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Sample records for cavern disposal concepts

  1. Cavern disposal concepts for HLW/SF: assuring operational practicality and safety with maximum programme flexibility

    International Nuclear Information System (INIS)

    McKinley, Ian G.; Apted, Mick; Umeki, Hiroyuki; Kawamura, Hideki

    2008-01-01

    Most conventional engineered barrier system (EBS) designs for HLW/SF repositories are based on concepts developed in the 1970s and 1980s that assured feasibility with high margins of safety, in order to convince national decision makers to proceed with geological disposal despite technological uncertainties. In the interval since the advent of such 'feasibility designs', significant progress has been made in reducing technological uncertainties, which has lead to a growing awareness of other, equally important uncertainties in operational implementation and challenges regarding social acceptance in many new, emerging national repository programs. As indicated by the NUMO repository concept catalogue study (NUMO, 2004), there are advantages in reassessing how previous designs can be modified and optimised in the light of improved system understanding, allowing a robust EBS to be flexibly implemented to meet nation-specific and site-specific conditions. Full-scale emplacement demonstrations, particularly those carried out underground, have highlighted many of the practical issues to be addressed; e.g., handling of compacted bentonite in humid conditions, use of concrete for support infrastructure, remote handling of heavy radioactive packages in confined conditions, quality inspection, monitoring / ease of retrieval of emplaced packages and institutional control. The CAvern REtrievable (CARE) concept reduces or avoids such issues by emplacement of HLW or SF within multi-purpose transportation / storage / disposal casks in large ventilated caverns at a depth of several hundred metres. The facility allows the caverns to serve as inspectable stores for an extended period of time (up to a few hundred years) until a decision is made to close them. At this point the caverns are backfilled and sealed as a final repository, effectively with the same safety case components as conventional 'feasibility designs'. In terms of operational practicality an d safety, the CARE

  2. Risk assessment of nonhazardous oil-field waste disposal in salt caverns

    International Nuclear Information System (INIS)

    Elcock, D.

    1998-01-01

    Salt caverns can be formed in underground salt formations incidentally as a result of mining or intentionally to create underground chambers for product storage or waste disposal. For more than 50 years, salt caverns have been used to store hydrocarbon products. Recently, concerns over the costs and environmental effects of land disposal and incineration have sparked interest in using salt caverns for waste disposal. Countries using or considering using salt caverns for waste disposal include Canada (oil-production wastes), Mexico (purged sulfates from salt evaporators), Germany (contaminated soils and ashes), the United Kingdom (organic residues), and the Netherlands (brine purification wastes). In the US, industry and the regulatory community are pursuing the use of salt caverns for disposal of oil-field wastes. In 1988, the US Environmental Protection Agency (EPA) issued a regulatory determination exempting wastes generated during oil and gas exploration and production (oil-field wastes) from federal hazardous waste regulations--even though such wastes may contain hazardous constituents. At the same time, EPA urged states to tighten their oil-field waste management regulations. The resulting restrictions have generated industry interest in the use of salt caverns for potentially economical and environmentally safe oil-field waste disposal. Before the practice can be implemented commercially, however, regulators need assurance that disposing of oil-field wastes in salt caverns is technically and legally feasible and that potential health effects associated with the practice are acceptable. In 1996, Argonne National Laboratory (ANL) conducted a preliminary technical and legal evaluation of disposing of nonhazardous oil-field wastes (NOW) into salt caverns. It investigated regulatory issues; the types of oil-field wastes suitable for cavern disposal; cavern design and location considerations; and disposal operations, closure and remediation issues. It determined

  3. Risk assessment of nonhazardous oil-field waste disposal in salt caverns.

    Energy Technology Data Exchange (ETDEWEB)

    Elcock, D.

    1998-03-10

    Salt caverns can be formed in underground salt formations incidentally as a result of mining or intentionally to create underground chambers for product storage or waste disposal. For more than 50 years, salt caverns have been used to store hydrocarbon products. Recently, concerns over the costs and environmental effects of land disposal and incineration have sparked interest in using salt caverns for waste disposal. Countries using or considering using salt caverns for waste disposal include Canada (oil-production wastes), Mexico (purged sulfates from salt evaporators), Germany (contaminated soils and ashes), the United Kingdom (organic residues), and the Netherlands (brine purification wastes). In the US, industry and the regulatory community are pursuing the use of salt caverns for disposal of oil-field wastes. In 1988, the US Environmental Protection Agency (EPA) issued a regulatory determination exempting wastes generated during oil and gas exploration and production (oil-field wastes) from federal hazardous waste regulations--even though such wastes may contain hazardous constituents. At the same time, EPA urged states to tighten their oil-field waste management regulations. The resulting restrictions have generated industry interest in the use of salt caverns for potentially economical and environmentally safe oil-field waste disposal. Before the practice can be implemented commercially, however, regulators need assurance that disposing of oil-field wastes in salt caverns is technically and legally feasible and that potential health effects associated with the practice are acceptable. In 1996, Argonne National Laboratory (ANL) conducted a preliminary technical and legal evaluation of disposing of nonhazardous oil-field wastes (NOW) into salt caverns. It investigated regulatory issues; the types of oil-field wastes suitable for cavern disposal; cavern design and location considerations; and disposal operations, closure and remediation issues. It determined

  4. Risk assessment of nonhazardous oil-field waste disposal in salt caverns

    International Nuclear Information System (INIS)

    Elcock, D.

    1998-01-01

    In 1996, Argonne National Laboratory (ANL) conducted a preliminary technical and legal evaluation of disposing of nonhazardous oil-field wastes (NOW) into salt caverns. Argonne determined that if caverns are sited and designed well, operated carefully, closed properly, and monitored routinely, they could be suitable for disposing of oil-field wastes. On the basis of these findings, Argonne subsequently conducted a preliminary evaluation of the possibility that adverse human health effects (carcinogenic and noncarcinogenic) could result from exposure to contaminants released from the NOW disposed of in domal salt caverns. Steps used in this evaluation included the following: identifying potential contaminants of concern, determining how humans could be exposed to these contaminants, assessing contaminant toxicities, estimating contaminant intakes, and calculating human cancer and noncancer risk estimates. Five postclosure cavern release scenarios were assessed. These were inadvertent cavern intrusion, failure of the cavern seal, failure of the cavern through cracks, failure of the cavern through leaky interbeds, and a partial collapse of the cavern roof. Assuming a single, generic, salt cavern and generic oil-field wastes, potential human health effects associated with constituent hazardous substances (arsenic, benzene, cadmium, and chromium) were assessed under each of these scenarios. Preliminary results provided excess cancer risk and hazard index (referring to noncancer health effects) estimates that were well within the US Environmental Protection Agency (EPA) target range for acceptable exposure risk levels. These results led to the preliminary conclusion that from a human health perspective, salt caverns can provide an acceptable disposal method for nonhazardous oil-field wastes

  5. Risk assessment of nonhazardous oil-field waste disposal in salt caverns.

    Energy Technology Data Exchange (ETDEWEB)

    Elcock, D.

    1998-03-05

    In 1996, Argonne National Laboratory (ANL) conducted a preliminary technical and legal evaluation of disposing of nonhazardous oil-field wastes (NOW) into salt caverns. Argonne determined that if caverns are sited and designed well, operated carefully, closed properly, and monitored routinely, they could be suitable for disposing of oil-field wastes. On the basis of these findings, Argonne subsequently conducted a preliminary evaluation of the possibility that adverse human health effects (carcinogenic and noncarcinogenic) could result from exposure to contaminants released from the NOW disposed of in domal salt caverns. Steps used in this evaluation included the following: identifying potential contaminants of concern, determining how humans could be exposed to these contaminants, assessing contaminant toxicities, estimating contaminant intakes, and calculating human cancer and noncancer risk estimates. Five postclosure cavern release scenarios were assessed. These were inadvertent cavern intrusion, failure of the cavern seal, failure of the cavern through cracks, failure of the cavern through leaky interbeds, and a partial collapse of the cavern roof. Assuming a single, generic, salt cavern and generic oil-field wastes, potential human health effects associated with constituent hazardous substances (arsenic, benzene, cadmium, and chromium) were assessed under each of these scenarios. Preliminary results provided excess cancer risk and hazard index (referring to noncancer health effects) estimates that were well within the US Environmental Protection Agency (EPA) target range for acceptable exposure risk levels. These results led to the preliminary conclusion that from a human health perspective, salt caverns can provide an acceptable disposal method for nonhazardous oil-field wastes.

  6. Risk analyses for disposing nonhazardous oil field wastes in salt caverns

    Energy Technology Data Exchange (ETDEWEB)

    Tomasko, D.; Elcock, D.; Veil, J.; Caudle, D.

    1997-12-01

    Salt caverns have been used for several decades to store various hydrocarbon products. In the past few years, four facilities in the US have been permitted to dispose nonhazardous oil field wastes in salt caverns. Several other disposal caverns have been permitted in Canada and Europe. This report evaluates the possibility that adverse human health effects could result from exposure to contaminants released from the caverns in domal salt formations used for nonhazardous oil field waste disposal. The evaluation assumes normal operations but considers the possibility of leaks in cavern seals and cavern walls during the post-closure phase of operation. In this assessment, several steps were followed to identify possible human health risks. At the broadest level, these steps include identifying a reasonable set of contaminants of possible concern, identifying how humans could be exposed to these contaminants, assessing the toxicities of these contaminants, estimating their intakes, and characterizing their associated human health risks. The contaminants of concern for the assessment are benzene, cadmium, arsenic, and chromium. These were selected as being components of oil field waste and having a likelihood to remain in solution for a long enough time to reach a human receptor.

  7. Computer-aided evaluation of waste disposal cavern construction methods. ISBN 3-9801713-0-2.

    International Nuclear Information System (INIS)

    Knissel, W.; Fahlbusch, M.

    1991-01-01

    The disposal of hazardous radioactive and toxic wastes in deep geological formations is considered the safest solution in many countries. The Federal Republic of Germany prefers salt formations for underground disposal on account of the special advantages of the rock salt. Calculation methods are presented for the mathematical description of mining techniques for the construction of waste disposal salt caverns. The developed calculation model allows one to evaluate different construction methods with regard to expenses and time. (orig./DG) [de

  8. Geological disposal concept hearings

    International Nuclear Information System (INIS)

    1996-01-01

    The article outlines the progress to date on AECL spent-nuclear fuel geological disposal concept. Hearings for discussion, organised by the federal Environmental Assessment Review Panel, of issues related to this type of disposal method occur in three phases, phase I focuses on broad societal issues related to long term management of nuclear fuel waste; phase II will focus on the technical aspects of this method of disposal; and phase III will consist of community visits in New Brunswick, Quebec, Ontario, Manitoba and Saskatchewan. This article provides the events surrounding the first two weeks of phase I hearings (extracted from UNECAN NEWS). In the first week of hearings, where submissions on general societal issues was the focus, there were 50 presentations including those by Natural Resources Canada, Energy Probe, Ontario Hydro, AECL, Canadian Nuclear Society, Aboriginal groups, environmental activist organizations (Northwatch, Saskatchewan Environmental Society, the Inter-Church Uranium Committee, and the Canadian Coalition for Nuclear responsibility). In the second week of hearings there was 33 presentations in which issues related to siting and implementation of a disposal facility was the focus. Phase II hearings dates are June 10-14, 17-21 and 27-28 in Toronto

  9. Borehole disposal design concept

    International Nuclear Information System (INIS)

    RANDRIAMAROLAHY, J.N.

