetriyltris(methyleneoxy))-tris(1,3-benzenedicarboxylato))-tetrakis(dimethylformamide)-diaqua-hexa-zinc)

KAUST Repository

Eubank, J.F.; Nouar, F.; Luebke, Ryan; Cairns, Amy; Wojtas, L.; Al Kordi, Mohamed; Bousquet, T.; Hight, M.R.; Eckert, J.; Embs, J.P.; Georgiev, P.A.; Eddaoudi, Mohamed

2013-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Centralized mouse repositories.

Science.gov (United States)

Donahue, Leah Rae; Hrabe de Angelis, Martin; Hagn, Michael; Franklin, Craig; Lloyd, K C Kent; Magnuson, Terry; McKerlie, Colin; Nakagata, Naomi; Obata, Yuichi; Read, Stuart; Wurst, Wolfgang; Hörlein, Andreas; Davisson, Muriel T

2012-10-01

Because the mouse is used so widely for biomedical research and the number of mouse models being generated is increasing rapidly, centralized repositories are essential if the valuable mouse strains and models that have been developed are to be securely preserved and fully exploited. Ensuring the ongoing availability of these mouse strains preserves the investment made in creating and characterizing them and creates a global resource of enormous value. The establishment of centralized mouse repositories around the world for distributing and archiving these resources has provided critical access to and preservation of these strains. This article describes the common and specialized activities provided by major mouse repositories around the world.

Demystifying the institutional repository for success

CERN Document Server

Buehler, Marianne

2013-01-01

Institutional repositories remain key to data storage on campus, fulfilling the academic needs of various stakeholders. Demystifying the Institutional Repository for Success is a practical guide to creating and sustaining an institutional repository through marketing, partnering, and understanding the academic needs of all stakeholders on campus. This title is divided into seven chapters, covering: traditional scholarly communication and open access publishing; the academic shift towards open access; what the successful institutional repository looks like; institutional repository collaboratio

Siting regions for deep geological repositories. Nagra’s proposals for stage 3

International Nuclear Information System (INIS)

2014-01-01

This brochure published by the Swiss National Cooperative for the Disposal of Radioactive Waste (NAGRA) discusses the selection of sites for deep geological repositories for nuclear wastes in Switzerland. The procedure proposed for the selection process is explained. The four sites for possible repositories of high-level radioactive waste as well as for low and intermediate-level wastes are described and rated with respect to the various safety factors involved. The reasons for the long-term safety measures proposed and the geological barriers involved are discussed. The four proposals for depository sites are looked at in more detail. The paper is well illustrated with several diagrams and tables

CCDC 1055169: Experimental Crystal Structure Determination : Ethyl 5,5-difluoro-3,7-bis(triphenylvinyl)-5H-4lambda5,5lambda5-dipyrrolo[1,2-c:2',1'-f][1,3,2]diazaborinine-10-carboxylate

KAUST Repository

Chua, Ming Hui; Ni, Yong; Garai, Monalisa; Zheng, Bin; Huang, Kuo-Wei; Xu, Qing-Hua; Xu, Jianwei; Wu, Jishan

2015-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

The European Repository Landscape 2008 Inventory of Digital Repositories for Research Output

CERN Document Server

Van der Graaf, Maurits

2009-01-01

It is widely acknowledged that a common knowledge base for European research is necessary. Research repositories are an important innovation to the scientific information infrastructure. In 2006, digital repositories in the 27 countries of the European we

Some inspirations drawn from the SKB license-application report for the construction of the final repository for spent nuclear fuel in Sweden

International Nuclear Information System (INIS)

Xu Guoqing

2014-01-01

The following problems are described in this paper: the current state of nuclear energy and spent fuel in Sweden, the brief process of repository site selection and the concise geological settings of candidate site Forsmark, the option of repository design, the data presented in license-application report on repository, construction, the review work presented by OECD/NEA international peer review team (IRT) and some considerations noted by the author: 1) Why the design of underground engineering, also known as 5 shafts + l ramp, is adopted? 2) Why the timescale for the assessment is one million years? 3) Why the computer codes used in performance assessment at Forsmark candidate repository site are different from those used at Yucca Mountain candidate repository site? 4) How to carry out the public involvement, support from local government and volumtary siting in China? 5) What is the most important in the R and D program of HLW disposal? 6) What shall we do for the future license-application report for the construction of the final repository in China? (author)

Office of Geologic Repositories quality assurance plan for high-level radioactive waste repositories

International Nuclear Information System (INIS)

1986-08-01

This document sets forth geologic repository program-wide quality assurance program requirements and defines management's quality assurance responsibilities for the Office of Geologic Repositories and its projects. (LM)

Virtual patient repositories--a comparative analysis.

Science.gov (United States)

Küfner, Julia; Kononowicz, Andrzej A; Hege, Inga

2014-01-01

Virtual Patients (VPs) are an important component of medical education. One way to reduce the costs for creating VPs is sharing through repositories. We conducted a literature review to identify existing repositories and analyzed the 17 included repositories in regards to the search functions and metadata they provide. Most repositories provided some metadata such as title or description, whereas other data, such as educational objectives, were less frequent. Future research could, in cooperation with the repository provider, investigate user expectations and usage patterns.

Technology overview of mined repositories

International Nuclear Information System (INIS)

Gimera, R.; Thirumalai, K.

1982-01-01

Mined repositories present an environmentally viable option for permanent disposal of nuclear waste. This paper reviews the state-of-the-art mining technologies and identifies technological issues and developments necessary to mine a repository in basalt. The thermal loading, isolation, and retrieval requirements of a repository present unique technological challenges unknown to conventional mining practice. The technology issues and developments required in the areas of excavation, roof and ground support, equipment development, instrumentation development, and sealing are presented. Performance assessment methods must be developed to evaluate the adequacies of technologies developed to design, construct, operate, and decommission a repository. A stepwise test-and-development approach is used in the Basalt Waste Isolation Project to develop cost-effective technologies for a repository

Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 2, Part A: Chapters 3, 4, and 5

International Nuclear Information System (INIS)

1988-12-01

This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1--5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 575 refs., 84 figs., 68 tabs

Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 2, Part A: Chapters 3, 4, and 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-01

This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1--5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 575 refs., 84 figs., 68 tabs.

Breast Cancer Tissue Repository

National Research Council Canada - National Science Library

Iglehart, J

1997-01-01

The Breast Tissue Repository at Duke enters its fourth year of finding. The purpose of the Repository at Duke is to provide substantial quantities of frozen tissue for explorative molecular studies...

Relationship of engineering geology to conceptual repository design in the Gibson Dome area, Utah

International Nuclear Information System (INIS)

Helgerson, R.; Henderson, N.

1984-01-01

The Paradox Basin in Southeastern Utah is being investigated as a potential site for development of a high-level nuclear waste repository. Geologic considerations are key areas of concern and influence repository design from a number of aspects: depth to the host rock, thickness of the host rock, and hydrologic conditions surrounding the proposed repository are of primary concern. Surface and subsurface investigations have provided data on these key geologic factors for input to the repository design. A repository design concept, based on the surface and subsurface geologic investigations conducted at Gibson Dome, was synthesized to provide needed information on technical feasibility and cost for repository siting decision purposes. Significant features of the surface and subsurface repository facilities are presented. 5 references, 4 figures

CCDC 1043464: Experimental Crystal Structure Determination : catena-[(mu-3,3',5,5'-tetracarboxylatobiphenyl)-bis(mu-hydroxo)-di-indium

KAUST Repository

Savage, Mathew; da Silva, Ivan; Johnson, Mark; Carter, Joseph H.; Newby, Ruth; Suetin, Mikhail; Besley, Elena; Manuel, Pascal; Rudić, Svemir; Fitch, Andrew N.; Murray, Claire; David, William I. F.; Yang, Sihai; Schrö der, Martin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

10 CFR 960.5-2-5 - Environmental quality.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Environmental quality. 960.5-2-5 Section 960.5-2-5 Energy... REPOSITORY Preclosure Guidelines Environment, Socioeconomics, and Transportation § 960.5-2-5 Environmental... repository siting, construction, operation, closure, and decommissioning, and projected environmental impacts...

Technical, institutional and economic factors important for developing a multinational radioactive waste repository

International Nuclear Information System (INIS)

1998-06-01

Countries planning and implementing nuclear energy programmes should assume responsibility for the safe management and final disposal of radioactive waste from their programmes. However, there are countries whose radioactive waste volumes do not easily justify a national repository, and/or countries which do not have the resources or favorable natural conditions for waste disposal to dedicate to a national repository project. These countries would benefit from multinational co-operation for the disposal. Interest in the concept of a multinational repository for radioactive waste has been expressed by several Member States and the waste management community in the light of the potential benefit to the partner countries from the safety, technical and economic standpoints. However, such an approach involves many political and public acceptance issues and therefore a consensus among countries or regions concerned is a prerequisite. In this context, it was deemed appropriate that the IAEA access the technical, institutional, ethical and economic factors to be taken into account in the process of such consensus building. This report is intended to provide an assessment which can serve as a general basis for establishing a waste management policy and/or further assessing specific issues such as ownership and liability, institutional aspects and problems related to long term commitments. This report is divided into five sections where the first section gives background, objectives, scope and structure of the report. Section 2 discusses multinational repository concept in terms of needs and the role of a multinational repository, interaction between host and partner countries and formulation of a multinational repository. Section 3 identifies basic issues to be considered for establishing a multinational repository, and some specific issues relating to specific waste categories. Section 4 analyses potential benefits and challenges to be addresses in establishing a

Studies on an advanced repository system with enhanced engineered barriers (a framework)

International Nuclear Information System (INIS)

Fujiwara, A.; Tashiro, S.; Ikari, S.; Suzuki, A.

1993-01-01

In order to propose advanced designs of repositories with enhanced engineered barriers of relatively high radioactive wastes such as burnable poisons, channel boxes, control rods and highly irradiated metals, studies started in 1987 and completed the first phase in 1992. This paper presents the framework and brief results of the first phase. The studies set preliminary design concepts of the repositories with various combinations with engineered barriers and natural barriers for different models and locations such as a silo type in shallow land or a tunnel type in intermediate depth. Through the designs, four component technics were picked up and studied for (1) construction of the components in repository; (2) performance evaluation to realize repository design; (3) improvement of circumstances inside or around repository; and (4) surveillance of repository performance to realize the repository designs. Finally, some repository systems were provided using obtained results, and then the applicability and the economy were evaluated. The studies will continue to the second phase focusing on the long-term performance of the repositories

Thermal dimensioning of spent fuel repository

International Nuclear Information System (INIS)

Ikonen, K.

2009-09-01

This report contains the temperature dimensioning of the KBS-3V type nuclear fuel repository in Olkiluoto for the BWR, VVER and EPR fuel canisters, which are disposed at vertical position in the horizontal tunnels in a rectangular geometry according to the preliminary Posiva plan. This report concerns only the temperature dimensioning of the repository and does not take into account the possible restrictions caused by the stresses induced in the rock. The maximum temperature on the canister-bentonite interface is limited to the design temperature of +100 deg C. However, due to uncertainties in thermal analysis parameters (like scattering in rock conductivity or in predicted decay power) the allowable calculated maximum canister temperature is set to 90 deg C causing a safety margin of 10 deg C. The allowable temperature is controlled by adjusting the space between adjacent canisters, adjacent tunnels and the pre-cooling time affecting on power of the canisters. The temperature of canister surfaces can be determined by superposing analytic line heat source models much more efficiently than by numerical analysis, if the analytic model is first calibrated by numerical analysis (by control volume method). This was done by comparing the surface temperatures of a single canister calculated numerically and analytically. For the Olkiluoto repository of one panel having 900 canisters of BWR, VVER and EPR spent fuel was analyzed. The analyses were performed with an initial canister power of 1 700 W, 1 370 W and 1 830 W, respectively. These decay heats are obtained when the pre-cooling times of the fuels are 32.9, 29.6 and 50.3 years (the burn-up values 40, 40 and 50 MWd/kgU, respectively). The analyses gave as a result the canister spacing (6.0-10.8 m), when the tunnel spacing was 25 m, 30 m or 40 m. On the edge areas of the panel with constant canister spacing the temperatures of the canisters are lower than in the middle area of the repository. Thus it is possible to pack

What requirements does the KBS-3 repository make on the host rock? Geoscientific suitability indicators and criteria for siting and site evaluation

Energy Technology Data Exchange (ETDEWEB)

Andersson, Johan [Golder Grundteknik AB (Sweden); Stroem, Anders; Svemar, Christer [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Almen, Karl-Erik [KEA Geo-Konsult AB, Naessjoe (Sweden); Ericsson, Lars O. [Chalmers University of Technology, Goeteborg (Sweden)

2000-04-01

This report gives an account of what requirements are made on the rock, what conditions in the rock are advantageous and how the fulfilment of requirements and preferences is to be judged prior to the selection of sites for a site investigation and during a site investigation. The conclusions and results of the report are based on the knowledge and experience acquired by SKB over many years of research and development. The results, and particularly the stipulated criteria, apply to a repository for spent fuel of the KBS-3 type, i.e. a repository where the fuel is contained in copper canisters embedded in bentonite clay at a depth of 400 - 700 m in the Swedish crystalline basement. The report analyzes how the rock's different geological conditions, mechanical, thermal, hydrogeological, chemical and transport properties influence the functions of the deep repository, and whether it is possible to determine requirements and preferences regarding the influence of these properties. Where possible, these requirements or preferences have then been translated into requirements or preferences regarding the individual properties. Criteria are formulated that are based on the quantities that can be measured or estimated at the relevant stage of the investigation. The following requirements are made on the rock: The rock in the repository's deposition zone may not have any ore potential. Regional plastic shear zones shall be avoided if it cannot be demonstrated that the properties of the zone do not deviate from those of the rest of the rock. There may, however, be so-called 'tectonic lenses' near regional plastic shear zones where the bedrock is homogeneous and relatively unaffected. Deposition tunnels and deposition holes for canisters may not pass through or be positioned too close to major regional and major local fracture zones. Deposition holes may not intersect identified local minor fracture zones. The rock's strength, fracture geometry and

Ventilation planning for a prospective nuclear waste repository

International Nuclear Information System (INIS)

Wallace, K.G. Jr.

1987-01-01

In 1982, the US Congress passed the Nuclear Waste Policy Act to provide for the development of underground repositories for spent nuclear fuel. This development will be managed by the United States Department of Energy. In 1986, the President selected three areas for site characterization to determine their suitability for the development of an underground repository; those sites were: (1) A site in volcanic tuff located at Yucca Mountain in Nevada, (2) a site in bedded salt located in Deaf Smith County in Texas, and (3) a site in basalt located in Hanford, Washington. At present conceptual repository designs are being developed for each site. A key element of a repository design is the underground ventilation system required to support construction, nuclear waste emplacement, and potential waste retrieval. This paper describes the preliminary ventilation systems designed for the repository in tuff. The concept provides separate ventilation systems for the construction and waste emplacement activities. The paper further describes the means by which acceptable environmental conditions will be re-established to allow re-entry into previously closed rooms for the purpose of inspection, maintenance or retrieval

Status of the implementation of Brazilian National Repository

International Nuclear Information System (INIS)

Tello, Cledola Cassia Oliveira de

2015-01-01

In Brazil, the use of nuclear energy and radioisotopes is increasing and it already justifies the construction of a national repository for radioactive wastes of low and intermediate-level. The Brazilian National Commission for Nuclear Energy (CNEN) is legally responsible for designing and constructing intermediate and final storages for radioactive wastes generated in all Country, in accordance to Federal Law No. 10308. Additionally, the Brazilian Environmental Regulator (IBAMA) lately is imposing to the implementation of new nuclear installations (e.g. Angra 3 NPP and Brazilian Multipurpose Reactor) that the National Repository should be in construction, before the start-up of those ones. In November 2009, the RBMN Project Charter was signed. The RBMN Project aims at the implantation of a National Repository to dispose the radioactive wastes of low- and intermediate-level. Some aspects about the Repository construction are very challenging, mainly due to the licensing process, which will be made for two different regulatory bodies, nuclear and environmental. The main achievements obtained till now are the establishment of the current Brazilian radioactive waste inventory, the conceptual design and the selection of candidate sites for the repository. The current status of the Project is summarized. (author)

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Summary report

International Nuclear Information System (INIS)

Smith, Paul; Neall, Fiona; Snellman, Margit; Pastina, Barbara; Nordman, Henrik; Johnson, Lawrence; Hjerpe, Thomas

2008-03-01

The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. KBS-3H and KBS-3V are the two design alternatives of the KBS-3 spent fuel disposal method. Posiva and SKB have conducted a joint research, demonstration and development (RDandD) programme in 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to the reference alternative KBS-3V. The overall objectives of the present phase covering the period 2004-2007 have been to demonstrate that the horizontal deposition alternative is technically feasible and to demonstrate that it fulfils the same long-term safety requirements as KBS-3V. The safety studies conducted as part of this programme include a safety assessment of a preliminary design of a KBS-3H repository for spent nuclear fuel located about 400 m underground at the Olkiluoto site, which is the proposed site for a spent fuel repository in Finland. This safety assessment is summarised in the present report. The scientific basis of the safety assessment includes around 30 years of scientific RandD and technical development in the Swedish and Finnish KBS-3V programmes. Much of this scientific basis is directly applicable to KBS-3H. This has allowed the KBS-3H safety studies to focus on those issues that are unique to this design alternative, identified in a systematic 'difference analysis' of KBS-3H and KBS-3V. This difference analysis has shown that the key differences in the evolution and performance of KBS-3H and KBS-3V relate mainly to the engineered barrier system and to the impact of local variations in the rate of groundwater inflow on buffer saturation along the KBS-3H deposition drifts. No features or processes specific to KBS-3H have been identified that could lead to a loss or substantial degradation of the safety functions of the engineered barriers over a million year time frame. Radionuclide release from the repository near field in the event of

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Summary report

Energy Technology Data Exchange (ETDEWEB)

Smith, Paul; Neall, Fiona; Snellman, Margit; Pastina, Barbara; Nordman, Henrik; Johnson, Lawrence; Hjerpe, Thomas

2008-03-15

The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. KBS-3H and KBS-3V are the two design alternatives of the KBS-3 spent fuel disposal method. Posiva and SKB have conducted a joint research, demonstration and development (RDandD) programme in 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to the reference alternative KBS-3V. The overall objectives of the present phase covering the period 2004-2007 have been to demonstrate that the horizontal deposition alternative is technically feasible and to demonstrate that it fulfils the same long-term safety requirements as KBS-3V. The safety studies conducted as part of this programme include a safety assessment of a preliminary design of a KBS-3H repository for spent nuclear fuel located about 400 m underground at the Olkiluoto site, which is the proposed site for a spent fuel repository in Finland. This safety assessment is summarised in the present report. The scientific basis of the safety assessment includes around 30 years of scientific RandD and technical development in the Swedish and Finnish KBS-3V programmes. Much of this scientific basis is directly applicable to KBS-3H. This has allowed the KBS-3H safety studies to focus on those issues that are unique to this design alternative, identified in a systematic 'difference analysis' of KBS-3H and KBS-3V. This difference analysis has shown that the key differences in the evolution and performance of KBS-3H and KBS-3V relate mainly to the engineered barrier system and to the impact of local variations in the rate of groundwater inflow on buffer saturation along the KBS-3H deposition drifts. No features or processes specific to KBS-3H have been identified that could lead to a loss or substantial degradation of the safety functions of the engineered barriers over a million year time frame. Radionuclide release from the repository near field in the

Stability of underground excavations in a repository system

International Nuclear Information System (INIS)

Calash, A.Y.; Greer, J.C.; Andrea, S.J.; Chowdhury, A.H.; Nguyen, V.V.

1988-01-01

The DOE is investigating the feasibility of constructing a deep geologic repository at the Hanford Site, Washington, for the permanent disposal of nuclear waste. The underground openings associated with the repository design include shafts, tunnels, emplacement rooms and boreholes. The stability of these underground openings, the extent and characteristics of the disturbed zones due to excavation, and their effects on groundwater flow path and travel time have a primary influence on the performance assessment of the Hanford Site as a nuclear waste repository. This study is being done in accordance with the requirements of the NRC. Results of structural analyses of shafts and tunnels under in situ stresses and/or medium weight are presented in this paper. Four different analyses were carried out to analyze the shaft: a plane strain model, axisymmetric model, 3-D model of a single material medium, and 3-D model of a three material medium

Methods of calculating the post-closure performance of high-level waste repositories

Energy Technology Data Exchange (ETDEWEB)

Ross, B. (ed.)

1989-02-01

This report is intended as an overview of post-closure performance assessment methods for high-level radioactive waste repositories and is designed to give the reader a broad sense of the state of the art of this technology. As described here, ''the state of the art'' includes only what has been reported in report, journal, and conference proceedings literature through August 1987. There is a very large literature on the performance of high-level waste repositories. In order to make a review of this breadth manageable, its scope must be carefully defined. The essential principle followed is that only methods of calculating the long-term performance of waste repositories are described. The report is organized to reflect, in a generalized way, the logical order to steps that would be taken in a typical performance assessment. Chapter 2 describes ways of identifying scenarios and estimating their probabilities. Chapter 3 presents models used to determine the physical and chemical environment of a repository, including models of heat transfer, radiation, geochemistry, rock mechanics, brine migration, radiation effects on chemistry, and coupled processes. The next two chapters address the performance of specific barriers to release of radioactivity. Chapter 4 treats engineered barriers, including containers, waste forms, backfills around waste packages, shaft and borehole seals, and repository design features. Chapter 5 discusses natural barriers, including ground water systems and stability of salt formations. The final chapters address optics of general applicability to performance assessment models. Methods of sensitivity and uncertainty analysis are described in Chapter 6, and natural analogues of repositories are treated in Chapter 7. 473 refs., 19 figs., 2 tabs.

Methods of calculating the post-closure performance of high-level waste repositories

International Nuclear Information System (INIS)

Ross, B.

1989-02-01

This report is intended as an overview of post-closure performance assessment methods for high-level radioactive waste repositories and is designed to give the reader a broad sense of the state of the art of this technology. As described here, ''the state of the art'' includes only what has been reported in report, journal, and conference proceedings literature through August 1987. There is a very large literature on the performance of high-level waste repositories. In order to make a review of this breadth manageable, its scope must be carefully defined. The essential principle followed is that only methods of calculating the long-term performance of waste repositories are described. The report is organized to reflect, in a generalized way, the logical order to steps that would be taken in a typical performance assessment. Chapter 2 describes ways of identifying scenarios and estimating their probabilities. Chapter 3 presents models used to determine the physical and chemical environment of a repository, including models of heat transfer, radiation, geochemistry, rock mechanics, brine migration, radiation effects on chemistry, and coupled processes. The next two chapters address the performance of specific barriers to release of radioactivity. Chapter 4 treats engineered barriers, including containers, waste forms, backfills around waste packages, shaft and borehole seals, and repository design features. Chapter 5 discusses natural barriers, including ground water systems and stability of salt formations. The final chapters address optics of general applicability to performance assessment models. Methods of sensitivity and uncertainty analysis are described in Chapter 6, and natural analogues of repositories are treated in Chapter 7. 473 refs., 19 figs., 2 tabs

INSTITUTIONAL REPOSITORY: EMPLOYMENT IN EDUCATION

Directory of Open Access Journals (Sweden)

Vasyl P. Oleksyuk

2012-11-01

Full Text Available The article investigated the concept of «institutional repository» and determined the aspects of institutional repositories in higher education. Institutional Repositories are information systems that allow preserving, storing and disseminating scientific knowledge produced in higher education and scientific research institutions. This study presented the main aspects using institutional repositories in educational process (such as storage of scientific and educational information, means of organization activity of students, object of studying. This article produced the structure of communities and collections of the institutional. It is described the experience of implementing of DSpace in the learning process.

Trust in Digital Repositories

Directory of Open Access Journals (Sweden)

Elizabeth Yakel

2013-06-01

Full Text Available ISO 16363:2012, Space Data and Information Transfer Systems - Audit and Certification of Trustworthy Digital Repositories (ISO TRAC, outlines actions a repository can take to be considered trustworthy, but research examining whether the repository’s designated community of users associates such actions with trustworthiness has been limited. Drawing from this ISO document and the management and information systems literatures, this paper discusses findings from interviews with 66 archaeologists and quantitative social scientists. We found similarities and differences across the disciplines and among the social scientists. Both disciplinary communities associated trust with a repository’s transparency. However, archaeologists mentioned guarantees of preservation and sustainability more frequently than the social scientists, who talked about institutional reputation. Repository processes were also linked to trust, with archaeologists more frequently citing metadata issues and social scientists discussing data selection and cleaning processes. Among the social scientists, novices mentioned the influence of colleagues on their trust in repositories almost twice as much as the experts. We discuss the implications our findings have for identifying trustworthy repositories and how they extend the models presented in the management and information systems literatures.

Project Guarantee 1985. Repository for high-level radioactive waste: construction and operation

International Nuclear Information System (INIS)

Anon.

1985-01-01

An engineering project study aimed at demonstrating the feasibility of constructing a deep repository for high-level waste (Type C repository) has been carried out; the study is based on a model data-set representing typical geological and rock mechanical conditions as found outside the so-called Permocarboniferous basin in the regions under investigation by Nagra in Cantons Aargau, Schaffhausen, Solothurn and Zuerich. The repository is intended for disposal of high-level waste and any intermediate-level waste from re-processing in which the concentration of long-lived alpha-emitters exceeds the permissible limits set for a Type B repository. Final disposal of high-level waste is in subterranean, horizontally mined tunnels and of intermediate-level waste in underground vertical silos. The repository is intended to accomodate a total of around 6'000 HWL-cylinders (gross volume of around 1'200 m3) and around 10'000 m3 of intermediate-level waste. The total excavated volume is around 1'100'000 m3 and a construction time for the whole repository (up to the beginning of emplacement) of around 15 years is expected. For the estimated 50-year emplacement operations, a working team of around 60 people will be needed and a team of around 160 for the simultaneous tunnelling operations and auxiliary work. The project described in the present report permits the conclusion that construction of a repository for high-level radioactive waste and, if necessary, spent fuel-rods is feasible with present-day technology

CCDC 855129: Experimental Crystal Structure Determination : catena-[(mu16-5,5',5'',5''',5'''',5'''''-(1,2,3,4,5,6-Benzenehexamethoxy)hexaisophthalato)-tetraaqua-tetra-copper tetrahydrate

KAUST Repository

Eubank, J.F.; Mouttaki, H.; Cairns, Amy; Belmabkhout, Youssef; Wojtas, L.; Luebke, Ryan; Al Kordi, Mohamed; Eddaoudi, Mohamed

2012-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Desiderata for healthcare integrated data repositories based on architectural comparison of three public repositories.

Science.gov (United States)

Huser, Vojtech; Cimino, James J

2013-01-01

Integrated data repositories (IDRs) are indispensable tools for numerous biomedical research studies. We compare three large IDRs (Informatics for Integrating Biology and the Bedside (i2b2), HMO Research Network's Virtual Data Warehouse (VDW) and Observational Medical Outcomes Partnership (OMOP) repository) in order to identify common architectural features that enable efficient storage and organization of large amounts of clinical data. We define three high-level classes of underlying data storage models and we analyze each repository using this classification. We look at how a set of sample facts is represented in each repository and conclude with a list of desiderata for IDRs that deal with the information storage model, terminology model, data integration and value-sets management.

CCDC 1404071: Experimental Crystal Structure Determination : 5,5-difluoro-10-phenyl-3-(1,2,2-triphenylethyl)-7-(triphenylvinyl)-5H-4lambda5,5lambda5-dipyrrolo[1,2-c:2',1'-f][1,3,2]diazaborinine

KAUST Repository

Chua, Ming Hui; Huang, Kuo-Wei; Xu, Jianwei; Wu, Jishan

2015-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Process mining software repositories

NARCIS (Netherlands)

Poncin, W.; Serebrenik, A.; Brand, van den M.G.J.

2011-01-01

Software developers' activities are in general recorded in software repositories such as version control systems, bug trackers and mail archives. While abundant information is usually present in such repositories, successful information extraction is often challenged by the necessity to

The Ec prototype repository project: implications of assessments for refining repository design

International Nuclear Information System (INIS)

Svemar, C.

2004-01-01

The most important issue in the evaluation of the repository performance is the long term safety of the repository. Analyses for this issue focuses on the 'steady state' conditions which start at the time when the repository has been saturated and the groundwater table returned to its normal level. The bentonite buffer around the canisters is saturated and homogeneous, and the canister is located exactly in the centre of the buffer. The backfill in the tunnel has been saturated as well and fills the earlier open spaces in the tunnel completely. The task of the activities taking places prior to the start of the 'steady state' conditions, like excavation, deposition, backfilling and sealing, with due consideration to the processes a consequences they may cause in the long run, is to provide for these 'ideal' conditions, as close as possible. While studying these activities in detail it has become obvious that development of methods and techniques needs to be carefully addressed before the decision is made on how to apply them in the repository. One general finding is that the situation in engineering of details is not that much different from the situation in geological characterisation of a site in detail; one more detail of engineering and the consequences it brings often complicates the situation rather than supports the solution prioritized so far. Many of the practical issues have been studied in the Prototype Repository project in the AEspoe Hard Rock Laboratory (Pusch et al., 2000). The Prototype Repository consists of two sections with four respectively two deposition holes with bentonite buffer and canister, the latter holding electrical heaters. The sections are separated by a concrete plug, and the whole test is to be separated from the rest of the laboratory by an outer plug. The project has two objectives: 1. To demonstrate the integrated function of tile deep repository components under realistic conditions and to compare results with models and

Repository performance confirmation

International Nuclear Information System (INIS)

Hansen, Francis D.

2011-01-01

Repository performance confirmation links the technical bases of repository science and societal acceptance. This paper explores the myriad aspects of what has been labeled performance confirmation in U.S. programs, which involves monitoring as a collection of distinct activities combining technical and social significance in radioactive waste management. This paper is divided into four parts: (1) A distinction is drawn between performance confirmation monitoring and other testing and monitoring objectives; (2) A case study illustrates confirmation activities integrated within a long-term testing and monitoring strategy for Yucca Mountain; (3) A case study reviews compliance monitoring developed and implemented for the Waste Isolation Pilot Plant; and (4) An approach for developing, evaluating and implementing the next generation of performance confirmation monitoring is presented. International interest in repository monitoring is exhibited by the European Commission Seventh Framework Programme 'Monitoring Developments for Safe Repository Operation and Staged Closure' (MoDeRn) Project. The MoDeRn partners are considering the role of monitoring in a phased approach to the geological disposal of radioactive waste. As repository plans advance in different countries, the need to consider monitoring strategies within a controlled framework has become more apparent. The MoDeRn project pulls together technical and societal experts to assimilate a common understanding of a process that could be followed to develop a monitoring program. A fundamental consideration is the differentiation of confirmation monitoring from the many other testing and monitoring activities. Recently, the license application for Yucca Mountain provided a case study including a technical process for meeting regulatory requirements to confirm repository performance as well as considerations related to the preservation of retrievability. The performance confirmation plan developed as part of the

Repository Planning, Design, and Engineering: Part II-Equipment and Costing.

Science.gov (United States)

Baird, Phillip M; Gunter, Elaine W

2016-08-01

Part II of this article discusses and provides guidance on the equipment and systems necessary to operate a repository. The various types of storage equipment and monitoring and support systems are presented in detail. While the material focuses on the large repository, the requirements for a small-scale startup are also presented. Cost estimates and a cost model for establishing a repository are presented. The cost model presents an expected range of acquisition costs for the large capital items in developing a repository. A range of 5,000-7,000 ft(2) constructed has been assumed, with 50 frozen storage units, to reflect a successful operation with growth potential. No design or engineering costs, permit or regulatory costs, or smaller items such as the computers, software, furniture, phones, and barcode readers required for operations have been included.

48 CFR 227.7108 - Contractor data repositories.

Science.gov (United States)

2010-10-01

... repositories. 227.7108 Section 227.7108 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS... Technical Data 227.7108 Contractor data repositories. (a) Contractor data repositories may be established when permitted by agency procedures. The contractual instrument establishing the data repository must...

Surgent University : The Establishment and Evaluation of a National Online Clinical Teaching Repository for Surgical Trainees and Students.

LENUS (Irish Health Repository)

2012-02-01

Introduction. The aim of this study was to develop a new teaching strategy for medical students while creating a national online repository system (Surgent University). Then, the potential of this e-learning modality to facilitate learning of clinical surgery was evaluated. Methods. An online repository and Internet-based interface was designed and hosted on the medical education Web site, www.surgent.ie. Participation was by medical students across 3 Irish universities. Student use of the repository was quantitatively assessed over an 8-week period. They were then invited to complete an anonymous survey assessing the effectiveness of the online repository. Statistical analysis was performed using SPSS version 15, with P < .05 considered significant. Results. Over the study period, the online repository received 6105 uploaded facts by 182 final-year medical students from 3 different universities. The repository Web pages were accessed 54 061 times with 4609 individual searches of the repository. Of the 60 participating students invited to provide survey-based feedback, there were 40 respondents, giving a 66.7% response rate. Of those surveyed, 70% (n = 28) rated the online repository as highly beneficial and 75% (n = 30) as highly relevant. Overall, 87.5% (n = 35) felt that it should be continued, and 70% (n = 28) felt that it should be expanded beyond surgery to include other hospital specialties. Those finding the program interface user-friendly were more likely to find it beneficial (P = .031) and relevant to their ongoing education (P = .002). Conclusions. A user-friendly interface allows for high levels of usage, whereas a "student-centered" structure ensures that the facts uploaded are beneficial and relevant to medical students\\' education.