    2007-01-01

    In Madagascar, the sealed radioactive sources are used in several socioeconomic sectors such as medicine, industry, research and agriculture. At the end of their useful lives, these radioactive sources become radioactive waste and can be still dangerous because they can cause harmful effects to the public and the environment. This work entitled 'Borehole disposal design concept' consists in putting in place a site of sure storage of the radioactive waste, in particular, sealed radioactive sources. Several technical aspects must be respected to carry out such a site like the geological, geomorphologic, hydrogeologic, geochemical, meteorological and demographic conditions. This type of storage is favorable for the developing countries because it is technologically simple and economic. The cost of construction depends on the volume of waste to store and the depth of the Borehole. The Borehole disposal concept provides a good level of safety to avoid the human intrusion. The future protection of the generations against the propagation of the radiations ionizing is then assured. [fr

  10. Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods

    Energy Technology Data Exchange (ETDEWEB)

    Veil, J.A.

    1997-09-01

    According to an American Petroleum Institute production waste survey reported on by P.G. Wakim in 1987 and 1988, the exploration and production segment of the US oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes, more than 20 billion bbl of produced water, and nearly 12 million bbl of associated wastes in 1985. Current exploration and production activities are believed to be generating comparable quantities of these oil field wastes. Wakim estimates that 28% of drilling wastes, less than 2% of produced water, and 52% of associated wastes are disposed of in off-site commercial facilities. In recent years, interest in disposing of oil field wastes in solution-mined salt caverns has been growing. This report provides information on the availability of commercial disposal companies in oil-and gas-producing states, the treatment and disposal methods they employ, and the amounts they charge. It also compares cavern disposal costs with the costs of other forms of waste disposal.

  11. A numerical study on the structural behavior of underground rock caverns for radioactive waste disposal

    International Nuclear Information System (INIS)

    Kim, Sun Hoon; Choi, Kyu Sup; Lee, Kyung Jin; Kim, Dae Hong

    1991-01-01

    In order to design safe and economical underground disposal structures for radioactive wastes, understanding the behavior of discontinuous rock masses is essential. This study includes discussions about the computational model for discontinuous rock masses and the structural analysis method for underground storage structures. Then, based on an engineering judgement a suitable selection and slight modifications on computational models and analysis methods have been made in order to analyze and understand the structural behavior of the rock cavern with discontinuities

  12. The progress and results of a demonstration test of a cavern-type disposal facility

    International Nuclear Information System (INIS)

    Akiyama, Yoshihiro; Terada, Kenji; Oda, Nobuaki; Yada, Tsutomu; Nakajima, Takahiro

    2011-01-01

    The cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity levels mainly generated from power reactor decommissioning and for part of transuranic (TRU) waste mainly from spent fuel reprocessing are designed to be constructed in a cavern 50 to 100 meters below ground, and to employ an engineered barrier system (EBS) of a combination of bentonite and cement materials in Japan. In order to advance the feasibility study for these disposal, a government-commissioned research project named Demonstration Test of Cavern-Type Disposal Facility started in fiscal 2005, and since fiscal 2007 a full-scale mock-up test facility has been constructed under actual subsurface environment. The main objective of the test is to establish construction methodology and procedures which ensure the required quality of the EBS on-site. By fiscal 2009 some parts of the facility have been constructed, and the test has demonstrated both practicability of the construction and achievement of the quality. They are respectively taken as low-permeability of less than 5x10 13 m/s and low-diffusivity of less than 1x10 -12 m 2 /s at the time of completion of construction. This paper covers the project outline and the test results obtained by the construction of some parts of a bentonite and cement materials. (author)

  13. Current status of the Demonstration Test of Underground Cavern-Type Disposal Facilities

    International Nuclear Information System (INIS)

    Akiyama, Yoshihiro; Terada, Kenji; Oda, Nobuaki; Yada, Tsutomu; Nakajima, Takahiro

    2011-01-01

    In Japan, the underground cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity, mainly generated from power reactor decommissioning, and for certain transuranic (TRU) waste, mainly from spent fuel reprocessing, are designed to be constructed in a cavern 50-100 m underground and to employ an engineered barrier system (EBS) made of bentonite and cement materials. To advance a disposal feasibility study, the Japanese government commissioned the Demonstration Test of Underground Cavern-Type Disposal Facilities in fiscal year (FY) 2005. Construction of a full-scale mock-up test facility in an actual subsurface environment started in FY 2007. The main test objective is to establish the construction methodology and procedures that ensure the required quality of the EBS on-site. A portion of the facility was constructed by 2010, and the test has demonstrated both the practicability of the construction and the achievement of quality standards: low permeability of less than 5x10 -13 m/s and low-diffusion of less than 1x10 -12 m 2 /s at the completion of construction. This paper covers the test results from the construction of certain parts using bentonite and cement materials. (author)

  14. Simulation of concrete deterioration in Finnish rock cavern conditions for final disposal of nuclear waste

    International Nuclear Information System (INIS)

    Kari, O.P.; Puttonen, J.

    2014-01-01

    Highlights: • Concrete deterioration in Finnish rock cavern disposal conditions was simulated. • Simulation requires advanced models instead of traditional linear diffusion models. • Concrete analysed performed moderately during the period of 500 years. • Corrosion of steel reinforcement cannot be excluded during the period analysed. - Abstract: A simulation of concrete ageing in Finnish rock cavern disposal conditions showed that the concrete undergoes complex deterioration processes during the period required for lowering the level of radiation. In respect of the concrete ageing, the life time of the disposal facilities shall be divided into the periods before and after the closing of the caverns. Generally, the sulphate-resistant type of concrete analysed performed moderately during the analysed period of 500 years contrary to the corrosion of steel reinforcement, which cannot be excluded. Simulation of ageing clearly requires thermodynamical methods instead of linear diffusion models based on Fick’s law, which are traditionally used in construction industry. The study proves that the thermodynamical simulation method developed with adequate experimental data also makes it possible to observe latent factors of concrete deterioration

  15. Republic of Korea. Closure concept development for LILW disposal facility in Republic of Korea

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear Environment Technology Institute (NETEC) of Korea Electric Power Corporation (KEPCO) is developing near surface disposal concepts for both a rock cavern type disposal facility, and a vault type facility; two types of facility are being considered to provide more options for LILW repository siting. The conceptual design for the vault type facility will be completed in 1999. As a part of conceptual design effort, a preliminary concept for the disposal facility closure has been identified

  16. Buffer Construction Methodology in Demonstration Test For Cavern Type Disposal Facility

    International Nuclear Information System (INIS)

    Yoshihiro, Akiyama; Takahiro, Nakajima; Katsuhide, Matsumura; Kenji, Terada; Takao, Tsuboya; Kazuhiro, Onuma; Tadafumi, Fujiwara

    2009-01-01

    A number of studies concerning a cavern type disposal facility have been carried out for disposal of low level radioactive waste mainly generated by power plant decommissioning in Japan. The disposal facility is composed of an engineered barrier system with concrete pit and bentonite buffer, and planed to be constructed in sub-surface 50 - 100 meters depth. Though the previous studies have mainly used laboratory and mock-up tests, we conducted a demonstration test in a full-size cavern. The main objectives of the test were to study the construction methodology and to confirm the quality of the engineered barrier system. The demonstration test was planned as the construction of full scale mock-up. It was focused on a buffer construction test to evaluate the construction methodology and quality control in this paper. Bentonite material was compacted to 1.6 Mg/m 3 in-site by large vibrating roller in this test. Through the construction of the buffer part, a 1.6 Mg/m 3 of the density was accomplished, and the data of workability and quality is collected. (authors)

  17. Demonstration test of underground cavern-type disposal facilities, fiscal 2010 status - 59180

    International Nuclear Information System (INIS)

    Akiyama, Yoshihiro; Terada, Kenji; Oda, Nobuaki; Yada, Tsutomu; Nakajima, Takahiro

    2012-01-01

    A test to demonstrate practical construction technology for underground cavern-type disposal facilities is currently underway. Cavern-type disposal facilities are a radioactive waste repository excavated to a depth of 50 to 100 m below ground and constructed with an engineered barrier system (EBS) that is a combination of low-permeable bentonite material and low-diffusive cementitious material. The disposed materials are low-level radioactive waste with relatively high radioactivity, mainly generated from power reactor decommissioning, and certain transuranic wastes that are mainly generated from spent fuel reprocessing. The project started in fiscal 2005*, and since fiscal 2007 a full-scale mock-up of a disposal facility has been constructed in an actual sub-surface environment. The main objective of the demonstration test is to establish construction procedures and methods which ensure the required quality of an EBS on-site. Certain component parts of the facility had been constructed in an underground cavern by fiscal 2010, and tests so far have demonstrated both the practicability of the construction and the achievement of the required quality. This paper covers the project outline and the test results obtained by the construction of certain EBS components. The following results were obtained from the construction test of EBS in the test cavern: 1) The dry density of bentonite buffer at the lower layer constructed by vibratory compaction shows that 95% of core samples have densities within the target range. 2) The specified mix for the low-diffusion layer has uniform density and crack-control properties, and meets the requirements for diffusion performance. 3) The specified mix of the concrete pit has sufficient passing ability through congested reinforcement and meets the requirements of strength performance. 4) The dry density of the bentonite buffer at the lateral layer constructed by the spraying method shows that 65% of the core samples are within the

  18. Evaluation on construction quality of pit filler material of cavern type radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Takechi, Shin-ichi; Yokozeki, Kosuke; Shimbo, Hiroshi; Terada, Kenji; Akiyama, Yoshihiro; Yada, Tsutomu; Tsuji, Yukikazu

    2014-01-01

    The pit filler material of the underground cavern-type radioactive waste disposal facility, which is poured directly around the radioactive waste packages where high temperature environment is assumed by their decay heat, is concerned to be adversely affected on the filling behavior and its hardened properties. There also are specific issues that required quality of construction must be achieved by unmanned construction with remote operation, because the pit filler construction shall be done under radiation environment. In this paper, the mix proportion of filler material is deliberated with filling experiments simulating high temperature environment, and also the effect of temperature on hardened properties are confirmed with high temperature curing test. Subsequently, the feasibility of unmanned construction method of filler material by pumping, and by movable bucket, are comparatively discussed through a real size demonstration. (author)

  19. Disposal and solidification of LAW/MAW in underground caverns, phase 4

    International Nuclear Information System (INIS)

    Ganser, B.; Dedegil, Y.

    1989-05-01

    In this report the concluding phase IV of the project for the containerless disposal of LAW/MAW-concentrate is described. This phase IV became necessary because of two pipe pluggings during phase III to demonstrate the technical performability. Compared with phase III the following plant and process modifications were performed: partially filled cross section of the feed pipe ('snifting air'), increased feed pipe diameter (47.4 to 59.4 mm), increased plant throughput (12 t/h to 24 t/h), feed pipe instrumentation (density, flow, pressure). In the pilot scale the modified process was tested in a 100 m-pipe (Asse, Blindschacht 4). The technical demonstration was performed by the 1000 m pipe from the above-day plant to the prototype cavern of the Asse salt mine. Overall more than 1000 t of product have been feeded within several shifts in successful performance. (orig.) [de

  20. Concept for Underground Disposal of Nuclear Waste

    Science.gov (United States)

    Bowyer, J. M.