What requirements does the KBS-3 repository make on the host rock? Geoscientific suitability indicators and criteria for siting and site evaluation

International Nuclear Information System (INIS)

Andersson, Johan; Stroem, Anders; Svemar, Christer; Almen, Karl-Erik; Ericsson, Lars O.

2000-04-01

This report gives an account of what requirements are made on the rock, what conditions in the rock are advantageous and how the fulfilment of requirements and preferences is to be judged prior to the selection of sites for a site investigation and during a site investigation. The conclusions and results of the report are based on the knowledge and experience acquired by SKB over many years of research and development. The results, and particularly the stipulated criteria, apply to a repository for spent fuel of the KBS-3 type, i.e. a repository where the fuel is contained in copper canisters embedded in bentonite clay at a depth of 400 - 700 m in the Swedish crystalline basement. The report analyzes how the rock's different geological conditions, mechanical, thermal, hydrogeological, chemical and transport properties influence the functions of the deep repository, and whether it is possible to determine requirements and preferences regarding the influence of these properties. Where possible, these requirements or preferences have then been translated into requirements or preferences regarding the individual properties. Criteria are formulated that are based on the quantities that can be measured or estimated at the relevant stage of the investigation. The following requirements are made on the rock: The rock in the repository's deposition zone may not have any ore potential. Regional plastic shear zones shall be avoided if it cannot be demonstrated that the properties of the zone do not deviate from those of the rest of the rock. There may, however, be so-called 'tectonic lenses' near regional plastic shear zones where the bedrock is homogeneous and relatively unaffected. Deposition tunnels and deposition holes for canisters may not pass through or be positioned too close to major regional and major local fracture zones. Deposition holes may not intersect identified local minor fracture zones. The rock's strength, fracture geometry and initial stresses may not be

Thermal Analysis of a Nuclear Waste Repository in Argillite Host Rock

Science.gov (United States)

Hadgu, T.; Gomez, S. P.; Matteo, E. N.

2017-12-01

Disposal of high-level nuclear waste in a geological repository requires analysis of heat distribution as a result of decay heat. Such an analysis supports design of repository layout to define repository footprint as well as provide information of importance to overall design. The analysis is also used in the study of potential migration of radionuclides to the accessible environment. In this study, thermal analysis for high-level waste and spent nuclear fuel in a generic repository in argillite host rock is presented. The thermal analysis utilized both semi-analytical and numerical modeling in the near field of a repository. The semi-analytical method looks at heat transport by conduction in the repository and surroundings. The results of the simulation method are temperature histories at selected radial distances from the waste package. A 3-D thermal-hydrologic numerical model was also conducted to study fluid and heat distribution in the near field. The thermal analysis assumed a generic geological repository at 500 m depth. For the semi-analytical method, a backfilled closed repository was assumed with basic design and material properties. For the thermal-hydrologic numerical method, a repository layout with disposal in horizontal boreholes was assumed. The 3-D modeling domain covers a limited portion of the repository footprint to enable a detailed thermal analysis. A highly refined unstructured mesh was used with increased discretization near heat sources and at intersections of different materials. All simulations considered different parameter values for properties of components of the engineered barrier system (i.e. buffer, disturbed rock zone and the host rock), and different surface storage times. Results of the different modeling cases are presented and include temperature and fluid flow profiles in the near field at different simulation times. Sandia National Laboratories is a multimission laboratory managed and operated by National Technology and

Environmental assessment overview, Reference repository location, Hanford site, Washington

International Nuclear Information System (INIS)

1986-05-01

In February 1983, the US Department of Energy (DOE) identified a reference repository location at the Hanford Site in Washington as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The site is in the Columbia Plateau, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Hanford site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. On the basis of the evaluations reported in this EA, the DOE has found that the Hanford site is not disqualified under the guidelines. On the basis of these findings, the DOE is nominating the Hanford site as one of five sites suitable for characterization. 3 figs

Analysis of Turkey’s Institutional Open Repositories: An Example of Dokuz Eylül University Institutional Open Repository

Directory of Open Access Journals (Sweden)

Korhan Levent Ertürk

2012-03-01

Full Text Available After the declaration of the Budapest Open Access Initiative in 2001, institutional open repositories are known as the most important tool of the self archiving, which is also known as green road. There are 26 institutional repositories, which are all compatible to international standards. All the institutional open repositories of Turkey mentioned before are listed in international open archive directories. In this study institutional open repository of Dokuz Eylül University is examined and institutional open repositories of Turkey are discussed.

Radioactive waste repository of high ecological safety

International Nuclear Information System (INIS)

Sobolev, I.; Barinov, A.; Prozorov, L.

2000-01-01

With the purpose to construct a radioactive waste repository of high ecological safety and reliable containment, MosNPO 'Radon' specialists have developed an advanced type repository - large diameter well (LBD) one. A project is started for the development of a technology for LDW repository construction and pilot operation of the new repository for 25-30 years. The 2 LDW repositories constructed at the 'Radon' site and the developed monitoring system are described

Subseabed radionuclide migration studies and preliminary repository design concepts

International Nuclear Information System (INIS)

Brush, L.H.

1982-01-01

Geochemical research carried out by the US Subseabed Disposal Program is described. Data from studies of high-temperature interactions between sediments and pore water (seawater) and from studies of sorption and diffusion of radionuclides in oxidized, deep-sea sediments are used, along with results from heat transfer studies, to predict migration rates of raionuclides in a subseabed repository. Preliminary results for most radionuclides in oxidized sediments are very encouraging. Fission products with moderate K/sub D/ values (10 2 to 10 5 ml/g) and actinides with high K/sub D/ values (10 3 to 10 6 ml/g) would not migrate significant distances before decaying to innocuous concentrations. Among this group are 137 Cs, 90 Sr, and 239 Pu. The results for anionic species in oxidized sediments are less encouraging. Planning for field verification of these laboratory and modeling studies is currently under way. Conceptual repository designs and emplacement options are also described. 33 references, 15 figures, 1 table

Disposal of radioactive waste in Swedish crystalline rocks

International Nuclear Information System (INIS)

Greis Dahlberg, Christina; Wikberg, Peter

2015-01-01

SKB, Swedish Nuclear Fuel and Waste Management Company is tasked with managing Swedish nuclear and radioactive waste. Crystalline rock is the obvious alternative for deep geological disposal in Sweden. SKB is, since 1988, operating a near surface repository for short-lived low and intermediate-level waste, SFR. The waste in SFR comprises operational and decommissioning waste from nuclear plants, industrial waste, research-related waste and medical waste. Spent nuclear fuel is currently stored in an interim facility while waiting for a license to construct a deep geological repository. The Swedish long-lived low and intermediate-level waste consists mainly of BWR control rods, reactor internals and legacy waste from early research in the Swedish nuclear programs. The current plan is to dispose of this waste in a separate deep geological repository, SFL, sometimes after 2045. Understanding of the rock properties is the basis for the design of the repository concepts. Swedish crystalline rock is mechanical stable and suitable for underground constructions. The Spent Fuel Repository is planned at approximately 500 meters depth in the rock at the Forsmark site. The host rock will keep the spent fuel isolated from human and near-surface environment. The rock will also provide the stable chemical and hydraulic conditions that make it possible to select suitable technical barriers to support the containment provided by the rock. A very long lasting canister is necessary to avoid release and transport of radionuclides through water conducting fractures in the rock. A canister designed for the Swedish rock, consists of a tight, 5 cm thick corrosion barrier of copper and a load-bearing insert of cast iron. To restrict the water flow around the canister and by that prevent fast corrosion, a bentonite buffer will surround the canister. Secondary, the bentonite buffer will retard a potential release by its strong sorption of radionuclides. The SFR repository is situated in

Disposal of radioactive waste in Swedish crystalline rocks

Energy Technology Data Exchange (ETDEWEB)

Greis Dahlberg, Christina; Wikberg, Peter [Svensk Kaernbraenslehantering AB, Stockholm (Sweden)

2015-07-01

SKB, Swedish Nuclear Fuel and Waste Management Company is tasked with managing Swedish nuclear and radioactive waste. Crystalline rock is the obvious alternative for deep geological disposal in Sweden. SKB is, since 1988, operating a near surface repository for short-lived low and intermediate-level waste, SFR. The waste in SFR comprises operational and decommissioning waste from nuclear plants, industrial waste, research-related waste and medical waste. Spent nuclear fuel is currently stored in an interim facility while waiting for a license to construct a deep geological repository. The Swedish long-lived low and intermediate-level waste consists mainly of BWR control rods, reactor internals and legacy waste from early research in the Swedish nuclear programs. The current plan is to dispose of this waste in a separate deep geological repository, SFL, sometimes after 2045. Understanding of the rock properties is the basis for the design of the repository concepts. Swedish crystalline rock is mechanical stable and suitable for underground constructions. The Spent Fuel Repository is planned at approximately 500 meters depth in the rock at the Forsmark site. The host rock will keep the spent fuel isolated from human and near-surface environment. The rock will also provide the stable chemical and hydraulic conditions that make it possible to select suitable technical barriers to support the containment provided by the rock. A very long lasting canister is necessary to avoid release and transport of radionuclides through water conducting fractures in the rock. A canister designed for the Swedish rock, consists of a tight, 5 cm thick corrosion barrier of copper and a load-bearing insert of cast iron. To restrict the water flow around the canister and by that prevent fast corrosion, a bentonite buffer will surround the canister. Secondary, the bentonite buffer will retard a potential release by its strong sorption of radionuclides. The SFR repository is situated in

Consistency analysis of network traffic repositories

NARCIS (Netherlands)

Lastdrager, Elmer; Lastdrager, E.E.H.; Pras, Aiko

Traffic repositories with TCP/IP header information are very important for network analysis. Researchers often assume that such repositories reliably represent all traffic that has been flowing over the network; little thoughts are made regarding the consistency of these repositories. Still, for

Sellafield repository design concept

International Nuclear Information System (INIS)

1998-01-01

Between 1989 and 1997, UK Nirex Ltd carried out a programme of investigations to evaluate the potential of a site adjacent to the BNFL Sellafield works to host a deep repository for the United Kingdom's intermediate-level and certain low-level radioactive waste. The programme of investigations was wound down following the decision in March 1997 to uphold the rejection of the Company's planning application for the Rock Characterisation Facility (RCF), an underground laboratory which would have allowed further investigations to confirm whether or not the site would be suitable. Since that time, the Company's efforts in relation to the Sellafield site have been directed towards documenting and publishing the work carried out. The design concept for a repository at Sellafield was developed in parallel with the site investigations through an iterative process as knowledge of the site and understanding of the repository system performance increased. This report documents the Sellafield repository design concept as it had been developed, from initial design considerations in 1991 up to the point when the RCF planning application was rejected. It shows, from the context of a project at that particular site, how much information and experience has been gained that will be applicable to the development of a deep waste repository at other potential sites

Influence analysis of Github repositories.

Science.gov (United States)

Hu, Yan; Zhang, Jun; Bai, Xiaomei; Yu, Shuo; Yang, Zhuo

2016-01-01

With the support of cloud computing techniques, social coding platforms have changed the style of software development. Github is now the most popular social coding platform and project hosting service. Software developers of various levels keep entering Github, and use Github to save their public and private software projects. The large amounts of software developers and software repositories on Github are posing new challenges to the world of software engineering. This paper tries to tackle one of the important problems: analyzing the importance and influence of Github repositories. We proposed a HITS based influence analysis on graphs that represent the star relationship between Github users and repositories. A weighted version of HITS is applied to the overall star graph, and generates a different set of top influential repositories other than the results from standard version of HITS algorithm. We also conduct the influential analysis on per-month star graph, and study the monthly influence ranking of top repositories.

Integrated management data system for radioactive waste repositories (SGI3R) - development of the inventory module

International Nuclear Information System (INIS)

Silva, Fabio; Tello, Cledola Cassia O. de

2011-01-01

In Brazil, CNEN is responsible for the intermediate and final storage of radioactive waste generated in the country. The CDTN/CNEN coordinates the RBMN Project for the implementation of the National Repository for disposal radioactive waste of low- and intermediate-level. The results of this Project should be presented so that all data being easily retrievable and useful for all institutions involved, including the regulators. To achieve this goal it was developed at the Waste Management Department - SEGRE/CDTN - a management database system, called 'Integrated Management System for the Management of Repository for Radioactive Waste' (SGI3R). The System consists of relational tables, forms and reports, preserving all available information, avoiding duplication of efforts, additional costs, and it will additionally give support to improve the management of RBMN Project. This paper presents a summary of this development with emphasis on the INVENTORY Module. The data from the inventory of disused sealed sources, which are stored in CDTN, were used to test the functionality of this module and of the SGI3R. These sources were categorized according to guidelines of the IAEA, and it was also presented how they should be safely managed over time. (author)

Stress-corrosion-cracking studies on candidate container alloys for the Tuff Repository

International Nuclear Information System (INIS)

Beavers, J.A.; Durr, C.L.

1992-05-01

Cortest Columbus Technologies, Inc. (CC Technologies) investigated the long-term performance of container materials used for high-level waste package as part of the information needed by the Nuclear Regulatory Commission (NRC) to assess the Department of Energy's application to construct to geologic repository for high-level radioactive waste. At the direction of the NRC, the program focused on the Tuff Repository. This report summarizes the results of Stress-Corrosion-Cracking (SCC) studies performed in Tasks 3, 5, and 7 of the program. Two test techniques were used; U-bend exposures and Slow-Strain-Rate (SSR) tests. The testing was performed on two copper-base alloys (Alloy CDA 102 and Alloy CDA 175) and two Fe-Cr-Ni alloys (Alloy 304L and Alloy 825) in simulated J-13 groundwater and other simulated solutions for the Tuff Repository. These solutions were designed to simulate the effects of concentration and irradiation on the groundwater composition. All SCC testing on the Fe-Cr-Ni Alloys was performed on solution-annealed specimens and thus issues such as the effect of sensitization on SCC were not addressed

The Yucca Mountain Repository - Too Little, Too Late

International Nuclear Information System (INIS)

Eriksson, L.G.; Pentz, D.L.

2009-01-01

In 2008, the U.S. Department of Energy (US DOE) announced that the nation's first (and only pursued) deep geological disposal system (repository) for 70,000 metric tonnes of spent nuclear fuel (SNF) and other high-level radioactive waste (HLW) at the Yucca Mountain (YM) site in Nevada would: 1. Not be able to accommodate the projected stockpile of utility-generated SNF beyond 2010. 2. Open no earlier than in 2020, i.e., more than 22 years behind the statutory-mandated opening date. In the meantime, the US DOE is legally obligated to compensate the utilities from January 31, 1998, until it takes title to the utilities' SNF. In 2005 when the YM SNF repository was projected to open in 2010, the utilities estimated that, depending upon how close to 2010 the YM repository opened, the 'breach-of-contract' compensation could be in the range of between 100 billion and 300 billion U.S. dollars ($300 B), which would exceed the 2008 projected life-cycle cost of $96 B for the YM repository. It thus seems appropriate to look beyond the YM repository and call upon the U.S. Congress to promptly act and open new avenues allowing the US DOE to more timely and cost-effectively take title to both existing and pending SNF the current fleet of 104 reactors will generate through the next 60 years. Options for SNF arising from an additional 50 reactors should also be provided. Based on our more than 60 years of combined involvement in nuclear waste management in the USA and abroad, we submit the following industrial-scale-proven, repository-related, nuclear-waste-management and disposition solutions for prompt Congressional consideration and action: 1. An increase in the disposal capacity (and perhaps mission) of the YM repository. 2. Prompt establishment of at least one large federal monitored retrievable storage (MRS) facility for utility-generated SNF. 3. Continued research in reprocessing options of existing and pending SNF with defined milestones. 4. Resurrection of a second

Safety case approach for a KBS-3 type repository in crystalline rock

International Nuclear Information System (INIS)

Pastina, Barbara; Lehikoinen, Jarmo; Puigdomenech, Ignasi

2012-01-01

Barbara Pastina of Saanio and Riekkola described the approach to considering cementitious materials in a safety case for a KBS-3 repository in Finland. In this concept, cements will be used predominantly as tunnel plugs and seals. Part of the Finnish approach has involved identifying the cement-related FEPs. For example, FEPs representing the effects of cement on spent fuel, on the canister and on radionuclide transport include: - Fuel matrix dissolution at high pH. - Copper corrosion at high pH. - Radionuclide speciation and solubility at high pH. - Radionuclide sorption and diffusion at high pH. - Radionuclide transport due to organic materials (e.g. super-plasticisers). - Colloid formation at a high pH plume front. FEPs representing the effects of cement on bentonite in the buffer and backfill include: - Potential changes in swelling pressure due to mass loss, decrease in clay density, and precipitation of secondary minerals. - Potential cracking and increase of hydraulic conductivity due to cementation. - Increase of the cation exchange capacity due to the loss of silica from the montmorillonite structure. Amongst the cement-related FEPs, the main concerns are related to effects on the performance of the bentonite buffer. Cement-bentonite interactions are complex, there are few experimental data, and there are significant modelling uncertainties (e.g. limited knowledge about the reactions that may occur and their rates, and the effects of temperature). Accepting the existence of various uncertainties, preliminary modelling studies performed using the TOUGHREACT code illustrate the potential for porosity reduction and clogging of porosity in bentonite affected by cementitious pore waters. The modelling also suggests that that the high pH of the pore waters moving from the cementitious materials into the bentonite may be rapidly lowered as a result of reactions with the bentonite close to the cement-bentonite interface. Taking account of the various research and

Engineering studies: high-level radioactive waste repositories task 3 - review of underground handling and emplacement. 1. Executive summary

Energy Technology Data Exchange (ETDEWEB)

1981-02-01

The report reviews proposals for transport, handling and emplacement of high-level radioactive waste in an underground repository with particular reference to: waste block size and configuration; self-shielded or partially-shielded block; stages of disposal; transport by road/rail to repository site; handling techniques within repository; emplacement in vertical holes or horizontal tunnels; repository access by adit, incline or shaft; conventional and radiological safety; costs; and major areas of uncertainty requiring research or development. In carrying out this programme due attention was given to work already carried out both in the U.K. and overseas and where appropriate comparisons with this work have been made to substantiate and explain the observations made in this report. The examination and use of this previous work however has been confined to those proposals which were considered capable of meeting the basic design criterion for a U.K. based repository, that the maximum temperature achieved by the host rock should not exceed 100/sup 0/C.

CRIS and Institutional Repositories

Directory of Open Access Journals (Sweden)

A Asserson

2010-04-01

Full Text Available CRIS (Current Research Information Systems provide researchers, research managers, innovators, and others with a view over the research activity of a domain. IRs (institutional repositories provide a mechanism for an organisation to showcase through OA (open access its intellectual property. Increasingly, organizations are mandating that their employed researchers deposit peer-reviewed published material in the IR. Research funders are increasingly mandating that publications be deposited in an open access repository: some mandate a central (or subject-based repository, some an IR. In parallel, publishers are offering OA but replacing subscription-based access with author (or author institution payment for publishing. However, many OA repositories have metadata based on DC (Dublin Core which is inadequate; a CERIF (Common-European Research Information Format CRIS provides metadata describing publications with formal syntax and declared semantics thus facilitating interoperation or homogeneous access over heterogeneous sources. The formality is essential for research output metrics, which are increasingly being used to determine future funding for research organizations.

National radioactive waste repository site selection study. Phase 2. A report on public comment

International Nuclear Information System (INIS)

1995-11-01

Agreement was reached in principle between State/Territory and the Commonwealth of Australia Governments that a suitable site for a radioactive wastes repository must be found. The discussion papers resulting from the Phase 1 and Phase 2 of the site selection study were released for public comment. The national repository will be for disposal of low level and short-lived intermediate level radioactive wastes streaming from the medical, research and industrial use of radioisotopes in Australia. The purpose of this report is to summarise and respond in general terms to comment received on the discussion paper -Phase 2 of the study. Forty five submissions were received. Of these: 18 supported the Phase 2 study approach and the concept of a national repository; 13 did not state a clear position but either requested more information or provided constructive comment on the siting process; 7 supported the site selection approach and the repository concept but suggested that the repository should not be sited in a particular area; 3 opposed the siting of the repository in their vicinity but not necessarily the repository concept and site selection approach; 4 opposed the concept of a national repository. This compares with 124 submissions on Phase 1 of the study, of which 57 opposed the national repository concept (52 of these were from letters elicited by Greenpeace) and 48 supported the establishment of a national repository and the site selection approach proposed. 3 figs

Effect of reprocessing and recycling on the geologic repository dose rate : status

International Nuclear Information System (INIS)

Morris, E. E.; Nutt, W. M.; Wigeland, R. A.; Nuclear Engineering Division

2007-01-01

Two simplified repository performance assessment models are used to assess the impact of modeling changes in on conclusions regarding the impact of various reprocessing and recycling strategies. Waste streams from a pressurized water reactor (PWR) and a preliminary design for an advanced burner test reactor (ABTR) are used for this study of the effects on the estimated dose rate resulting from the release of radionuclides from a geologic repository. Calculations for the PWR make use of radionuclide discharge vectors for an assumed burnup of 51 GWd/MTIHM[1]. The repository is assumed to be filled with 70,000 MT of the spent fuel or with a glass waste form containing the radionuclides from 70,000 MT of spent PWR fuel. For the ABTR, the radionuclide inventory discharged at the end of an equilibrium cycle[2] is processed into a glass waste form for repository disposal, assuming actinide recovery efficiencies ranging from 90% to 99.99%. The recovered actinides are returned to the reactor. To compare with the PWR results, the repository is assumed to be filled with ABTR waste from fuel that has generated the same amount of thermal energy as 70,000 MT of the PWR fuel. The two repository performance assessment models, the first a simplified model[3] (SSR) based on the site recommendation model used by the Yucca Mountain Project (YMP)[4], and the second an updated simplified model (US) based on more recent modeling developments by the YMP are implemented in the computer simulation code GoldSim[5]. The updated model is based on a simplified model used to conduct a sensitivity analysis to evaluate factors that potentially influence performance of a repository at Yucca Mountain over the period of peak dose[6]. Factors that have either a minor or no effect on the peak dose either were not included in that simplified model or were included in a bounding representation. In the US model, enhancements were made to include some factors that have an effect on the dose occurring

Microbiological activities in a shallow-ground repository with cementitious wasteform

International Nuclear Information System (INIS)

Varlakova, G.A.; Dyakonova, A.T.; Netrusov, A.I.; Ojovan, M.I.

2012-01-01

Cementitious wasteform with immobilised nuclear power plant operational radioactive waste disposed in a near surface testing repository for about 20 years have been analysed for microbiological activities. Clean cultures were selected from the main metabolic groups expected within repository environment e.g. anaerobic de-nitrifying, fermenting, sulphur-reducing, iron-reducing, and oxidizing, thio-bacterium and mushrooms. Microbiological species were identified within cementitious wasteform, in the clayey soil near the wasteform and in the contacting water. The most populated medium was the soil with microbial populations Bacillus, Pseudomonas and Micrococcus, and densities of populations up to 3.6*10 5 colony/g. Microbial populations of generic type Bacillus, Pseudomonas, Rhodococcus, Alcaligenes, Micrococcus, Mycobacterium, and Arthrobacter were identified within cementitious wasteform. Populations of Arthrobacter, Pseudomonas, Alcaligenes, Rhodococcus, Bacillus and Flavobacterium were identified in the water samples contacting the cementitious wasteform. Microbiological species identified are potential destructors of cementitious wasteform and containers. (authors)

Nuclear waste repository design and construction

International Nuclear Information System (INIS)

Bohlke, B.M.; Monsees, J.E.

1987-01-01

Extensive underground excavation will be required for construction of a mined geologic repository for nuclear waste. Hundreds of thousands of feet of drift will be required based on the conceptual layout design for each candidate nuclear waste repository. Comparison of boring and blasting excavation methods are discussed, as are special design and construction requirements (e.g., quality assurance procedures and performance assessment) for the nuclear waste repository. Comparisons are made between boring and blasting construction methods for the repository designs proposed for salt, volcanic tuff, and basalt

Logistics Modeling of Emplacement Rate and Duration of Operations for Generic Geologic Repository Concepts

Energy Technology Data Exchange (ETDEWEB)

Kalinina, Elena Arkadievna; Hardin, Ernest

2015-11-01

This study identified potential geologic repository concepts for disposal of spent nuclear fuel (SNF) and (2) evaluated the achievable repository waste emplacement rate and the time required to complete the disposal for these concepts. Total repository capacity is assumed to be approximately 140,000 MT of spent fuel. The results of this study provide an important input for the rough-order-of-magnitude (ROM) disposal cost analysis. The disposal concepts cover three major categories of host geologic media: crystalline or hard rock, salt, and argillaceous rock. Four waste package sizes are considered: 4PWR/9BWR; 12PWR/21BWR; 21PWR/44BWR, and dual purpose canisters (DPCs). The DPC concepts assume that the existing canisters will be sealed into disposal overpacks for direct disposal. Each concept assumes one of the following emplacement power limits for either emplacement or repository closure: 1.7 kW; 2.2 kW; 5.5 kW; 10 kW; 11.5 kW, and 18 kW.

Logistics Modeling of Emplacement Rate and Duration of Operations for Generic Geologic Repository Concepts

International Nuclear Information System (INIS)

Kalinina, Elena Arkadievna; Hardin, Ernest

2015-01-01

This study identified potential geologic repository concepts for disposal of spent nuclear fuel (SNF) and (2) evaluated the achievable repository waste emplacement rate and the time required to complete the disposal for these concepts. Total repository capacity is assumed to be approximately 140,000 MT of spent fuel. The results of this study provide an important input for the rough-order-of-magnitude (ROM) disposal cost analysis. The disposal concepts cover three major categories of host geologic media: crystalline or hard rock, salt, and argillaceous rock. Four waste package sizes are considered: 4PWR/9BWR; 12PWR/21BWR; 21PWR/44BWR, and dual purpose canisters (DPCs). The DPC concepts assume that the existing canisters will be sealed into disposal overpacks for direct disposal. Each concept assumes one of the following emplacement power limits for either emplacement or repository closure: 1.7 kW; 2.2 kW; 5.5 kW; 10 kW; 11.5 kW, and 18 kW.

Production of polyhydroxyalkanoates (PHA) by bacterial consortium from excess sludge fermentation liquid at laboratory and pilot scales.

Science.gov (United States)

Jia, Qianqian; Xiong, Huilei; Wang, Hui; Shi, Hanchang; Sheng, Xinying; Sun, Run; Chen, Guoqiang

2014-11-01

The generation of polyhydroxyalkanoates (PHA) from excess sludge fermentation liquid (SFL) was studied at lab and pilot scale. A PHA-accumulated bacterial consortium (S-150) was isolated from activated sludge using simulated SFL (S-SFL) contained high concentration volatile fatty acids (VFA) and nitrogen. The maximal PHA content accounted for 59.18% in S-SFL and dropped to 23.47% in actual SFL (L-SFL) of the dry cell weight (DCW) at lab scale. The pilot-scale integrated system comprised an anaerobic fermentation reactor (AFR), a ceramic membrane system (CMS) and a PHA production bio-reactor (PHAR). The PHA content from pilot-scale SFL (P-SFL) finally reached to 59.47% DCW with the maximal PHA yield coefficient (YP/S) of 0.17 g PHA/g COD. The results indicated that VFA-containing SFL was suitable for PHA production. The adverse impact of excess nitrogen and non-VFAs in SFL might be eliminated by pilot-scale domestication, which might resulted in community structure optimization and substrate selective ability improvement of S-150. Copyright © 2014 Elsevier Ltd. All rights reserved.

Information base for waste repository design. Volume 3. Waste/rock interactions

International Nuclear Information System (INIS)

Koplick, C.M.; Pentz, D.L.; Oston, S.G.; Talbot, R.

1979-01-01

This report describes the important effects resulting from interaction between radioactive waste and the rock in a nuclear waste repository. The state of the art in predicting waste/rock interactions is summarized. Where possible, independent numerical calculations have been performed. Recommendations are made pointing out areas which require additional research

Final repository for spent nuclear fuel. Underground design Simpevarp, Layout D1

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-04-15

4,500. However, in order to accommodate the uncertainty entailed by possible future extensions of the operating periods of the nuclear power plants, the deposition area should, according to SKB, be designed for a capacity of 6,000 canisters. The strategy for answering the question 'Can the repository be accommodated within the assigned area' is to build an appropriate risk model. The most important results obtained from the calculations are: There is a very high (> 99%) probability that 6,000 canisters can be accommodated within the studied area at a depth of 500 m. Total deposition hole loss is 13% on average. The average area needed to host the 6,000 canisters at a depth of 500 m is 3.5 km{sup 2}, with a range of 2-5.6 km{sup 2}. This is within the limits of what was found in the layout studies in Chapter 5, where an area of 4.5 km{sup 2} was found to be needed. It should be noted that the layout study was not optimized. The three factors that have the greatest impact on uncertainty are: Hole spacing due to thermal properties; Loss percentage due to fractures with R > 100 m; and Dip of external boundary deformation zone.

SCOAP3 where libraries, scientists and publishers meet repositories, peer-reviewed journals and Open Access

CERN Document Server

Mele, Salvatore

2009-01-01

The inexorable growth of both Open Access and library budgetary concerns are calling for innovation in scholarly communication. The field of High-Energy Physics has decades of tradition in cross-border collaboration and Open Access and is now proposing an innovative model for scientific publishing: SCOAP3. This article presents a synopsis of this opportunity for libraries, scientists and publishers to invent a new future at the interface of Open Access, peer-reviewed journals and repositories.

National radioactive wasterRepository Mochovce

International Nuclear Information System (INIS)

2000-01-01

In this leaflet the scheme of the Mochovce National radioactive waste repository for the Slovak Republic is presented. The National radioactive waste repository in Mochovce is a surface type storage facility. It is intended for final disposal of solid and solidified low and intermediate radioactive waste produced during the operation of nuclear power plants and institutions located within the territory of the Slovak Republic. The Repository site is situated about 2 km northwest to the Mochovce NPP

CCDC 1440039: Experimental Crystal Structure Determination : catena-[(mu-biphenyl-3,3',5,5'-tetracarboxylato)-bis(mu-hydroxo)-di-indium dideuterium

KAUST Repository

Savage, Mathew; da Silva, Ivan; Johnson, Mark; Carter, Joseph H.; Newby, Ruth; Suetin, Mikhail; Besley, Elena; Manuel, Pascal; Rudić, Svemir; Fitch, Andrew N.; Murray, Claire; David, William I. F.; Yang, Sihai; Schrö der, Martin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

CCDC 1043466: Experimental Crystal Structure Determination : catena-[(mu-biphenyl-3,3',5,5'-tetracarboxylato)-bis(mu-hydroxo)-di-indium perdeuteromethane

KAUST Repository

Savage, Mathew; da Silva, Ivan; Johnson, Mark; Carter, Joseph H.; Newby, Ruth; Suetin, Mikhail; Besley, Elena; Manuel, Pascal; Rudić, Svemir; Fitch, Andrew N.; Murray, Claire; David, William I. F.; Yang, Sihai; Schrö der, Martin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

CCDC 1043467: Experimental Crystal Structure Determination : catena-[(mu-biphenyl-3,3',5,5'-tetracarboxylato)-bis(mu-hydroxo)-di-indium perdeuteromethane

KAUST Repository

Savage, Mathew; da Silva, Ivan; Johnson, Mark; Carter, Joseph H.; Newby, Ruth; Suetin, Mikhail; Besley, Elena; Manuel, Pascal; Rudić, Svemir; Fitch, Andrew N.; Murray, Claire; David, William I. F.; Yang, Sihai; Schrö der, Martin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

CCDC 1440041: Experimental Crystal Structure Determination : catena-[(mu-biphenyl-3,3',5,5'-tetracarboxylato)-bis(mu-hydroxo)-di-indium dideuterium

KAUST Repository

Savage, Mathew; da Silva, Ivan; Johnson, Mark; Carter, Joseph H.; Newby, Ruth; Suetin, Mikhail; Besley, Elena; Manuel, Pascal; Rudić, Svemir; Fitch, Andrew N.; Murray, Claire; David, William I. F.; Yang, Sihai; Schrö der, Martin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

CCDC 1440038: Experimental Crystal Structure Determination : catena-[(mu-biphenyl-3,3',5,5'-tetracarboxylato)-bis(mu-hydroxo)-di-indium dideuterium

KAUST Repository

Savage, Mathew; da Silva, Ivan; Johnson, Mark; Carter, Joseph H.; Newby, Ruth; Suetin, Mikhail; Besley, Elena; Manuel, Pascal; Rudić, Svemir; Fitch, Andrew N.; Murray, Claire; David, William I. F.; Yang, Sihai; Schrö der, Martin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

CCDC 1440040: Experimental Crystal Structure Determination : catena-[(mu-biphenyl-3,3',5,5'-tetracarboxylato)-bis(mu-hydroxo)-di-indium dideuterium

KAUST Repository

Savage, Mathew; da Silva, Ivan; Johnson, Mark; Carter, Joseph H.; Newby, Ruth; Suetin, Mikhail; Besley, Elena; Manuel, Pascal; Rudić, Svemir; Fitch, Andrew N.; Murray, Claire; David, William I. F.; Yang, Sihai; Schrö der, Martin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

CCDC 1440042: Experimental Crystal Structure Determination : catena-[(mu-biphenyl-3,3',5,5'-tetracarboxylato)-bis(mu-hydroxo)-di-indium dideuterium

KAUST Repository

Savage, Mathew; da Silva, Ivan; Johnson, Mark; Carter, Joseph H.; Newby, Ruth; Suetin, Mikhail; Besley, Elena; Manuel, Pascal; Rudić, Svemir; Fitch, Andrew N.; Murray, Claire; David, William I. F.; Yang, Sihai; Schrö der, Martin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

CCDC 1043465: Experimental Crystal Structure Determination : catena-[(mu-biphenyl-3,3',5,5'-tetracarboxylato)-bis(mu-hydroxo)-di-indium perdeuteromethane

KAUST Repository

Savage, Mathew; da Silva, Ivan; Johnson, Mark; Carter, Joseph H.; Newby, Ruth; Suetin, Mikhail; Besley, Elena; Manuel, Pascal; Rudić, Svemir; Fitch, Andrew N.; Murray, Claire; David, William I. F.; Yang, Sihai; Schrö der, Martin

2016-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

RIP Input Tables From WAPDEG for LA Design Selection: Repository Horizon Elevation - 2-Level AML 50% and Near Maximum

International Nuclear Information System (INIS)

B.E. Bullard

1999-01-01

The purpose of this calculation is to document the WAPDEG version 3.09 (CRWMS M and O 1998b). Software Routine Report for WAPDEG (Version 3.09) simulations used to analyze waste package degradation and failure under the repository exposure conditions characterized by a two-tier thermal loading repository design. Also documented is the post-processing of these results into tables of waste-package-degradation-time histories suitable for use as input into the Integrated Probabilistic Simulator for Environmental Systems (RIP) version 5.19.01 (Golder Associates 1998) computer program. Specifically, the WAPDEG simulations discussed in this calculation correspond to waste package emplacement conditions (repository environment and design) as defined in the Total System Performance Assessment-Viability Assessment (CRWMS M and O 1998a). Total System Performance Assessment-Viability Assessment (TSPA-VA) Analyses Technical Basis Document--Chapter 5, Waste Package Degradation Modeling And Abstraction, pp. 5-27 to 5-29, with the exception that a two-tier thermal loading design feature as specified in the License Application Design Selection (LADS) study was analyzed. The particular design feature evaluated in this report is a modification of the repository horizon elevation and layout within the Topopah Springs Member of Yucca Mountain. Specifically, the modification consists of adding a second level, 50-m above the base case repository layout. Two options were considered, representing two variations in thermal loading. In Design Feature 25e (designated DF25e), each level has an Areal Mass Loading (AML) of 42.5 MTU/acre (i.e., half the VA base case). In Design Feature 25f (designated DF25), each level has an AML of 64MTU/acre. As a result of the change in waste package placement relative to the TSPA-VA base-case design, different temperature and relative humidity time histories at the waste package surface are calculated (input to the WAPDEG simulations), and consequently

Biological Web Service Repositories Review.