    1987-01-01

    Packaged waste placed in empty oil-shale mines. Concept for disposal of nuclear waste economically synergistic with earlier proposal concerning backfilling of oil-shale mines. New disposal concept superior to earlier schemes for disposal in hard-rock and salt mines because less uncertainty about ability of oil-shale mine to contain waste safely for millenium.

  1. Research on base rock mechanic characteristics of caverns for radioactive waste disposal

    International Nuclear Information System (INIS)

    Isei, Takehiro; Katsuyama, Kunihisa; Seto, Masahiro; Ogata, Yuji; Utagawa, Manabu

    1997-01-01

    It has been considered that underground space is mechanically stable as compared with on the ground, and superior for storing radioactive waste for long period. However, in order to utilize underground space for the place of radioactive waste disposal, its long term stability such as the aseismatic ability of base rocks must be ensured, and for this purpose, it is necessary to grasp the mechanical characteristics of the base rocks around caverns, and to advance the technology for measuring and evaluating minute deformation and earth pressure change. In this research, the study on the fracture mechanics characteristics of base rocks and the development of the technology for measuring long terms stress change of base rocks were carried out. In this research, what degree the memory of past stress is maintained by rocks was presumed by measuring AE and strain when stress was applied to rock test pieces. The rocks tested were tuff, sandstone and granite. The experimental method and the experimental results of the prestress by AE method and DRA are reported. (K.I.)

  2. Preliminary Technical and Legal Evaluation of Disposing of Nonhazardous Oil Field Waste into Salt Caverns

    National Research Council Canada - National Science Library

    Veil, John

    1996-01-01

    .... These caverns are either created incidentally as a result of salt recovery or intentionally to create an underground chamber that can be used for storing hydrocarbon products or compressed air...

  3. Assessment of alternative disposal concepts

    Energy Technology Data Exchange (ETDEWEB)

    Autio, J.; Saanio, T.; Tolppanen, P. [Saanio and Riekkola Consulting Engineers, Helsinki (Finland); Raiko, H.; Vieno, T. [VTT Energy, Espoo (Finland); Salo, J.P. [Posiva Oy, Helsinki (Finland)

    1996-12-01

    Four alternative repository designs for the disposal of spent nuclear in the Finnish crystalline bedrock were assessed in the study. The alternatives were: (1) the basic KBS-3 design in which copper canisters are emplaced in vertical deposition holes bored in the floors of horizontal tunnels, (2) the KBS-3-2C design with two canisters in a deposition hole, (3) Short Horizontal Holes (SHH) in the side walls of the tunnels, and (4) the Medium Long Holes (MLH) concept in which approximately 25 canisters are emplaced in a horizontal deposition hole about 200 metres in length bored between central and side tunnels. In all the alternatives considered, the thickness of the layer of compacted bentonite between copper canister and bedrock is 35 cm. Two different copper canister designs were also assessed. Technical feasibility and flexibility, post-closure safety and repository cost were assessed for each of the alternative canister and repository designs. On the basis of this assessment it is recommended that further development and studies should focus on the vacuum- or inert gas-filled cast insert type copper canister and the basic KBS-3 type repository design with a single canister in a vertical deposition hole. The KBS-3 design is robust and flexible and provides excellent post-closure safety. The transfer, emplacement and sealing operations are technically uncomplicated. The alternative options assessed do not offer any significant benefits in safety or cost over the basic design, but they are technically more complex and also in some respects more vulnerable to malfunction during the emplacement of canisters and buffer, as well as common mode failures. (60 refs.).

  4. Assessment of alternative disposal concepts

    International Nuclear Information System (INIS)

    Autio, J.; Saanio, T.; Tolppanen, P.; Raiko, H.; Vieno, T.; Salo, J.P.

    1996-12-01

    Four alternative repository designs for the disposal of spent nuclear in the Finnish crystalline bedrock were assessed in the study. The alternatives were: (1) the basic KBS-3 design in which copper canisters are emplaced in vertical deposition holes bored in the floors of horizontal tunnels, (2) the KBS-3-2C design with two canisters in a deposition hole, (3) Short Horizontal Holes (SHH) in the side walls of the tunnels, and (4) the Medium Long Holes (MLH) concept in which approximately 25 canisters are emplaced in a horizontal deposition hole about 200 metres in length bored between central and side tunnels. In all the alternatives considered, the thickness of the layer of compacted bentonite between copper canister and bedrock is 35 cm. Two different copper canister designs were also assessed. Technical feasibility and flexibility, post-closure safety and repository cost were assessed for each of the alternative canister and repository designs. On the basis of this assessment it is recommended that further development and studies should focus on the vacuum- or inert gas-filled cast insert type copper canister and the basic KBS-3 type repository design with a single canister in a vertical deposition hole. The KBS-3 design is robust and flexible and provides excellent post-closure safety. The transfer, emplacement and sealing operations are technically uncomplicated. The alternative options assessed do not offer any significant benefits in safety or cost over the basic design, but they are technically more complex and also in some respects more vulnerable to malfunction during the emplacement of canisters and buffer, as well as common mode failures. (60 refs.)

  5. Underground radioactive waste disposal concept

    International Nuclear Information System (INIS)

    Frgic, L.; Tor, K.; Hudec, M.

    2002-01-01

    The paper presents some solutions for radioactive waste disposal. An underground disposal of radioactive waste is proposed in deep boreholes of greater diameter, fitted with containers. In northern part of Croatia, the geological data are available on numerous boreholes. The boreholes were drilled during investigations and prospecting of petroleum and gas fields. The available data may prove useful in defining safe deep layers suitable for waste repositories. The paper describes a Russian disposal design, execution and verification procedure. The aim of the paper is to discuss some earlier proposed solutions, and present a solution that has not yet been considered - lowering of containers with high level radioactive waste (HLW) to at least 500 m under the ground surface.(author)

  6. Concept development for HLW disposal research tunnel

    International Nuclear Information System (INIS)

    Queon, S. K.; Kim, K. S.; Park, J. H.; Jeo, W. J.; Han, P. S.

    2003-01-01

    In order to dispose high-level radioactive waste in a geological formation, it is necessary to assess the safety of a disposal concept by excavating a research tunnel in the same geological formation as the host rock mass. The design concept of a research tunnel depends on the actual disposal concept, repository geometry, experiments to be carried at the tunnel, and geological conditions. In this study, analysis of the characteristics of the disposal research tunnel, which is planned to be constructed at KAERI site, calculation of the influence of basting impact on neighbor facilities, and computer simuation for mechanical stability analysis using a three-dimensional code, FLAC3D, had been carried out to develop the design concept of the research tunnel

  7. Gamma knife radiosurgery for benign cavernous sinus tumors. Treatment concept and outcomes in 120 cases

    International Nuclear Information System (INIS)

    Hayashi, Motohiro; Chernov, Mikhail; Tamura, Noriko

    2012-01-01

    Availability of modern computer-aided robotized devices, such as the Automatic Positioning System (APS TM ; Elekta Instruments AB, Stockholm, Sweden) and Perfexion TM (Elekta Instruments AB), allowed us to develop the original concept of robotic gamma knife microradiosurgery, which is based on the very precise irradiation of the lesion with regard to conformity and selectivity; intentional avoidance of the excessive irradiation of functionally-important anatomical structures, particularly cranial nerves, located both within and in the vicinity of the target; and delivery of sufficient irradiation energy to the tumor with the intention to attain lesion shrinkage, while keeping the marginal dose sufficiently low for prevention of possible complications. The results of such treatment strategy were evaluated retrospectively in 120 patients with benign cavernous sinus neoplasms (pituitary adenomas, meningiomas, schwannomas, and hemangiomas), who were followed up from 24 to 78 months (mean 47 months) after radiosurgery. Tumor growth control and shrinkage rates were 98% and 68%, respectively. More than 50% volume reduction was noted in 25% of lesions. The most prominent volumetric tumor response was observed in hemangiomas, followed by schwannomas, pituitary adenomas, and meningiomas. Treatment-related complications were marked in 7% of cases, and were mainly related to transient isolated cranial neuropathy appearing within several months after radiosurgery. Major morbidity was limited to one patient (0.8%). Application of microradiosurgical treatment principles provides effective and safe management of benign cavernous sinus tumors and is associated with high probability of lesion shrinkage and minimal risk of complications. (author)

  8. Mined Geologic Disposal System Concept of Operations

    International Nuclear Information System (INIS)

    Heidt, R.M.

    1995-01-01

    A Concept of Operations has been developed for the disposal of high-level radioactive waste in the potential geologic repository at Yucca Mountain. The Concept of Operations has been developed to document a cormion understanding of how the repository is to be operated. It is based on the repository architecture identified in the Initial Summary Report for Repository/Waste Package Advanced Conceptual Design and describes the operation of the repository from the initial receipt of waste through repository closure. Also described are operations for waste retrieval

  9. Borehole disposal design concept in Madagascar

    International Nuclear Information System (INIS)

    Randriamarolahy, J.N.; Randriantseheno, H.F.; Andriambololona, Raoelina

    2008-01-01

    Full text: In Madagascar, sealed radioactive sources are used in several socio-economic sectors such as medicine, industry, research and agriculture. At the end of their useful lives, these radioactive sources become ionizing radiations waste and can be still dangerous because they can cause harmful effects to the public and the environment. 'Borehole disposal design concept' is needed for sitting up a safe site for storage of radioactive waste, in particular, sealed radioactive sources. Borehole disposal is an option for long-term management of small quantities of radioactive waste in compliance with the internationally accepted principles for radioactive waste management. Several technical aspects must be respected to carry out such a site like the geological, geomorphologic, hydrogeology, geochemical, meteorological and demographic conditions. Two sites are most acceptable in Madagascar such as Ankazobe and Fanjakana. A Borehole will be drilled and constructed using standard techniques developed for water abstraction, oil exploration. At the Borehole, the sealed radioactive sources are encapsulated. The capsule is inserted in a container. This type of storage is benefit for the developing countries because it is technologically simple and economic. The construction cost depends on the volume of waste to store and the Borehole depth. The borehole disposal concept provides a good level of safety to avoid human intrusion. The future protection of the generations against the propagation of the ionizing radiations is then assured. (author)

  10. Waste and Disposal: Concept and Demonstration

    International Nuclear Information System (INIS)

    Neerdael, B.; Buyens, M.; De Bruyn, D.; Volckaert, G.