Science.gov (United States)

Urdidiales-Nieto, David; Navas-Delgado, Ismael; Aldana-Montes, José F

2017-05-01

Web services play a key role in bioinformatics enabling the integration of database access and analysis of algorithms. However, Web service repositories do not usually publish information on the changes made to their registered Web services. Dynamism is directly related to the changes in the repositories (services registered or unregistered) and at service level (annotation changes). Thus, users, software clients or workflow based approaches lack enough relevant information to decide when they should review or re-execute a Web service or workflow to get updated or improved results. The dynamism of the repository could be a measure for workflow developers to re-check service availability and annotation changes in the services of interest to them. This paper presents a review on the most well-known Web service repositories in the life sciences including an analysis of their dynamism. Freshness is introduced in this paper, and has been used as the measure for the dynamism of these repositories. © 2017 The Authors. Published by Wiley-VCH Verlag GmbH & Co. KGaA.

Gamma radiation and radon concentration levels at the radioactive waste repositories 'Richard' and 'Bratrstvi'

International Nuclear Information System (INIS)

Berka, Z.; Sabol, J.; Janu, M.

1998-01-01

Owing to the fact that cosmic rays are shielded off, the photon equivalent dose rates in the corridors of the Richard repository are usually slightly lower than outside. However, in points close to barrels containing radioactive waste, the dose rates can reach values as high as tens of μSv/h. Because of high concentrations of natural radionuclides, the dose rates in the Bratrstvi repository is generally considerably higher, as much as 5 times the normal background value. Radon concentrations exhibit specific time variations which are modified by ventilation. Where ventilation is poor or absent, the radon concentrations are extremely high, viz. up to 30 and 300 kBq/m 3 in the Richard and Bratrstvi repositories, respectively. Personal exposure of workers depend on the total time spent underground and on the ventilation rate. While the contribution from photons can be kept below the relevant limits, the radon-related doses may be significant and even exceed the professional limits if no precautions are taken. (P.A.)

IAEA safeguards for geological repositories

International Nuclear Information System (INIS)

Moran, B.W.

2005-01-01

In September. 1988, the IAEA held its first formal meeting on the safeguards requirements for the final disposal of spent fuel and nuclear material-bearing waste. The consensus recommendation of the 43 participants from 18 countries at this Advisory Group Meeting was that safeguards should not terminate of spent fuel even after emplacement in, and closure of, a geologic repository.' As a result of this recommendation, the IAEA initiated a series of consultants' meetings and the SAGOR Programme (Programme for the Development of Safeguards for the Final Disposal of Spent Fuel in Geologic Repositories) to develop an approach that would permit IAEA safeguards to verify the non-diversion of spent fuel from a geologic repository. At the end of this process, in December 1997, a second Advisory Group Meeting, endorsed the generic safeguards approach developed by the SAGOR Programme. Using the SAGOR Programme results and consultants' meeting recommendations, the IAEA Department of Safeguards issued a safeguards policy paper stating the requirements for IAEA safeguards at geologic repositories. Following approval of the safeguards policy and the generic safeguards approach, the Geologic Repository Safeguards Experts Group was established to make recommendations on implementing the safeguards approach. This experts' group is currently making recommendations to the IAEA regarding the safeguards activities to be conducted with respect to Finland's repository programme. (author)

Thermal analysis of a heat generating waste repository on the seabed

International Nuclear Information System (INIS)

Maynard, M.J.; Butler, T.P.; Firmin, G.H.

1987-02-01

The time dependent thermal behaviour of a repository containing heat generating waste has been investigated during loading, transport, and subsequent emplacement on the seabed. Variations of less than 1 0 C in the sealed repository water temperature were calculated to be sufficient to create adequate water circulation. Conservative 1-D analyses were used to estimate a maximum repository water temperature of 256 0 C, occuring about 3 years after emplacement. The temperature distributions within the heat generating waste canisters and grouted titanium tubes have been calculated using 2-D axisymmetric finite element models. Peak temperatures at the waste centre-line were found to be approx. 40 0 C above the repository water temperature. The sensitivity of the results to assumed thermal parameters and to the effect of sediment accumulation have been considered. The possibility and consequences of steam formation within a vented repository have been discussed. (author)

Uncertainties in sealing a nuclear waste repository in partially saturated tuff

International Nuclear Information System (INIS)

Tillerson, J.R.; Fernandez, J.A.; Hinkebein, T.E.

1989-01-01

Sealing a nuclear waste repository in partially saturated tuff presents unique challenges to assuring performance of sealing components. Design and performance of components for sealing shafts, ramps, drifts, and exploratory boreholes depend on specific features of both the repository design and the site; of particular importance is the hydrologic environment in the unsaturated zone, including the role of fracture flow. Repository design features important to sealing of a repository include the size and location of shaft and ramp accesses, excavation methods, and the underground layout features such as grade (drainage direction) and location relative to geologic structure. Uncertainties about seal components relate to the postclosure environment for the seals, the emplacement methods, the material properties, and the potential performance of the components. An approach has been developed to reduce uncertainties and to increase confidence in seal performance; it includes gathering extensive site characterization data, establishing conservative design requirements, testing seal components in laboratory and field environments, and refining designs of both the seals and the repository before seals are installed. 9 refs., 5 figs., 2 tabs

Geological study of radioactive waste repositories

International Nuclear Information System (INIS)

Oyama, Takahiro; Kitano, Koichi

1987-01-01

The investigation of the stability and the barrier efficiency of the deep underground radioactive waste repositories become a subject of great concern. The purpose of this paper is to gather informations on the geology, engineering geology and hydrogeology in deep galleries in Japan. Conclusion can be summarised as follows: (1) The geological structure of deep underground is complicated. (2) Stress in deep underground is greatly affected by crustal movement. (3) Rock-burst phenomena occur in the deep underground excavations. (4) In spite of deep underground, water occasionally gush out from the fractured zone of rock mass. These conclusion will be useful for feasibility study of underground waste disposal and repositories in Japan. (author)

Repository site characterization

International Nuclear Information System (INIS)

Voss, J.W.; Pentz, D.L.

1987-01-01

The characterization of candidate repository sites has a number of programmatic objectives. Principal among these is the acquisition of data: a) to determine the suitability of a site relative to the DOE repository siting guidelines, b) to support model development and calculations to determine the suitability of a site relative to the post closure criteria of the NRC and EPA, c) to support the design of a disposal system, including the waste package and the engineered barrier system, as well as the shafts and underground openings of the repository. In meeting the gaols of site characterization, the authors have an obligation to conduct their investigations within an appropriate budget and schedule. This mandates that a well-constructed and systematic plan for field investigations be developed. Such a plan must fully account for the mechanisms which will control the radiologic performance in the repository. The plan must also flexibly and dynamically respond to the results of each step of field investigation, responding to the spatial variability of earth as well as to enhanced understandings of the performance of the disposal system. Such a plan must ensure that sufficient data are available to support the necessary probabilistic calculations of performance. This paper explores the planning for field data acquisition with specific reference to requirements for demonstrations of the acceptable performance for disposal systems

CCDC 1003817: Experimental Crystal Structure Determination : 6,13-bis(4-nonylphenyl)[1]benzothieno[2''',3''':4'',5'']thieno[2'',3'':4',5']pentaleno[2',1':4,5]thieno[3,2-b][1]benzothiophene

KAUST Repository

Dai, Gaole; Chang, Jingjing; Shi, Xueliang; Zhang, Wenhua; Zheng, Bin; Huang, Kuo-Wei; Chi, Chunyan

2014-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

CCDC 1047859: Experimental Crystal Structure Determination : catena-[bis(2-aminopropan-1-aminium) (mu-3,5-diselanyl-3-(selanyl)-5-(selanyl)-1,2,4,3,5-triselenadigermolanato)-bis(propane-1,2-diamine)-selanyl-dimanganese

KAUST Repository

Zhang, Guodong

2015-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Gas generation in repositories

International Nuclear Information System (INIS)

Biddle, P.; Rees, J.H.; McGahan, D.; Rushbrook, P.E.

1987-09-01

The nature and quantities of gases likely to be produced by various processes in repositories for low level and intermediate level radioactive wastes are examined in this preliminary study. Many simplifying assumptions are made where published or experimental data is unavailable. The corrosion of the canisters and metallic components in wastes is likely to be the major gas production process in both types of repository. A significant contribution from microbiological activity is expected to occur in low level repositories, predominantly where no cement grouting of the cans has been carried out. A number of areas for further research, required before a more comprehensive study could be carried out, have been identified. (author)

An open data repository and a data processing software toolset of an equivalent Nordic grid model matched to historical electricity market data

Directory of Open Access Journals (Sweden)

Luigi Vanfretti

2017-04-01

This Nordic 44 equivalent model was also used in iTesla project (iTesla [3] to carry out simulations within a dynamic security assessment toolset (iTesla, 2016 [4], and has been further enhanced during the ITEA3 OpenCPS project (iTEA3 [5]. The raw, processed data and output models utilized within the iTesla platform (iTesla, 2016 [4] are also available in the repository. The CIM and Modelica snapshots of the “Nordic 44” model for the year 2015 are available in a Zenodo repository.

Nuclear waste repository siting

International Nuclear Information System (INIS)

Soloman, B.D.; Cameron, D.M.

1987-01-01

This paper discusses the geopolitics of nuclear waste disposal in the USA. Constitutional choice and social equity perspectives are used to argue for a more open and just repository siting program. The authors assert that every potential repository site inevitably contains geologic, environmental or other imperfections and that the political process is the correct one for determining sites selected

Granite-repository - geochemical environment

International Nuclear Information System (INIS)

1979-04-01

Some geochemical data of importance for a radioactive waste repository in hard rock are reviewed. The ground water composition at depth is assessed. The ground water chemistry in the vicinity of uranium ores is discussed. The redox system in Swedish bedrock is described. Influences of extreme climatic changes and of repository mining and construction are also evaluated

Workshop: Creating Your Institutional Research Repository

KAUST Repository

Grenz, Daryl M.

2016-11-08

In 2002, the Scholarly Publishing and Academic Resources Coalition (SPARC) proposed the concept of an institutional repository to simultaneously disrupt and enhance the state of scholarly communications in the academic world. Thirteen years later, thousands of universities and other institutions have answered this call, but many more have not due to gaps in budgets, awareness and, most of all, practical guidance on creating an institutional repository. This workshop provides you with an essential primer on what it takes to establish a fully-functioning institutional repository. Every aspect of the process will be covered, including policies, procedures, staffing guidelines, workflows and repository technologies.

Improvement of storage conditions and closure of the radioactive waste repository - Rozan

International Nuclear Information System (INIS)

Dutton, L.M.C.; Pacey, N.R.; Buckley, M.J.; Thomson, J.G.; Miller, W.; Barraclough, I.; Tomczak, W.; Mitrega, J.; Smietanski, L.

2005-01-01

The Rozan repository is a near-surface repository on the site of an ex-military fort, operated by Radioactive Waste Management Plant (RWMP). Solid or encapsulated waste is consigned to the repository. Low- and medium-activity waste produced in Poland is collected, processed, solidified and prepared for disposal at the Swierk facility. The waste is currently stored or disposed of within the fort structures, these have robust concrete walls, that provide both shielding and containment. The project, funded by the European Commission through the Phare Programme, aimed to improve the storage conditions and determine a strategy for closure achieving two key results; Stakeholder agreement to a strategy for the management and closure of the repository, and; Approval by the National Atomic Energy Agency of the safety case for the selected strategy. The strategy was selected using a multi-criteria analysis methodology at workshops that involved experts, regulators and other stakeholders. The selected strategy proposed that the waste in Facilities 3A and 8 should be left in situ and these facilities should continue to operate until the repository is closed. The waste in Rooms K7 to K9 of Facility 1 and in Facilities 2 and 3 should be retrieved, assayed, treated and packaged prior to redisposal. The short-lived waste that is retrieved from Rooms K7 to K9 of Facility 1 and Facilities 2 and 3 should be emplaced in Facility 8 subject to acceptance by the NAEA of the dose of 0.3mSv/y that might occur at long times in the future from a very unlikely scenario. When operations at the repository end, Facilities 3A and 8 should be covered with a multi-layer cap. Following selection of the strategy, assessment work was undertaken to support the production of the suite of safety cases. (author)

LIFE Materials: Fuel Cycle and Repository Volume 11

Energy Technology Data Exchange (ETDEWEB)

Shaw, H; Blink, J A

2008-12-12

The fusion-fission LIFE engine concept provides a path to a sustainable energy future based on safe, carbon-free nuclear power with minimal nuclear waste. The LIFE design ultimately offers many advantages over current and proposed nuclear energy technologies, and could well lead to a true worldwide nuclear energy renaissance. When compared with existing and other proposed future nuclear reactor designs, the LIFE engine exceeds alternatives in the most important measures of proliferation resistance and waste minimization. The engine needs no refueling during its lifetime. It requires no removal of fuel or fissile material generated in the LIFE engine. It leaves no weapons-attractive material at the end of life. Although there is certainly a need for additional work, all indications are that the 'back end' of the fuel cycle does not to raise any 'showstopper' issues for LIFE. Indeed, the LIFE concept has numerous benefits: (1) Per unit of electricity generated, LIFE engines would generate 20-30 times less waste (in terms of mass of heavy metal) requiring disposal in a HLW repository than does the current once-through fuel cycle. (2) Although there may be advanced fuel cycles that can compete with LIFE's low mass flow of heavy metal, all such systems require reprocessing, with attendant proliferation concerns; LIFE engines can do this without enrichment or reprocessing. Moreover, none of the advanced fuel cycles can match the low transuranic content of LIFE waste. (3) The specific thermal power of LIFE waste is initially higher than that of spent LWR fuel. Nevertheless, this higher thermal load can be managed using appropriate engineering features during an interim storage period, and could be accommodated in a Yucca-Mountain-like repository by appropriate 'staging' of the emplacement of waste packages during the operational period of the repository. The planned ventilation rates for Yucca Mountain would be sufficient for LIFE waste

LIFE Materials: Fuel Cycle and Repository Volume 11

International Nuclear Information System (INIS)

Shaw, H.; Blink, J.A.

2008-01-01

The fusion-fission LIFE engine concept provides a path to a sustainable energy future based on safe, carbon-free nuclear power with minimal nuclear waste. The LIFE design ultimately offers many advantages over current and proposed nuclear energy technologies, and could well lead to a true worldwide nuclear energy renaissance. When compared with existing and other proposed future nuclear reactor designs, the LIFE engine exceeds alternatives in the most important measures of proliferation resistance and waste minimization. The engine needs no refueling during its lifetime. It requires no removal of fuel or fissile material generated in the LIFE engine. It leaves no weapons-attractive material at the end of life. Although there is certainly a need for additional work, all indications are that the 'back end' of the fuel cycle does not to raise any 'showstopper' issues for LIFE. Indeed, the LIFE concept has numerous benefits: (1) Per unit of electricity generated, LIFE engines would generate 20-30 times less waste (in terms of mass of heavy metal) requiring disposal in a HLW repository than does the current once-through fuel cycle. (2) Although there may be advanced fuel cycles that can compete with LIFE's low mass flow of heavy metal, all such systems require reprocessing, with attendant proliferation concerns; LIFE engines can do this without enrichment or reprocessing. Moreover, none of the advanced fuel cycles can match the low transuranic content of LIFE waste. (3) The specific thermal power of LIFE waste is initially higher than that of spent LWR fuel. Nevertheless, this higher thermal load can be managed using appropriate engineering features during an interim storage period, and could be accommodated in a Yucca-Mountain-like repository by appropriate 'staging' of the emplacement of waste packages during the operational period of the repository. The planned ventilation rates for Yucca Mountain would be sufficient for LIFE waste to meet the thermal constraints of

Post-test examination of a copper electrode from deposition hole 5 in the Prototype Repository

International Nuclear Information System (INIS)

Rosborg, Bo

2013-04-01

Three copper electrodes have been exposed for eight years in the outer section of the Prototype Repository at Aespoe. The electrodes were installed in the upper bentonite block of deposition hole 5 in May 2003. Most of the time the temperature of the electrodes has been somewhat below 35 deg C. The electrodes were retrieved for post-test examination in September 2011. This report presents results from electrochemical measurements and the post-test examination of one of the electrodes. The corrosion potential of the examined copper electrode was -40 mV SHE (2011-02-04) when part of the concrete plug to the outer section of the repository had been removed and made measurements possible. When the back-fill in the deposition tunnel had been removed it was 25 mV SHE (2011-09-12). Finally, before letting loose the copper electrode from the retrieved bentonite block, the corrosion potential was found to be 165 mV SHE (2011-11-15) being a sign of air ingress to the electrode/ bentonite interface. It was immediately obvious from the appearance of the copper electrode, when part of the surrounding bentonite had been removed, that both Cu(I) and Cu(II) corrosion products existed on the electrode surface. X-ray diffraction measurements also verified the presence of cuprite, Cu 2 O, and malachite, Cu 2 (OH) 2 CO 3 , on the electrode; however, paratacamite, Cu 2 (OH) 3 Cl, was not found. The performed Fourier transform infrared and Raman spectroscopy confirmed these observations. The corrosion product film, of which cuprite is the main part, was quite uneven and porous. No unmistakable signs of pitting have been found. The appearance of the copper electrode reminded of the coupons from the retrieved LOT test parcels, but was different from the appearance of the surface on the full-size canisters. For the latter blue-green Cu(II) corrosion products have not or only rarely been observed from visual examination immediately after removing the surrounding bentonite. Differences that

Post-test examination of a copper electrode from deposition hole 5 in the Prototype Repository

Energy Technology Data Exchange (ETDEWEB)

Rosborg, Bo [Rosborg Consulting, Nykoeping (Sweden)

2013-04-15

Three copper electrodes have been exposed for eight years in the outer section of the Prototype Repository at Aespoe. The electrodes were installed in the upper bentonite block of deposition hole 5 in May 2003. Most of the time the temperature of the electrodes has been somewhat below 35 deg C. The electrodes were retrieved for post-test examination in September 2011. This report presents results from electrochemical measurements and the post-test examination of one of the electrodes. The corrosion potential of the examined copper electrode was -40 mV SHE (2011-02-04) when part of the concrete plug to the outer section of the repository had been removed and made measurements possible. When the back-fill in the deposition tunnel had been removed it was 25 mV SHE (2011-09-12). Finally, before letting loose the copper electrode from the retrieved bentonite block, the corrosion potential was found to be 165 mV SHE (2011-11-15) being a sign of air ingress to the electrode/ bentonite interface. It was immediately obvious from the appearance of the copper electrode, when part of the surrounding bentonite had been removed, that both Cu(I) and Cu(II) corrosion products existed on the electrode surface. X-ray diffraction measurements also verified the presence of cuprite, Cu{sub 2}O, and malachite, Cu{sub 2}(OH){sub 2}CO{sub 3}, on the electrode; however, paratacamite, Cu{sub 2}(OH){sub 3}Cl, was not found. The performed Fourier transform infrared and Raman spectroscopy confirmed these observations. The corrosion product film, of which cuprite is the main part, was quite uneven and porous. No unmistakable signs of pitting have been found. The appearance of the copper electrode reminded of the coupons from the retrieved LOT test parcels, but was different from the appearance of the surface on the full-size canisters. For the latter blue-green Cu(II) corrosion products have not or only rarely been observed from visual examination immediately after removing the surrounding

Appraisal of hard rock for potential underground repositories of radioactive wastes

International Nuclear Information System (INIS)

Cook, N.G.W.

1977-10-01

The mechanical safety and stability of such an underground repository depends largely on the virgin state of stress in the rock, groundwater pressures, the strengths of the rocks, heating by the decay of the radioactive wastes, and the layout of the excavations and the disposition of waste cannisters within them. A large body of pertinent data exists in the literature, and each of these factors has been analyzed in the light of this information. The results indicate that there are no fundamental geological nor mechanical reasons why repositories capable of storing radioactive wastes should not be excavated at suitable sites in hard rock. However, specific tests to determine the mechanical and thermal properties of the rocks at a site would be needed to provide the data for the engineering design of a repository. Also, little experience exists of the effects on underground excavations of thermal loads, so that this aspect requires theoretical study and experimental validation. The depths of these potential repositories would lie in the range from 0.5 to 2.0 km below surface, depending upon the strength of the rock. Virgin states of stress have been measured at such depths which would retard the ingress of groundwater and obviate the incidence of faulting. A typical repository comprising three horizons each with a total area of 5 km 2 would have the capacity to store wastes with thermal output of 240 MW

Safeguards for geological repositories

International Nuclear Information System (INIS)

Fattah, A.

2000-01-01

Direct disposal of spent nuclear fuel in geological repositories is a recognised option for closing nuclear fuel cycles. Geological repositories are at present in stages of development in a number of countries and are expected to be built and operated early next century. A State usually has an obligation to safely store any nuclear material, which is considered unsuitable to re-enter the nuclear fuel cycle, isolated from the biosphere. In conjunction with this, physical protection has to be accounted for to prevent inadvertent access to such material. In addition to these two criteria - which are fully under the State's jurisdiction - a third criterion reflecting international non-proliferation commitments needs to be addressed. Under comprehensive safeguards agreements a State concedes verification of nuclear material for safeguards purposes to the IAEA. The Agency can thus provide assurance to the international community that such nuclear material has been used for peaceful purposes only as declared by the State. It must be emphasised that all three criteria mentioned constitute a 'unit'. None can be sacrificed for the sake of the other, but compromises may have to be sought in order to make their combination as effective as possible. Based on comprehensive safeguards agreements signed and ratified by the State, safeguards can be terminated only when the material has been consumed or diluted in such a way that it can no longer be utilised for any nuclear activities or has become practicably irrecoverable. As such safeguards for nuclear material in geological repositories have to be continued even after the repository has been back-filled and sealed. The effective application of safeguards must assure continuity-of-knowledge that the nuclear material in the repository has not been diverted for an unknown purpose. The nuclear material disposed in a geological repository may eventually have a higher and long term proliferation risk because the inventory is

CCDC 874217: Experimental Crystal Structure Determination : Methyl 3-(4-bromophenyl)-5-((1-(4-bromophenyl)-4-methyl-2,5-dioxo-2,5-dihydro-1H-pyrrol-3-yl)(phenyl)methyl)-4,5-dihydro-1,2-oxazole-5-carboxylate

KAUST Repository

Yang, W.; Tan, Davin; Li, L.; Han, Z.; Yan, L.; Huang, Kuo-Wei; Tan, C-H.; Jiang, Z.

2013-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Geologic environments for nuclear waste repositories

Directory of Open Access Journals (Sweden)

Paleologos Evan K.

2017-01-01

Full Text Available High-level radioactive waste (HLW results from spent reactor fuel and reprocessed nuclear material. Since 1957 the scientific consensus is that deep geologic disposal constitutes the safest means for isolating HLW for long timescales. Nuclear power is becoming significant for the Arab Gulf countries as a way to diversify energy sources and drive economic developments. Hence, it is of interest to the UAE to examine the geologic environments currently considered internationally to guide site selection. Sweden and Finland are proceeding with deep underground repositories mined in bedrock at depths of 500m, and 400m, respectively. Equally, Canada’s proposals are deep burial in the plutonic rock masses of the Canadian Shield. Denmark and Switzerland are considering disposal of their relative small quantities of HLW into crystalline basement rocks through boreholes at depths of 5,000m. In USA, the potential repository at Yucca Mountain, Nevada lies at a depth of 300m in unsaturated layers of welded volcanic tuffs. Disposal of low and intermediate-level radioactive wastes, as well as the German HLW repository favour structurally-sound layered salt stata and domes. Our article provides a comprehensive review of the current concepts regarding HLW disposal together with some preliminary analysis of potentially appropriate geologic environments in the UAE.

Modelling saline intrusion for repository performance assessment

International Nuclear Information System (INIS)

Jackson, C.P.

1989-04-01

UK Nirex Ltd are currently considering the possibility of disposal of radioactive waste by burial in deep underground repositories. The natural pathway for radionuclides from such a repository to return to Man's immediate environment (the biosphere) is via groundwater. Thus analyses of the groundwater flow in the neighbourhood of a possible repository, and consequent radionuclide transport form an important part of a performance assessment for a repository. Some of the areas in the UK that might be considered as possible locations for a repository are near the coast. If a repository is located in a coastal region seawater may intrude into the groundwater flow system. As seawater is denser than fresh water buoyancy forces acting on the intruding saline water may have significant effects on the groundwater flow system, and consequently on the time for radionuclides to return to the biosphere. Further, the chemistry of the repository near-field may be strongly influenced by the salinity of the groundwater. It is therefore important for Nirex to have a capability for reliably modelling saline intrusion to an appropriate degree of accuracy in order to make performance assessments for a repository in a coastal region. This report describes work undertaken in the Nirex Research programme to provide such a capability. (author)

Analisis Konten dan Kebijakan Akses Institutional Repository

Directory of Open Access Journals (Sweden)

Amirul Ulum

2016-07-01

Abstract; Institutional repository has become a major concern of higher education in Indonesia. The number of institutional respository was increased, one of the reason is the ranking web of repositories has been conducted by the Cybermetrics Lab in 2008. At that time, many institutions started to build institutional repository in order to manage the scientific work and also trying to reach the better ranks. Meanwhile, it is an achievement of institution performance which can be promote and increase visibility for the institution. University of Surabaya has also developed the institutional repository and managed by the library. The aims of this study is to analyze the content availability and access policies defined by the University of Surabaya repository  providing services to the academic community and external users. The method used in this study by using observations of the institutional repository University of Surabaya with a literature review to clarify the analysis of the content and access policies. The results of this study indicate that the library's role is has the authority to manage the scientific work of academic community can be done through the institutional repository. However there is still need for library to be proactive to communicate regulations on mandatory deposit of scientific work and create intensive promotion of the institutional repository.

The situation on the site of closed Maisiagala repository. Modelling and measurements

International Nuclear Information System (INIS)

Mazeika, J.; Baltrunas, D.; Butkus, D.; Duskesas, G.; Remeikis, V.

2001-01-01

The safety of RADON type RMI disposal facility was investigated by means of the computer modelling and by measurements of concentrations of radionuclides in the water samples taken from the control wells. The repository was built on the top of the sandy hill in 1963. The dimensions of the monolithic reinforced concrete vault are 5 m x 15 m x 3 m, the thickness of the sidewalls is about 0.25 m and the thickness of the bottom is about 0.2 m. The sidewalls are covered from inside and outside with cement and sodium aluminate coatings 0.02 m thick. From outside they were also covered with two layers of hot bitumen. The bottom of the vault is covered with bitumen and two layers of rubberoid. During the exploitation time the vault was filled with radioactive waste (in a chaotic way and sources were buried together with their biological shielding). In the course of burial radioactive waste was constantly interlaid with concrete. When the disposal facility was closed in 1988 only three fifths of its volume was filled; the total activity of 3 H, 239 Pu and Pu-Be neutron sources was 4.18 10 15 Bq, 2.4 10 11 Bq, and 12.5 10 9 n/s, respectively (according the documentation). Empty two fifths of the vault was filled with concrete, then with sand, then with the concrete (0.01 m), hot bitumen and the 0.05 m asphalt layers. Monolithic concrete that was covered with bitumen and 0.05 m thick layer of asphalt closed the vault. Sand layer the thickness of which was not less than 1.2 m formed the cap. Four wells - one on each side - near the repository and four wells in the anticipated direction of ground water flow were drilled with the purpose to control the radiological situation around the repository. The volume activity of 3 H in the wells was measured with the liquid scintillator detector Tri-Carb. The highest volume activity was found in the same nearest well in all years with the exception of the year 2000. The activity of other radionuclides was measured with the Canberra

Safety Problems of Disposal of Disused Sealed Sources in the Baldone Near Surface Repository

International Nuclear Information System (INIS)

Dreimanis, A.

2003-01-01

Current Latvian regulations encourage re-export of DSS, however, up to now in the repository has been disposed a lot of DSS. Baldone repository has received RW (mainly DSS) from ∼ 300 Latvia objects and from Kaliningrad region (from 1964 to 1973). DSS cause the major part of activity of the repository - from the total activity in facility ∼ 400 TBq more than 300 TBq is due to DSS. A long term Safety Assessment (SA) of the Baldone Radon-type near surface disposal facility has been performed by the consortium CASSIOPEE and recommendations are given. The waste disposal system consists of: vaults 1-6 (closed, as permanent disposal site), vault 7 (as a long-term retrievable storage site); 2 main components of the engineered barriers: the capping system and the vaults. Vaults 1 and 3-6 (of re-fabricated concrete elements, closed with reinforced concrete slabs, covered with hydro isolating layer completed by a sand/ soil layer). The vault No.7 (ten 130 m 3 underground concrete walled storage cells, protected from the weather by the building. These 10 underground storage cells are adjacent (2x5) with additional concrete walls in some of them. The cells are covered by 40 cm concrete slabs placed side to side. The assessment context and development of scenarios are presented in the paper. The results from the SA are presented. For the waste pathway scenarios - the resulting doses - ∼ 4 mSv/y at 30 y in the current status without cover, justify the implantation of a cover for the closure period of the repository. For air pathway scenarios - the basic dose target 1 mSv/y (for public) is not satisfied for all scenarios; the resulting effective dose for the on-site 'Western' residential scenario for the vaults with highest content of DSS: vault 3 - 303 mSv/y; vault 7 - 204 mSv/y. The main recommendations from the SA are: General Advice - to dispose sources with half-lives < 5,3 y; for the spent sources - to build a new long-term storage; 2. To move DSS from Vault 7 to the

Process model repositories and PNML

NARCIS (Netherlands)

Hee, van K.M.; Post, R.D.J.; Somers, L.J.A.M.; Werf, van der J.M.E.M.; Kindler, E.

2004-01-01

Bringing system and process models together in repositories facilitates the interchange of model information between modelling tools, and allows the combination and interlinking of complementary models. Petriweb is a web application for managing such repositories. It supports hierarchical process

The recharge area concept: A strategy for siting nuclear waste repositories

International Nuclear Information System (INIS)

Sheng, G.; Toth, J.