    2001-01-01

    Principal achievements in 2000 with regard to the PRACLAY programme are presented. The PRACLAY project has been conceived to demonstrate the construction and the operation of a gallery for the disposal of HLW in a clay formation. Within this context, various aspects concerning design and operation are investigated.The PRACLAY experiment will contribute to enhance understanding of water flow and mass transport in dense clay-based materials as well as to improve the design of the reference disposal concept. In 2000, efforts were focussed on the operation of the OPHELIE mock-up, which is a surface experiment designed to prepare and to complement PRACLAY-related experimental work in the HADES Underground Research Laboratory

  11. The surface disposal concept for VLL waste

    International Nuclear Information System (INIS)

    2011-01-01

    Disposal facilities for very-low-level (VLL) waste have been designed to accommodate both residues originating from the decommissioning of nuclear facilities and used components. Those residues have very low specific-activity levels that lie below a few hundreds of becquerels per gram (Bq/g). As for the average activity found in any disposal facility, it never exceeds more than a few tens of becquerels per gram. In that case, waste disposal involves no special processing or conditioning, except for handling requirements or volume-gain purposes. The main barrier against radionuclide dispersion is provided by the geological formation being used for waste disposal. Basic disposal concept The design and construction provisions allow for the optimal operation of the disposal facility without any risk of altering the required safety level. They also ensure a satisfactory containment level for several centuries at the end of the operating lifetime. Hence, the natural materials in their original context constitute a particular advantage for the safety demonstration over the long term. With due account of the nature of VLL waste, their containment envelope (drums, big bags, etc.) has no role in confining radioactivity, but rather in facilitating handling and disposal operations, while protecting operators. Approximately 30% of all waste received at the CSTFA undergo a specific treatment before disposal. Low-density residues (plastics, thermal-insulation materials, etc.) are first compacted by a baling press, then strapped and wrapped in clear plastic-sheet. Another bundle press is used to reduce the volume of scrap metal. Some waste, such as the polluted waters generated on site or the sludges sent by producers, are processed in the solidification and stabilisation unit. Disposal cells are excavated progressively, as needed, directly in the clay formation down to a depth of 8 m and are operated in sequence. Cell design has evolved to maximize the disposal volume, and now

  12. The surface disposal concept for VLL waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    Disposal facilities for very-low-level (VLL) waste have been designed to accommodate both residues originating from the decommissioning of nuclear facilities and used components. Those residues have very low specific-activity levels that lie below a few hundreds of becquerels per gram (Bq/g). As for the average activity found in any disposal facility, it never exceeds more than a few tens of becquerels per gram. In that case, waste disposal involves no special processing or conditioning, except for handling requirements or volume-gain purposes. The main barrier against radionuclide dispersion is provided by the geological formation being used for waste disposal. Basic disposal concept The design and construction provisions allow for the optimal operation of the disposal facility without any risk of altering the required safety level. They also ensure a satisfactory containment level for several centuries at the end of the operating lifetime. Hence, the natural materials in their original context constitute a particular advantage for the safety demonstration over the long term. With due account of the nature of VLL waste, their containment envelope (drums, big bags, etc.) has no role in confining radioactivity, but rather in facilitating handling and disposal operations, while protecting operators. Approximately 30% of all waste received at the CSTFA undergo a specific treatment before disposal. Low-density residues (plastics, thermal-insulation materials, etc.) are first compacted by a baling press, then strapped and wrapped in clear plastic-sheet. Another bundle press is used to reduce the volume of scrap metal. Some waste, such as the polluted waters generated on site or the sludges sent by producers, are processed in the solidification and stabilisation unit. Disposal cells are excavated progressively, as needed, directly in the clay formation down to a depth of 8 m and are operated in sequence. Cell design has evolved to maximize the disposal volume, and now

  13. Department of Energy low-level radioactive waste disposal concepts

    International Nuclear Information System (INIS)

    Ozaki, C.; Page, L.; Morreale, B.; Owens, C.

    1990-01-01

    The Department of Energy manages its low-level waste (LLW), regulated by DOE Order 5820.2A by using an overall systems approach. This systems approach provides an improved and consistent management system for all DOE LLW waste, from generation to disposal. This paper outlines six basic disposal concepts used in the systems approach, discusses issues associated with each of the concepts, and outlines both present and future disposal concepts used at six DOE sites

  14. Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

    International Nuclear Information System (INIS)

    Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu

    2016-01-01

    In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea

  15. Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea.

  16. Evaluation on applicability of construction methods and construction quality of low-diffusion layer of cavern type radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Takechi, Shin-ichi; Yokozeki, Kosuke; Terada, Kenji; Akiyama, Yoshihiro; Yada, Tsutomu; Tsuji, Yukikazu

    2014-01-01

    A performance verification experiment of cavern type radioactive waste disposal facility with a real scale construction is being conducted to evaluate the applicability of proposed construction methods and construction quality of the facility. In this paper, we confirmed that the low-diffusion layer, which is one of the cementitious materials based members, could be filled with mortar from end to end of the member; cracks of low-diffusion layer would not affect the long-term safety evaluation of the facility. And also we figured out the relationship between the material strength and the accumulated temperature, relationship between diffusion coefficient and porosity of low-diffusion layer. (author)

  17. Pore pressure measurement plan of near field rock used on three dimensional groundwater flow analysis in demonstration test of cavern type disposal facility

    International Nuclear Information System (INIS)

    Onuma, Kazuhiro; Terada, Kenji; Matsumura, Katsuhide; Koyama, Toshihiro; Yajima, Kazuaki

    2008-01-01

    Demonstration test of underground cavern type disposal facilities is planed though carrying out construction of full scale engineering barrier system which simulated in the underground space in full scale and under actual environment. This test consists of three part, these are construction test, performance test and measurement test. Behavior of near field rock mass is measured about hydrological behavior under and after construction to evaluate effect at test facility. To make plan of pore pressure measurement, three dimensional groundwater flow analysis has been carried out. Based on comparison of analysis before and after test, detail plan has been studied. (author)

  18. Comparison of disposal concepts for rock salt and hard rock

    International Nuclear Information System (INIS)

    Papp, R.

    1998-01-01

    The study was carried out in the period 1994-1996. The goals were to prepare a draft on spent fuel disposal in hard rock and additionally a comparison with existing disposal concepts for rock salt. A cask for direct disposal of spent fuel and a repository for hard rock including a safeguards concept were conceptually designed. The results of the study confirm, that the early German decision to employ rock salt was reasonable. (orig.)

  19. Alternative Concept to Enhance the Disposal Efficiency for CANDU Spent Fuel Disposal System

    International Nuclear Information System (INIS)

    Lee, Jong Youl; Cho, Dong Geun; Kook, Dong Hak; Lee, Min Soo; Choi, Heui Joo

    2011-01-01

    There are two types of nuclear reactors in Korea and they are PWR type and CANDU type. The safe management of the spent fuels from these reactors is very important factor to maintain the sustainable energy supply with nuclear power plant. In Korea, a reference disposal system for the spent fuels has been developed through a study on the direct disposal of the PWR and CANDU spent fuel. Recently, the research on the demonstration and the efficiency analyses of the disposal system has been performed to make the disposal system safer and more economic. PWR spent fuels which include a lot of reusable material can be considered being recycled and a study on the disposal of HLW from this recycling process is being performed. CANDU spent fuels are considered being disposed of directly in deep geological formation, since they have little reusable material. In this study, based on the Korean Reference spent fuel disposal System (KRS) which was to dispose of both PWR type and CANDU type, the more effective CANDU spent fuel disposal systems were developed. To do this, the disposal canister for CANDU spent fuels was modified to hold the storage basket for 60 bundles which is used in nuclear power plant. With these modified disposal canister concepts, the disposal concepts to meet the thermal requirement that the temperature of the buffer materials should not be over 100 .deg. C were developed. These disposal concepts were reviewed and analyzed in terms of disposal effective factors which were thermal effectiveness, U-density, disposal area, excavation volume, material volume etc. and the most effective concept was proposed. The results of this study will be used in the development of various wastes disposal system together with the HLW wastes from the PWR spent fuel recycling process.

  20. Technical concept for a Greater Confinement Disposal test facility

    International Nuclear Information System (INIS)

    Hunter, P.H.

    1982-01-01

    For the past two years, Ford, Bacon and Davis has been performing technical services for the Department of Energy at the Nevada Test Site in specific development of defense low-level waste management concepts for greater confinement disposal concept with particular application to arid sites. The investigations have included the development of Criteria for Greater Confinement Disposal, NVO-234, which was published in May of 1981 and the draft of the technical concept for Greater Confinement Disposal, with the latest draft published in November 1981. The final draft of the technical concept and design specifications are expected to be published imminently. The document is prerequisite to the actual construction and implementation of the demonstration facility this fiscal year. The GCD Criteria Document, NVO-234 is considered to contain information complimentary and compatible with that being developed for the reserved section 10 CFR 61.51b of the NRCs proposed licensing rule for low level waste disposal facilities

  1. Concept development for saltstone and low level waste disposal

    International Nuclear Information System (INIS)

    Wilhite, E.L.

    1987-03-01

    A low-level alkaline salt solution will be a byproduct in the processing of high-level waste at the Savannah River Plant (SRP). This solution will be incorporated into a cement wasteform, saltstone, and placed in surface vaults. Laboratory and field testing and mathematical modeling have demonstrated the predictability of contaminant release from cement wasteforms. Saltstone disposal in surface vaults will meet drinking water standards in shallow groundwater at the disposal area boundary. Planning for new Low-Level Waste (LLW) disposal could incorporate concepts developed for saltstone disposal

  2. State of the art for fabricating and emplacing concrete containers into large horizontal disposal caverns in the french geological repository - 59267

    International Nuclear Information System (INIS)

    Bosgiraud, Jean-Michel; Guariso, Maurice; Pineau, Francois

    2012-01-01

    The research and development work presented in this paper was initialized by Andra in 2007. The work necessary for manufacturing and testing a full scale demonstrator is presently implemented. The case story is twofold. The first part is related to the initial development of a high performance concrete formulation used for fabricating concrete storage containers (containing Intermediate Level and Long Lived Waste primary canisters) to be stacked and emplaced into 400-m long concrete lined horizontal disposal vaults (also called cavern), excavated in the Callovo-Oxfordian clay host formation at a 550 to 600-m depth, with an inside diameter of approximately 8-m. The fabrication of the concrete boxes is illustrated. The second part presents the outcome at the end of the detailed design phase, for a system which is now being manufactured (for further test and assembly), for the emplacement of the concrete containers inside the vault. The application was engineered for remote emplacing a pile of 2 concrete containers (the containers are preliminarily stacked in a pile of 2, inside a hot cell, thanks to a ground travelling gantry crane). The emplacement process is justified and the related emplacement synoptic is illustrated. The test campaign is scheduled in 2011-2012. The successful completion of the technical trials is mandatory to confirm the mechanical feasibility of remotely emplacing concrete containers into large horizontal disposal caverns over long distances. The later display of the machinery at work in Andra's showroom will be instrumental for the confidence building process involving the various stakeholders concerned by the public enquiry period (mid-2013) preceding the deep geological repository license application (2014-2015). (authors)

  3. History of geological disposal concept (3). Implementation phase of geological disposal (2000 upward)

    International Nuclear Information System (INIS)

    Masuda, Sumio; Sakuma, Hideki; Umeki, Hiroyuki

    2015-01-01

    Important standards and concept about geological disposal have been arranged as an international common base and are being generalized. The authors overview the concept of geological disposal, and would like this paper to help arouse broad discussions for promoting the implementation plan of geological disposal projects in the future. In recent years, the scientific and technological rationality of geological disposal has been recognized internationally. With the addition of discussions from social viewpoints such as ethics, economy, etc., geological disposal projects are in the stage of starting after establishment of social consensus. As an international common base, the following consolidated and systematized items have been presented as indispensable elements in promoting business projects: (1) step-by-step approach, (2) safety case, (3) reversibility and recovery potential, and (4) trust building and communications. This paper outlines the contents of the following cases, where international common base was reflected on the geological disposal projects in Japan: (1) final disposal method and safety regulations, and (2) impact of the Great East Japan Earthquake and Fukushima Daiichi Nuclear Power Station accident on geological disposal plan. (A.O.)