2000-01-01

The Recharge Area Concept is the proposition that in Canadian-Shield type natural environments recharge areas of regional groundwater flow systems are superior for high-level nuclear waste repositories to other types of groundwater flow regimes, especially to areas of groundwater discharge. This conclusion is reached from an analysis of basinal groundwater flow models. The calculations were made for a two-dimensional flank of a fully saturated topographic basin, 20 km long and 4 km deep, in which groundwater is driven by gravity. Variants of hydraulic-conductivity distributions were considered: 1) homogeneous; 2) stratified; and 3) stratified-faulted. The faults attitudes were changed by steps from vertical to horizontal for different variants. The model is assumed conceptually to represent the crystalline-rock environment of the Canadian Shield. The hydrogeologic performances of hypothetical repositories placed 500 m deep in the recharge and discharge areas were characterized by thirteen parameters. The principal advantages of recharge- over discharge-area locations are: 1) longer travel paths and return-flow times from repository to surface; 2) robustness of predicted values of performance parameters; 3) field-verifiability of favourable hydrogeologic conditions (amounting to an implicit validation of the calculated minimum values of return-flow times); 4) site acceptance based on quantifiable and observable flow-controlling parameters; and 5) simple logistics and favourable economics of site selection and screening. As a by-product of modeling, it is demonstrated that the presence of old water is not an indication of stagnancy. (author)

Performance Assessment Strategy Plan for the Geologic Repository Program

International Nuclear Information System (INIS)

1990-01-01

Performance assessment is a major constituent of the program being conducted by the US Department of Energy (DOE) to develop a geologic repository. Performance assessment is the set of activities needed for quantitative evaluations to assess compliance with the performance requirements in the regulations for a geologic repository and to support the development of the repository. The strategy for these evaluations has been documented in the Performance Assessment Strategy Plan (DOE, 1989). The implementation of the performance assessment strategy is defined in this document. This paper discusses the scope and objectives of the implementation plan, the relationship of the plan to other program plans, summarizes the performance assessment areas and the integrated strategy of the performance assessment program. 1 fig., 3 tabs

Statistical methods for mechanistic model validation: Salt Repository Project

International Nuclear Information System (INIS)

Eggett, D.L.

1988-07-01

As part of the Department of Energy's Salt Repository Program, Pacific Northwest Laboratory (PNL) is studying the emplacement of nuclear waste containers in a salt repository. One objective of the SRP program is to develop an overall waste package component model which adequately describes such phenomena as container corrosion, waste form leaching, spent fuel degradation, etc., which are possible in the salt repository environment. The form of this model will be proposed, based on scientific principles and relevant salt repository conditions with supporting data. The model will be used to predict the future characteristics of the near field environment. This involves several different submodels such as the amount of time it takes a brine solution to contact a canister in the repository, how long it takes a canister to corrode and expose its contents to the brine, the leach rate of the contents of the canister, etc. These submodels are often tested in a laboratory and should be statistically validated (in this context, validate means to demonstrate that the model adequately describes the data) before they can be incorporated into the waste package component model. This report describes statistical methods for validating these models. 13 refs., 1 fig., 3 tabs

SKB's safety case for a final repository license application

International Nuclear Information System (INIS)

Hedin, Allan; Andersson, Johan

2014-01-01

The safety assessment SR-Site is a main component in SKB's license application, submitted in March 2011, to construct and operate a final repository for spent nuclear fuel at Forsmark in the municipality of Oesthammar, Sweden. Its role in the application is to demonstrate long-term safety for a repository at Forsmark. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. The principal regulatory acceptance criterion, issued by the Swedish Radiation Safety Authority (SSM), requires that the annual risk of harmful effects after closure not exceed 10 -6 for a representative individual in the group exposed to the greatest risk. SSM's regulations also imply that the assessment time for a repository of this type is one million years after closure. The licence applied for is one in a stepwise series of permits, each requiring a safety report. The next step concerns a permit to start excavation of the repository and requires a preliminary safety assessment report (PSAR) covering both operational and post-closure safety. Later steps include permission to commence trial operation, to commence regular operation and to close the final repository. (authors)

Fair rules for siting a high-level nuclear waste repository

International Nuclear Information System (INIS)

Easterling, D.

1992-01-01

Geologic repositories are designed to resolve the ever-growing problem of high-level nuclear waste, but these facilities invite intense local opposition due to the perceived severity of the risks and the possibility of stigma effects. This analysis examines whether the perceived fairness of the siting process affects local residents' support for hosting a repository. In particular, a survey of 1,001 Nevada residents is used to test the hypothesis that an individual's willingness to accept a local repository will increase if he or she is convinced that this is the safest disposal option available. A logistic analysis indicates that beliefs regarding relative suitability have an independent effect on the acceptability of a local repository (i.e., Yucca Mountain). The article then considers the question of how to implement an optimizing strategy for siting facilities, comparing an idealized strategy against the original Nuclear Waste Policy Act (NWPA) of 1982 and the Amendments Act of 1987. Although choosing the safest site seems as if it could enhance public acceptance of the repository program, there is currently little prospect of identifying the best option to the high-level waste problem and, as a results, little chance of gaining the public support that is necessary to promote a successful siting outcome. 81 refs., 1 fig., 5 tabs

Open DOAR the Directory of Open Access Repositories

CERN Multimedia

CERN. Geneva

2005-01-01

The last year has seen wide-spread growth in the idea of using open access repositories as a part of a research institution's accepted infrastructure. Policy development from institutions and funding bodies has also supported the growth of the repository network. The next stage of expansion will be in the provision of services and cross-repository facilities and resources. Of course, it is hoped that these will then establish a feed-back loop to encourage repository population and further repository establishment, as the potential of open access to research materials is realised. The growth of repositories has been organic, with a variety of different repositories based in departments, institutions, funding agencies or subject communities, with a range of content, both in type and subject. Existing repositories are expanding their holdings, from eprints to associated research data-sets, or with learning objects and multimedia material. This presentation will look at the development of the Directory of Open Ac...

Evaluasi Website Repositori Institusi Universitas Surabaya

Directory of Open Access Journals (Sweden)

Amirul Ulum

2015-11-01

Full Text Available The  development  of  institutional  repositories  (IRs  in Indonesia within the broader framework of open access has significant impact on preserving intellectual capital and scholarly communication. Institutional  repositories  play  a  fundamental  role  in  centralizing, preserving,  and  making  accessible  institution’s  intellectual  capital. Evaluation of the system is to determine the functionality the system to meet the users need. Using a descriptive analysis this study wants to evaluate institutional repositories of University of Surabaya. The result is usefull for institution to develop the repository systems.

Final repository for spent nuclear fuel. Underground design Forsmark, Layout D1

International Nuclear Information System (INIS)

Brantberger, Martin; Zetterqvist, Anders; Arnbjerg-Nielsen, Torben; Olsson, Tommy; Outters, Nils; Syrjaenen, Pauli

2006-04-01

This report comprises the design step D1 related to the underground design for a deep repository located at the Forsmark site. The design is based on the Site Descriptive Model Forsmark v1.2. All studies have been focussed at an area southeast of the Forsmark nuclear plant, which has been considered to be the most promising area for hosting the repository. SKB has developed guidelines for the design of the repository, which further describes the methodology applied for the studies. From these guidelines the following basic objectives for the design step D1 are summarized: to determine whether the final repository can be accommodated within the studied site; to identify site-specific facility critical issues; to test and evaluate the design methodology; to provide feedback to: the design organisation regarding additional studies that needs to be done; the site investigation and modelling organization regarding further investigations required; and the safety assessment team. The possible locations for a tentative deep repository are analysed in Chapter 3 of the report. The most promising area for the repository (denoted 'priority site') has been defined by SKB to be located southeast of the Forsmark nuclear plant and northwest of the gently dipping deformation zone ZFMNE00A2. Regarding the repository depth, present knowledge acquired from the site investigations indicates that it is possible to locate the repository at all stipulated depths according to SKB, that is between 400 m and 700 m depth. The preliminary assessment made in Chapter 3 clearly demonstrates that the repository can be accommodated within the 'priority site'. The potential to accommodate the repository is essentially the same for both 400 m and 500 m depths. The design of the deposition areas is reported in Chapter 4, which includes the design of layout features for all tunnels and deposition holes, orientation of tunnels, calculation of anticipated loss of deposition holes due to the applied

Final repository for spent nuclear fuel. Underground design Forsmark, Layout D1

Energy Technology Data Exchange (ETDEWEB)

Brantberger, Martin; Zetterqvist, Anders [Ramboell Sweden AB, Stockholm (Sweden); Arnbjerg-Nielsen, Torben [Ramboell Denmark A/S, Virum (Denmark); Olsson, Tommy [IandT Olsson AB, Uppsala (Sweden); Outters, Nils [Golder Associates AB, Uppsala (Sweden); Syrjaenen, Pauli [Gridpoint Oy, Helsinki (Sweden)

2006-04-15

This report comprises the design step D1 related to the underground design for a deep repository located at the Forsmark site. The design is based on the Site Descriptive Model Forsmark v1.2. All studies have been focussed at an area southeast of the Forsmark nuclear plant, which has been considered to be the most promising area for hosting the repository. SKB has developed guidelines for the design of the repository, which further describes the methodology applied for the studies. From these guidelines the following basic objectives for the design step D1 are summarized: to determine whether the final repository can be accommodated within the studied site; to identify site-specific facility critical issues; to test and evaluate the design methodology; to provide feedback to: the design organisation regarding additional studies that needs to be done; the site investigation and modelling organization regarding further investigations required; and the safety assessment team. The possible locations for a tentative deep repository are analysed in Chapter 3 of the report. The most promising area for the repository (denoted 'priority site') has been defined by SKB to be located southeast of the Forsmark nuclear plant and northwest of the gently dipping deformation zone ZFMNE00A2. Regarding the repository depth, present knowledge acquired from the site investigations indicates that it is possible to locate the repository at all stipulated depths according to SKB, that is between 400 m and 700 m depth. The preliminary assessment made in Chapter 3 clearly demonstrates that the repository can be accommodated within the 'priority site'. The potential to accommodate the repository is essentially the same for both 400 m and 500 m depths. The design of the deposition areas is reported in Chapter 4, which includes the design of layout features for all tunnels and deposition holes, orientation of tunnels, calculation of anticipated loss of deposition holes due

CCDC 1055170: Experimental Crystal Structure Determination : Methyl 5,5-difluoro-1,3,7,9-tetramethyl-2,8-bis(triphenylvinyl)-5H-4lambda5,5lambda5-dipyrrolo[1,2-c:2',1'-f][1,3,2]diazaborinine-10-carboxylate tetrahydrofuran solvate

KAUST Repository

Chua, Ming Hui; Ni, Yong; Garai, Monalisa; Zheng, Bin; Huang, Kuo-Wei; Xu, Qing-Hua; Xu, Jianwei; Wu, Jishan

2015-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Nuclide release calculation in the near-field of a reference HLW repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Hwang, Yong Soo; Kang, Chul Hyung

2004-01-01

The HLW-relevant R and D program for disposal of high-level radioactive waste has been carried out at Korea Atomic Energy Research Institute (KAERI) since early 1997 in order to develop a conceptual Korea Reference Repository System for direct disposal of nuclear spent fuel by the end of 2007. A preliminary reference geologic repository concept considering such established criteria and requirements as waste and generic site characteristics in Korea was roughly envisaged in 2003 focusing on the near-field components of the repository system. According to above basic repository concept, which is similar to that of Swedish KBS-3 repository, the spent fuel is first encapsulated in corrosion resistant canisters, even though the material has not yet been determined, and then emplaced into the deposition holes surrounded by high density bentonite clay in tunnels constructed at a depth of about 500 m in a stable plutonic rock body. Not only to demonstrate how much a reference repository is safe in the generic point of view with several possible scenarios and cases associated with a preliminary repository concept by conducting calculations for nuclide release and transport in the near-field components of the repository, even though enough information has not been available that much yet, but also to show a methodology by which a generic safety assessment could be performed for further development of Korea reference repository concept, nuclide release calculation study strongly seems to be necessary

Alternative measure for performance of HLW geologic repository

International Nuclear Information System (INIS)

Joonhang, Ahn; Chambre, P.L.

2001-01-01

A repository performance model that can show effects of canister multiplicity and repository configuration has been developed. Masses of a radionuclide in the repository and in the far field are proposed as performance measures. Canister multiplicity has significant effects on the release of long-lived radionuclides from the repository. As more canisters are included in the same water stream, the radionuclide concentration in the stream increases, but becomes independent of the number of canisters for sufficiently many canisters. Effects of reduction of radionuclide mass in the repository on the repository performance are clearly observed if the canister multiplicity is taken into account and the mass-based measures are applied. (author)

Accelerator Physics Code Web Repository

CERN Document Server

Zimmermann, Frank; Bellodi, G; Benedetto, E; Dorda, U; Giovannozzi, Massimo; Papaphilippou, Y; Pieloni, T; Ruggiero, F; Rumolo, G; Schmidt, F; Todesco, E; Zotter, Bruno W; Payet, J; Bartolini, R; Farvacque, L; Sen, T; Chin, Y H; Ohmi, K; Oide, K; Furman, M; Qiang, J; Sabbi, G L; Seidl, P A; Vay, J L; Friedman, A; Grote, D P; Cousineau, S M; Danilov, V; Holmes, J A; Shishlo, A; Kim, E S; Cai, Y; Pivi, M; Kaltchev, D I; Abell, D T; Katsouleas, Thomas C; Boine-Frankenheim, O; Franchetti, G; Hofmann, I; Machida, S; Wei, J

2006-01-01

In the framework of the CARE HHH European Network, we have developed a web-based dynamic acceleratorphysics code repository. We describe the design, structure and contents of this repository, illustrate its usage, and discuss our future plans, with emphasis on code benchmarking.

ACCELERATION PHYSICS CODE WEB REPOSITORY.

Energy Technology Data Exchange (ETDEWEB)

WEI, J.

2006-06-26

In the framework of the CARE HHH European Network, we have developed a web-based dynamic accelerator-physics code repository. We describe the design, structure and contents of this repository, illustrate its usage, and discuss our future plans, with emphasis on code benchmarking.

Integrating repositories with fuel cycles: The airport authority model

Energy Technology Data Exchange (ETDEWEB)

Forsberg, C. [Massachusetts Inst. of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139-4307 (United States)

2012-07-01

appointed by the state governor, county governments, and city governments. This structure (1) enables state and local governments to work together to maximize job and tax benefits to local communities and the state, (2) provides a mechanism to address local concerns such as airport noise, and (3) creates an institutional structure with large incentives to maximize the value of the common asset, the runway. A repository site authority would have a similar structure and be the local interface to any national waste management authority. (authors)

Integrating repositories with fuel cycles: The airport authority model

International Nuclear Information System (INIS)

Forsberg, C.

2012-01-01

appointed by the state governor, county governments, and city governments. This structure (1) enables state and local governments to work together to maximize job and tax benefits to local communities and the state, (2) provides a mechanism to address local concerns such as airport noise, and (3) creates an institutional structure with large incentives to maximize the value of the common asset, the runway. A repository site authority would have a similar structure and be the local interface to any national waste management authority. (authors)

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Process report

Energy Technology Data Exchange (ETDEWEB)

Gribi, Peter; Johnson, Lawrence; Suter, Daniel; Smith, Paul; Pastina, Barbara; Snellman, Margit

2008-01-15

shell and other steel structural materials, repository sealing and backfilling, and geosphere. The process description is based on a 'difference analysis' approach comparing processes in KBS-3V and KBS-3H. The focus mostly on internal processes relevant to a single deposition drift and its immediate environment (near-field rock, drift end plugs), but also include the impact of important external factors such as glaciation and post-glacial faulting. The issues that were evaluated in detail are the following: i) piping and erosion during the operational phase; ii) displacements of the supercontainers and the distance blocks due to hydraulic pressure differences in the drift; iii) rupturing of the supercontainer due to buffer swelling; iv) impact of gas generation from the corrosion of steel components in the drift; v) iron-bentonite interaction due to the presence of the supercontainer steel shell; vi) cement-bentonite interaction; and vii) water ingress followed by radionuclide expulsion from an initially penetrated canister. Except issues ii, iii, iv, the others are in common with KBS-3V. Piping/erosion, along with the potential displacement of the supercontainer and distance blocks are viewed as processes that can be avoided or minimised with further developments of the KBS-3H design. Rupturing of the supercontainer due to buffer swelling was considered because it may result in corrosion products in direct contact with the rock hence having a negative effect on the canister lifetime and radionuclide transport. Gas generation from the corrosion of the steel supercontainer shell (and other steel components in the drift) will last approximately 4,500-5,000 years, based on the steel components' thickness and a steel corrosion rate of 1 micrometre/year. The potential consequences are transient high gas pressures and delayed resaturation but no impacts on long-term safety have been identified. The interaction between iron and bentonite was considered because

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Process report

International Nuclear Information System (INIS)

Gribi, Peter; Johnson, Lawrence; Suter, Daniel; Smith, Paul; Pastina, Barbara; Snellman, Margit

2008-01-01

shell and other steel structural materials, repository sealing and backfilling, and geosphere. The process description is based on a 'difference analysis' approach comparing processes in KBS-3V and KBS-3H. The focus mostly on internal processes relevant to a single deposition drift and its immediate environment (near-field rock, drift end plugs), but also include the impact of important external factors such as glaciation and post-glacial faulting. The issues that were evaluated in detail are the following: i) piping and erosion during the operational phase; ii) displacements of the supercontainers and the distance blocks due to hydraulic pressure differences in the drift; iii) rupturing of the supercontainer due to buffer swelling; iv) impact of gas generation from the corrosion of steel components in the drift; v) iron-bentonite interaction due to the presence of the supercontainer steel shell; vi) cement-bentonite interaction; and vii) water ingress followed by radionuclide expulsion from an initially penetrated canister. Except issues ii, iii, iv, the others are in common with KBS-3V. Piping/erosion, along with the potential displacement of the supercontainer and distance blocks are viewed as processes that can be avoided or minimised with further developments of the KBS-3H design. Rupturing of the supercontainer due to buffer swelling was considered because it may result in corrosion products in direct contact with the rock hence having a negative effect on the canister lifetime and radionuclide transport. Gas generation from the corrosion of the steel supercontainer shell (and other steel components in the drift) will last approximately 4,500-5,000 years, based on the steel components' thickness and a steel corrosion rate of 1 micrometre/year. The potential consequences are transient high gas pressures and delayed resaturation but no impacts on long-term safety have been identified. The interaction between iron and bentonite was considered because of the close

Consistency of Network Traffic Repositories: An Overview

NARCIS (Netherlands)

Lastdrager, E.; Lastdrager, E.E.H.; Pras, Aiko

2009-01-01

Traffc repositories with TCP/IP header information are very important for network analysis. Researchers often assume that such repositories reliably represent all traffc that has been flowing over the network; little thoughts are made regarding the consistency of these repositories. Still, for

48 CFR 227.7207 - Contractor data repositories.

Science.gov (United States)

2010-10-01

... repositories. 227.7207 Section 227.7207 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS... Computer Software and Computer Software Documentation 227.7207 Contractor data repositories. Follow 227.7108 when it is in the Government's interests to have a data repository include computer software or to...

Reference repository design concept for bedded salt

Energy Technology Data Exchange (ETDEWEB)

Carpenter, D.W.; Martin, R.W.

1980-10-08

A reference design concept is presented for the subsurface portions of a nuclear waste repository in bedded salt. General geologic, geotechnical, hydrologic and geochemical data as well as descriptions of the physical systems are provided for use on generic analyses of the pre- and post-sealing performance of repositories in this geologic medium. The geology of bedded salt deposits and the regional and repository horizon stratigraphy are discussed. Structural features of salt beds including discontinuities and dissolution features are presented and their effect on repository performance is discussed. Seismic hazards and the potential effects of earthquakes on underground repositories are presented. The effect on structural stability and worker safety during construction from hydrocarbon and inorganic gases is described. Geohydrologic considerations including regional hydrology, repository scale hydrology and several hydrological failure modes are presented in detail as well as the hydrological considerations that effect repository design. Operational phase performance is discussed with respect to operations, ventilation system, shaft conveyances, waste handling and retrieval systems and receival rates of nuclear waste. Performance analysis of the post sealing period of a nuclear repository is discussed, and parameters to be used in such an analysis are presented along with regulatory constraints. Some judgements are made regarding hydrologic failure scenarios. Finally, the design and licensing process, consistent with the current licensing procedure is described in a format that can be easily understood.

Reference repository design concept for bedded salt

International Nuclear Information System (INIS)

Carpenter, D.W.; Martin, R.W.

1980-01-01

A reference design concept is presented for the subsurface portions of a nuclear waste repository in bedded salt. General geologic, geotechnical, hydrologic and geochemical data as well as descriptions of the physical systems are provided for use on generic analyses of the pre- and post-sealing performance of repositories in this geologic medium. The geology of bedded salt deposits and the regional and repository horizon stratigraphy are discussed. Structural features of salt beds including discontinuities and dissolution features are presented and their effect on repository performance is discussed. Seismic hazards and the potential effects of earthquakes on underground repositories are presented. The effect on structural stability and worker safety during construction from hydrocarbon and inorganic gases is described. Geohydrologic considerations including regional hydrology, repository scale hydrology and several hydrological failure modes are presented in detail as well as the hydrological considerations that effect repository design. Operational phase performance is discussed with respect to operations, ventilation system, shaft conveyances, waste handling and retrieval systems and receival rates of nuclear waste. Performance analysis of the post sealing period of a nuclear repository is discussed, and parameters to be used in such an analysis are presented along with regulatory constraints. Some judgements are made regarding hydrologic failure scenarios. Finally, the design and licensing process, consistent with the current licensing procedure is described in a format that can be easily understood

CCDC 1419446: Experimental Crystal Structure Determination : ((2,10-Di-t-butylthiochromeno[2''',3''':4'',5'']thieno[2'',3'':4',5']thieno[2',3':4,5]thieno[3,2-b]thiochromene-12,15-diyl)diethyne-2,1-diyl)bis(tri-isopropylsilane)

KAUST Repository

Shi, Xueliang; Quintero, Estefaní a; Lee, Sangsu; Jing, Linzhi; Herng, Tun Seng; Zheng, Bin; Huang, Kuo-Wei; Navarrete, Juan T. Ló pez; Ding, Jun; Kim, Dongho; Casado, Juan; Chi, Chunyan

2015-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

The fast multiple-path NUCTRAN model -- Calculating the radionuclide release from a repository

International Nuclear Information System (INIS)

Romero, L.; Moreno, L.; Neretnieks, I.

1995-01-01

The NUCTRAN model has been applied to the Swedish KBS-3 nuclear waste repository concept, where the migration of radionuclides is through various barriers and pathways. The escape of the nuclides from the canister occurs through a small hole. This hole controls the release of nuclides from the repository. NUCTRAN is a useful tool to calculate the nonstationary transport in a repository for high-level nuclear waste. The advantage of this model is the use of a coarse compartmentalization of the repository, which makes it flexible and easy to adapt to different geometries. The several radionuclide release calculations made with NUCTRAN have shown the capability of this to handle different situations rapidly and easily. The particularity of these calculations is the high accuracy obtained by using a coarse compartmentalization of the Swedish KBS-3 repository and the small requirements of computing time. At short times for short-lived nuclides, the calculated releases are exaggerated. The error can be considerably reduced by an additional subdivision of large compartments into a few compartments

Geoelectric monitoring of bentonite barrier resaturation in the Aespoeprototype repository. Final report

Energy Technology Data Exchange (ETDEWEB)

Wieczorek, Klaus; Komischke, Michael; Miehe, Ruediger; Moog, Helge

2014-10-15

In 1994, SKB started constructing the ''Prototype Repository'', a full-scale replica of a part of a future KBS-3 repository in crystalline rock, at the AespoeHard Rock Laboratory. Six emplacement boreholes were planned and constructed in two tunnel sections until end of 1999. The international EC co-funded Prototype Repository project was started in 2000 (contract FIKW-CT-2000-00055). The project partners were SKB (Sweden), POSIVA (Finland), ENRESA (Spain), GRS (Germany), BGR (Germany), UWC (UK), and JNC (Japan). Between 2000 and 2003 the complete Prototype Repository was equipped and instrumented, and monitoring was started. In February 2004 the EC funding expired. The Prototype Repository project was continued with national funding of the project partners. In 2011, dismantling of Section II was started in a three-year project. Backfill, buffer and canisters as well as part of the instrumentation were retrieved, and numerous laboratory investigations on buffer and backfill samples were performed. GRS' part in the Prototype Repository was the monitoring of backfill and buffer resaturation using geoelectric tomography. The measurements were completed in 2013.

Nirex 97 an assessment of the post-closure performance of a deep waste repository at Sellafield. Volume 3; the groundwater pathway

International Nuclear Information System (INIS)

Baker, A.; Chambers, A.; Jackson, C.

1997-01-01

repository zone beneath Longlands Farm. In style, scope and presentation, Nirex 97 is primarily aimed at the scientific community, other radioactive waste disposal agencies and regulators. The report is published as part of Nirex's commitment to open publication of its scientific findings. The main value of the report currently is as a demonstration of the generic capability which has been developed to assess the radiological safety performance of candidate repository sites. The safety assessment reported as Nirex 97 was carried out between April 1996 and August 1997. It updates a preliminary assessment of the groundwater pathway for a repository at Sellafield, 'Nirex 95' published in July 1995. Nirex 97 takes account of further data obtained from the Nirex waste inventory, design, site characterisation and research programmes. In addition, Nirex 97 extends the Nirex 95 evaluation to include consideration of the potential radiological and flammability hazards in the biosphere arising from the effects of gas generation within the repository and the extent of pressurisation within the repository vaults. The assessment also takes account of the latest guidance from the Environment Agencies on requirements for authorisation of disposal facilities on land. Volume 3: The Groundwater Pathway, describes the groundwater flow models used to develop an analysis of risks from the groundwater pathway due to natural discharges and well abstraction. It describes the models of the repository source term and radionuclide transport through the geosphere and biosphere. The detailed understanding of repository performance is explored through the development of some simple 'insight' models

Hydrothermal conditions around a radioactive waste repository

International Nuclear Information System (INIS)

Thunvik, R.; Braester, C.

1981-12-01

Numerical solutions for the hydrothermal conditions around a hard rock repository for nuclear fuel waste are presented. The objective of the present investigation is to illustrate in principle the effect of heat released from a hypothetical radioactive waste repository with regard to anisotropy in the rock permeability. Permeability and porosity are assumed to be constant or to decrease exponentially with depth. The hypothetical repository is situated below a horizontal ground surface or below the crest of a hill, and it is assumed that the water table follows the topography. Major interest in the analysis is directed towards the influence of anisotropy in the permeability on the flow patterns and travel times for water particles, being traced from the repository to the ground surface. The presented results show that anisotropy in the permeability may have a significant influence on the flow conditions around the repository and subsequently also on the travel times from the repository. (Authors)

CCDC 887626: Experimental Crystal Structure Determination : 3-(4,4,4-Trifluoro-3-(2-methyl-5-oxo-2,5-dihydrofuran-2-yl)butanoyl)-1,3-oxazolidin-2-one

KAUST Repository

Zhang, Wen

2013-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Repository operational criteria comparative analysis

International Nuclear Information System (INIS)

Hageman, J.P.; Chowdhury, A.H.

1994-06-01

The objective of the ''Repository Operational Criteria (ROC) Feasibility Studies'' (or ROC task) was to conduct comprehensive and integrated analyses of repository design, construction, and operations criteria in 10 CFR Part 60 regulations considering the interfaces among the components of the regulations and impacts of any potential changes to those regulations. The ROC task addresses regulatory criteria and uncertainties related to the preclosure aspects of the geologic repository. Those parts of 10 CFR Part 60 that require routine guidance or minor changes to the rule were addressed in Hageman and Chowdhury, 1992. The ROC task shows a possible need for further regulatory clarity, by major changes to the rule, related to the design bases and siting of a geologic repository operations area and radiological emergency planning in order to assure defense-in-depth. The analyses, presented in this report, resulted in the development and refinement of regulatory concepts and their supporting rationale for recommendations for potential major changes to 10 CFR Pan 0 regulations

Principal organic materials in a repository for spent nuclear fuel

International Nuclear Information System (INIS)

Hallbeck, Lotta

2010-01-01

The largest pool of organic material in a repository at closure is the organic material in the bentonite in buffer and backfill. It is impossible to make any assumptions as to how much of this material will be available for biodegradation, since the character of the material is unknown. However, it is unlikely that this organic material can dissolve in groundwater unless the bentonite loses its swelling capacity. The second largest pool will be the biofilms formed on the rock surfaces. This assumption presupposes that no cleaning is undertaken before repository closure. The third largest pool is the organic material produced by microorganisms using hydrogen from the anaerobic corrosion of iron in steel as an energy source. The following provides summary descriptions of the different pools of organic material that will remain in the repository: 1. Microorganisms. Their effect would mainly be to reduce the redox potential soon after repository closure. They may contribute to the depletion of the oxygen entrapped during repository construction, an effect that would not jeopardise repository stability. If the dominant microorganisms in the anaerobic environment are sulphate-reducing bacteria, oxidation of organic material would lead to the formation of HS - . The produced sulphide could corrode the copper canisters under anaerobic conditions if it reaches them. Another effect of microorganisms would be to increase the complexing capacity of the groundwater due to excreted metabolites. The impact of these compounds is not yet clear, although it will surely not be very important, due to the small amounts of such substances. 2. Materials in the ventilation air. Their effect will probably be to help maintain reducing conditions in the area, although this effect will likely be minimal or negligible. 3. Construction materials. Among these materials, we emphasise the organic materials present in concrete, asphalt, bentonite, and wood. Hydrocarbons from asphalt may help reduce

Principal organic materials in a repository for spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Hallbeck, Lotta (Microbial Analytics Sweden AB, Moelnlycke (Sweden))

2010-01-15

The largest pool of organic material in a repository at closure is the organic material in the bentonite in buffer and backfill. It is impossible to make any assumptions as to how much of this material will be available for biodegradation, since the character of the material is unknown. However, it is unlikely that this organic material can dissolve in groundwater unless the bentonite loses its swelling capacity. The second largest pool will be the biofilms formed on the rock surfaces. This assumption presupposes that no cleaning is undertaken before repository closure. The third largest pool is the organic material produced by microorganisms using hydrogen from the anaerobic corrosion of iron in steel as an energy source. The following provides summary descriptions of the different pools of organic material that will remain in the repository: 1. Microorganisms. Their effect would mainly be to reduce the redox potential soon after repository closure. They may contribute to the depletion of the oxygen entrapped during repository construction, an effect that would not jeopardise repository stability. If the dominant microorganisms in the anaerobic environment are sulphate-reducing bacteria, oxidation of organic material would lead to the formation of HS-. The produced sulphide could corrode the copper canisters under anaerobic conditions if it reaches them. Another effect of microorganisms would be to increase the complexing capacity of the groundwater due to excreted metabolites. The impact of these compounds is not yet clear, although it will surely not be very important, due to the small amounts of such substances. 2. Materials in the ventilation air. Their effect will probably be to help maintain reducing conditions in the area, although this effect will likely be minimal or negligible. 3. Construction materials. Among these materials, we emphasise the organic materials present in concrete, asphalt, bentonite, and wood. Hydrocarbons from asphalt may help reduce

Highly permeable, cement-bounded backfilling mortars for SMA repositories

International Nuclear Information System (INIS)

Jacobs, F.; Mayer, G.; Wittmann, F.H.

1994-03-01

In low- and intermediate-level waste repositories, gas is produced due e.g. to corrosion. This gas must be able to escape from the repository in order to prevent damage to the repository structure. A cement-based backfill should take over this function. For this purpose, the composition of cement-based materials was varied to study their influence on porosity and permeability. In parallel to this study the behaviour of fresh concrete, the liberation of the heat of hydration and the hardened concrete properties were investigated. To characterize the permeability of cement-based materials the following parameters are important: 1) composition of the material (pore fabric), 2) storage conditions (degree of saturation), 3) degree of hydration (age), 4) measuring fluid. A change in the composition of cement-based materials can vary the permeability by ten orders of magnitude. It is shown that, by using dense aggregates, the transport of the fluid takes place through the matrix and along the aggregate/matrix interface. By using porous aggregates the permeability can be increased by two orders of magnitude. In the case of a dense matrix, porous aggregates do not alter the permeability. Increasing the matrix content or interface content increases permeability. Hence light weight mortars are an obvious choice. Like-grained mixes showed higher permeabilities in combination with better mechanical properties but, in comparison to normal mixes, they showed worse flow properties. With the composition cement-: water-: aggregate content 1:0.4:5.33 the likegrained mix with aggregates ranging from 2 to 3 mm proved to be a suitable material. With a low compaction after 28 days this mix reaches a permeability of 4.10 -12 m 2 and an uniaxial cylinder compressive strength of 16 N/mm 2 . (author) 58 figs., 23 tabs., refs

What do we mean by a cold repository?

International Nuclear Information System (INIS)

Halsey, W.G.

1994-01-01

The topic of thermal loading of a potential repository at Yucca Mountain in Nevada has been the subject of intense discussion within the project technical community. While terms such as ''Hot Repository'' and ''Cold Repository'' are frequently used, they have not been clearly defined. In particular, the definition of a cold repository has remained the opinion of each individual. This has led to confusion and misunderstanding. In this paper, a number of observed definitions for a cold repository are discussed along with the technical implications, assumptions and inconsistencies. Finally, a common language is suggested

Deep geological isolation of nuclear waste: numerical modeling of repository scale hydrology

International Nuclear Information System (INIS)

Dettinger, M.D.

1980-04-01

The Scope of Work undertaken covers three main tasks, described as follows: (Task 1) CDM provided consulting services to the University on modeling aspects of the study having to do with transport processes involving the local groundwater system near the repository and the flow of fluids and vapors through the various porous media making up the repository system. (Task 2) CDM reviewed literature related to repository design, concentrating on effects of the repository geometry, location and other design factors on the flow of fluids within the repository boundaries, drainage from the repository structure, and the eventual transport of radionucldies away from the repository site. (Task 3) CDM, in a joint effort with LLL personnel, identified generic boundary and initial conditions, identified processes to be modeled, and recommended a modeling approach with suggestions for appropriate simplifications and approximations to the problem and identifiying important parameters necessary to model the processes. This report consists of two chapters and an appendix. The first chapter (Chapter III of the LLL report) presents a detailed description and discussion of the modeling approach developed in this project, its merits and weaknesses, and a brief review of the difficulties anticipated in implementing the approach. The second chapter (Chapter IV of the LLL report) presents a summary of a survey of researchers in the field of repository performance analysis and a discussion of that survey in light of the proposed modeling approach. The appendix is a review of the important physical processes involved in the potential hydrologic transport of radionuclides through, around and away from deep geologic nuclear waste repositories

Aespoe Hard Rock Laboratory. Prototype Repository. Acoustic emission and ultrasonic monitoring results from deposition hole DA3545G01 in the Prototype Repository between October 2007 and March 2008

Energy Technology Data Exchange (ETDEWEB)

Duckworth, D.; Haycox, J.; Pettitt, W.S. (Applied Seismology Consultants, Shrewsbury (United Kingdom))

2008-12-15

This report describes results from acoustic emission (AE) and ultrasonic monitoring around a canister deposition hole (DA3545G01) in the Prototype Repository Experiment at SKB's Hard Rock Laboratory (HRL), Sweden. The experiment has been designed to simulate a disposal tunnel in a real deep repository environment for storage of high-level radioactive waste. The test consists of a 90 m long, 5 m diameter subhorizontal tunnel excavated in dioritic granite. The monitoring aims to examine changes in the rock mass caused by an experimental repository environment, in particular due to thermal stresses induced from canister heating and pore pressures induced from tunnel sealing.

Aespoe Hard Rock Laboratory. Prototype Repository. Acoustic emission and ultrasonic monitoring results from deposition hole DA3545G01 in the Prototype Repository between October 2007 and March 2008

International Nuclear Information System (INIS)

Duckworth, D.; Haycox, J.; Pettitt, W.S.

2008-12-01

This report describes results from acoustic emission (AE) and ultrasonic monitoring around a canister deposition hole (DA3545G01) in the Prototype Repository Experiment at SKB's Hard Rock Laboratory (HRL), Sweden. The experiment has been designed to simulate a disposal tunnel in a real deep repository environment for storage of high-level radioactive waste. The test consists of a 90 m long, 5 m diameter subhorizontal tunnel excavated in dioritic granite. The monitoring aims to examine changes in the rock mass caused by an experimental repository environment, in particular due to thermal stresses induced from canister heating and pore pressures induced from tunnel sealing

A Climate Statistics Tool and Data Repository

Science.gov (United States)

Wang, J.; Kotamarthi, V. R.; Kuiper, J. A.; Orr, A.

2017-12-01

Researchers at Argonne National Laboratory and collaborating organizations have generated regional scale, dynamically downscaled climate model output using Weather Research and Forecasting (WRF) version 3.3.1 at a 12km horizontal spatial resolution over much of North America. The WRF model is driven by boundary conditions obtained from three independent global scale climate models and two different future greenhouse gas emission scenarios, named representative concentration pathways (RCPs). The repository of results has a temporal resolution of three hours for all the simulations, includes more than 50 variables, is stored in Network Common Data Form (NetCDF) files, and the data volume is nearly 600Tb. A condensed 800Gb set of NetCDF files were made for selected variables most useful for climate-related planning, including daily precipitation, relative humidity, solar radiation, maximum temperature, minimum temperature, and wind. The WRF model simulations are conducted for three 10-year time periods (1995-2004, 2045-2054, and 2085-2094), and two future scenarios RCP4.5 and RCP8.5). An open-source tool was coded using Python 2.7.8 and ESRI ArcGIS 10.3.1 programming libraries to parse the NetCDF files, compute summary statistics, and output results as GIS layers. Eight sets of summary statistics were generated as examples for the contiguous U.S. states and much of Alaska, including number of days over 90°F, number of days with a heat index over 90°F, heat waves, monthly and annual precipitation, drought, extreme precipitation, multi-model averages, and model bias. This paper will provide an overview of the project to generate the main and condensed data repositories, describe the Python tool and how to use it, present the GIS results of the computed examples, and discuss some of the ways they can be used for planning. The condensed climate data, Python tool, computed GIS results, and documentation of the work are shared on the Internet.

CCDC 1055168: Experimental Crystal Structure Determination : Methyl 5,5-difluoro-1,9-dimethyl-3,7-bis(2-(4-(triphenylvinyl)phenyl)vinyl)-5H-6lambda5,5lambda5-dipyrrolo[1,2-c:2',1'-f][1,3,2]diazaborinine-10-carboxylate ethanol solvate sesquihydrate

KAUST Repository

Chua, Ming Hui; Ni, Yong; Garai, Monalisa; Zheng, Bin; Huang, Kuo-Wei; Xu, Qing-Hua; Xu, Jianwei; Wu, Jishan

2015-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

The projected environmental impacts of transportation of radioactive material to the first United States repository site

International Nuclear Information System (INIS)

Cashwell, J.W.; Neuhauser, K.S.; Reardon, P.C.; McNair, G.W.

1987-01-01

The relative national environmental impacts of transporting spent fuel and other nuclear wastes to each of 9 candidate repository sites in the United States were analyzed for the 26-year period of repository operation. Two scenarios were examined for each repository: 1) shipment of 5-year-old spent fuel and Defence High-Level Waste (DHLW) directly from their points of origin to a repository (reference case); and 2) shipment of 5-year-old spent fuel to a Monitored Retrievable Storage (MRS) facility and shipment (by dedicated rail) of 10-year-old consolidated spent fuel from the MRS to a repository. Transport by either all truck or all rail from the points of origin were analyzed as bounding cases. The computational system used to analyze these impacts included the WASTES II logistics code and the RADTRAN III risk analysis code. The radiological risks for the reference case increased as the total shipment miles to a repository increased for truck; the risks also increased with mileage for rail but at a lower rate. For the MRS scenario the differences between repository sites were less pronounced for both modal options, because of the reduction in total shipment miles possible with the large dedicated rail casks. All the risks reported are small in comparison to the radiological risks due to 'natural background'

MAJOR REPOSITORY DESIGN ISSUES

International Nuclear Information System (INIS)

JACK N. BAILEY, DWAYNE CHESTNUT, JAMES COMPTON AND RICHARD D. SNELL

1997-01-01

The Yucca Mountain Project is focused on producing a four-part viability assessment in late FY98. Its four components (design, performance assessment, cost estimate, and licensing development plan) must be consistent. As a tool to compare design and performance assessment options, a series of repository pictures were developed for the sequential time phases of a repository. The boundaries of the time phases correspond to evolution in the engineered barrier system (EBS)

A Deterministic Safety Assessment of a Pyro-processed Waste Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae; Choi, Jong Won

2012-01-01

A GoldSim template program for a safety assessment of a hybrid-typed repository system, called 'A-KRS', in which two kinds of pyro-processed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyro-processing of PWR nuclear spent fuels are disposed of, has been developed. This program is ready both for a deterministic and probabilistic total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios. The A-KRS has been deterministically assessed with 5 various normal and abnormal scenarios associated with nuclide release and transport in and around the repository. Dose exposure rates to the farming exposure group have been evaluated in accordance with all the scenarios and then compared among other.

An analysis of repository waste-handling operations

International Nuclear Information System (INIS)

Dennis, A.W.

1990-09-01

This report has been prepared to document the operational analysis of waste-handling facilities at a geologic repository for high-level nuclear waste. The site currently under investigation for the geologic repository is located at Yucca Mountain, Nye County, Nevada. The repository waste-handling operations have been identified and analyzed for the year 2011, a steady-state year during which the repository receives spent nuclear fuel containing the equivalent of 3000 metric tons of uranium (MTU) and defense high-level waste containing the equivalent of 400 MTU. As a result of this analysis, it has been determined that the waste-handling facilities are adequate to receive, prepare, store, and emplace the projected quantity of waste on an annual basis. In addition, several areas have been identified where additional work is required. The recommendations for future work have been divided into three categories: items that affect the total waste management system, operations within the repository boundary, and the methodology used to perform operational analyses for repository designs. 7 refs., 48 figs., 11 tabs

Evaluation of the thermal effect in a KBS-3 type repository. A literary survey

Energy Technology Data Exchange (ETDEWEB)

Goblet, P. [Ecole Nationale Superieure des Mines de Paris, Fontainebleau (France). Centre d' Informatique Geologique; Marsily, Ghislain de [Univ. Pierre et Marie Curie, Paris (France). Laboratoire de Geologie Appliquee

2000-03-01

This report provides an overview of the existing thermal studies in high-level nuclear waste disposal, based on the available literature assembled during this survey. Although the emphasis is on a granitic repository, some results obtained by experiments or numerical analyses of other rock types are also given. Excessive heat loading can generate mechanical failure of the rock, chemical degradation and transformation of the buffer and rock, water vaporisation and condensation. If the repository is backfilled and resaturated, the heat load can generate convective movement of the water and therefore, transport of dissolved elements away from the repository. The maximum temperature at the repository level is generally reached after a few hundred years, but even if the temperature starts to decrease, the total heat loading of the rock formation continues to increase, until the temperature front reaches the upper boundary of the system and releases the heat into the atmosphere. The total heat load of the host rock typically starts to decrease only after about 10,000 years. The mechanical effects can therefore peak long after the maximum temperature has been reached. The surface deformation of the rock by expansion (on the order of 1 m above a repository) is often reached at such large time-intervals. The maximum heat loading in a repository is an important design parameter when the extent of a repository is determined, given the amount of waste and the age at which this waste must be disposed. To determine this heat loading, it is necessary to define either the maximum acceptable temperature at the buffer-rock contact, and/or at the outer boundary of the canister. Design options include the nature and dimension of the buffer zone, its water saturation (in the case of clay) and the distance between canisters. The temperature distribution in the host rock, in the buffer and inside the waste package can be determined by thermal calculations, if the density of waste in the

Salt repository project closeout status report

International Nuclear Information System (INIS)

1988-06-01

This report provides an overview of the scope and status of the US Department of Energy (DOE's) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report reviews the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort. Each area is briefly described and the major items of information are noted. This report, the three salt Environmental Assessments, and the Site Characterization Plan are the suggested starting points for any search of the literature and information developed by the program participants. Prior to termination, DOE was preparing to characterize three candidate sites for the first mined geologic repository for the permanent disposal of high-level nuclear waste. The sites were in Nevada, a site in volcanic tuff; Texas, a site in bedded salt (halite); and Washington, a site in basalt. These sites, identified by the screening process described in Chapter 3, were selected from the nine potentially acceptable sites shown on Figure I-1. These sites were identified in accordance with provisions of the Nuclear Waste Policy Act of 1982. 196 refs., 21 figs., 11 tabs

Memory provisions for the Manche Surface Repository

International Nuclear Information System (INIS)

Dumont, Jean-Noel; Espiet-Subert, Florence

2015-01-01

The French La Manche repository site received its last radioactive waste package in 1994. In 2003, the official surveillance phase of the closed repository started under the supervision of Andra (the national industrial operator), the French Nuclear Safety Authority (ASN) and society (e.g. the local municipalities). Florence Espiet explained that information on the existence of the repository, its content, how it was operated and how it works needs to be preserved. It also is planned to review the information periodically for a minimum of 300 years. She described the creation of two documents on memory (a detailed and a summary one), both on permanent paper, and the preservation of the land registration. The latter constitutes 'passive' provisions for preserving memory. In addition, a number of 'active' provisions are and will be put in place: guided visits, exhibitions, partnerships with organisations dealing with memory preservation, and the creation of a think tank. The latter consists of local citizens and politicians, retired employees from Andra and artists that meet several times a year and reflect on memory preservation from the perspective of, for instance, local history, education, arts and rituals. Finally, two types of markers will be used to preserve the repository's memory: i) three herbaria cataloguing the plants growing on the site of the repository, including a very short description of the repository, will be stored at different sites in France; ii) a stele indicating the main characteristics of the repository, potentially linked to an art work, will be erected at the repository

ENHANCED CHARACTERIZATION OF THE REPOSITORY BLOCK REQUIREMENTS DOCUMENT (ECRB-RD)

International Nuclear Information System (INIS)

G.M. Teraoka

1998-01-01

This Enhanced Characterization of the Repository Block Requirements Document (ECRB-RD) provides applicable design and construction requirements for the Enhanced Characterization of the Repository Block (ECRB) East-West Drift and its associated equipment. This document also identifies the applicable requirements from the Exploratory Studies Facilities Design Requirements (ESFDR) Document (YMPICM-00 19, Revision 2, ICN- 1) for design and construction of the ECRB East-West Drift, ground support, constructor support utilities and components. These requirements have been tailored specifically for the ECRB East-West Drift design and construction. The allocated requirements for the ECRB East-West Drift are in Sections III through VI. The requirements in sections III through VI contain requirement numbers from the ESFDR, Rev 2, ICN-1 for reference back to the ESFDR. Each requirement in the ECRB-RD also identifies a trace to the Site Design and Test Requirements Document (YMP/CM-0021, Rev. 2, ICN-1) and 10CFR60 similar to the style used in the ESFDR. These traces to 10CFR60 are consistent with the 1995 version of 10CFR60 used by the SD and TRD and the ESFDR. Those ESFDR requirements statements that were technically modified are identified as such and those that were derived as part of this allocation are also identified. An activity evaluation has been performed in accordance with QAP-2-0 and has determined that the QA program is applicable to this document. Therefore, the development of this document was performed in compliance with QAP-3-5, Revision 7, Development of Technical Documents and checked and reviewed in compliance with Section 5.3. This is consistent with the IOC from R. Stambaugh to M. Lugo on the subject of ECRB-RD, Revision 1, TDPP Applicability (LV.SEI.,RMS.03/98-0 12, Dated 3/12/98). The ECRB East-West Drift includes those excavated underground openings to support enhanced characterization testing activities for the repository block and provides potential

INIS: Nuclear Grey Literature Repository

International Nuclear Information System (INIS)

Savić, Dobrica

2016-01-01

As one of the world's largest collections of published information on the peaceful uses of nuclear science and technology, INIS represents an extraordinary example of world cooperation. Currently, as INIS members, 130 countries and 24 international organizations share and allow access to their valuable nuclear information resources, preserving them for future generations and offering a freely available nuclear knowledge repository. Since its creation in 1970, INIS has collected and provided access to more than 3.8 million bibliographic references to publications, documents, technical reports, non-copyrighted documentation, and other grey literature, as well as over a million full texts. Public interest throughout the years in accessing the INIS Collection has been remarkable. This paper deals with the challenges faced by INIS in its endeavour to increase the use, accessibility, usability and expandability of its on-line repository. It also describes document collection, the features and characteristics of implementing a new search engine, as well as the lessons learned. (author)

Siting regions for deep geological repositories. Why just here?; Standortgebiete fuer geologische Tiefenlager. Warum gerade hier?

Energy Technology Data Exchange (ETDEWEB)

Rieser, A

2009-09-15

This report helps to the popularization of the Nagra works accomplished for the management and disposal of the radioactive wastes in Switzerland. The programme for management and disposal of the radioactive wastes are extensively determined by regulations. Protection of mankind and environment is the primary objective. The basic storage process is considered as having been solved. The question addressed in the report is where the facility has to be built; the site selection procedure includes five steps: 1) according to their type the wastes have to be allocated to two different repositories: for low- and intermediate-level wastes (L/ILW), and for high-level and alpha-toxic wastes (HLW); 2) the safety concept for both repositories and the requirements on the geology have to be determined; 3) large suitable geological-tectonic zones must be found where repositories could be built; 4) in these geological zones a suitable host rock has to be identified; 5) the most important spatial geological conditions of the host rock (minimum depth with respect to surface erosion, maximum depth in terms of engineering requirements, lateral extent) have to be identified. Based on these criteria, three suitable siting regions for a HLW repository were found in the North of Switzerland. The preferred host rock is Opalinus clay because of its very low permeability; it is therefore an excellent barrier against nuclide transport. In the three proposed siting regions, Opalinus clay is present in sufficient volumes at a suitable depth. For a L/ILW repository six different possible siting regions were identified, five in Northern Switzerland and one in Central Switzerland. In the three siting regions found for a possible HLW repository, it would also be possible to built a combined repository for both HLW and L/ILW wastes.

CCDC 866711: Experimental Crystal Structure Determination : catena-((mu~12~-5,5',5''-(Benzene-1,3,5-triyltris(methyleneoxy))-tri-isophthalato)-hexa-aqua-hexa-copper)

KAUST Repository

Eubank, J.F.; Nouar, F.; Luebke, Ryan; Cairns, Amy; Wojtas, L.; Al Kordi, Mohamed; Bousquet, T.; Hight, M.R.; Eckert, J.; Embs, J.P.; Georgiev, P.A.; Eddaoudi, Mohamed

2013-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Repository-Based Software Engineering Program: Working Program Management Plan

Science.gov (United States)

1993-01-01

Repository-Based Software Engineering Program (RBSE) is a National Aeronautics and Space Administration (NASA) sponsored program dedicated to introducing and supporting common, effective approaches to software engineering practices. The process of conceiving, designing, building, and maintaining software systems by using existing software assets that are stored in a specialized operational reuse library or repository, accessible to system designers, is the foundation of the program. In addition to operating a software repository, RBSE promotes (1) software engineering technology transfer, (2) academic and instructional support of reuse programs, (3) the use of common software engineering standards and practices, (4) software reuse technology research, and (5) interoperability between reuse libraries. This Program Management Plan (PMP) is intended to communicate program goals and objectives, describe major work areas, and define a management report and control process. This process will assist the Program Manager, University of Houston at Clear Lake (UHCL) in tracking work progress and describing major program activities to NASA management. The goal of this PMP is to make managing the RBSE program a relatively easy process that improves the work of all team members. The PMP describes work areas addressed and work efforts being accomplished by the program; however, it is not intended as a complete description of the program. Its focus is on providing management tools and management processes for monitoring, evaluating, and administering the program; and it includes schedules for charting milestones and deliveries of program products. The PMP was developed by soliciting and obtaining guidance from appropriate program participants, analyzing program management guidance, and reviewing related program management documents.

Evaluation of radionuclide releases from underground waste repositories using the method of status vectors

International Nuclear Information System (INIS)

Zappe, D.

1983-01-01

For safety analyses of underground repositories for radioactive wastes various possible release scenarios have to be defind and anticipated consequences to be calculated and compared. Normally only the main exposure pathways (i.e. the critical pathways) of the radionuclides disposed of in the repository are calculated using deterministic methods and varying the parameters. It is proposed to evaluate all the individual pathways including those differing considerably from the critical pathway by forming weighted averages of their consequences. This offers the possibility of including, without any restriction, in the evaluation of the repository the various possible events and processes that influence the function of barriers for the retention of radionuclides. Various states (scenarios) of a repository in a salt formation, which might occur in the course of time have been used as an example. The consequences related to these states and the probabilities of their occurrence or the scenario weights form the components of 'status vectors'. For low- and intermediate-level wastes the overall consequences obtained from these calculations are negligibly small, for high-level wastes they are about 3 x 10 - 5 Sv a - 1 /GW a. These values are reached if at least a part of the barriers is effective. Variations of the weighting factors for the states and their influence on the overall consequences are given. (author)

Waste inventory, waste characteristics and waste repositories in Japan

International Nuclear Information System (INIS)

Shimooka, K.

1997-01-01

There are two types of repositories for the low level radioactive wastes in Japan. One is a trench type repository only for concrete debris generated from the dismantling of the research reactor. According to the safety assurance system, Japan Atomic Energy Research Institute (JAERI) has disposed of the concrete debris arose from the dismantling of the Japan Power Demonstration Reactor (JPDR). The other type is the concreted pit with engineered barriers. Rokkasho Low Level Radioactive Waste Disposal Center has this type of repository mainly for the power plant wastes. Japan Nuclear Fuel Ltd. (JNFL) established by electric power companies is the operator of the LLW disposal project. JNFL began the storage operation in 1992 and buried approximately 60,000 drums there. Two hundred thousand drums of uniformly solidified, waste may be buried ultimately. 4 refs, 3 tabs

Investigations on the populations of introduced and resident micro-organisms in deep repositories and their effects on containment of radioactive wastes

International Nuclear Information System (INIS)

West, J.M.; Arme, S.C.; Christofi, N.; Philp, J.C.

1986-01-01

The present study has sought to establish basic facts concerning the importance of microbial presence in a radioactive waste repository. These are: (1) establishing the presence of microbes in relevant geological formations; (2) defining the importance of isolated groups to radioactive waste containment; (3) establishing the ability of sampled microbes to tolerate repository environmental conditions; (4) conducting preliminary work on microbial ability to influence radionuclide migration characteristics; (5) attempting basic modelling of the effects of micro-organisms on containment and radionuclide migration. Results have shown that micro-organisms of significance (e.g. sulphur cycle bacteria) are present in relevant formations. These groups can tolerate repository conditions and influence migration studies. Their growth, however, would seem to be limited by the nutrient availability. Simple modelling has concentrated on conservative calculations on the constraints of maximum effects of microbial contamination of a high-level waste repository

Safety analysis in subsurface repositories

International Nuclear Information System (INIS)

1985-06-01

The development of mathematical models to represent the repository-geosphere-biosphere system, and the development of a structure for data acquisition, processing, and use to analyse the safety of subsurface repositories, are presented. To study the behavior of radionuclides in geosphere a laboratory to determine the hydrodynamic dispersion coefficient was constructed. (M.C.K.) [pt

Design and construction issues associated with sealing of a repository in salt

International Nuclear Information System (INIS)

Cook, R.

1991-01-01

The isolation of radioactive wastes in geologic repositories requires that man-made penetrations such as shafts, tunnels and boreholes are adequately sealed. This paper presents the current design and construction issues for sealing a repository in salt and outlines some proposed solutions. The sealing components include shaft seals, tunnel seals, panel seals, and disposal room backfill. The performance requirements and construction constraints determine the types of materials selected and their necessary properties. The current issues of interest include: (1) selection of materials for rigid bulkheads used to promote recovery of the disturbed zone permeability; (2) the selection of bulkhead geometry to cutoff flow through more permeable zones, or zones where recovery of the backfill properties occurs more slowly or not at all; and (3) the interaction of fluids with hazardous wastes with brine and, subsequently, with seal materials that might affect seal material longevity. 19 refs., 5 figs., 1 tab

Performance assessment plans and methods for the Salt Repository Project

International Nuclear Information System (INIS)

1984-08-01

This document presents the preliminary plans and anticipated methods of the Salt Repository Project (SRP) for assessing the postclosure and radiological aspects of preclosure performance of a nuclear waste repository in salt. This plan is intended to be revised on an annual basis. The emphasis in this preliminary effort is on the method of conceptually dividing the system into three subsystems (the very near field, the near field, and the far field) and applying models to analyze the behavior of each subsystem and its individual components. The next revision will contain more detailed plans being developed as part of Site Characterization Plan (SCP) activities. After a brief system description, this plan presents the performance targets which have been established for nuclear waste repositories by regulatory agencies (Chapter 3). The SRP approach to modeling, including sensitivity and uncertainty techniques is then presented (Chapter 4). This is followed by a discussion of scenario analysis (Chapter 5), a presentation of preliminary data needs as anticipated by the SRP (Chapter 6), and a presentation of the SRP approach to postclosure assessment of the very near field, the near field, and the far field (Chapters 7, 8, and 9, respectively). Preclosure radiological assessment is discussed in Chapter 10. Chapter 11 presents the SRP approach to code verification and validation. Finally, the Appendix lists all computer codes anticipated for use in performance assessments. The list of codes will be updated as plans are revised

Thermal analyses of spent nuclear fuel repository

International Nuclear Information System (INIS)

Ikonen, K.

2003-06-01

This report contains the temperature dimensioning of the KBS-3V type 1- or 2-panel repository based on the rock properties measured from the Olkiluoto investigations. The report describes first the development of a calculation methodology for the thermal analysis of a repository for nuclear fuel. The disposed canisters produce residual heat due to decay (or disintegration) of radioactive products. The decay heat is conducted to surrounding rock mass. The methods were applied to determine the effect of different parameters on the highest canister temperature and to support the planning, dimensioning and operation of the repository. The thermal diffusivity of the rock is low and the heat released from the canisters is spread into the surrounding rock volume quite slowly causing thermal gradient in the rock close to canisters and the canister temperature is increased remarkably. The maximum temperature on the canister surface is limited to the design temperature of +100 deg C. However, due to uncertainties in thermal analysis parameters (like scattering in rock conductivity) the allowable calculated maximum canister temperature is set to 90 deg C causing a safety margin of 10 deg C. The allowable temperature is controlled by the spacing between adjacent canisters, adjacent tunnels and the distance between separate panels of the repository and the pre-cooling time affecting power of the canisters. Because of the fact that the disposal operation takes several decades, the moment of disposal of an individual canister in addition to the location has an influence on the maximum temperature in the canister. Also, a second disposal panel in the repository has a thermal interaction with the other panel. This interaction is expressed after a few decades at the strongest. It became apparent that the temperature of canister surfaces can be determined by analytic line heat source model much more efficiently than by numerical analysis, if the analytic model is first verified and

Stockholm international conference 2003 on geological repositories: Political and technical progress

International Nuclear Information System (INIS)

2004-01-01

The conference reviewed global progress made as well as current perspectives on the activities to develop geologic repositories. The objectives were to review the progress in policy making as well as technical issues and to strengthen international co-operation on waste management and disposal issues. The first day of the conference addressed the policy aspects of geological repositories and the second day featured the more technical issues. Session 1: International progress in performing long-term safety studies and security of geological disposal were discussed and reviewed with examples from OECD/NEA, Belgium, Sweden, USA, Switzerland and Russia. Session 2: Views on stakeholder involvement and decision making process were presented by international organisations and national implementers from Japan, United Kingdom, Belgium and OECD/NEA. Session 3: Views on stakeholder involvement and decision making process were presented by regional and local stakeholders from France, Finland, Korea and Sweden. Session 4: International instruments assisting in the implementation of geological repositories were discussed, for example ICRP and IAEA/NEA safety documents, Joint Convention, Safeguard agreements, Nuclear Liability Conventions, etc. Session 5: The contribution of Research, Development and Demonstration was discussed with overviews of the progress achieved on scientific and technical issues over the past four years. Progress and key issues were presented from Switzerland, USA, Finland, Japan, Sweden and IAEA. Each of the papers and poster presentations have been analysed and indexed separately

Digital Repositories An investigation of best practices for content recruitment to academic digital repositories and the conditions for their livelihood

CERN Document Server

Hagen, Reidun Anette

2009-01-01

A digital repository is a web accessible database, aimed at preserving the research material of an institution or scientific community. A digital repository serves as a tool for dissemination of research material and can increase the impact of the research by making it freely accessible. Digital repositories are often mentioned as a possible aid in relation to the Open Access debate; how research material should be freely accessible to anyone, anywhere at any time. However, for a digital repository to fully unleash its potential as a crucial component of Open Access, it is reliant on the ability to successfully collect and organize content. To a large extent this involves initiating self-archiving of research material by scientists throughout the academic world. This is not a trivial task, and many current repositories are inadequate in this respect, remaining empty, unvisited shelves. This thesis explores best practices for content recruitment to digital repositories, through the review of literature, and an...

The Effect of Subcutaneous Fat on Electrical Impedance Myography: Electrode Configuration and Multi-Frequency Analyses.

Directory of Open Access Journals (Sweden)

Le Li

Full Text Available This study investigates the impact of the subcutaneous fat layer (SFL thickness on localized electrical impedance myography (EIM, as well as the effects of different current electrodes, varying in distance and direction, on EIM output. Twenty-three healthy subjects underwent localized multi-frequency EIM on their biceps brachii muscles with a hand-held electrode array. The EIM measurements were recorded under three different configurations: wide (or outer longitudinal configuration 6.8 cm, narrow (or inner longitudinal configuration 4.5 cm, and narrow transverse configuration 4.5 cm. Ultrasound was applied to measure the SFL thickness. Coefficients of determination (R2 of three EIM variables (resistance, reactance, and phase and SFL thickness were calculated. For the longitudinal configuration, the wide distance could reduce the effects of the subcutaneous fat when compared with the narrow distance, but a significant correlation still remained for all three EIM parameters. However, there was no significant correlation between SFL thickness and reactance in the transverse configuration (R2 = 0.0294, p = 0.434. Utilizing a ratio of 50kHz/100kHz phase was found to be able to help reduce the correlation with SFL thickness for all the three configurations. The findings indicate that the appropriate selection of the current electrode distance, direction and the multi-frequency phase ratio can reduce the impact of subcutaneous fat on EIM. These settings should be evaluated for future clinical studies using hand-held localized arrays to perform EIM.

CCDC 1029500: Experimental Crystal Structure Determination : 1,3-Dibromo-5-butyryl-4H-thieno[3,4-c]pyrrole-4,6(5H)-dione

KAUST Repository

Warnan, Julien; Cabanetos, Clement; Bude, Romain; El Labban, Abdulrahman; LI, LIANG; Beaujuge, Pierre

2014-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

CCDC 836213: Experimental Crystal Structure Determination : (S,S)-2-((1,3-Dimethyl-4,5-diphenylimidazolidin-2-ylidene)amino)-1,3-dimethyl-4,5-diphenyl-4,5-dihydro-1H-imidazol-3-ium chloride ethyl acetate solvate monohydrate

KAUST Repository

Ma, Ting; Fu, Xiao; Kee, Choon Wee; Zong, Lili; Pan, Yuanhang; Huang, Kuo-Wei; Tan, Choon-Hong

2011-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

A GoldSim Based Biosphere Assessment Model for a HLW Repository

International Nuclear Information System (INIS)

Lee, Youn-Myoung; Hwang, Yong-Soo; Kang, Chul-Hyung

2007-01-01

To demonstrate the performance of a repository, the dose exposure to a human being due to nuclide releases from a repository should be evaluated and the results compared to the dose limit presented by the regulatory bodies. To evaluate a dose rate to an individual due to a long-term release of nuclides from a HLW repository, biosphere assessment models and their implemented codes such as ACBIO1 and ACBIO2 have been developed with the aid of AMBER during the last few years. BIOMASS methodology has been adopted for a HLW repository currently being considered in Korea, which has a similar concept to the Swedish KBS-3 HLW repository. Recently, not just only for verifying the purpose for biosphere assessment models but also for varying the possible alternatives to assess the consequences in a biosphere due to a HLW repository, another version of the assessment modesl has been newly developed in the frame of development programs for a total system performance assessment modeling tool by utilizing GoldSim. Through a current study, GoldSim approach for a biosphere modeling is introduced. Unlike AMBER by which a compartment scheme can be rather simply constructed with an appropriate transition rate between compartments, GoldSim was designed to facilitate the object-oriented modules by which specific models can be addressed in an additional manner, like solving jig saw puzzles

CCDC 831594: Experimental Crystal Structure Determination : 2,5-bis(2-octyldodecyl)-3,6-bis(5-(pyren-2-yl)-2-thienyl)-2,5-dihydropyrrolo[3,4-c]pyrrole-1,4-dione

KAUST Repository

Lee, O.P.; Yiu, A.T.; Beaujuge, Pierre; Woo, C.H.; Holcombe, T.W.; Millstone, J.E.; Douglas, J.D.; Chen, M.S.; Frechet, Jean

2012-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Long-term safety for KBS-3 repositories at Forsmark and Laxemar - a first evaluation. Main Report of the SR-Can project

International Nuclear Information System (INIS)

Hedin, Allan

2006-10-01

effective dose limit of about 1.4x10 -5 Sv/yr. This, in turn, corresponds to around one percent of the effective dose due to natural background radiation in Sweden. The time frame for the assessment is one million years after repository closure, in accordance with regulatory requirements. The above risk limit is applicable as a quantitative regulatory limit during approximately the first one hundred thousand years, and thereafter as a basis for discussing the protective capability of the repository, according to SSI. Following the introductory Chapter 1, this report outlines the methodology for the SR-Can assessment in Chapter 2, and presents in Chapter 3 the handling of features, events and processes, FEPs, of importance for long-term safety. Chapters 4, and 6 present the initial state of the system for both of the sites, and the plans and methods for handling external influences and internal processes, respectively. Safety functions and safety function indicators are discussed in Chapter 7. The collection of input data for the assessment is described in Chapter 8. The Material presented in the first eight chapters is utilised in the analysis of the reference evolution in Chapter 9, focussing on isolation, and Chapter 10, addressing radionuclide transport and dose assessments. Scenarios for the further evaluation of safety are selected in Chapter 11 and the selected scenarios are analysed in Chapter 12. Finally, conclusions and feedback are provided in Chapter 13. References are provided in Chapter 14. Appendix A is an account of how applicable regulations are addressed in the assessment. Miscellaneous calculation models are presented in Appendix B and Material relating to reviews of previous assessments in Appendix C. A glossary of abbreviations and specialised terms used in SR-Can is found in Appendix D

Long-term safety for KBS-3 repositories at Forsmark and Laxemar - a first evaluation. Main Report of the SR-Can project

Energy Technology Data Exchange (ETDEWEB)

Hedin, Allan (ed.)