  4. Multi-Pack Disposal Concepts for Spent Fuel (Revision 1)

    International Nuclear Information System (INIS)

    Hardin, Ernest; Matteo, Edward N.; Hadgu, Teklu

    2016-01-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media. Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all "enclosed,"whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative "open"modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design. Thermal analysis showed that if "enclosed"concepts are constrained by peak package/buffer temperature, that waste package capacity is limited to 4 PWR assemblies (or 9 BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems. This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  5. Multi-pack Disposal Concepts for Spent Fuel (Rev. 0)

    Energy Technology Data Exchange (ETDEWEB)

    Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Matteo, Edward N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media (Hardin et al., 2012). Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all “enclosed,” whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative “open” modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design (CRWMS M&O, 1999). Thermal analysis showed that, if “enclosed” concepts are constrained by peak package/buffer temperature, waste package capacity is limited to 4 PWR assemblies (or 9-BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems (EnergySolution, 2015). This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  6. Multi-Pack Disposal Concepts for Spent Fuel (Revision 1)

    Energy Technology Data Exchange (ETDEWEB)

    Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Matteo, Edward N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media. Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all “enclosed,” whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative “open” modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design. Thermal analysis showed that if “enclosed” concepts are constrained by peak package/buffer temperature, that waste package capacity is limited to 4 PWR assemblies (or 9 BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems. This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  7. The disposal of orphan wastes using the greater confinement disposal concept

    International Nuclear Information System (INIS)

    Bonano, E.J.; Chu, M.S.Y.; Price, L.L.; Conrad, S.H.; Dickman, P.T.

    1991-01-01

    In the United States, radioactive wastes are conventionally classified as high-level wastes, transuranic wastes, or low-level wastes. Each of these types of wastes, by law, has a ''home'' for their final disposal; i.e., high-level wastes are destined for disposal at the proposed repository at Yucca Mountain, transuranic waste for the proposed Waste Isolation Pilot Plant, and low-level waste for shallow-land disposal sites. However, there are some radioactive wastes within the United States Department of Energy (DOE) complex that do not meet the criteria established for disposal of either high-level waste, transuranic waste, or low-level waste. The former are called ''special-case'' or ''orphan'' wastes. This paper describes an ongoing project sponsored by the DOE's Nevada Operations Office for the disposal of orphan wastes at the Radioactive Waste Management Site at Area 5 of the Nevada Test Site using the greater confinement disposal (GCD) concept. The objectives of the GCD project are to evaluate the safety of the site for disposal of orphan wastes by assessing compliance with pertinent regulations through performance assessment, and to examine the feasibility of this disposal concept as a cost-effective, safe alternative for management of orphan wastes within the DOE complex. Decisions on the use of GCD or other alternate disposal concepts for orphan wastes be expected to be addressed in a Programmatic Environmental Impact Statement being prepared by DOE. The ultimate decision to use GCD will require a Record of Decision through the National Environmental Policy Act (NEPA) process. 20 refs., 3 figs., 2 tabs

  8. Disposal Concepts for Radioactive Waste. Final Report of the Expert Group on Disposal Concepts for Radioactive Waste (EKRA)

    Energy Technology Data Exchange (ETDEWEB)

    Wildi, Walter; Dermange, Francois [Univ. of Geneva, CH-1211 Geneva (Switzerland); Appel, Detlef [PanGeo, Hannover (Germany); Buser, Marcos [Buser and Finger, Zurich (Switzerland); Eckhardt, Anne [Basler and Hofmann, Zurich (Switzerland); Hufschmied, Peter [Emch and Berger, Bern (Switzerland); Keusen, Hans-Rudolf [Geotest, Zollikofen (Switzerland); Aebersold, Michael [Swiss Federal Office of Energy (BFE), CH-3003 Bern (Switzerland)

    2000-01-15

    At the beginning of 1999, talks between the Swiss Federal Government, the siting Cantons (Cantons in which nuclear power plants are located and Canton Nidwalden), environmental organisations and the nuclear power plant operators on the lifetime of the existing power plants and solution of the waste management problem failed to reach a satisfactory outcome. In view of this, the Head of the Federal Department for the Environment, Transport, Energy and Communication (UVEK) decided to set up the Expert Group on Disposal Concepts for Radioactive Waste (EKRA) in June 1999. EKRA then worked on providing the background for a comparison of different waste management concepts. The group developed the concept of monitored long-term geological disposal and compared this with geological disposal, interim storage and indefinite storage. The aspects of active and passive safety, monitoring and control, as well as retrievability of waste were at the fore-front of these deliberations. This report presents the conclusions and recommendations of EKRA.

  9. Disposal Concepts for Radioactive Waste. Final Report of the Expert Group on Disposal Concepts for Radioactive Waste (EKRA)

    International Nuclear Information System (INIS)

    Wildi, Walter; Dermange, Francois; Appel, Detlef; Buser, Marcos; Eckhardt, Anne; Hufschmied, Peter; Keusen, Hans-Rudolf; Aebersold, Michael

    2000-01-01

    At the beginning of 1999, talks between the Swiss Federal Government, the siting Cantons (Cantons in which nuclear power plants are located and Canton Nidwalden), environmental organisations and the nuclear power plant operators on the lifetime of the existing power plants and solution of the waste management problem failed to reach a satisfactory outcome. In view of this, the Head of the Federal Department for the Environment, Transport, Energy and Communication (UVEK) decided to set up the Expert Group on Disposal Concepts for Radioactive Waste (EKRA) in June 1999. EKRA then worked on providing the background for a comparison of different waste management concepts. The group developed the concept of monitored long-term geological disposal and compared this with geological disposal, interim storage and indefinite storage. The aspects of active and passive safety, monitoring and control, as well as retrievability of waste were at the fore-front of these deliberations. This report presents the conclusions and recommendations of EKRA

  10. Progress report on disposal concept for TRU waste in Japan

    International Nuclear Information System (INIS)

    2000-03-01

    The object of this report is to contribute towards establishing a national TRU waste disposal program by integrating the results of research and development work carried out by JNC and the electricity utilities and summarizing the findings concerning safe methods for TRU waste disposal. The report consists of 5 chapters: the first describes the boundary conditions for the review of the TRU waste disposal concept (including geological conditions) and the basic concept adopted; the second describes the generation and characteristics of TRU waste and the third outlines the disposal technology; the fourth gives the key of the safety assessment and the fifth presents the conclusions of the report and lists issues for future consideration. The geological environment of Japan is simply classified into crystalline and sedimentary rock types (in terms of groundwater flow properties and rock strength) and a set of target conditions/properties for each rock type is then established. Based on this, a case which represents the basis for performance assessment (the reference case) will be defined. Alternatives to the reference case are studied to investigate the flexibility of the disposal concept. Under the conditions assumed in this study, the perturbing events considered showed no significant effects on the dose at the 100 meter evaluation point, owing to the relatively high efficiency of the natural barrier. However, the significant effect of these events on nuclide from the EBS shows that, in the case of a less efficient natural barrier, their effects could influence resulting dose. (S.Y.)

  11. Study on the background information for the geological disposal concept

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Murano, Tohru; Hirusawa, Shigenobu; Komoto, Harumi

    1999-11-01

    Japan Nuclear Cycle Development Institute (JNC) has published the first R and D progress report in 1992. In which the fruits of the R and D works were compiled. Since then the next step of R and D has been developing progressively in Japan. Now JNC has a plan to make the second R and D progress report until before 2000, in which information on the geological disposal of high level radioactive waste(HLW) will be presented to show the technical reliability and technical basis to contribute for the site selection or the safety-standard developments. Recognizing the importance of the social consensus to the geological disposal of international discussions in 1990's, understanding and consensus by the society are essential to the development and realization of the geological disposal of HLW. For getting social understanding and consensus, it is quite important to present the broad basis background information on the geological disposal of HLW, together with the technical basis and also the international discussion of the issues. In this report, the following studies have been done to help to prepare the background information for the 2nd R and D progress report, based on the recent informations and research and assessment works of last 2 years. These are, (1) As the part of general discussion, characteristics of HLW disposal and several issues to be considered for establishing the measures of the disposal of HLW were identified and analyzed from both practical and logical points of view. Those issues were the concept and image of the long term safety measures, the concept and criteria of geological disposal, and, safety assessment and performance assessment. (2) As the part of specific discussion, questions and concerns frequently raised by the non-specialists were taken up and 10 topics in relation to the geological disposal have been identified based on the discussion. Scientific and technical facts, consensus by the specialists on the issues, and international

  12. Concepts and Technologies for Radioactive Waste Disposal in Rock Salt

    Directory of Open Access Journals (Sweden)

    Wernt Brewitz

    2007-01-01

    Full Text Available In Germany, rock salt was selected to host a repository for radioactive waste because of its excellent mechanical properties. During 12 years of practical disposal operation in the Asse mine and 25 years of disposal in the disused former salt mine Morsleben, it was demonstrated that low-level wastes (LLW and intermediate-level wastes (ILW can be safely handled and economically disposed of in salt repositories without a great technical effort. LLW drums were stacked in old mining chambers by loading vehicles or emplaced by means of the dumping technique. Generally, the remaining voids were backfilled by crushed salt or brown coal filter ash. ILW were lowered into inaccessible chambers through a borehole from a loading station above using a remote control.Additionally, an in-situ solidification of liquid LLW was applied in the Morsleben mine. Concepts and techniques for the disposal of heat generating high-level waste (HLW are advanced as well. The feasibility of both borehole and drift disposal concepts have been proved by about 30 years of testing in the Asse mine. Since 1980s, several full-scale in-situ tests were conducted for simulating the borehole emplacement of vitrified HLW canisters and the drift emplacement of spent fuel in Pollux casks. Since 1979, the Gorleben salt dome has been investigated to prove its suitability to host the national final repository for all types of radioactive waste. The “Concept Repository Gorleben” disposal concepts and techniques for LLW and ILW are widely based on the successful test operations performed at Asse. Full-scale experiments including the development and testing of adequate transport and emplacement systems for HLW, however, are still pending. General discussions on the retrievability and the reversibility are going on.