2006-10-15

. The risk limit corresponds to an effective dose limit of about 1.4x10{sup -5} Sv/yr. This, in turn, corresponds to around one percent of the effective dose due to natural background radiation in Sweden. The time frame for the assessment is one million years after repository closure, in accordance with regulatory requirements. The above risk limit is applicable as a quantitative regulatory limit during approximately the first one hundred thousand years, and thereafter as a basis for discussing the protective capability of the repository, according to SSI. Following the introductory Chapter 1, this report outlines the methodology for the SR-Can assessment in Chapter 2, and presents in Chapter 3 the handling of features, events and processes, FEPs, of importance for long-term safety. Chapters 4, and 6 present the initial state of the system for both of the sites, and the plans and methods for handling external influences and internal processes, respectively. Safety functions and safety function indicators are discussed in Chapter 7. The collection of input data for the assessment is described in Chapter 8. The Material presented in the first eight chapters is utilised in the analysis of the reference evolution in Chapter 9, focussing on isolation, and Chapter 10, addressing radionuclide transport and dose assessments. Scenarios for the further evaluation of safety are selected in Chapter 11 and the selected scenarios are analysed in Chapter 12. Finally, conclusions and feedback are provided in Chapter 13. References are provided in Chapter 14. Appendix A is an account of how applicable regulations are addressed in the assessment. Miscellaneous calculation models are presented in Appendix B and Material relating to reviews of previous assessments in Appendix C. A glossary of abbreviations and specialised terms used in SR-Can is found in Appendix D.

Building Scientific Data's list of recommended data repositories

Science.gov (United States)

Hufton, A. L.; Khodiyar, V.; Hrynaszkiewicz, I.

2016-12-01

When Scientific Data launched in 2014 we provided our authors with a list of recommended data repositories to help them identify data hosting options that were likely to meet the journal's requirements. This list has grown in size and scope, and is now a central resource for authors across the Nature-titled journals. It has also been used in the development of data deposition policies and recommended repository lists across Springer Nature and at other publishers. Each new addition to the list is assessed according to a series of criteria that emphasize the stability of the resource, its commitment to principles of open science and its implementation of relevant community standards and reporting guidelines. A preference is expressed for repositories that issue digital object identifiers (DOIs) through the DataCite system and that share data under the Creative Commons CC0 waiver. Scientific Data currently lists fourteen repositories that focus on specific areas within the Earth and environmental sciences, as well as the broad scope repositories, Dryad and figshare. Readers can browse and filter datasets published at the journal by the host repository using ISA-explorer, a demo tool built by the ISA-tools team at Oxford University1. We believe that well-maintained lists like this one help publishers build a network of trust with community data repositories and provide an important complement to more comprehensive data repository indices and more formal certification efforts. In parallel, Scientific Data has also improved its policies to better support submissions from authors using institutional and project-specific repositories, without requiring each to apply for listing individually. Online resources Journal homepage: http://www.nature.com/scientificdata Data repository criteria: http://www.nature.com/sdata/policies/data-policies#repo-criteria Recommended data repositories: http://www.nature.com/sdata/policies/repositories Archived copies of the list: https

Radioactive Waste Repositories and Incentives to Local Communities

International Nuclear Information System (INIS)

Knapp, A.; Medakovic, S.

2008-01-01

Public acceptance of radioactive waste (RW) repository depends on various and often community-specific factors. Although radiological risk from a properly constructed low and intermediate level waste (LILW) repository is practically negligible, routine safety considerations will favor low populated areas and therefore probably underdeveloped communities. Repository acceptance in such communities is more likely to be facilitated by prospective benefits to local economy, such as infrastructure development and increased employment, as well as by dedicated financial incentives to the community. Direct financial compensation to the local community for acceptance of the repository has been considered in some documents in countries experienced in RW management, but it has not become a widely accepted practice. In Croatia, a possibility for such compensation is mentioned in the land use plan in conjunction with the prospective RW repository site. In Slovenia, the government has already specified the annual amount of 2.33 million euro as a compensation for 'limited land use' to be shared by local communities in the vicinity of the planned LILW repository during its operation. Applicability of the Slovenian compensations to the prospective joint Slovenian-Croatian repository is not yet clear, at least in the aspect of joint funding. The joint Slovenian-Croatian Decommissioning and LILW and SF management program for NPP Krsko from 2004 did conservatively include the compensations into the repository cost estimates, but that might not be retained in subsequent revisions of the Program. According to the agreement between governments of Slovenia and Croatia on the Nuclear power plant Krsko, Croatian side has no obligations to participate in 'public expenditures' introduced after the agreement, as would be the case of community compensations for LILW repository in Slovenia. Before further decisions on joint NPP Krsko waste management are made, including the issue of LILW

Preliminary analyses of scenarios for potential human interference for repositories in three salt formations

International Nuclear Information System (INIS)

1985-10-01

Preliminary analyses of scenarios for human interference with the performance of a radioactive waste repository in a deep salt formation are presented. The following scenarios are analyzed: (1) the U-Tube Connection Scenario involving multiple connections between the repository and the overlying aquifer system; (2) the Single Borehole Intrusion Scenario involving penetration of the repository by an exploratory borehole that simultaneously connects the repository with overlying and underlying aquifers; and (3) the Pressure Release Scenario involving inflow of water to saturate any void space in the repository prior to creep closure with subsequent release under near lithostatic pressures following creep closure. The methodology to evaluate repository performance in these scenarios is described and this methodology is applied to reference systems in three candidate formations: bedded salt in the Palo Duro Basin, Texas; bedded salt in the Paradox Basin, Utah; and the Richton Salt Dome, Mississippi, of the Gulf Coast Salt Dome Basin

Low- and intermediate-level waste repository-induced effects

Energy Technology Data Exchange (ETDEWEB)

Leupin, O.X.; Marschall, P.; Johnson, L.; Cloet, V.; Schneider, J. [National Cooperative for the Disposal of Radioactive Waste (NAGRA), Wettingen (Switzerland); Smith, P. [Safety Assessment Management Ltd, Henley-On-Thames, Oxfordshire (United Kingdom); Savage, D. [Savage Earth Associates Ltd, Bournemouth, Dorset (United Kingdom); Senger, R. [Intera Inc., Ennetbaden (Switzerland)

2016-10-15

system has been designed to perform with sufficient safety margin for a range of siting conditions. The barriers include the host rock, its surrounding geological setting, the waste forms, drums and the cementitious backfill. They have a range of attributes that intrinsically favour safety and that avoid or minimise detrimental phenomena and uncertainties or mitigate their effects. Nevertheless, potentially detrimental repository-induced effects remain and in the present report, these are investigated and discussed considering a broad spectrum of parameters, reflecting, among other things, the range of potential siting conditions. The L/ILW emplacement caverns are designed, constructed, operated and finally backfilled in such a way that formation of excavation damaged zones is limited. Specifically this is achieved by restricting the size of the excavations and the depth of the repository, using a low-deformation, controlled construction and excavation method and by the fact that the excavations will be backfilled relatively soon after construction with grain supported mortar. At expected repository depths, the caverns will need to be supported to ensure stability and worker protection; this will prevent rock falls and further extension of the EDZ. Based on the modelling results, it can be concluded that the extent of the EDZ around the L/ILW emplacement caverns will not exceed a thickness of one cavern diameter and that the hydraulic conductance of the EDZ around the emplacement caverns, access tunnels and shafts will not exceed a value of 10{sup -7} m{sup 3}/s. Self sealing of the EDZ and low hydraulic gradients along the tunnels will result in negligible radionuclide transport by the EDZ pathway. It is shown that gas pressure build-up is controlled by the gas transport capacity of the pathways between the main repository and the access tunnel forming the so-called EGTS. Results obtained with the sensitivity cases for a repository depth of 500 m below ground level

Low- and intermediate-level waste repository-induced effects

International Nuclear Information System (INIS)

Leupin, O.X.; Marschall, P.; Johnson, L.; Cloet, V.; Schneider, J.; Smith, P.; Savage, D.; Senger, R.

2016-10-01

system has been designed to perform with sufficient safety margin for a range of siting conditions. The barriers include the host rock, its surrounding geological setting, the waste forms, drums and the cementitious backfill. They have a range of attributes that intrinsically favour safety and that avoid or minimise detrimental phenomena and uncertainties or mitigate their effects. Nevertheless, potentially detrimental repository-induced effects remain and in the present report, these are investigated and discussed considering a broad spectrum of parameters, reflecting, among other things, the range of potential siting conditions. The L/ILW emplacement caverns are designed, constructed, operated and finally backfilled in such a way that formation of excavation damaged zones is limited. Specifically this is achieved by restricting the size of the excavations and the depth of the repository, using a low-deformation, controlled construction and excavation method and by the fact that the excavations will be backfilled relatively soon after construction with grain supported mortar. At expected repository depths, the caverns will need to be supported to ensure stability and worker protection; this will prevent rock falls and further extension of the EDZ. Based on the modelling results, it can be concluded that the extent of the EDZ around the L/ILW emplacement caverns will not exceed a thickness of one cavern diameter and that the hydraulic conductance of the EDZ around the emplacement caverns, access tunnels and shafts will not exceed a value of 10 -7 m 3 /s. Self sealing of the EDZ and low hydraulic gradients along the tunnels will result in negligible radionuclide transport by the EDZ pathway. It is shown that gas pressure build-up is controlled by the gas transport capacity of the pathways between the main repository and the access tunnel forming the so-called EGTS. Results obtained with the sensitivity cases for a repository depth of 500 m below ground level indicate that

THEREDA - a contribution to long-term safety of repositories of nuclear and non-nuclear wastes

International Nuclear Information System (INIS)

Altmaier, M.; Kienzler, B.; Marquardt, C.M.; Neck, V.; Voigt, W.; Wilhelm, S.

2008-01-01

Long-term safety analyses of German repositories of radioactive waste as well as underground repositories for chemical toxic waste and other uses (contaminated site remediation) urgently require a standardized, comprehensive thermodynamic reference database. The former 'Thermodynamic Standard Database Working Party' was set up to establish such a database. The activities of that group have been supported within the integrated 'THEREDA' (Thermodynamic Reference Database) project since July 2006 for an initial period of 3 years by the German Federal Ministries of Education and Research, of Economics, and by the Federal Office of Radiation Protection. THEREDA at present is composed of 5 partner institutions essentially representing the key German research institutions in the field of repository safety research. THEREDA is to improve the transparency and validity of safety analyses in Germany and, for the first time, provides consistent thermodynamic datasets for the repository options discussed in Germany. Quality levels are indicated for each thermodynamic quantity on the basis of unambiguously defined evaluation criteria, which allow users to either include or exclude data in accordance with the specific problems at hand. Missing thermodynamic data are substituted in THEREDA by well-founded estimates, thus permitting future model calculations for safety analysis to be carried out on a clearly broader basis of data. The data are managed centrally in a database and will be available to users free of charge on the Internet. Import formats allowing THEREDA to be transferred into the most common modeling codes (EQ3/6, PHREEQC, Geochemist's Workbench, CHEMAPP, etc.) are also made available free of charge. (orig.)

Proceedings of the 5th US/German Workshop on Salt Repository Research Design and Operation

Energy Technology Data Exchange (ETDEWEB)

Hansen, Francis D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Leigh, Christi [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Walter [Karlsruhe Inst. of Technology (KIT) (Germany); Bollingerfehr, Wilhelm [DBE Technology, Peine (Germany); Von Berlepsche, Thilo [DBE Technology, Peine (Germany)

2015-01-01

The 5th US/German Workshop on Salt Repository Research, Design, and Operation was held in Santa Fe New Mexico September 8-10, 2014. The forty seven registered participants were equally divided between the United States (US) and Germany, with one participant from The Netherlands. The agenda for the 2014 workshop was under development immediately upon finishing the 4th Workshop. Ongoing, fundamental topics such as thermomechanical behavior of salt, plugging and sealing, the safety case, and performance assessment continue to advance the basis for disposal of heat-generating nuclear waste in salt formations. The utility of a salt underground research laboratory (URL) remains an intriguing concept engendering discussion of testing protocol. By far the most interest in this years’ workshop pertained to operational safety. Given events at the Waste Isolation Pilot Plant (WIPP), this discussion took on a new sense of relevance and urgency.

Management of radioactive waste at Novi Han Repository

International Nuclear Information System (INIS)

Stefanova, I.G.; Mateeva, M.D.; Milanov, M.V.

2002-01-01

The Novi Han Repository is the only existing repository in Bulgaria for the disposal of radioactive waste from nuclear applications in industry, medicine and research. The repository was constructed in the early sixties according to the existing requirements. It was operated by the Institute for Nuclear Research and Nuclear Energy for more than thirty years without any accident or release of radioactivity to the environment, but without any investment for upgrading. As a consequence, the Bulgarian Nuclear Safety Authority temporarily stopped the operation of the repository in 1994. The measures for upgrading the Novi Han Repository, supported by the IAEA under TC Project BUL/4/005 'Increasing Safety of Novi Han Repository', are presented in this paper. They comprise: assessment of radionuclide inventory and future waste arisings, characterisation of disposal vaults, characterisation of the site, safety assessment, upgrading of the monitoring system, option study for the selection of treatment and conditioning processes and the development of a conceptual design for low and intermediate level waste processing and storage facility, immediate measures for improvement of the existing disposal vaults and infrastructure, construction of above-ground temporary storage structures, and resuming the operation of the Novi Han Repository. The necessary activities for re-licensing of the Novi Han Repository, construction of a waste processing and storage facility and a disposal facility for spent sealed sources are discussed. (author)

Ethical considerations surrounding nuclear waste repository siting and mitigation

International Nuclear Information System (INIS)

Peters, T.F.

1983-01-01

The potential long-term health and safety effects of the nuclear materials stored in repositories, the extremely long periods of time over which such materials may be dangerous, and the equity implications of the siting of a repository in any given area are unlike the issues involved in other large-scale projects. They involve major philosophical issues basic to human perspectives on social relationships and on insuring the future of mankind. Safety and permanence are the two basic criteria for determining whether a waste proposal is satisfactory. This chapter takes the approach of public (or micro) ethics, whose task is to 1) articulate and clarify public values relevant to a problem, 2) identify and evaluate public options, and 3) rank alternatives in some order of ethical preferability. It addresses the four major repository-related issues: uncertainty and risks, geographic equity, intergenerational ethics, and implementation ethics

Reliable predictions of waste performance in a geologic repository

International Nuclear Information System (INIS)

Pigford, T.H.; Chambre, P.L.

1985-08-01

Establishing reliable estimates of long-term performance of a waste repository requires emphasis upon valid theories to predict performance. Predicting rates that radionuclides are released from waste packages cannot rest upon empirical extrapolations of laboratory leach data. Reliable predictions can be based on simple bounding theoretical models, such as solubility-limited bulk-flow, if the assumed parameters are reliably known or defensibly conservative. Wherever possible, performance analysis should proceed beyond simple bounding calculations to obtain more realistic - and usually more favorable - estimates of expected performance. Desire for greater realism must be balanced against increasing uncertainties in prediction and loss of reliability. Theoretical predictions of release rate based on mass-transfer analysis are bounding and the theory can be verified. Postulated repository analogues to simulate laboratory leach experiments introduce arbitrary and fictitious repository parameters and are shown not to agree with well-established theory. 34 refs., 3 figs., 2 tabs

Foreign materials in the repository. Update of estimated quantities

International Nuclear Information System (INIS)

Karvonen, T.

2011-06-01

A variety of materials are used during the construction process and the operation of the repository for spent nuclear fuel at Olkiluoto in Eurajoki, Finland. In addition to materials necessary for the construction and operation, some materials may be transported into the repository with the ventilation air, as emissions from vehicles etc. Both of these two types of materials are considered here and both introduced quantities and the quantities that remain after the closure in the repository are estimated here based on the most recent information. This work is intended to update the previous estimations, and it takes advantage of the experience collected during the construction of the underground rock characterisation facility called ONKALO at Olkiluoto. The implemented quantities as well as designs and preliminary designs have been used in calculating the quantities of the foreign materials. The estimations made in this report are specific to a KBS-3V type repository. In some cases more generic information has been used, particularly when the relevant quantities have not been monitored in ONKALO. The estimations are based on the new repository layout produced in 2010 and consider the latest plans for grouting and rock support. As all of these plans are not final some quantities may change in the future. As the repository layout may still go through some changes this report also provides the foreign materials for a hundred meters of different deposition tunnels designed for the OL and LO type canisters1. The results have also been calculated for a space demanded by a deposition tunnel end plug and the tunnel lengths before and after one. The most significant foreign materials are certain accessory minerals of the clay materials followed by organic materials (including the organic carbon from the clay materials), cement, steel and silica. (orig.)

CAED Document Repository

Data.gov (United States)

U.S. Environmental Protection Agency — Compliance Assurance and Enforcement Division Document Repository (CAEDDOCRESP) provides internal and external access of Inspection Records, Enforcement Actions, and...

Upgrading of radon's type near surface repository in Latvia

International Nuclear Information System (INIS)

Abramenkovs, A.

2006-01-01

In 1959, the Soviet government decided to construct the near surface radioactive wastes repository 'Radons' near the Baldone city. It was put in operation in 1962. The changes in the development of the repository were induced by the necessarily to upgrade it for disposal of radioactive wastes from the decommissioning of the Salaspils Research Reactor (SRR). The safety assessment of repository was performed during 2000-2001 under the PHARE project for necessary upgrades of repository. The outline design for new vaults and interim storage for long lived radioactive wastes was elaborated during 2003-2004 years. The Environmental Impact Assessment (EIA) for upgrade of Baldone repository was performed during 2004-2005 years. It was found, that additional efforts must be devoted for solution of social aspects o for successful operation and upgrade of repository. It was shown by EIA, that the local population has a negative opinion against the upgrade of repository in Latvia. The main recommendations for upgrades were connected with increasing the safety of repository, increasing of PR activities for education of society and developing of compensation mechanism for local municipality. (author)

Selection of Corrosion Resistant Materials for Nuclear Waste Repositories

International Nuclear Information System (INIS)

R.B. Rebak

2006-01-01

Several countries are considering geological repositories to dispose of nuclear waste. The environment of most of the currently considered repositories will be reducing in nature, except for the repository in the US, which is going to be oxidizing. For the reducing repositories, alloys such as carbon steel, stainless steels and titanium are being evaluated. For the repository in the US, some of the most corrosion resistant commercially available alloys are being investigated. This paper presents a summary of the behavior of the different materials under consideration for the repositories and the current understanding of the degradation modes of the proposed alloys in ground water environments from the point of view of general corrosion, localized corrosion and environmentally assisted cracking

Numerical modeling of magma-repository interactions

NARCIS (Netherlands)

Bokhove, Onno

2001-01-01

This report explains the numerical programs behind a comprehensive modeling effort of magma-repository interactions. Magma-repository interactions occur when a magma dike with high-volatile content magma ascends through surrounding rock and encounters a tunnel or drift filled with either a magmatic

Predicting spent fuel oxidation states in a tuff repository

International Nuclear Information System (INIS)

Einziger, R.E.; Woodley, R.E.

1987-01-01

Nevada Nuclear Waste Storage Investigations Project (NNWSI) is studying the suitability of the tuffaceous rocks at Yucca Mountain as a waste repository for spent fuel disposal. The oxidation state of the LWR spent fuel in the moist air environment of a tuff repository could be a significant factor in determining its leaching and dissolution characteristics. Predictions as to which oxidation states would be present are important in analyzing such a repository and thus the present study was undertaken. A set of TGA (thermogravimetric analysis) tests were conducted on well-controlled samples of irradiated PWR fuel with time and temperature as the only variables. The tests were conducted between 140 and 225 0 C for a duration up to 2200 hours. The weight gain curves were analyzed in terms of diffusion through a layer of U 3 O 7 , diffusion into the grains to form a solid solution, a simplified empirical representation of a combination of grain boundary diffusion and bulk grain oxidation. Reaction rate constants were determined in each case, but analysis of these data could not establish a definitive mechanism. 21 refs., 10 figs., 3 tabs

Multinational/regional repository - an illusion or solution

International Nuclear Information System (INIS)

Mele, I.

2006-01-01

The concept and current status of multinational and regional repositories are presented in the paper. Particular emphasis is given to the results and findings of the recent EU project SAPIERR, investigating the feasibility of regional repository concepts in Europe. Prospects for further development of multinational repositories are also brought forward and the impact and potential benefits of this approach to our national disposal programme are discussed as well. (author)

Characteristics of mercury emission from linear type of spent fluorescent lamp.

Science.gov (United States)

Rhee, Seung-Whee; Choi, Hyo-Hyun; Park, Hun-Su

2014-06-01

In order to recycle the linear type of SFL (spent fluorescent lamp), mercury from SFL should be controlled to prevent leaking into the environment. For mercury emission from SFL, mercury concentration is estimated in the parts of SFL such as glass tube, phosphor powder, and base cap using the end-cutting unit. It is also evaluated mercury emission in the effluent gas in the end-cutting unit with changing flow rate. From the results of mercury emission from SFLs, phosphor powder has greater than 80% of mercury amount in SFL and about 15% of mercury amount contained in glass tube. The initial mercury concentration in vapor phase is almost decreased linearly with increasing airflow rate from 0.7 L/min to 1.3 L/min. It is desirable that airflow rate should be high until the concentration of mercury vapor will be stable because the stabilized concentration becomes to be low and the stabilized time goes to be short as increased airflow rate. From KET and TCLP results, finally, phosphor powder should be managed as a hazardous waste but base-cap and glass are not classified as hazardous wastes. Copyright © 2013 Elsevier Ltd. All rights reserved.

NASA Biological Specimen Repository

Science.gov (United States)

McMonigal, K. A.; Pietrzyk, R. A.; Sams, C. F.; Johnson, M. A.

2010-01-01

The NASA Biological Specimen Repository (NBSR) was established in 2006 to collect, process, preserve and distribute spaceflight-related biological specimens from long duration ISS astronauts. This repository provides unique opportunities to study longitudinal changes in human physiology spanning may missions. The NBSR collects blood and urine samples from all participating ISS crewmembers who have provided informed consent. These biological samples are collected once before flight, during flight scheduled on flight days 15, 30, 60, 120 and within 2 weeks of landing. Postflight sessions are conducted 3 and 30 days after landing. The number of in-flight sessions is dependent on the duration of the mission. Specimens are maintained under optimal storage conditions in a manner that will maximize their integrity and viability for future research The repository operates under the authority of the NASA/JSC Committee for the Protection of Human Subjects to support scientific discovery that contributes to our fundamental knowledge in the area of human physiological changes and adaptation to a microgravity environment. The NBSR will institute guidelines for the solicitation, review and sample distribution process through establishment of the NBSR Advisory Board. The Advisory Board will be composed of representatives of all participating space agencies to evaluate each request from investigators for use of the samples. This process will be consistent with ethical principles, protection of crewmember confidentiality, prevailing laws and regulations, intellectual property policies, and consent form language. Operations supporting the NBSR are scheduled to continue until the end of U.S. presence on the ISS. Sample distribution is proposed to begin with selections on investigations beginning in 2017. The availability of the NBSR will contribute to the body of knowledge about the diverse factors of spaceflight on human physiology.

The Lincoln Repository presentation: ten reasons why you should put a copy of your work in the Repository

OpenAIRE

Stainthorp, Paul

2010-01-01

Slideshow presentation created to promote the Lincoln Repository to staff at the University of Lincoln. Consists of ten reasons why academic authors should consider depositing copies of their work in the Repository.

International perspective on repositories for low level waste

International Nuclear Information System (INIS)

Bergstroem, Ulla; Pers, Karin; Almen, Ylva

2011-12-01

Nuclear energy production gives rise to different types of radioactive waste. The use of nuclear isotopes within the research, industry and medical sectors also generates radioactive waste. To protect man and the environment from radiation the waste is isolated and contained by deposition in repositories. These repositories may have various designs regarding location, barriers etc depending on the potential danger of the waste. In Sweden, low- and intermediate level waste (LILW) is disposed of in the SFR repository in Forsmark. The repository is located 60 metres down into the bedrock under the bottom of the sea and covered by 6 metres of water. It is planned to extend SFR to accommodate decommissioning waste from the dismantling of the Swedish nuclear power facilities and also for the additional operation waste caused by the planned prolonged operation time. When planning the extension consultations will be carried out with the host municipality, authorities, organisations and general public. In planning the extension, SKB has performed a worldwide compilation of how other countries have, or plan to, handle the final disposal of similar wastes. The aim of this report is to give a brief description of LILW repositories worldwide; including general brief descriptions of many facilities, descriptions of the waste and the barriers as well as safety assessments for a few chosen repositories which represent different designs. The latter is performed, where possible, to compare certain features against the Swedish SFR. To provide a background and context to this study, international organisations and conventions are also presented along with internationally accepted principles regarding the management of radioactive waste. Similar to SFR, suitable locations for the repositories have, in many countries, been found at sites that already have, or used to have nuclear activities, such as reactor sites. Abandoned and disused mines, such as the salt mines in Germany, also

International perspective on repositories for low level waste

Energy Technology Data Exchange (ETDEWEB)

Bergstroem, Ulla; Pers, Karin; Almen, Ylva (SKB International AB (Sweden))

2011-12-15

Nuclear energy production gives rise to different types of radioactive waste. The use of nuclear isotopes within the research, industry and medical sectors also generates radioactive waste. To protect man and the environment from radiation the waste is isolated and contained by deposition in repositories. These repositories may have various designs regarding location, barriers etc depending on the potential danger of the waste. In Sweden, low- and intermediate level waste (LILW) is disposed of in the SFR repository in Forsmark. The repository is located 60 metres down into the bedrock under the bottom of the sea and covered by 6 metres of water. It is planned to extend SFR to accommodate decommissioning waste from the dismantling of the Swedish nuclear power facilities and also for the additional operation waste caused by the planned prolonged operation time. When planning the extension consultations will be carried out with the host municipality, authorities, organisations and general public. In planning the extension, SKB has performed a worldwide compilation of how other countries have, or plan to, handle the final disposal of similar wastes. The aim of this report is to give a brief description of LILW repositories worldwide; including general brief descriptions of many facilities, descriptions of the waste and the barriers as well as safety assessments for a few chosen repositories which represent different designs. The latter is performed, where possible, to compare certain features against the Swedish SFR. To provide a background and context to this study, international organisations and conventions are also presented along with internationally accepted principles regarding the management of radioactive waste. Similar to SFR, suitable locations for the repositories have, in many countries, been found at sites that already have, or used to have nuclear activities, such as reactor sites. Abandoned and disused mines, such as the salt mines in Germany, also

Data repositories for medical education research: issues and recommendations.

Science.gov (United States)

Schwartz, Alan; Pappas, Cleo; Sandlow, Leslie J

2010-05-01

The authors explore issues surrounding digital repositories with the twofold intention of clarifying their creation, structure, content, and use, and considering the implementation of a global digital repository for medical education research data sets-an online site where medical education researchers would be encouraged to deposit their data in order to facilitate the reuse and reanalysis of the data by other researchers. By motivating data sharing and reuse, investigators, medical schools, and other stakeholders might see substantial benefits to their own endeavors and to the progress of the field of medical education.The authors review digital repositories in medicine, social sciences, and education, describe the contents and scope of repositories, and present extant examples. The authors describe the potential benefits of a medical education data repository and report results of a survey of the Society for Directors of Research in Medicine Education, in which participants responded to questions about data sharing and a potential data repository. Respondents strongly endorsed data sharing, with the caveat that principal investigators should choose whether or not to share data they collect. A large majority believed that a repository would benefit their unit and the field of medical education. Few reported using existing repositories. Finally, the authors consider challenges to the establishment of such a repository, including taxonomic organization, intellectual property concerns, human subjects protection, technological infrastructure, and evaluation standards. The authors conclude with recommendations for how a medical education data repository could be successfully developed.

Determination of gross alpha and gross beta in soil around repository facility at Bukit Kledang, Perak, Malaysia

Science.gov (United States)

Adziz, Mohd Izwan Abdul; Siong, Khoo Kok

2018-04-01

Recently, the Long Term Storage Facility (LTSF) in Bukit Kledang, Perak, Malaysia, has been upgraded to repository facility upon the completion of decontamination and decommissioning (D&D) process. Thorium waste and contaminated material that may contain some minor amounts of thorium hydroxide were disposed in this facility. This study is conducted to determine the concentrations of gross alpha and gross beta radioactivities in soil samples collected around the repository facility. A total of 12 soil samples were collected consisting 10 samples from around the facility and 2 samples from selected residential area near the facility. In addition, the respective dose rates were measured 5 cm and 1 m above the ground by using survey meter with Geiger Muller (GM) detector and Sodium Iodide (NaI) detector. Soil samples were collected using hand auger and then were taken back to the laboratory for further analysis. Samples were cleaned, dried, pulverized and sieved prior to analysis. Gross alpha and gross beta activity measurements were carried out using gas flow proportional counter, Canberra Series 5 XLB - Automatic Low Background Alpha and Beta Counting System. The obtained results show that, the gross alpha and gross beta activity concentration ranged from 1.55 to 5.34 Bq/g with a mean value of 3.47 ± 0.09 Bq/g and 1.64 to 5.78 Bq/g with a mean value of 3.49 ± 0.09 Bq/g, respectively. These results can be used as an additional data to represent terrestrial radioactivity baseline data for Malaysia environment. This estimation will also serve as baseline for detection of any future related activities of contamination especially around the repository facility area.

The Hidden Risk Decisions in Waste Repository Regulation

International Nuclear Information System (INIS)

Frishman, Steve

2001-01-01

The move toward risk-informed, performance-based regulation of activities involving radioactive materials is becoming wide spread and broadly applied. While this approach may have some merit in specific applications in which there is a considerable body of experience, its strict application in regulation of geologic repositories for highly radioactive wastes may not be appropriate for this unproven and socially controversial technology. The U.S. Nuclear Regulatory Commission describes risk-informed, performance-based regulation as 'an approach in which risk insights, engineering analysis and judgement (eg. defense in depth), and performance history are used to (1) focus attention on the most important activities, (2) establish objective criteria based upon risk insights for evaluating performance, (3) develop measurable or calculable parameters for monitoring system and licensee performance, and (4) focus on the results as the primary basis for regulatory decision-making.' Both the risk-informed and performance-based elements of the approach are problematic when considering regulation of geologic repositories for highly radioactive wastes - an activity yet to be accomplished by any nation. In investigating potential sites for geologic repositories there will always be residual uncertainty in understanding the natural system and the events and processes that affect it. The more complex the natural system, the greater will be the uncertainty in both the data and the models used to describe the characteristics of the site's natural barriers, and the events and processes that could affect repository waste isolation. The engineered barriers also are subject to uncertainties that are important to the repository system. These uncertainties translate themselves into a range of probabilities that certain events or processes, detrimental to waste isolation, will occur. The uncertainties also translate to a range of consequences and magnitudes of consequences, should the

The development of safeguards for geological repositories

International Nuclear Information System (INIS)

Van der Meer, K.

2009-01-01

Traditionally, research and development on geological repositories for High Level Waste (HLW) focuses on the short- and long-term safety aspects of the repository. If the repository will also be used for the disposal of spent fuel, safeguards aspects have to be taken into account. Safety and safeguards requirements may be contradictory; the safety of a geological repository is based on the non-intrusion of the geological containment, while safeguards require regular inspections of position and amount of the spent fuel. Examples to reconcile these contradictory requirements are the use of information required for the safety assessment of the geological repository for safeguards purposes and the adaptation of the safeguards approach to use non-intrusive inspection techniques. The principles of an inspection approach for a geological repository are now generally accepted within the IAEA. The practical applicability of the envisaged inspection techniques is still subject to investigation. It is specifically important for the Belgian situation that an inspection technique can be used in clay, the geological medium in which Belgium intends to dispose its HLW and spent fuel. The work reported in this chapter is the result of an international cooperation in the framework of the IAEA, in which SCK-CEN participates

Investigative study of standards for digital repositories and related services

CERN Document Server

Foulonneau, Muriel; Badolato, Anne-Marie

2008-01-01

This study is meant for institutional repository managers, service providers, repository software developers and generally, all players taking an active part in the creation of the digital repository infrastructure for e-research and e-learning. It reviews the current standards, protocols and applications in the domain of digital repositories. Special attention is being paid to the interoperability of repositories to enhance the exchange of data in repositories. It aims to stimulate discussion about these topics and supports initiatives for the integration of and, where needed, development of

The rock mechanical stability of the VLJ repository

International Nuclear Information System (INIS)

Kuula, H.; Johansson, E.

1991-03-01

The aim of the study was to determine the rock mechanical stability around the VLJ repository based on the rock mechanical monitoring and rock mechanical modeling. Rock mechanical calculations were made in order to calculate the rock mass displacements and to analyze the stability around the VLJ repository The calculations were performed with three diiferent methods: continuum finite difference code FLAC, distinct element code UDEC and three dimensional distinct element code 3DEC. The first analyses were based on preliminary site investigations. The final modeling was based on investigations and rock mechanical monitoring done during the excavation. Some sensitive analyses were also performed. The modelled rock mass behaviour and the measured behaviour are generally close to each other. Both results show that the VLJ repository is rock mechanically stable. The modelled displacements and stresses were small enough to cause no instability around the rock caverns. The measured values do not indicate any discontinuous deformations like block movements or joint slip. The measured displacements in the extensometers during excavation indicates that the rock mass is even stiffer than anticipated

Digital Preservation Tools for Repository Managers 2: institutional and lifecycle preservation costs

OpenAIRE

Hitchcock, Steve; Beagrie, Neil; Hole, Brian

2010-01-01

The 5-module JISC KeepIt course on Digital Preservation Tools for Repository Managers was designed by repository managers. Each module consists of a mix of short presentations and hands-on exercises to learn about the basics and gain practice with each of the tools covered. Module 2 covers lifecycle costs for managing digital objects, based on the LIFE approach, and institutional costs. Tools include Keeping Research Data Safe (KRDS) a model, method and survey for assessing the institutional ...

Refinancing of the search for a repository and of the repository for heat generating radioactive Waste. Pt. 2

International Nuclear Information System (INIS)

Moench, Christoph

2013-01-01

Part I of this article, which appeared in the preceding issue, described in general terms the background to the search for a disposal site and the result of the exploration to date of the repository, which would appear to be suitable from a mining standpoint according to the present knowledge. According to the rules in effect up to now, the exploration and construction would be financed by advance payments on the contributions of the waste producing companies, in particular the utility companies. The working draft of an 'Act on the search for and selection of a site for a repository for heat generating radioactive waste' (Gesetz zur Suche und Auswahl eines Standortes fuer ein Endlager fuer waermeentwickelnde radioaktive Abfaelle) from autumn 2012 provides for a new version of section 21b Atomic Energy Act, under which the costs for 'carrying out a repository selection procedure pursuant to the Repository Selection Act (Standort-auswahlgesetz)' would be allocated to the future users of the repository who are obliged to make contributions as a 'necessary expense'. Part II evaluates this provision of the working draft on the basis of the financial constitutional law. A comparison of sites is not a measure that could be allocated to the future users of the repository who are obliged to make contributions as a 'necessary expense'. Moreover, there is a lack of responsibility for the financing and of a legally relevant advantage that would be conferred by a cumulative alternative repository search for the later users of the repository who are obliged to provide the pre-financing. The costs can therefore not be allocated to the later users as either a contribution or a special charge, not even by way of an association with mandatory membership (Zwangsverband). They must be borne by the state. Consequently, the allocation stipulated by provision would constitute an impermissible charge under financial constitutional law. (orig.)

CCDC 878572: Experimental Crystal Structure Determination : catena-(bis(chloro-(4,4',4'',4'''-porphyrin-5,10,15,20-tetrayltetrakis(1-methylpyridinium))-cadmium) bis(mu~6~-biphenyl-3,4',5-tricarboxylato)-pentakis(mu~5~-biphenyl-3,4',5-tricarboxylato)-(mu~4~-biphenyl-3,4',5-tricarboxylato)-tetraaqua-di-cadmium-hepta-manganese unknown solvate)

KAUST Repository

Zhang, Zhenjie; Gao, Wen-Yang; Wojtas, L.; Ma, Shengqian; Eddaoudi, Mohamed; Zaworotko, M.J.

2013-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Knowledge and opinion about smoke-free laws and second-hand smoke among hospitality venue managers in Gujarat and Andhra Pradesh, India.

Science.gov (United States)

Gupta, Vinay K; Arora, Monika; Sharma, Indrani; Nazar, Gaurang P; Modi, Bhavesh; Singh, Deepti; Millett, Christopher; Reddy, K Srinath

2013-01-01

India's Smoke-Free Law (SFL) was implemented in 2004 and reinforced on 2nd October 2008. This research attempts to understand the knowledge and opinion of hospitality venue (HV) managers about second-hand smoke (SHS) and SFL as well as self-reported compliance with SFL in two Indian states. A survey was conducted among 804 randomly sampled HVs from project STEPS (Strengthening of tobacco control efforts through innovative partnerships and strategies) in Gujarat and Andhra Pradesh, India. Four hundred and three HVs from two districts in Gujarat and 401 HVs from six districts in Andhra Pradesh were selected. The owner, manager or supervisor of each HV was interviewed using a pre-tested structured interview schedule. Association of opinion scales with respondents' background characteristics was assessed through the analysis of variance (ANOVA) method. Out of the 403 respondents in Gujarat and 401 in Andhra Pradesh, 56.1% and 84.3% had knowledge about SFL respectively. Compliance of HVs with SFL was 21.8% in Gujarat and 31.2% in Andhra Pradesh as reported by the managers. Knowledge about SHS was noted among 39.7% of respondents in Gujarat and 25.4% in Andhra Pradesh. Bivariate results indicated that more educated HV managers showed higher support for smoke-free public places (P < 0.001) and were more concerned about the health effects of SHS exposure (P = 0.002). Complete self-reported compliance with, and knowledge of SFL as well as SHS was not found in Gujarat and Andhra Pradesh. The education level of HV managers is an important determinant to ensure compliance with SFL in public places.

Investigations of possibilities to dispose of spent nuclear fuel in Lithuania: a model case. Volume 3, Generic Safety Assessment of Repository in Crystalline Rocks

International Nuclear Information System (INIS)

Motiejunas, S.; Poskas, P.

2005-01-01

In this Volume a generic safety assessment of the repository for spent nuclear fuel in crystalline rock in Lithuania is presented. Modeling of safety relevant radionuclide release from the defected canister and their transport through the near field and far field was performed. Doses to humans due to released radionuclides in the well water were calculated and compared with the dose restrictions existing in Lithuania. For this stage of generic safety assessment only two scenarios were chosen: base scenario and canister defect scenario. KBS-3 concept developed by SKB for disposal of spent nuclear fuel in Sweden was chosen as prototype for repository in crystalline basement in Lithuania. The KBS-3H design with horizontal canister emplacement is proposed as a reference design for Lithuania

Modelling of Fracture Initiation, Propagation and Creep of a KBS-3V and KBS-3H Repository in Sparsely Fractured Rock with Application to the Design at Forsmark Candidate Site

International Nuclear Information System (INIS)

Backers, Tobias; Stephansson, Ove

2008-01-01

The stability issues of deposition holes of a repository layout according to the KBS-3 concept in the sparsely fractured Forsmark granites are analysed with the emphasis on fracture mechanics. At the start of the project the rock mass is viewed as a continuum. In a second step explicit fracture networks are introduced and included in the numerical rock fracture models. The software Fracod2D was used for the rock fracture mechanics analysis. Assuming deposition holes located in a continuous, homogeneous elastic rock mass and The presented stress state of the rock mass the following results were obtained: For single KBS-3H deposition holes oriented in the direction of the minimum horizontal stress, Sh, bore hole breakouts are introduced for all depth levels. For KBS-3H holes which are oriented in direction of SH, no significant fracturing can be expected. In case of vertical deposition holes according to KBS-3V an increased risk of fracturing at greater depth levels (> 500m) is evident. At shallow depth levels ( 5MPa gives a favourable situation about spalling for the KBS-3H and KBS-3V layouts. To prevent spalling, it is important to build up a swelling pressure soon after excavation, so that the enhanced stresses in the surrounding of the deposition ii holes are reduced. This has a positive impact on other excavation activities and also on time-dependent fracturing. After excavation and filling of the deposition holes with subsequent increase of swelling pressure, the temperature will increase in the vicinity of the excavation. For the range of swelling pressures predicted for the KBS-3 concept, i.e. 5.5MPa to 7.2MPa, no significant fracturing for the KBS-3H concept with the axis parallel SH at depths below about 600m was discovered. The results from other layouts bare the risk of partly significant fracturing. About 60ka from closing the repository an ice cover of approximately 3km is expected over Forsmark. This dead load increases the in-situ stresses and

Institutional Repositories as Infrastructures for Long-Term Preservation

Science.gov (United States)

Francke, Helena; Gamalielsson, Jonas; Lundell, Björn

2017-01-01

Introduction: The study describes the conditions for long-term preservation of the content of the institutional repositories of Swedish higher education institutions based on an investigation of how deposited files are managed with regards to file format and how representatives of the repositories describe the functions of the repositories.…

CCDC 1006896: Experimental Crystal Structure Determination : 1,3,5-tris(4-(2,4-Diamino-1,3,5-triazin-6-yl)phenyl)benzene unknown solvate

KAUST Repository

Li, Peng; He, Yabing; Zhao, Yunfeng; Weng, Linhong; Wang, Hailong; Krishna, Rajamani; Wu, Hui; Zhou, Wei; O'Keeffe, Michael; Han, Yu; Chen, Banglin

2014-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Evaluation of alternative shaft-sinking techniques for high-level nuclear waste (HLW) deep geologic repositories. Final report (Task 3), June 1981-July 1982

International Nuclear Information System (INIS)

Gonano, L.; Findley, D.; Wildanger, W.; Gates, R.; Phillips, S.

1983-03-01

This report represents the results of Task 3 of US Nuclear Regulatory Commission (NRC) Contract, Technical Assistance for Repository Design. The purpose of the complete project is to provide NRC with technical assistance for the following reasons: To enable the focused, adequate review by NRC of aspects related to design and construction of an in situ test facility and final geologic repository, as presented in US Department of Energy (DOE) Site Characterization Reports (SRC), To ascertain that the DOE site characterization program will provide, as far as possible, all the information necessary to permit a review to be conducted by NRC of a license application for construction authorization. It is assumed that the Site Characterization Report and License Application will describe the exploratory shaft and concept designs for the repository shafts. This report provides a comparative evaluation of various shaft sinking techniques for production shafts for a repository. The primary comparative evaluation has been conducted for 14-ft internal diameter shafts developed in two composite media using four different methods of sinking/lining. The technical, cost and schedule comparisons draw a major distinction between shafts sunk blind and those which utilize bottom access. Based on the system of ranking introduced to grade the significant attributes of each method and the resulting design, it is concluded that for application to repository access, no one particular method of sinking exhibits a clear overall superiority. When a specific site is made available for a study of the most suitable shaft sinking methods, it will be necessary to establish actual geological conditions and technological capabilities and the comparisons presented herein reviewed accordingly

Characteristics of potential repository wastes

International Nuclear Information System (INIS)

Notz, K.J.

1989-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the spent fuels and other wastes that will be disposed of in a geologic repository. The two major sources of these materials are commercial light-water reactor (LWR) spent fuel and immobilized high-level waste (HLW). Other wastes that may require long-term isolation include non-LWR spent fuels and miscellaneous sources such as activated metals. Detailed characterizations are required for all of these potential repository wastes. These characterizations include physical, chemical, and radiological properties. The latter must take into account decay as a function of time. This information has been extracted from primary data sources, evaluated, and assembled in a Characteristics Data Base which provides data in four formats: hard copy standard reports, menu-driven personal computer (PC) data bases, program-level PC data bases, and mainframe computer files. The Characteristics Data Base provides a standard set of self-consistent data to the various areas of responsibility including systems integration and waste stream analysis, storage, transportation, and geologic disposal. The data will be used for design studies, evaluation of alternatives, and system optimization by OCRWM and supporting contractors. 7 refs., 5 figs., 7 tabs

Electronic Repository of Russian Historical Statistics

NARCIS (Netherlands)

Tykhonov, Vyacheslav; Kessler, Gijs; Markevich, Andrei; de Vries, Jerry

2014-01-01

The Electronic Repository for Russian Historical Statistics brings together data extracted from various published and unpublished sources in one place. Its principal focus is Russian economic and social history of the last three centuries (18th-21st). The repository caters to the needs of the

Curriculum influence on interdisciplinary oral health education and practice.

Science.gov (United States)

Clark, Melinda; Quinonez, Rocio; Bowser, Jonathan; Silk, Hugh

2017-06-01

Oral diseases are very prevalent across the lifespan and impact overall health, yet are largely preventable. The Smiles for Life (SFL) curriculum was created to educate healthcare providers about oral disease and support integration of oral health and primary care. This study examines SFL's influence on clinical practice and education. Surveys were sent to registered users of SFL. Users who self-identified as direct care providers (DCPs), or educators, were included in the analysis. Survey response rate was 18 percent, with 87 percent identifying as DCPs and 13 percent as educators. Across professions, 85 percent of DCPs reported SFL influencing their practice to some degree, with variance among profession type and experience. DCPs most commonly reported that SFL led them to improve how they conduct oral health activities, with 60 percent performing the activity more skillfully following completion of SFL. Fluoride varnish application was the most common practice behavior initiated, and caries risk assessments was the oral health activity affected to the greatest degree. A majority of educators (94 percent) reported that SFL led them to incorporate or enhance oral health in their teaching. SFL helped educators emphasize the importance of oral health, improved their ability to teach content, raised motivation, and reduced barriers to teaching oral health. Data supports that SFL is positively influencing oral health practice across professions, especially in areas of caries risk assessment and fluoride varnish application. SFL improves the frequency and quality with which DCPs and educators participate in oral health activities, and facilitates oral health inclusion in primary care. © 2017 American Association of Public Health Dentistry.

VerSi. A method for the quantitative comparison of repository systems

Energy Technology Data Exchange (ETDEWEB)

Kaempfer, T.U.; Ruebel, A.; Resele, G. [AF-Consult Switzerland Ltd, Baden (Switzerland); Moenig, J. [GRS Braunschweig (Germany)

2015-07-01

Decision making and design processes for radioactive waste repositories are guided by safety goals that need to be achieved. In this context, the comparison of different disposal concepts can provide relevant support to better understand the performance of the repository systems. Such a task requires a method for a traceable comparison that is as objective as possible. We present a versatile method that allows for the comparison of different disposal concepts in potentially different host rocks. The condition for the method to work is that the repository systems are defined to a comparable level including designed repository structures, disposal concepts, and engineered and geological barriers which are all based on site-specific safety requirements. The method is primarily based on quantitative analyses and probabilistic model calculations regarding the long-term safety of the repository systems under consideration. The crucial evaluation criteria for the comparison are statistical key figures of indicators that characterize the radiotoxicity flux out of the so called containment-providing rock zone (einschlusswirksamer Gebirgsbereich). The key figures account for existing uncertainties with respect to the actual site properties, the safety relevant processes, and the potential future impact of external processes on the repository system, i.e., they include scenario-, process-, and parameter-uncertainties. The method (1) leads to an evaluation of the retention and containment capacity of the repository systems and its robustness with respect to existing uncertainties as well as to potential external influences; (2) specifies the procedures for the system analyses and the calculation of the statistical key figures as well as for the comparative interpretation of the key figures; and (3) also gives recommendations and sets benchmarks for the comparative assessment of the repository systems under consideration based on the key figures and additional qualitative

Potential host media for a high-level waste repository

Energy Technology Data Exchange (ETDEWEB)

Hustrulid, W

1982-01-01

Earlier studies of burial of radioactive wastes in geologic repositories had concentrated on salt formations for well-publicized reasons. However, under the Carter administration, significant changes were made in the US nuclear waste management program. Changes which were made were: (1) expansion of the number of rock types under consideration; (2) adoption of the multiple-barrier approach to waste containment; (3) additional requirements for waste retrieval; and (4) new criteria proposed by the Nuclear Regulatory Commission for the isolation of high-level waste in geologic repositories. Results of the studies of different types of rocks as repository sites are summarized herein. It is concluded that each generic rock type has certain advantages and disadvantages when considered from various aspects of the waste disposal problem and that characteristics of rocks are so varied that a most favorable or least favorable rock type cannot be easily identified. This lack of definitive characteristics of rocks makes site selection and good engineering barriers very important for containment of the wastes. (BLM)

Fons antic i repositoris universitaris a Espanya

Directory of Open Access Journals (Sweden)

Herrera Morillas, José Luis

2015-12-01

Full Text Available Es mostra la presència de col·leccions de fons antic en els repositoris de les biblioteques universitàries espanyoles després d'analitzar tots els repositoris. Per a aquesta anàlisi, com a part de la metodologia emprada, s'ha elaborat un model o llista que consta d'onze elements. Del conjunt de les universitats espanyoles, seixanta tenen repositoris, vint-i-vuit dels quals (16,8 % disposen de col·leccions de fons antic. Com que del concepte de repositori institucional no sembla desprendre's que tingui com a finalitat incloure aquest tipus de col·leccions, es reflexiona sobre la peculiaritat que una part dels repositoris universitaris espanyols inclogui col·leccions d'aquestes característiques.Se muestra la presencia de colecciones de fondo antiguo en los repositorios de las bibliotecas universitarias españolas después de analizar todos los repositorios. Para este análisis, como parte de la metodología empleada, se ha elaborado un modelo o lista que consta de once elementos. Del conjunto de las universidades españolas, sesenta cuentan con repositorios y, de estos, veintiocho (16,8 % disponen de colecciones de fondo antiguo. Debido a que del concepto de repositorio institucional no parece desprenderse que tenga como finalidad albergar este tipo de colecciones, se hace una reflexión sobre la peculiaridad de que parte de los repositorios universitarios españoles incluya colecciones de estas características.This paper uses an analysis of the repositories of Spanish universities to identify which institutions contain rare book and manuscript collections. The method used in this analysis involved examining each university on the basis of a list comprising eleven elements. A total of 60 universities were found to have repositories but only 28 (16.8 % of these contained rare book and manuscript collections. In the light of these figures, which suggest that Spanish university repositories do not generally consider the preservation of rare

Decompression of magma into repository tunnels

NARCIS (Netherlands)

Bokhove, Onno; Woods, A.W.

2002-01-01

It is nontrivial to find and design safe repository sites for nuclear waste. It appears common sense to drill tunnels as repository sites in a mountain in remote and relatively dry regions. However, erosion of the waste canisters by naturally abundant chemicals in the mountains water cycle remains a

Technical basis for high-level waste repository land control requirements for Palo Duro Basin, Paradox Basin, and Richton Dome

International Nuclear Information System (INIS)

Chen, C.P.; Raines, G.E.

1987-02-01

Three sites, the Palo Duro Basin in Texas, the Paradox Basin in Utah, and the Richton Dome in Mississippi, are being investigated by the US Department of Energy for high-level radioactive-waste disposal in mined, deep geologic repositories in salt. This report delineates the use of regulatory, engineering, and performance assessment information to establish the technical basis for controlled area requirements. Based on the size of the controlled area determined, plus that of the geologic repository operations area, recommendations of possible land control or ownership area requirements for each locale are provided. On a technical basis, the following minimum land control or ownership requirements are recommended, assuming repository operations area of 2240 ac (907 ha), or 3.5 mi 2 (9.1 km 2 ): Palo Duro Basin - 4060 ac (1643 ha), or 6.3 mi 2 (16.4 km 2 ); Paradox Basin - 4060 ac (1643 ha), or 6.3 mi 2 (16.4 km 2 ); and Richton Dome - 5000 ac (2024 ha), or 7.8 mi 2 (20.2 km 2 ). Of the factors used to determine the technically based recommendations, one was found to dominate each locale. For the Palo Duro and Paradox Basins, the dominant factor was the need to limit potential radionuclide release by ground-water flow to the accessible environment. For the Richton Dome, the dominant factor was the need to limit the potential effects of solution mining on dome and repository integrity

Paper and digital repositories in the United States

Directory of Open Access Journals (Sweden)

David F. Kohl

2003-09-01

Full Text Available What you've asked me to talk about today is basically what can libraries do with all the stuff they have and continue to get. Where do we put it all; what do we do with it? As we know, libraries have three core functions: collecting, organizing and preserving the key documents of the human enterprise. And, with apologies to Saint Paul, the greatest of these is preservation. For without preservation neither of the first two ultimately matter. My assignment this morning is to bring you up to date on one specific aspect of the preservation function, library repositories, and indeed, library repository developments in the US. The plan for this morning's presentation is the following: after a brief background review to give us a context for American developments we will examine first the various kinds of print repositories and then the various initiatives for electronic repositories. Because other presentations at this conference deal with electronic repositories, the main focus today will be on U.S. print repositories.

Institutional Repository Sebagai Sarana Komunikasi Ilmiah Yang Sustainable Dan Reliable

Directory of Open Access Journals (Sweden)

Faizuddin Harliansyah

2016-07-01

Full Text Available Abstract; Institutional repositories development has drawn the attention of many scholars throughout the world. Using the keywords ‘institutional repositories’, there are over 300 peer-reviewed articles related on the topic has been indexed in Library, Information Science, & Technology Abstracts (LISTA and SCOPUS. There are also hundreds of theses, dissertations, and websites dedicated on this blooming trends. These are proofs that the importance of IR in higher education has been acknowledged by many professionals in the field. This paper aims at clarifying the role of repositories in strengthening scholarly communication in higher education and research institution and explaining some basic repositories concepts (types of repositories and their characteristics, as well as exploring its relations with open access movement, the development ideas, and resources that could be kept in repositories and deposit policies. Abstrak; Pengembangan institutional repositories telah banyak menyita perhatian dari kalangan ilmiah di seluruh dunia. Melalui kata kunci ‘institutional repositories’, ada lebih dari 300 artikel terulas mitra bestari yang berhubungan dengan topik ini, yang telah terindeks di Library, Information Science, & Technology Abstracts (LISTA, dan SCOPUS. Terdapat juga ratusan tesis, disertasi, dan website yang mengulas trend ini. Inilah bukti bahwa pentingnya institutional repositories (IR telah dipahami oleh para profesional di bidangnya. Tulisan ini akan menjelaskan aturan-aturan repository dalam memperkuat komunikasi ilmiah di perguruan tinggi dan lembaga riset, menjelaskan konsep-konsep dasar repositories, termasuk tipe-tipe repository dan karakteristiknya. Tulisan ini juga akan memperdalam konsep repositories dalam hubungannya dengan gerakan open access, pengembangan ide-ide, sumber-sumber ilmiah yang dapat disimpan di repositories, serta kebijakan penyimpanan di dalamnya.

Purification, characterization and biological effect of lectin from the marine sponge Stylissa flexibilis (Lévi, 1961).

Science.gov (United States)

Hung, Le Dinh; Ly, Bui Minh; Hao, Vo Thi; Trung, Dinh Thanh; Trang, Vo Thi Dieu; Trinh, Phan Thi Hoai; Ngoc, Ngo Thi Duy; Quang, Thai Minh

2018-02-01

SFL, a lectin from the marine sponge Stylissa flexibilis was purified by cold ethanol precipitation followed by ion exchange chromatography on DEAE Sepharose column and Sephacryl S-200 gel filtration. SFL is a dimeric glycoprotein of 32kDa subunits linked by a disulfide bridge with a molecular mass of 64kDa by SDS-PAGE and 65kDa by Sephacryl S-200 gel filtration. SFL preferentially agglutinated enzyme treated human A erythrocytes. The activity of lectin was strongly inhibited by monosaccharide d-galactose and glycoproteins asialo-porcine stomach mucin and asialo-fetuin. The lectin was Ca 2+ dependent, stable over a range of pH from 5 to 8, and up to 60°C for 30min. The N-terminal amino acid sequence of SFL was also determined and a blast search on amino acid sequences revealed that the protein showed similarity only with lectins from the marine sponge Spheciospongia vesparia. SFL caused agglutination of Vibrio alginolyticus and V. parahaemolyticus in a dose dependent manner and inhibited the growth rates of the virulent bacterial strains. Growth inhibition of V. alginolyticus and V. parahaemolyticus with SFL was not observed in the presence of d-galactose or asialo-porcine stomach mucin, suggesting that the lectin caused the agglutination through binding to the target receptor(s) on the surface of Vibrios. Thus, the marine sponge S. flexibilis could promise to be a good source of a lectin(s) that may be useful as a carbohydrate probe and an antibacterial reagent. Copyright © 2017 Elsevier Inc. All rights reserved.

New Roles, New Responsibilities: Examining Training Needs of Repository Staff

Directory of Open Access Journals (Sweden)

Natasha Simons

2012-05-01

Full Text Available INTRODUCTION Institutional repositories play a critical role in the research lifecycle. Funding agencies are increasingly seeking an improved return on their investment in research. Repositories facilitate this process by providing storage of, and access to, institutional research outputs and, more recently, research data. While repositories are generally managed within the academic library, repository staff require different skills and knowledge compared with traditional library roles. This study reports on a survey of Australasian institutional repository staff to identify skills and knowledge sets. METHODS Institutional repository staff working at universities in Australia and New Zealand were invited to participate in an online survey which incorporated both open and closed-ended question types. RESULTS The survey found significant gaps in the current provision of formal training and coursework related to institutional repositories, which echoed findings in the United Kingdom, Italy, and the United States. DISCUSSION There is clearly a need for more and varied training opportunities for repository professionals. Repository work requires a specific set of skills that can be difficult to find and institutions will benefit from investing in training and ongoing development opportunities for repository staff. CONCLUSION The data from this study could be used to facilitate staff recruitment, development, training, and retention strategies.

General conceptual design study for a high level radioactive waste repository in a granite formation. Volume 1

International Nuclear Information System (INIS)

1982-01-01

The object of the general conceptual design study for a repository for disposal of radioactive waste in a granite formation is to ensure that the technology available in 1980 is suitable for the construction of such a repository. The recommended techniques and equipment are suitable for construction of a repository, located at a depth of 1000 metres in a granite batholith, with a capacity of 30,000 AVM canisters, cooled for 30 years on the surface, at a rate of 1,000 canisters per year. The structure consists of six access shafts of 4 and 5 metres diameter, drilled from the surface by the big-hole method, serving a network of 82 parallel galleries, 2,300 metres long, mined by conventional blasting. Shafts 100 metres deep are drilled in the floor of each gallery (74 shafts per gallery), each shaft accommodating five canisters. This represents an aggregate gallery length of 200 kilometres and an aggregate shaft length of 600 kilometres. The cost of the operation is 1.3% of the cost (ex-works) of the energy produced by the power stations generating the waste. Construction, operation and final abandonment will take 81 years. The sensitivity study of the design showed, by varying certain parameters, that location of the repository at a depth of 500 metres is not recommended and that the area covered by the repository of 4 km 2 is halved if the canisters are first cooled for 100 years

Thermal Management and Analysis for a Potential Yucca Mountain Repository

International Nuclear Information System (INIS)

Dr. A. Van Luik

2004-01-01

includes a summary of the technical basis that supports these evaluations. The majority of the material presented here is summarized from the Yucca Mountain Science and Engineering Report [l]. A companion paper in this publication entitled ''Characterizing the Evolution of the In-Drift Environment in a Proposed Yucca Mountain Repository'' schematically illustrates the processes being controlled through the management of thermal loading in its Figure 3

Evaluation of repository safety

Energy Technology Data Exchange (ETDEWEB)

Sagar, B.; Patrick, W.; Dasgupta, B.; Mohanty, S. [Center for Nuclear Waste Regulatory Analyses, San Antonio (United States)

2002-07-01

The United States high-level waste program requires evaluation of radiological safety during two distinct time intervals. The first interval, commonly referred to as the preclosure period, deals with receipt of waste at the site, transfer into disposal containers, if needed, emplacement in the underground openings, monitoring and maintenance activities, backfill and closure of the underground openings, and decontamination and decommissioning of the surface facilities of the geologic repository. The preclosure period may extend from a few tens of years to as long as a few hundred of years, depending on repository design and societal norms regarding a final decision to permanently seal the repository. During the preclosure or operational period, performance confirmation studies are conducted to provide a basis for updating and reevaluating estimates of postclosure performance and, finally, to provide a basis for a closure decision. The postclosure period during which expected repository performance must meet certain standards may range from ten thousands years, as it does in the United States, to millions of years, as it does in some European nations. Waste handling operations in the preclosure period are to be evaluated in relation to their potential effect on workers, members of general public, and the general environment. During this period, releases of radioactivity are to be monitored and appropriate actions taken whenever established limits are approached or exceeded. Preclosure safety is highly dependent on facility design, operational hardware and automated systems, operational sequences, and reliability of humans involved in operations. Preclosure safety analyses conducted before operations begin play a major role in the design process, selection of equipment, and development of operational procedures. Because of the complexity, duration, and spatial scales of the operations, analyses are conducted using mathematical models implemented in computer codes

Evaluation of repository safety

International Nuclear Information System (INIS)

Sagar, B.; Patrick, W.; Dasgupta, B.; Mohanty, S.

2002-01-01

The United States high-level waste program requires evaluation of radiological safety during two distinct time intervals. The first interval, commonly referred to as the preclosure period, deals with receipt of waste at the site, transfer into disposal containers, if needed, emplacement in the underground openings, monitoring and maintenance activities, backfill and closure of the underground openings, and decontamination and decommissioning of the surface facilities of the geologic repository. The preclosure period may extend from a few tens of years to as long as a few hundred of years, depending on repository design and societal norms regarding a final decision to permanently seal the repository. During the preclosure or operational period, performance confirmation studies are conducted to provide a basis for updating and reevaluating estimates of postclosure performance and, finally, to provide a basis for a closure decision. The postclosure period during which expected repository performance must meet certain standards may range from ten thousands years, as it does in the United States, to millions of years, as it does in some European nations. Waste handling operations in the preclosure period are to be evaluated in relation to their potential effect on workers, members of general public, and the general environment. During this period, releases of radioactivity are to be monitored and appropriate actions taken whenever established limits are approached or exceeded. Preclosure safety is highly dependent on facility design, operational hardware and automated systems, operational sequences, and reliability of humans involved in operations. Preclosure safety analyses conducted before operations begin play a major role in the design process, selection of equipment, and development of operational procedures. Because of the complexity, duration, and spatial scales of the operations, analyses are conducted using mathematical models implemented in computer codes

Semantic Linking of Learning Object Repositories to DBpedia

Science.gov (United States)

Lama, Manuel; Vidal, Juan C.; Otero-Garcia, Estefania; Bugarin, Alberto; Barro, Senen

2012-01-01

Large-sized repositories of learning objects (LOs) are difficult to create and also to maintain. In this paper we propose a way to reduce this drawback by improving the classification mechanisms of the LO repositories. Specifically, we present a solution to automate the LO classification of the Universia repository, a collection of more than 15…

NIDDK Central Repository

Data.gov (United States)

U.S. Department of Health & Human Services — The NIDDK Central Repository stores biosamples, genetic and other data collected in designated NIDDK-funded clinical studies. The purpose of the NIDDK Central...

Researching radioactive waste disposal. [Underground repository

Energy Technology Data Exchange (ETDEWEB)

Feates, F; Keen, N [UKAEA Research Group, Harwell. Atomic Energy Research Establishment

1976-02-16

At present it is planned to use the vitrification process to convert highly radioactive liquid wastes, arising from nuclear power programme, into glass which will be contained in steel cylinders for storage. The UKAEA in collaboration with other European countries is currently assessing the relative suitability of various natural geological structures as final repositories for the vitrified material. The Institute of Geological Sciences has been commissioned to specify the geological criteria that should be met by a rock structure if it is to be used for the construction of a repository though at this stage disposal sites are not being sought. The current research programme aims to obtain basic geological data about the structure of the rocks well below the surface and is expected to continue for at least three years. The results in all the European countries will then be considered so that the United Kingdom can choose a preferred method for isolating their wastes. It is only at that stage that a firm commitment may be made to select a site for a potential repository, when a far more detailed scientific research study will be instituted. Heat transfer problems and chemical effects which may occur within and around repositories are being investigated and a conceptual design study for an underground repository is being prepared.

Appraisal of hard rock for potential underground repositories of radioactive wastes. LBL-7004

International Nuclear Information System (INIS)

Cook, N.G.W.