  13. Study on the background information for the geological disposal concept

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Murano, Tohru; Hirusawa, Shigenobu; Komoto, Harumi

    2000-03-01

    Japan Nuclear Cycle Development Institute (JNC) has published first R and D report in 1992, in which the fruits of the R and D work were compiled. Since then, JNC, has been promoting the second R and D progress report until before 2000, in which the background information on the geological disposal of high level radioactive waste (HLW) was to be presented as well as the technical basis. Recognizing the importance of the social consensus to the geological disposal, understanding and consensus by the society are essential to the development and realization of the geological disposal of HLW. In this fiscal year, studies were divided into 2 phases, considering the time schedule of the second R and D progress report. 1. Phase 1: Analysis of the background information on the geological disposal concept. Based on the recent informations and the research works of last 2 years, final version of the study was made to contribute to the background informations for the second R and D progress report. (This was published in Nov. 1999 as the intermediate report: JNC TJ 1420 2000-006). 2. Phase 2: Following 2 specific items were selected for the candidate issues which need to be studied, considering the present circumstances around the R and D of geological disposal. (1) Educational materials and strategies related to nuclear energy and nuclear waste. Specific strategies and approaches in the area of nuclear energy and nuclear waste educational outreach and curriculum activities by the nuclear industry, government and other entities in 6 countries were surveyed and summarized. (2) Alternatives to geological disposal of HLW: Past national/international consideration and current status. The alternatives for the disposal of HLW have been discussed in the past and the major waste-producing countries have almost all chosen deep geological disposal as preferred method. Here past histories and recent discussions on the variations to geological disposal were studied. (author)

  14. The surface disposal concept for LIL/SL waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    Most low-level and intermediate-level short-lived (LIL/SL) waste result from the nuclear-power industry. Their specific activity level is sufficiently high to justify a protective conditioning and to ensure proper confinement until that level has decreased to harmless levels for human beings and the environment (a few centuries considering the half lives of the radionuclides contained in LIL/SL waste). The disposal concept for such residues relies on a multi-barrier protective system, each barrier being designed to fulfil different or redundant functions in order to delay or mitigate radionuclide transfers first into the environment and onwards to human beings. The originality of the concept pertains to its flexibility, since: it is adaptable to various geological environments and its overall performance may be guaranteed by modulating that of the engineered barriers, and it is suitable for the disposal of different types and sizes of waste packages, as long as their characteristics are consistent with acceptance criteria, which are de facto specific to each case. To provide its wide-ranging competences in the field of waste management and disposal, ANDRA offers multiple solutions, from consultancy and documents reviewing, to technology transfer and turnkey projects. The safety of the disposal facility is guaranteed by the combination of the package, the concrete structures, the filling materials between packages and the watertight clay cap that will be installed at the end of the operating lifetime of the facility. That layout also takes all natural risks into account. Lastly, all disposal structures are built away from any potential flood zones and from the highest possible level of the groundwater table. Concrete and metal packages are disposed of in slightly different structures. Once a structure is full, concrete packages are immobilised with gravel, whereas metal packages are blocked in place by pouring concrete between them. Once a disposal structure is

  15. The surface disposal concept for LIL/SL waste

    International Nuclear Information System (INIS)

    2011-01-01

    Most low-level and intermediate-level short-lived (LIL/SL) waste result from the nuclear-power industry. Their specific activity level is sufficiently high to justify a protective conditioning and to ensure proper confinement until that level has decreased to harmless levels for human beings and the environment (a few centuries considering the half lives of the radionuclides contained in LIL/SL waste). The disposal concept for such residues relies on a multi-barrier protective system, each barrier being designed to fulfil different or redundant functions in order to delay or mitigate radionuclide transfers first into the environment and onwards to human beings. The originality of the concept pertains to its flexibility, since: it is adaptable to various geological environments and its overall performance may be guaranteed by modulating that of the engineered barriers, and it is suitable for the disposal of different types and sizes of waste packages, as long as their characteristics are consistent with acceptance criteria, which are de facto specific to each case. To provide its wide-ranging competences in the field of waste management and disposal, ANDRA offers multiple solutions, from consultancy and documents reviewing, to technology transfer and turnkey projects. The safety of the disposal facility is guaranteed by the combination of the package, the concrete structures, the filling materials between packages and the watertight clay cap that will be installed at the end of the operating lifetime of the facility. That layout also takes all natural risks into account. Lastly, all disposal structures are built away from any potential flood zones and from the highest possible level of the groundwater table. Concrete and metal packages are disposed of in slightly different structures. Once a structure is full, concrete packages are immobilised with gravel, whereas metal packages are blocked in place by pouring concrete between them. Once a disposal structure is

  16. Deep Borehole Disposal Concept: Development of Universal Canister Concept of Operations

    Energy Technology Data Exchange (ETDEWEB)

    Rigali, Mark J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Applied Systems Analysis and Research; Price, Laura L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Applied Systems Analysis and Research

    2016-08-01

    This report documents key elements of the conceptual design for deep borehole disposal of radioactive waste to support the development of a universal canister concept of operations. A universal canister is a canister that is designed to be able to store, transport, and dispose of radioactive waste without the canister having to be reopened to treat or repackage the waste. This report focuses on the conceptual design for disposal of radioactive waste contained in a universal canister in a deep borehole. The general deep borehole disposal concept consists of drilling a borehole into crystalline basement rock to a depth of about 5 km, emplacing WPs in the lower 2 km of the borehole, and sealing and plugging the upper 3 km. Research and development programs for deep borehole disposal have been ongoing for several years in the United States and the United Kingdom; these studies have shown that deep borehole disposal of radioactive waste could be safe, cost effective, and technically feasible. The design concepts described in this report are workable solutions based on expert judgment, and are intended to guide follow-on design activities. Both preclosure and postclosure safety were considered in the development of the reference design concept. The requirements and assumptions that form the basis for the deep borehole disposal concept include WP performance requirements, radiological protection requirements, surface handling and transport requirements, and emplacement requirements. The key features of the reference disposal concept include borehole drilling and construction concepts, WP designs, and waste handling and emplacement concepts. These features are supported by engineering analyses.

  17. New safety concept for geological disposal in Japan - -16339

    International Nuclear Information System (INIS)

    Kitayama, Kazumi

    2009-01-01

    This paper describes a new safety concept for the Japanese geological disposal program, which is a development of the conventional multi-barrier system concept. The Japanese government established the 'Nuclear Waste Management Organization of Japan' (NUMO) as an implementation body in 2000 based on the 'Final disposal act' following the publication of the 'H-12 Report', which confirmed the scientific and engineering feasibility of HLW geological disposal in Japan. Since then, NUMO has undertaken further technical developments aimed at achieving safe and efficient implementation of final disposal. The safety concept developed in the 'H-12 Report' provides sufficient safety on the basis of site-generic considerations. However, it is considered to be over-conservative and therefore does not represent the most probable performance of the engineered or natural barriers. Recently, concrete measures have been proposed requiring the safety case to be presented in terms of a realistic assessment of the most probable performance. This approach takes into account the safety functions of both engineered and natural barriers as well as the long-term static geochemical equilibrium. In particular, the evolution of the safety performance of engineered and natural barriers can be efficiently augmented by the realistic long-term geochemical equilibrium. (author)

  18. Direct ultimate disposal of spent fuel DEAB. Systems analysis. Ultimate disposal concepts. Final report. Main volume

    International Nuclear Information System (INIS)

    Wahl, A.

    1995-10-01

    The results elaborated under the project, systems analysis of mixed radwaste disposal concepts and systems analysis of ultimate disposal concepts, provide a comprehensive description and assessment of a radwaste repository, for heat generating wastes and for wastes with negligible heat generation, and thus represent the knowledge basis for forthcoming planning work for a repository in an abandoned salt mine. A fact to be considered is that temperature field calculations have shown that there is room for further optimization with regard to the mine layout. The following aspects have been analysed: (1) safety of operation; (2) technical feasibility and realisation and licensability of the concepts; (3) operational aspects; (4) varieties of utilization of the salt dome for the intended purpose (boreholes for waste emplacement, emplacement in galleries, multi-horizon systems); (5) long-term structural stability of the mine; (6) economic efficiency; (7) nuclear materials safeguards. (orig./HP) [de

  19. Study on operational safety issues in the Japanese disposal concept

    International Nuclear Information System (INIS)

    Suzuki, Satoru; Kitagawa, Yoshito; Hyodo, Hideaki; Kubota, Shigeru; Iijima, Masayoshi; Tamura, Akio; Ishiguro, Katsuhiko; Fujihara, Hiroshi

    2014-01-01

    In Japan, vitrified high-level radioactive waste (HLW) and certain types of low-level radioactive waste that results from the reprocessing of spent fuel and classified as TRU waste will be disposed of in deep geological formations. NUMO aims to ensure the safety of local residents and workers during the operational phase and after repository closure and will therefore establish a safety case for the geological disposal programme at the end of each stage of the stepwise siting process. Although the Japanese programme is still in the stage before initiation of the siting process, updating the generic (non-site-specific) safety case is required for building confidence among stakeholders. This study focuses on operational safety issues for the Japanese HLW disposal concept. (authors)

  20. KBS-3H - Development of the horizontal disposal concept

    International Nuclear Information System (INIS)

    Thurner, Eric; Pettersson, Stig; Snellman, Margit; Autio, Jorma

    2006-01-01

    SKB and Posiva are performing an R and D programme over the period of 2002-2007 with the overall aim to find out whether the KBS-3H concept can be regarded as an alternative to the KBS-3V concept for disposal of spent nuclear fuel. A feasibility study of the KBS-3H concept was carried out in 2002, followed by the setting up of basic design in 2003, and since 2004 the demonstration phase is ongoing, ending with the evaluation of the potencial of the concept in 2007. In order to find out whether the concept can be regarded as a viable alternative to the KBS-3V concept demonstration and design work involve development of excavation technology of the drift, detailed studies on the function of the buffer bentonite, deposition equipment and methods for construction of low-pH shotcrete plugs. The investigations related to long-term safety are based on difference analyses between KBS-3V and KBS-3H and focus on KBS-3H specific processes. By the end of 2007 the KBS-3H concept will be reported including a preliminary safety case of the concept with Olkiluoto in Finland as a reference site. (author)

  1. Exploring the concept of compressed air energy storage (CAES) in lined rock caverns at shallow depth: A modeling study of air tightness and energy balance

    International Nuclear Information System (INIS)

    Kim, Hyung-Mok; Rutqvist, Jonny; Ryu, Dong-Woo; Choi, Byung-Hee; Sunwoo, Choon; Song, Won-Kyong

    2012-01-01

    Highlights: ► We carried out coupled thermodynamic, multiphase fluid flow and heat transport analysis. ► Coupled behavior associated with underground lined caverns for CAES was investigated. ► Air leakage could be reduced by controlling the permeability of concrete lining. ► Heat loss during compression would be gained back at subsequent decompression phase. -- Abstract: This paper presents a numerical modeling study of coupled thermodynamic, multiphase fluid flow and heat transport associated with underground compressed air energy storage (CAES) in lined rock caverns. Specifically, we explored the concept of using concrete lined caverns at a relatively shallow depth for which constructing and operation costs may be reduced if air tightness and stability can be assured. Our analysis showed that the key parameter to assure long-term air tightness in such a system was the permeability of both the concrete lining and the surrounding rock. The analysis also indicated that a concrete lining with a permeability of less than 1 × 10 −18 m 2 would result in an acceptable air leakage rate of less than 1%, with the operation pressure range between 5 and 8 MPa at a depth of 100 m. It was further noted that capillary retention properties and the initial liquid saturation of the lining were very important. Indeed, air leakage could be effectively prevented when the air-entry pressure of the concrete lining is higher than the operation air pressure and when the lining is kept at relatively high moisture content. Our subsequent energy-balance analysis demonstrated that the energy loss for a daily compression and decompression cycle is governed by the air-pressure loss, as well as heat loss by conduction to the concrete liner and surrounding rock. For a sufficiently tight system, i.e., for a concrete permeability of less than 1 × 10 −18 m 2 , heat loss by heat conduction tends to become proportionally more important. However, the energy loss by heat conduction can be

  2. Exploring the concept of compressed air energy storage (CAES) in lined rock caverns at shallow depth: A modeling study of air tightness and energy balance

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H.-M.; Rutqvist, J.; Ryu, D.-W.; Choi, B.-H.; Sunwoo, C.; Song, W.-K.

    2011-07-15

    This paper presents a numerical modeling study of coupled thermodynamic, multiphase fluid flow and heat transport associated with underground compressed air energy storage (CAES) in lined rock caverns. Specifically, we explored the concept of using concrete lined caverns at a relatively shallow depth for which constructing and operational costs may be reduced if air tightness and stability can be assured. Our analysis showed that the key parameter to assure long-term air tightness in such a system was the permeability of both the concrete lining and the surrounding rock. The analysis also indicated that a concrete lining with a permeability of less than 1×10{sup -18} m{sup 2} would result in an acceptable air leakage rate of less than 1%, with the operational pressure range between 5 and 8 MPa at a depth of 100 m. It was further noted that capillary retention properties and the initial liquid saturation of the lining were very important. Indeed, air leakage could be effectively prevented when the air-entry pressure of the concrete lining is higher than the operational air pressure and when the lining is kept moist at a relatively high liquid saturation. Our subsequent energy-balance analysis demonstrated that the energy loss for a daily compression and decompression cycle is governed by the air-pressure loss, as well as heat loss by conduction to the concrete liner and surrounding rock. For a sufficiently tight system, i.e., for a concrete permeability off less than 1×10{sup -18} m{sup 2}, heat loss by heat conduction tends to become proportionally more important. However, the energy loss by heat conduction can be minimized by keeping the air-injection temperature of compressed air closer to the ambient temperature of the underground storage cavern. In such a case, almost all the heat loss during compression is gained back during subsequent decompression. Finally, our numerical simulation study showed that CAES in shallow rock caverns is feasible from a leakage

  3. Thermohydromechanical stability analysis upon joint characteristics and depth variations in the region of an underground repository for the study of a disposal concept of high level radioactive wastes

    International Nuclear Information System (INIS)

    Kim, Jhin Wung; Bae, Dae Suk; Kang, Chul Hyung; Choi, Jong Won

    2003-02-01

    The objective of the present study is to understand a long term(500 years) thermohydromechanical interaction behavior in the vicinity of a repository cavern upon joint location and repository depth variations, and then, to contribute to the development of a disposal concept. The model includes a saturated rock mass, PWR spent fuels in a disposal canister surrounded by compacted bentonite inside a deposition hole, and mixed bentonite backfilled in the rest of the space within a cavern. It is assumed that two joint sets exist within a model. A joint set 1 includes 56 .deg. dip joints, 20m spaced, and a joint set 2 is in the direction perpendicular to a joint set 1 and includes 34 .deg. dip joints, 20m spaced. In order to understand the behavior change upon joint location variations, 5 different models of 500m depth are analyzed, and additional 3 different models of 1km depth are analyzed to understand the effect of a depth variation. The two dimensional distinct element code, UDEC is used for the analysis. To understand the joint behavior adjacent to a repository cavern, Barton-Bandis joint model is used. Effect of the decay heat for PWR spent fuels on a repository model is analyzed, and a steady state algorithm is used for a hydraulic analysis. According to the thermohydromechanical interaction behavior of a repository model upon variations of joint locations and a repository depth, during the period of 500 years from waste emplacement, the effect of a depth variation on the stress and displacement behavior of a model is comparatively smaller than the effect of decay heat from radioactive materials. From the study of the joint location variation effect, it is advisable not to locate an underground opening in the region very close to the joint crossings

  4. Design concepts of definitive disposal for high level radioactive wastes

    International Nuclear Information System (INIS)

    Badillo A, V.E.; Alonso V, G.

    2007-01-01

    It is excessively known the importance about finding a solution for the handling and disposition of radioactive waste of all level. However, the polemic is centered in the administration of high level radioactive waste and the worn out fuel, forgetting that the more important volumes of waste its are generated in the categories of low level wastes or of very low level. Depending on the waste that will be confined and of the costs, several technological modalities of definitive disposition exist, in function of the depth of the confinement. The concept of deep geologic storage, technological option proposed more than 40 years ago, it is a concept of isolation of waste of long half life placed in a deep underground installation dug in geologic formations that are characterized by their high stability and their low flow of underground water. In the last decades, they have registered countless progresses in technical and scientific aspects of the geologic storage, making it a reliable technical solution supported with many years of scientific work carried out by numerous institutions in the entire world. In this work the design concepts that apply some countries for the high level waste disposal that its liberate heat are revised and the different geologic formations that have been considered for the storage of this type of wastes. (Author)

  5. Execution techniques for high-level radioactive waste disposal. 2. Fundamental concept of geological disposal and implementing approach of disposal project

    International Nuclear Information System (INIS)

    Kawanishi, Motoi; Komada, Hiroya; Tsuchino, Susumu; Shiozaki, Isao; Kitayama, Kazumi; Akasaka, Hidenari; Inagaki, Yusuke; Kawamura, Hideki

    1999-01-01

    The making high activity of the high-level radioactive waste disposal business shall be fully started after establishing of the implementing organization which is planned around 2000. Considering each step of disposal business, in this study, the implementation procedure for a series of disposal business such as the selection of the disposal site, the construction and operation of the disposal facility, the closure and decommissioning of the disposal facility and the management after closure, which are carried forward by the implementation body is discussed in detail from the technical viewpoint and an example of the master schedule is proposed. Furthermore, we investigate and propose the concept of the geological disposal which becomes important in carrying forward to making of the business of the disposal, such as the present site selection smoothly, the fundamental idea of the safe securing for disposal, the basic idea to get trust to the disposal technique and the geological environmental condition which is the basic condition of this whole study for the disposal business making. (author)

  6. Fully Disposable Manufacturing Concepts for Clinical and Commercial Manufacturing and Ballroom Concepts.

    Science.gov (United States)

    Boedeker, Berthold; Goldstein, Adam; Mahajan, Ekta

    2017-11-04

    The availability and use of pre-sterilized disposables has greatly changed the methods used in biopharmaceuticals development and production, particularly from mammalian cell culture. Nowadays, almost all process steps from cell expansion, fermentation, cell removal, and purification to formulation and storage of drug substances can be carried out in disposables, although there are still limitations with single-use technologies, particularly in the areas of pretesting and quality control of disposables, bag and connections standardization and qualification, extractables and leachables (E/L) validation, and dependency on individual vendors. The current status of single-use technologies is summarized for all process unit operations using a standard mAb process as an example. In addition, current pros and cons of using disposables are addressed in a comparative way, including quality control and E/L validation.The continuing progress in developing single-use technologies has an important impact on manufacturing facilities, resulting in much faster, less expensive and simpler plant design, start-up, and operation, because cell culture process steps are no longer performed in hard-piped unit operations. This leads to simpler operations in a lab-like environment. Overall it enriches the current landscape of available facilities from standard hard-piped to hard-piped/disposables hybrid to completely single-use-based production plants using the current segregation and containment concept. At the top, disposables in combination with completely and functionally closed systems facilitate a new, revolutionary design of ballroom facilities without or with much less segregation, which enables us to perform good manufacturing practice manufacturing of different products simultaneously in unclassified but controlled areas.Finally, single-use processing in lab-like shell facilities is a big enabler of transferring and establishing production in emergent countries, and this is

  7. Fracture and Healing of Rock Salt Related to Salt Caverns

    International Nuclear Information System (INIS)

    Chan, K.S.; Fossum, A.F.; Munson, D.E.

    1999-01-01

    In recent years, serious investigations of potential extension of the useful life of older caverns or of the use of abandoned caverns for waste disposal have been of interest to the technical community. All of the potential applications depend upon understanding the reamer in which older caverns and sealing systems can fail. Such an understanding will require a more detailed knowledge of the fracture of salt than has been necessary to date. Fortunately, the knowledge of the fracture and healing of salt has made significant advances in the last decade, and is in a position to yield meaningful insights to older cavern behavior. In particular, micromechanical mechanisms of fracture and the concept of a fracture mechanism map have been essential guides, as has the utilization of continuum damage mechanics. The Multimechanism Deformation Coupled Fracture (MDCF) model, which is summarized extensively in this work was developed specifically to treat both the creep and fracture of salt, and was later extended to incorporate the fracture healing process known to occur in rock salt. Fracture in salt is based on the formation and evolution of microfractures, which may take the form of wing tip cracks, either in the body or the boundary of the grain. This type of crack deforms under shear to produce a strain, and furthermore, the opening of the wing cracks produce volume strain or dilatancy. In the presence of a confining pressure, microcrack formation may be suppressed, as is often the case for triaxial compression tests or natural underground stress situations. However, if the confining pressure is insufficient to suppress fracture, then the fractures will evolve with time to give the characteristic tertiary creep response. Two first order kinetics processes, closure of cracks and healing of cracks, control the healing process. Significantly, volume strain produced by microfractures may lead to changes in the permeability of the salt, which can become a major concern in

  8. The State of the Art of the Borehole Disposal Concept for High Level Radioactive Waste

    International Nuclear Information System (INIS)

    Ji, Sung Hoon; Koh, Yong Kwon; Choi, Jong Won

    2012-01-01

    As an alternative of the high-level radioactive waste disposal in the subsurface repository, a deep borehole disposal is reviewed by several nuclear advanced countries. In this study, the state of the art on the borehole disposal researches was reviewed, and the possibility of borehole disposal in Korean peninsula was discussed. In the deep borehole disposal concept radioactive waste is disposed at the section of 3 - 5 km depth in a deep borehole, and it has known that it has advantages in performance and cost due to the layered structure of deep groundwater and small surface disposal facility. The results show that it is necessary to acquisite data on deep geologic conditions of Korean peninsula, and to research the engineering barrier system, numerical modeling tools and disposal techniques for deep borehole disposal.

  9. Summary of the Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    1994-01-01

    This is the Summary of the Environmental Impact Statement (EIS) prepared by Atomic Energy of Canada Limited (AECL) on the concept for disposal of Canada's nuclear fuel waste. The proposed concept is a method for geological disposal, based on a system of natural and engineered barriers. The EIS provides information requested by the Environmental Assessment Panel reviewing the disposal concept and presents AECL's case for the acceptability of the concept. The introductory chapter of this Summary provides background information on several topics related to nuclear fuel waste, including current storage practices for used fuel, the need for eventual disposal of nuclear fuel waste, the options for disposal, and the reasons for Canada's focus on geological disposal. Chapter 2 describes the concept for disposal of nuclear fuel waste. Because the purpose of implementing the concept would he to protect human health and the natural environment far into the future, we discuss the long-term performance of a disposal system and present a case study of potential effects on human health and the natural environment after the closure of a disposal facility. The effects and social acceptability of disposal would depend greatly on how the concept was implemented. Chapter 3 describes AECL's proposed approach to concept implementation. We discuss how the public would be involved in implementation; activities that would be undertaken to protect human health, the natural environment, and the socio-economic environment; and a case study of the potential effects of disposal before the closure of a disposal facility. The last chapter presents AECL's Conclusion, based on more than 15 years of research and development, that implementation of the disposal concept represents a means by which Canada can safely dispose of its nuclear fuel waste. This chapter also presents AECL's recommendation that Canada progress toward disposal of its nuclear fuel waste by undertaking the first stage of concept

  10. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 1

    International Nuclear Information System (INIS)

    Wuschke, D.M.; Gillespie, P.A.; Main, D.E.

    1985-07-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second assessment was performed in 1984 and is documented in the Second Interim assessment of the Canadian Concept for Nuclear Fuel Waste Disposal Volumes 1 to 4. This volume, entitled Summary, is a condensation of Volumes 2, 3 and 4. It briefly describes the Canadian nuclear fuel waste disposal concept, and the methods and results of the second interim pre-closure and post-closure assessments of that concept. 46 refs

  11. Technical concept for a greater-confinement-disposal test facility

    International Nuclear Information System (INIS)

    Hunter, P.H.

    1982-01-01

    Greater confinement disposal (GCO) has been defined by the National Low-Level Waste Program as the disposal of low-level waste in such a manner as to provide greater containment of radiation, reduce potential for migration or dispersion or radionuclides, and provide greater protection from inadvertent human and biological intrusions in order to protect the public health and safety. This paper discusses: the need for GCD; definition of GCD; advantages and disadvantages of GCD; relative dose impacts of GCD versus shallow land disposal; types of waste compatible with GCD; objectives of GCD borehole demonstration test; engineering and technical issues; and factors affecting performance of the greater confinement disposal facility

  12. Disposing of nuclear waste: an economic analysis of two alternative concepts

    International Nuclear Information System (INIS)

    Dippold, D.G.; Tzemos, S.

    1987-01-01

    WADCOM II is a nuclear waste disposal cost model intended to provide its users with relatively quick, although macro, insight into the economics of hypothetical nuclear waste disposal scenarios. The nuclear waste management system represented by the model, the philosophy underlying the model's design, and the logic of the model itself are described. The model is used to analyze the economics of two nuclear waste disposal concepts, the borehold package concept and the generic package concept. Results indicate the generic package concept leads to the higher costs under all the assumed conditions

  13. Disposal of radwastes and recycling of wastes and structural materials -fundamental principles, concepts, results

    International Nuclear Information System (INIS)

    Schaller, G.; Arens, G.; Brennecke, P.; Goertz, R.; Poschner, J.; Thieme, M.

    1997-01-01

    This report describes the German concept for the disposal of radioactive waste, and the re-use or recycling of contaminated materials. All radioactive waste can be disposed of in deep geological formations (practised at ERAM disposal site, planned for Konrad disposal site). Radioactively contaminated material below clearance levels can proceed for disposal at waste disposal sites and incineration plants, or for re-use and recycling, especially where the material consists of contaminated steel and of buildings. The basic principles (dose limits and model structures for deriving recommendations), reference values, or limits are described. The latest concepts are described in greater detail. Waste management in Germany is compared with international concepts. (orig.) [de

  14. Alternative concepts for Low-Level Radioactive Waste Disposal: Conceptual design report

    International Nuclear Information System (INIS)

    1987-06-01

    This conceptual design report is provided by the Department of Energy's Nuclear Energy Low-Level Waste Management Program to assist states and compact regions in developing new low-level radioactive waste (LLW) disposal facilities in accordance with the Low-Level Radioactive Waste Policy Amendment Act of 1985. The report provides conceptual designs and evaluations of six widely considered concepts for LLW disposal. These are shallow land disposal (SLD), intermediate depth disposal (IDD), below-ground vaults (BGV), above-ground vaults (AGV), modular concrete canister disposal (MCCD), earth-mounded concrete bunker (EMCB). 40 refs., 45 figs., 77 tabs

  15. Research on geological disposal: R and D concept on geological disposal

    International Nuclear Information System (INIS)

    1993-01-01

    The objective on geological disposal of high-level radioactive wastes are to ensure the long term radiological protection of the human and his environment in accordance with current internationally agreed radiation protection principles. The principle of geological disposal is to settle the high-level wastes in deep underground so as to isolate them from the human and his environment considering the existence of groundwater. Japan is currently in the stage of assessing technical feasibility of geological disposal to the extent practicable. In accordance with the AEC (Atomic Energy Commission) policy in 1989, PNC (Power Reactor and Nuclear Fuel Development Corporation) has conducted the research and development on geological disposal in three areas: 1) studies of geological environment, 2) research and development of disposal technology, and 3) performance assessment study. (author)

  16. A design concept of underground facilities for the deep geologic disposal of spent fuel

    International Nuclear Information System (INIS)

    Lee, Jong Youl; Choi, Heui Joo; Choi, Jong Won; Hahn, Pil Soo

    2005-01-01

    Spent nuclear fuel from nuclear power plants can be disposed in the underground repository. In this paper, a concept of Korean Reference HLW disposal System (KRS-1) design is presented. Though no site for the underground repository has been specified in Korea, but a generic site with granitic rock is considered for reference spent fuel repository design. To implement the concept, design requirements such as spent fuel characteristics and capacity of the repository and design principles were established. Then, based on these requirements and principles, a concept of the disposal process, the facilities and the layout of the repository was developed

  17. Retrievability in the Belgian deep disposal concept in clay

    International Nuclear Information System (INIS)

    Preter, P. de

    2000-01-01

    While radioactive waste disposal implies that there is no intention to retrieve the waste, retrievability refers to the potential to retrieve the waste. So, retrievability can be an integrated element of a disposal solution. The different reasons for considering retrievability in the development of a disposal solution are discussed. Amongst them, the precautionary principle takes an important place. The development of a disposal solution should be in the first place safety-driven. The use of robust, high-integrity waste containers or overpacks contributes directly to safety, but also to the enhancement of the retrievability. Indeed, as long as the first barrier is intact, safe waste retrieval is in principle possible. By extending the period of easy access to the waste, i.e. by keeping the repository open during a longer period than needed for waste disposal operations, safety and retrievability goals can become contradictory. Indefinitely postponing the decision to close the repository enhances the risk of unforeseen perturbations of the disposal system and the risk of abandonment. This pleads of course for limiting the duration of the open phase to a reasonable period of time. Otherwise, the advantage of a prolonged open repository, as a means to prolong retrievability of the waste, is cancelled by the increasing risks of a system whose safety relies on societal, political and decisional stability, and not on a robust, passive multi-barrier system. (author)

  18. Pre-feasibility study for final disposal of radioactive waste. Disposal concepts. Main report

    International Nuclear Information System (INIS)

    Andersen, L.; Skov, C.; Kueter, A.; Schepper, L.; Gottberg Roemer, H.; Refsgaard, A.; Utko, M.; Kristiansen, Torben

    2011-05-01

    This prefeasibility study is part of the overall process related to the decision on placement and design of a repository for the Danish low and medium level radioactive waste primarily from the facilities at Risoe. The prefeasibility study encompasses the preliminary design of a number of repository types based on the overall types set out in the 'Parliamentary decision' together with a preliminary safety assessment of these repository types based on their possible placement in a set of typical Danish geologies. The report consists of three parts. Part I is the descriptive part containing information on the waste to be disposed of, the potential conditioning (packaging) possibilities for the waste before placement in a repository, the suggested preliminary design of the different repository types, and the suggested visual appearance of the repository. Part II is the assessment part. It contains an introduction to the concepts used in the preliminary safety assessment, which encompasses: the assessment of potential long term impact and the assessment of possible accidental incidents. The division of the preliminary safety assessment in to these two categories has several reasons. One is that the criteria to which impact is to be compared are different for the two types of impact, another is that while the possible variation in the long term impact is primarily due to the possible variation in the parameters influencing the impact, the impact from accidental incidents is governed by the probability of the occurrence of these incidents and the potential consequence of the impact, which calls for a different assessment approach. Since the suggestions for packaging of the different waste types is a result of both types of assessments, part II also contains a description of these suggestions based on the preliminary safety assessments. Finally part II contains the costs related to the different types of repositories and the suggested packaging. Part III of the report

  19. Pre-feasibility study for final disposal of radioactive waste. Disposal concepts. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Andersen, L.; Skov, C.; Kueter, A.; Schepper, L.; Gottberg Roemer, H.; Refsgaard, A.; Utko, M.; Kristiansen, Torben (COWI A/S, Kgs. Lyngby (Denmark))

    2011-05-15

    This prefeasibility study is part of the overall process related to the decision on placement and design of a repository for the Danish low and medium level radioactive waste primarily from the facilities at Risoe. The prefeasibility study encompasses the preliminary design of a number of repository types based on the overall types set out in the 'Parliamentary decision' together with a preliminary safety assessment of these repository types based on their possible placement in a set of typical Danish geologies. The report consists of three parts. Part I is the descriptive part containing information on the waste to be disposed of, the potential conditioning (packaging) possibilities for the waste before placement in a repository, the suggested preliminary design of the different repository types, and the suggested visual appearance of the repository. Part II is the assessment part. It contains an introduction to the concepts used in the preliminary safety assessment, which encompasses: the assessment of potential long term impact and the assessment of possible accidental incidents. The division of the preliminary safety assessment in to these two categories has several reasons. One is that the criteria to which impact is to be compared are different for the two types of impact, another is that while the possible variation in the long term impact is primarily due to the possible variation in the parameters influencing the impact, the impact from accidental incidents is governed by the probability of the occurrence of these incidents and the potential consequence of the impact, which calls for a different assessment approach. Since the suggestions for packaging of the different waste types is a result of both types of assessments, part II also contains a description of these suggestions based on the preliminary safety assessments. Finally part II contains the costs related to the different types of repositories and the suggested packaging. Part III of the

  20. Vault submodel for the second interim assessment of the Canadian concept for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    LeNeveu, D.M.

    1986-02-01

    The consequences to man and the environment of the disposal of nuclear fuel waste are being studied within the Canadian Nuclear Fuel Waste Management Program. The concept being assessed is that of a sealed disposal vault at a depth of 1000 m in plutonic rock in the Canadian Shield. To determine the consequences, the vault and its environment are simulated using a SYstem Variability Analysis Code (SYVAC), a stochastic model of the disposal system. SYVAC contains three submodels that represent the three major parts of the disposal system: the vault, the geosphere and the biosphere. This report documents the conceptual and mathematical framework of the vault submodel

  1. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 2

    International Nuclear Information System (INIS)

    Gillespie, P.A.; Wuschke, D.M.; Guvanasen, V.M.; Mehta, K.K.; McConnell, D.B.; Tamm, J.A.; Lyon, R.B.

    1985-12-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the burial of corrosion-resistant containers of waste in a vault located deep in plutonic rock in the Canadian Shield. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluatin of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have if the concept were implemented. The second assessment was performed in 1984 and is documented in Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1 to 4. This volume, entitled Background, discusses Canadian nuclear fuel wastes and the desirable features of a waste disposal method. It outlines several disposal options being considered by a number of countries, including the option chosen for development and assessment in Canada. The reference disposal systems assumed for the second assessment are described, and the approach used for concept assessment is discussed briefly. 79 refs

  2. Development of a tunnel backfilling concept for nuclear waste disposal

    International Nuclear Information System (INIS)

    Gunnarsson, D.; Borgesson, L.

    2003-01-01

    In the main concept for disposal of the Swedish Nuclear Waste (KBS-3V) it is vital that the drifts can be backfilled with sufficiently good material at high density to fulfill the following requirements: - to obstruct upwards swelling of bentonite from the deposition holes, - to prevent or restrict the water flow in the