1978-01-01

Underground burial of radioactive wastes in hard rock may be an effective and safe means of isolating them from the environment and from man. The mechanical safety and stability of such an underground repository depends largely on the virgin state of stress in the rock, groundwater pressures, the strengths of the rocks, heating by the decay of the radioactive wastes, and the layout of the excavations and the disposition of waste cannisters within them. A large body of pertinent data exists in the literature, and each of these factors has been analyzed in the light of this information. The results indicate that there are no fundamental geological nor mechanical reasons why repositories capable of storing radioactive wastes should not be excavated at suitable sites in hard rock. However, specific tests to determine the mechanical and thermal properties of the rocks at a site would be needed to provide the data for the engineering design of a repository. Also, little experience exists of the effects on underground excavations of thermal loads, so that this aspect requires theoretical study and experimental validation. The depths of these potential repositories would lie in the range from 0.5 km to 2.0 km below surface, depending upon the strength of the rock. Virgin states of stress have been measured at such depths which would retard the ingress of groundwater and obviate the incidence of faulting. A typical repository comprising three horizons each with a total area of 5 km 2 would have the capacity to store wastes with thermal output of 240 MW

Pre-treatment of bituminized NPP wastes for disposal in near-surface repository

Energy Technology Data Exchange (ETDEWEB)

Vieira, Vanessa Mota; Tello, Clédola Cássia Oliveira de, E-mail: vanessamotavieira@gmail.com, E-mail: tellocc@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

The implementation of the national repository is an important technical requirement, and a legal requirement for the entry into operation of the nuclear power plant Angra 3. The Brazilian repository is being planned to be a near-surface one. In Brazil the low and intermediate level radioactive wastes are immobilized using cement and bitumen for Angra 1 and Angra 2 NPP, respectively. The main problems due to the disposal of bituminized wastes in repositories are swelling of the waste products and their degradation in the long term. To accommodate the swelling of the bituminized wastes, the drums are filled up to 70 - 90% of their volume, which reduces the structural the repository stability and the disposal availability. Countries, which use bitumen in the solidification of NPP's radioactive waste and have near-surface repositories, need to immobilize this bituminized waste within other drums containing cement pastes or mortars to disposal them. This study aims to find solutions for the storage in surface repository of bituminized radioactive waste products, making them compatible with the acceptance criteria of cemented waste products. It was also performed a modeling with the results obtained in the leaching test using the ALT program and defined the transport model of the cesium leachate element and it was verified that in the early times the leaching was governed by the diffusion model and later by the partition model. The results obtained in this study can be used in the evaluation of performance of repositories. (author)

Pre-treatment of bituminized NPP wastes for disposal in near-surface repository

International Nuclear Information System (INIS)

Vieira, Vanessa Mota; Tello, Clédola Cássia Oliveira de

2017-01-01

The implementation of the national repository is an important technical requirement, and a legal requirement for the entry into operation of the nuclear power plant Angra 3. The Brazilian repository is being planned to be a near-surface one. In Brazil the low and intermediate level radioactive wastes are immobilized using cement and bitumen for Angra 1 and Angra 2 NPP, respectively. The main problems due to the disposal of bituminized wastes in repositories are swelling of the waste products and their degradation in the long term. To accommodate the swelling of the bituminized wastes, the drums are filled up to 70 - 90% of their volume, which reduces the structural the repository stability and the disposal availability. Countries, which use bitumen in the solidification of NPP's radioactive waste and have near-surface repositories, need to immobilize this bituminized waste within other drums containing cement pastes or mortars to disposal them. This study aims to find solutions for the storage in surface repository of bituminized radioactive waste products, making them compatible with the acceptance criteria of cemented waste products. It was also performed a modeling with the results obtained in the leaching test using the ALT program and defined the transport model of the cesium leachate element and it was verified that in the early times the leaching was governed by the diffusion model and later by the partition model. The results obtained in this study can be used in the evaluation of performance of repositories. (author)

Cross Institutional Cooperation on a Shared Bit Repository

DEFF Research Database (Denmark)

Zierau, Eld; Kejser, Ulla Bøgvad

2013-01-01

This paper explores how independent institutions, such as archives and libraries, can cooperate on managing a shared bit repository with bit preservation, in order to use their resources for preservation in a more cost-effective way. It uses the OAIS Reference Model to provide a framework...... for systematically analysing institutions technical and organisational requirements for a remote bit repository. Instead of viewing a bit repository simply as Archival Storage for the institutions repositories, we argue for viewing it as consisting of a subset of functions from all entities defined by the OAIS...... Reference Model. The work is motivated by and used in a current Danish feasibility study for establishing a national bit repository. The study revealed that depending on their missions and the collections they hold, the institutions have varying requirements e.g. for bit safety, accessibility...

Cross Institutional Cooperation on a Shared Bit Repository

DEFF Research Database (Denmark)

Zierau, Eld; Kejser, Ulla Bøgvad

2010-01-01

This paper explores how independent institutions, such as archives and libraries, can cooperate on managing a shared bit repository with bit preservation in order to use their resources for preservation n in a more cost-effective way. It uses the OAIS Reference Model to provide a framework...... for systematically analysing the technical and organizational requirements of institutions for a remote bit repository. Instead of viewing a bit repository simply as Archival Storage for the institutions’ repositories, we argue for viewing it as consisting of a subset of functions from all entities defined...... by the OAIS Reference Model. The work is motivated by and used in a current Danish feasibility study for establishing a national bit repository. The study revealed that depending on their missions and the collections they hold, the institutions have varying requirements, such as for bit safety, accessibility...

Recommendations: Procedure to develop a preliminary safety report as part of the radioactive waste repository construction licensing process

International Nuclear Information System (INIS)

2003-01-01

The structure of a preliminary safety report for the title purpose should be as follows: A. Textual part: 1. General (Introduction, Basic information about the construction, Timetable); 2. Site information (Siting, Geography and demography, Meteorology and climatic situation, Hydrology, Geology and hydrogeology); 3. Repository design description (Basic function and performance requirements, Design, Auxiliary systems, Fire prevention/protection, Emergency plans); 4. Operation of the repository (Waste acceptance and inspection, Waste handling and interim storage, Waste disposal, Operating monitoring), 5. Health and environmental impact assessment (Radionuclide inventory, Radionuclide transport paths and mechanisms of release into the environment, Radionuclide release in normal and emergency situations, Radiation protection - health impact assessment and regulatory compliance, Draft operating limits and conditions, Proposed ways of assuring physical protection, Uncertainty assessment), 6. Safe repository shutdown/decommissioning concept, 7 Quality assurance assessment, 8. List of selected equipment. B. Annexes: Maps, Drawings, Diagrams, Miscellaneous; C. Documentation: Previous safety report amendments, Protocols, Miscellaneous. (P.A.)

Tools for Managing Repository Objects

OpenAIRE

Banker, Rajiv D.; Isakowitz, Tomas; Kauffman, Robert J.; Kumar, Rachna; Zweig, Dani

1993-01-01

working Paper Series: STERN IS-93-46 The past few years have seen the introduction of repository-based computer aided software engineering (CASE) tools which may finally enable us to develop software which is reliable and affordable. With the new tools come new challenges for management: Repository-based CASE changes software development to such an extent that traditional approaches to estimation, performance, and productivity assessment may no longer suffice - if they ever...

Rock stability considerations for siting and constructing a KBS-3 repository. Based on experiences from Aespoe HRL, AECL's URL, tunnelling and mining

International Nuclear Information System (INIS)

Martin, C.D.; Christiansson, Rolf; Soederhaell, J.

2001-12-01

Over the past 25 years the international nuclear community has carried out extensive research into the deep geological disposal of nuclear waste in hard rocks. In two cases this research has resulted in the construction of dedicated underground research facilities: SKB's Aespoe Hard Rock Laboratory, Sweden and AECL's Underground Research Laboratory, Canada. Both laboratories are located in hard rocks considered representative of the Fennoscandian and Canadian Shields, respectively. This report is intended to synthesize the important rock mechanics findings from these research programs. In particular the application of these finding to assessing the stability of underground openings. As such the report draws heavily on the published results from the SKB's ZEDEX Experiment in Sweden and AECL's Mine- by Experiment in Canada. The objectives of this report are to: 1. Describe, using the current state of knowledge, the role rock engineering can play in siting and constructing a KBS-3 repository. 2. Define the key rock mechanics parameters that should be determined in order to facilitate repository siting and construction. 3. Discuss possible construction issues, linked to rock stability, that may arise during the excavation of the underground openings of a KBS-3 repository. 4. Form a reference document for the rock stability analysis that has to be carried out as a part of the design works parallel to the site investigations. While there is no unique or single rock mechanics property or condition that would render the performance of a nuclear waste repository unacceptable, certain conditions can be treated as negative factors. Outlined below are major rock mechanics issues that should be addressed during the siting, construction and closure of a nuclear waste repository in Sweden in hard crystalline rock. During the site investigations phase, rock mechanics information will be predominately gathered from examination and testing of the rock core and mapping of the

CCDC 1036004: Experimental Crystal Structure Determination : catena-[(mu5-5-(pyridin-3-ylamino)isophthalato)-copper unknown solvate

KAUST Repository

Chen, Zhijie

2015-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

Environmental program overview for a high-level radioactive waste repository at Yucca Mountain

International Nuclear Information System (INIS)

1988-12-01

The United States plans to begin operating the first repository for the permanent disposal of high-level nuclear waste early in the next century. In February 1983, the US Department of Energy (DOE) identified Yucca Mountain, in Nevada, as one of nine potentially acceptable sites for a repository. To determine its suitability, the DOE evaluated the Yucca Mountain site, along with eight other potentially acceptable sites, in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. The purpose of the Environmental Program Overview (EPO) for the Yucca Mountain site is to provide an overview of the overall, comprehensive approach being used to satisfy the environmental requirements applicable to sitting a repository at Yucca Mountain. The EPO states how the DOE will address the following environmental areas: aesthetics, air quality, cultural resources (archaeological and Native American components), noise, radiological studies, soils, terrestrial ecosystems, and water resources. This EPO describes the environmental program being developed for the sitting of a repository at Yucca Mountain. 1 fig., 3 tabs

CCDC 910696: Experimental Crystal Structure Determination : Tricarbonyl-(eta^5^-5,5-bis(ethoxycarbonyl)-2-oxido-1,3-bis(trimethylsilyl)-1,4,5,6-tetrahydropentalen-1-yl)-iron

KAUST Repository

Dentel, H.

2014-01-01

An entry from the Cambridge Structural Database, the world’s repository for small molecule crystal structures. The entry contains experimental data from a crystal diffraction study. The deposited dataset for this entry is freely available from the CCDC and typically includes 3D coordinates, cell parameters, space group, experimental conditions and quality measures.

The Laxemar and Forsmark repositories. An analysis of the water inflow distribution

International Nuclear Information System (INIS)

Svensson, Urban

2006-12-01

A numerical simulation model is used to estimate the water inflow distribution to the Laxemar and Forsmark repositories. In particular statistics for the inflow to individual deposition holes, i.e. inflow distribution expressed as litre/min, deposition hole, is requested. Different grouting efficiencies are evaluated, including no grouting. The simulations are based on the code DarcyTools version 3.0, which was also used in simulations of the impact of the Repositories in Forsmark and Laxemar. Both the code and the simulations include many novel features and all simulations should hence be regarded as tentative. For the Laxemar repository it is found that less than 2% of all deposition holes will have an inflow larger than 1.0 l/min. This number will increase to about 20% if the inflow limit is put to 0.1 l/min. For the Forsmark repository it is found that 99.9% of all deposition holes will have an inflow smaller than 0.01 l/min

Gas generation and release from the VLJ repository

International Nuclear Information System (INIS)

Vieno, T.; Valkiainen, M.

1992-01-01

The VLJ repository is an underground disposal facility located at the Olkiluoto nuclear power plant site on the west coast of Finland. The repository will house low (LLW) and intermediate level radioactive wastes (MLW) from the TVO I and TVO II BWR's and the spent fuel interim store at Olkiluoto. The disposal rooms have been excavated at a depth of 60... 100 meters in the crystalline bedrock. They consist of two rock silos - one for the LLW and the other for MLW. Low level waste is usually packed in steel drums and steel boxes. Medium level wastes consists of bituminized resins in steel drums. Wastes packages are emplaced in concrete boxes before transportation into the repository. Low level wastes are emplaced in the shotcreted rock silo where no backfilling will used. For medium level wastes, a separate silo of reinforced concrete has been constructed inside the rock silo. No backfilling will be used inside the concrete silo and an opening will be made in the lid of the concrete silo for gas release. The microbial degradation of low level wastes is the principle gas generation process in the repository. The gas transport though the bedrock covering the repository is evaluated with the help of ground water flow study. It is recommended that the shotcrete lining on the ceiling of the repository cavern is partly removed before the final sealing of the repository. Provided that dissipation of gases from the disposal cavern into the rock can been assured, the overall effects of gas generation on the long-term safety of the repository are insignificant. 10 refs., 6 figs

Preliminary analysis of the operating characteristics of a generic repository receiving facility: Status report

International Nuclear Information System (INIS)

1985-10-01

The operating characteristics of a repository receiving facility structured around current technology and practices have been reviewed. Cask turnaround times and operator doses were estimated. Large throughout and long-term receiving operations at a nuclear waste repository result in an unprecedented number of casks being handled. While the current generation of material-handling equipment is adequate to process the casks, personnel radiation exposures for the generic facility analyzed are unacceptably high. This emphasizes the need for development of occupational radiation exposure control concepts for application in repository receiving facilities. 3 refs., 22 figs., 6 tabs

Post-closure radiation dose assessment for Yucca Mountain repository

International Nuclear Information System (INIS)

Jia Mingyan; Zhang Xiabin; Yang Chuncai

2006-01-01

A brief introduction of post-closure long-term radiation safety assessment results was represented for the yucca mountain high-level waste geographic disposal repository. In 1 million years after repository closure, for the higher temperature repository operating mode, the peak annual dose would be 150 millirem (120 millirem under the lower-temperature operating mode) to a reasonably maximally exposed individual approximately 18 kilometers (11 miles) from the repository. The analysis of a drilling intrusion event occurring at 30,000 years indicated a peak of the mean annual dose to the reasonably maximally exposed individual approximately 18 kilometers (11 miles) downstream of the repository would be 0.002 millirem. The analysis of an igneous activity scenario, including a volcanic eruption event and igneous intrusion event indicated a peak of the mean annual dose to the reasonably maximally exposed individual approximately 18 kilometers downstream of the repository would be 0.1 millirem. (authors)

Design of repository sealing systems - 1981

International Nuclear Information System (INIS)

Ellison, R.D.; Shukla, D.K.; Kelsall, P.C.; D'Appolonia Consulting Engineers, Albuquerque, NM)

1982-01-01

Isolating nuclear waste in geologic repositories will require the sealing of penetrations such as access shafts and tunnels, disposal rooms, and exploration boreholes. This paper discusses seal designs developed for a repository in bedded salt referenced to the stratigraphy of southeastern New Mexico. Designs are based on a multiple component concept whereby individual components are designed for a specific function and location. For a repository in salt the major function of the seals is to exclude groundwater inflow. Two main types of component are included for this purpose: (1) bulk-heads are dense concrete structures keyed into the walls of the penetration and are intended to reduce flow at the interface between the seal and the salt; (2) backfills are granular materials compacted in place in the penetration. In the repository the major backfill material is crushed salt, which is expected to consolidate and recrystallize as the rooms close in response to salt creep. Densely compacted clays will be used as backfill in the shafts closer to potential sources of water inflow. 22 references, 10 figures, 1 table

Creation of Data Repositories to Advance Nursing Science.

Science.gov (United States)

Perazzo, Joseph; Rodriguez, Margaret; Currie, Jackson; Salata, Robert; Webel, Allison R

2017-12-01

Data repositories are a strategy in line with precision medicine and big data initiatives, and are an efficient way to maximize data utility and form collaborative research relationships. Nurse researchers are uniquely positioned to make a valuable contribution using this strategy. The purpose of this article is to present a review of the benefits and challenges associated with developing data repositories, and to describe the process we used to develop and maintain a data repository in HIV research. Systematic planning, data collection, synthesis, and data sharing have enabled us to conduct robust cross-sectional and longitudinal analyses with more than 200 people living with HIV. Our repository building has also led to collaboration and training, both in and out of our organization. We present a pragmatic and affordable way that nurse scientists can build and maintain a data repository, helping us continue to make to our understanding of health phenomena.

Nuclear waste repository transparency technology test bed demonstrations at WIPP

International Nuclear Information System (INIS)

Betsill J, David; Elkins, Ned Z.; Wu, Chuan-Fu; Mewhinney, James D.; Aamodt, Paul

2000-01-01

repository, the Waste Isolation Pilot Plant (WIPP) offers a unique opportunity to serve as an international cooperative test bed for developing and demonstrating technologies and processes in a fully operational repository system setting. To address the substantial national security implications for the US resulting from the lack of integrated, transparent management and disposition of nuclear materials at the back-end of the nuclear fuel and weapons cycles, it is proposed that WIPP be used as a test bed to develop and demonstrate technologies that will enable the transparent and proliferation-resistant geologic isolation of nuclear materials. The objectives of this initiative are to: (1) enhance public confidence in safe, secure geologic isolation of nuclear materials; (2) develop, test, and demonstrate transparency measures and technologies for the back-end of nuclear fuel cycle; and (3) foster international collaborations leading to workable, effective, globally-accepted standards for the transparent monitoring of geological repositories for nuclear materials. Test-bed activities include: development and testing of monitoring measures and technologies; international demonstration experiments; transparency workshops; visiting scientist exchanges; and educational outreach. These activities are proposed to be managed by the Department of Energy/Carlsbad Area Office (DOE/CAO) as part of The Center for Applied Repository and Underground Studies (CARUS)

Reducing Psychological Resistance to Digital Repositories

Directory of Open Access Journals (Sweden)

Brian Quinn

2010-06-01

Full Text Available The potential value of digital repositories is dependent on the cooperation of scholars to deposit their work. Although many researchers have been resistant to submitting their work, the literature on digital repositories contains very little research on the psychology of resistance. This article looks at the psychological literature on resistance and explores what its implications might be for reducing the resistance of scholars to submitting their work to digital repositories. Psychologists have devised many potentially useful strategies for reducing resistance that might be used to address the problem; this article examines these strategies and how they might be applied.

Augmenting interoperability across repositories architectural ideas

CERN Multimedia

CERN. Geneva

2005-01-01

The aDORe digital repository architecture designed and implemented by the Los Alamos Research Library is fully standards-based and highly modular, with the various components of the architecture interacting in a protocol-driven manner. Although aDORe was designed for use in the context of the Los Alamos Library, its modular and standards-based design has led to interesting insights regarding possible new levels of interoperability in a federation of heterogeneous repositories. The presentation will discuss these insights, and will illustrate that attractive federations of repositories can be built by introducing rather basic interoperability requirements. The presentation will also show that, once these requirements are met, a powerful service framework that overlays the federation can emerge.

Executive-style briefings on selected repository design issues

International Nuclear Information System (INIS)

1978-01-01

This document is a collection of executive-style briefings on selected repository design issues. Most of the briefings discuss differences between the US repository design bases presented in US Working Draft on Repository Physical Descriptions in a Salt Formation, prepared in support of INFCE discussions of May 1978 and the FRG-Netherlands design bases, presented in Design Study of a Radioactive Waste Repository to be Mined in a Medium-Size Salt Dome by Hamstra and Velzeboer, Netherlands Energy Research Foundation, January 1978. Advantages and disadvantages of the two sets of design bases are discussed, and the impacts of adopting either of these bases on the other's programs and positions are identified

An open data repository and a data processing software toolset of an equivalent Nordic grid model matched to historical electricity market data.

Science.gov (United States)

Vanfretti, Luigi; Olsen, Svein H; Arava, V S Narasimham; Laera, Giuseppe; Bidadfar, Ali; Rabuzin, Tin; Jakobsen, Sigurd H; Lavenius, Jan; Baudette, Maxime; Gómez-López, Francisco J

2017-04-01

This article presents an open data repository, the methodology to generate it and the associated data processing software developed to consolidate an hourly snapshot historical data set for the year 2015 to an equivalent Nordic power grid model (aka Nordic 44), the consolidation was achieved by matching the model׳s physical response w.r.t historical power flow records in the bidding regions of the Nordic grid that are available from the Nordic electricity market agent, Nord Pool. The model is made available in the form of CIM v14, Modelica and PSS/E (Siemens PTI) files. The Nordic 44 model in Modelica and PSS/E were first presented in the paper titled "iTesla Power Systems Library (iPSL): A Modelica library for phasor time-domain simulations" (Vanfretti et al., 2016) [1] for a single snapshot. In the digital repository being made available with the submission of this paper (SmarTSLab_Nordic44 Repository at Github, 2016) [2], a total of 8760 snapshots (for the year 2015) that can be used to initialize and execute dynamic simulations using tools compatible with CIM v14, the Modelica language and the proprietary PSS/E tool are provided. The Python scripts to generate the snapshots (processed data) are also available with all the data in the GitHub repository (SmarTSLab_Nordic44 Repository at Github, 2016) [2]. This Nordic 44 equivalent model was also used in iTesla project (iTesla) [3] to carry out simulations within a dynamic security assessment toolset (iTesla, 2016) [4], and has been further enhanced during the ITEA3 OpenCPS project (iTEA3) [5]. The raw, processed data and output models utilized within the iTesla platform (iTesla, 2016) [4] are also available in the repository. The CIM and Modelica snapshots of the "Nordic 44" model for the year 2015 are available in a Zenodo repository.

Publishers and repositories

CERN Multimedia

CERN. Geneva

2007-01-01

The impact of self-archiving on journals and publishers is an important topic for all those involved in scholarly communication. There is some evidence that the physics arXiv has had no impact on physics journals, while 'economic common sense' suggests that some impact is inevitable. I shall review recent studies of librarian attitudes towards repositories and journals, and place this in the context of IOP Publishing's experiences with arXiv. I shall offer some possible reasons for the mis-match between these perspectives and then discuss how IOP has linked with arXiv and experimented with OA publishing. As well as launching OA journals we have co-operated with Cornell and the arXiv on Eprintweb.org, a platform that offers new features to repository users. View Andrew Wray's biography

Design principle of TVO's final repository and preliminary adaptation to site specific conditions

International Nuclear Information System (INIS)

Salo, J-P.; Reikkola, R.

1995-01-01

Teollisuuden Voima Oy (TVO) is responsible for the management of spent fuel produced by the Olkiluoto power plant. TVO's current programme of spent fuel management is based on the guidelines and time schedule set by the Finnish Government. TVO has studied a final disposal concept in which the spent fuel bundles are encapsulated in copper canisters and emplaced in Finnish bedrock. According to the plan the final repository for spent fuel will be in operation by 2020. TVO's updated technical plans for the disposal of spent fuel together with a performance analysis (TVO-92) were submitted to the authorities in 1992. The paper describes the design principle of TVO's final repository and preliminary adaptation of the repository to site specific conditions. (author). 10 refs., 5 figs

Business models for digital repositories

CERN Document Server

CERN. Geneva; Bjørnshauge, Lars

2007-01-01

Those setting up, or planning to set up, a digital repository may be interested to know more about what has gone before them. What is involved, what is the cost, how many people are needed, how have others made the case to their institution, and how do you get anything into it once it is built? I have recently undertaken a study of European repository business models for the DRIVER project and will present an overview of the findings.

Waste package/repository impact study: Final report

Energy Technology Data Exchange (ETDEWEB)

1985-09-01

The Waste Package/Repository Impact Study was conducted to evaluate the feasibility of using the current reference salt waste package in the salt repository conceptual design. All elements of the repository that may impact waste package parameters, i.e., (size, weight, heat load) were evaluated. The repository elements considered included waste hoist feasibility, transporter and emplacement machine feasibility, subsurface entry dimensions, feasibility of emplacement configuration, and temperature limits. The evaluations are discussed in detail with supplemental technical data included in Appendices to this report, as appropriate. Results and conclusions of the evaluations are discussed in light of the acceptability of the current reference waste package as the basis for salt conceptual design. Finally, recommendations are made relative to the salt project position on the application of the reference waste package as a basis for future design activities. 31 refs., 11 figs., 11 tabs.

Waste package/repository impact study: Final report

International Nuclear Information System (INIS)

1985-09-01

The Waste Package/Repository Impact Study was conducted to evaluate the feasibility of using the current reference salt waste package in the salt repository conceptual design. All elements of the repository that may impact waste package parameters, i.e., (size, weight, heat load) were evaluated. The repository elements considered included waste hoist feasibility, transporter and emplacement machine feasibility, subsurface entry dimensions, feasibility of emplacement configuration, and temperature limits. The evaluations are discussed in detail with supplemental technical data included in Appendices to this report, as appropriate. Results and conclusions of the evaluations are discussed in light of the acceptability of the current reference waste package as the basis for salt conceptual design. Finally, recommendations are made relative to the salt project position on the application of the reference waste package as a basis for future design activities. 31 refs., 11 figs., 11 tabs

Repository exploration

International Nuclear Information System (INIS)

Pentz, D.L.

1984-01-01

This paper discusses exploration objectives and requirements for a nuclear repository in the U.S.A. The importance of designing the exploration program to meet the system performance objectives is emphasized and some examples of the extent of exploration required before the License Application for Construction Authorization is granted are also discussed

Calculation of fluxes through a repository caused by a local well

International Nuclear Information System (INIS)

Thunvik, R.

1983-05-01

The purpose of the present study is to roughly estimate the ground water flux through a radioactive repository in relation to the flux into a local well under various conditions. The well is assumed to be located at a depth of either 60 or 200 metres below the ground surface. Two main settings are considered, in one the well is located in a vertical fracture zone at a distance of 100 metres from one of the outer edges of the repository. The withdrawal from the well is assumed to be 6 m 3 /day. The flow domain is characterized by a rather low permeability. The boundary conditions considered are either a continuously saturated upper boundary and impervious lateral boundaries, or a phreatic upper boundary and hydrostatic lateral boundaries. The ratio of the flux through the repository to the flux into the well was obtained to be in the range from about 10- 5 to 10- 3 , depending on the boundary conditions and the depth of the well. The lowest figures were obtained in the examples, in which the upper boundary was assumed to be continually saturated. It is concluded that these examples may be considered representative of the actual flow problem. This conclusion is based upon the fact that in the case of a phreatic boundary the drawdown caused by the well was very small and the flow responses were very slow, implying that rather a small infiltration rate is requied to maintain saturated conditions at the upper boundary. The regional gradients caused by the well were rather small in comparison with the typically naturally occurring gradients. The flow to the well will therefore have little influence on the regional flow pattern in most practical cases. (author)

Learning frameworks as an alternative to repositories

DEFF Research Database (Denmark)

Dalsgaard, Christian

2005-01-01

This paper presents the concept of ‘learning frameworks’. The purpose of the paper is to discuss and question collections of digital learning objects in large repositories and to argue for large learning frameworks which organise a number of thematically related digital learning materials. Whereas...... a learning object repository contains all kinds of materials, a learning framework consists of an organisation of materials related to a common theme. Further, a repository consists of single, self-contained objects, whereas a learning framework is an open-ended environment which presents a number...

NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

Energy Technology Data Exchange (ETDEWEB)

None

1982-07-01

This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

International Nuclear Information System (INIS)

1982-07-01

This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules

Spent fuel as a waste form: Data needs to allow long term performance assessment under repository disposal conditions

International Nuclear Information System (INIS)

Oversby, V.M.

1986-12-01

Performance assessment calculations are required for high level waste repositories for a period of 10,000 years. The Siting Guidelines require a comparison of sites following site characterization and prior to final site selection to be made over a 100,000 year period. To perform the required calculations, a detailed knowledge of the physical and chemical processes that affect waste form performance will be needed for each site. This paper will review the factors that affect the release of radionuclides from spent fuel under repository conditions, summarize our present state of knowledge, and suggest areas where more work is needed to support the performance assessment calculations. 17 refs., 5 figs., 3 tabs

Shear-induced Fracture Slip and Permeability Change. Implications for Long-term Performance of a Deep Geological Repository

International Nuclear Information System (INIS)

Min, Ki-Bok; Stephansson, Ove

2009-03-01

Opening of fractures induced by shear dilation or normal deformation can be a significant source of fracture permeability change in jointed rock, which is important for the performance assessment of geological repositories for spent nuclear fuel. As the repository generates heat and later cools the fluid-carrying ability of the rocks becomes a dynamic variable during the lifespan of the repository. Heating causes expansion of the rock close to the repository and, at the same time, contraction close to the surface. During the cooling phase of the repository, the opposite takes place. Heating and cooling together with the virgin stress can induce shear dilation of fractures and deformation zones and change the flow field around the repository. The objectives of this project are to examine the contribution of thermal stress to the shear slip of fracture in mid- and far-field around a KBS-3 type of repository and to investigate the effect of evolution of stress on the rock mass permeability. The first part of the study is about the evolution of thermal stresses in the rock during the lifetime of the repository. Critical sections of heat generated stresses around the repository are selected and classified. Fracture data from Forsmark is used to establish fracture network models (DFN) and the models are subjected to the sum of virgin stress and thermal stresses and the shear slip and related permeability change are studied. In the first part of this study, zones of fracture shear slip were examined by conducting a three-dimensional, thermo-mechanical analysis of a spent fuel repository model. Stress evolutions of importance for fracture shear slip are: (1) comparatively high horizontal compressive thermal stress at the repository level, (2) generation of vertical tensile thermal stress right above the repository, (3) horizontal tensile stress near the surface, which can induce tensile failure, and generation of shear stresses at the corners of the repository. In the

Shear-induced Fracture Slip and Permeability Change. Implications for Long-term Performance of a Deep Geological Repository

Energy Technology Data Exchange (ETDEWEB)

Min, Ki-Bok (School of Civil, Environmental and Mining Engineering, Univ. of Adelaide, Adelaide (Australia)); Stephansson, Ove (Steph Rock Consulting AB, Berlin (Germany))

2009-03-15

Opening of fractures induced by shear dilation or normal deformation can be a significant source of fracture permeability change in jointed rock, which is important for the performance assessment of geological repositories for spent nuclear fuel. As the repository generates heat and later cools the fluid-carrying ability of the rocks becomes a dynamic variable during the lifespan of the repository. Heating causes expansion of the rock close to the repository and, at the same time, contraction close to the surface. During the cooling phase of the repository, the opposite takes place. Heating and cooling together with the virgin stress can induce shear dilation of fractures and deformation zones and change the flow field around the repository. The objectives of this project are to examine the contribution of thermal stress to the shear slip of fracture in mid- and far-field around a KBS-3 type of repository and to investigate the effect of evolution of stress on the rock mass permeability. The first part of the study is about the evolution of thermal stresses in the rock during the lifetime of the repository. Critical sections of heat generated stresses around the repository are selected and classified. Fracture data from Forsmark is used to establish fracture network models (DFN) and the models are subjected to the sum of virgin stress and thermal stresses and the shear slip and related permeability change are studied. In the first part of this study, zones of fracture shear slip were examined by conducting a three-dimensional, thermo-mechanical analysis of a spent fuel repository model. Stress evolutions of importance for fracture shear slip are: (1) comparatively high horizontal compressive thermal stress at the repository level, (2) generation of vertical tensile thermal stress right above the repository, (3) horizontal tensile stress near the surface, which can induce tensile failure, and generation of shear stresses at the corners of the repository. In the

Gabbro as a host rock for a nuclear waste repository

International Nuclear Information System (INIS)

Ahlbom, K.; Leijon, B.; Smellie, J.; Liedholm, M.

1992-09-01

As an alternative to granitic rocks, gabbro and other basic rock types have been investigated with respect to their suitability to host a nuclear waste repository. The present report summarizes and examines existing geoscientific knowledge of relevance in assessing the potential merits of gabbro as a repository host rock. Implications in terms of site selection, repository construction and post-closure repository performance are also discussed. The objective of the study is to provide a basis for decisions as regards future consideration of the gabbro alternative. It is found that there are rather few gabbro bodies in Sweden, that are potentially of sufficient size to host a repository. Thus, gabbro offers little latitude as regards site selection. In comparison to siting a repository in granitic rocks, this is a major disadvantage, and it may in fact remove gabbro from further consideration. The potential advantages of gabbro refer to repository performance, and include low hydraulic conductivity and a chemical environment promoting efficient radionuclide retardation. However, results from field investigations show that groundwater flow in gabbro bodies is largely controlled by intersecting heterogeneities, in particular granitic dykes, that are significantly more conductive to water than the gabbro. In the far-field scale significant to repository performance, this may reduce or eliminate the potential effects of favourable hydraulic and chemical characteristics of the gabbro itself. In conclusion, there are apparent difficulties associated with siting a repository in gabbro, due to lack of sufficiently large gabbro bodies. On the basis of the present state of knowledge, no decisive differences can be demonstrated when comparing gabbro with granitic rocks, neither with respects to repository construction, nor as regards repository performance. (au)

Hydrogen modelling for vitrified wastes repository

International Nuclear Information System (INIS)

Voinis, S.; Breton, J.

1992-01-01

Safety assessments for High Level Wastes (HLW) have led ANDRA (Agence Nationale pour la gestion des Dechets Radioactifs) to study the occurrence of a gas production rate in a repository. This paper deals with the description of an analytical model used for the gas production rate assessment and brings us the first results. The geometry used is restrained to a single borehole associated with a drift in a crystalline formation. Different concepts were studied in this assessment. First results have been obtained. For example, in the case of a permeable plug, the saturation time of the borehole is about 300 years. 5 refs., 5 figs

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2010-09-01

The RD and D programme 2010 gives an account of SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas - the programme for Low and Intermediate Level Waste (the Loma program) and the Nuclear Fuel Program. The RD and D Programme 2010 consists of five parts: Part I: Overall Plan, Part II: Loma program, Part III: Nuclear Fuel Program, Part IV: Research on analysis of long-term safety, Part V: Social Science Research. The 2007 RD and D programme was focused primarily on technology development to realize the final repository for spent nuclear fuel. The actions described were aimed at increasing awareness of long-term safety and to obtain technical data for application under the Nuclear Activities Act for the final repository for spent fuel and under the Environmental Code of the repository system. Many important results from these efforts are reported in this program. An overall account of the results will be given in the Licensing application in early 2011. The authorities' review of RD and D programme in 2007 and completion of the program called for clarification of plans and programs for the final repository for short-lived radioactive waste, SFR, and the final repository for waste, SFL. This RD and D program describes these plans in a more detailed way

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste; Fud-program 2010. Program foer forskning, utveckling och demonstration av metoder foer hantering och slutfoervaring av kaernavfall

Energy Technology Data Exchange (ETDEWEB)

2010-09-15

The RD and D programme 2010 gives an account of SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas - the programme for Low and Intermediate Level Waste (the Loma program) and the Nuclear Fuel Program. The RD and D Programme 2010 consists of five parts: Part I: Overall Plan, Part II: Loma program, Part III: Nuclear Fuel Program, Part IV: Research on analysis of long-term safety, Part V: Social Science Research. The 2007 RD and D programme was focused primarily on technology development to realize the final repository for spent nuclear fuel. The actions described were aimed at increasing awareness of long-term safety and to obtain technical data for application under the Nuclear Activities Act for the final repository for spent fuel and under the Environmental Code of the repository system. Many important results from these efforts are reported in this program. An overall account of the results will be given in the Licensing application in early 2011. The authorities' review of RD and D programme in 2007 and completion of the program called for clarification of plans and programs for the final repository for short-lived radioactive waste, SFR, and the final repository for waste, SFL. This RD and D program describes these plans in a more detailed way

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2010-09-01

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2010-09-15

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly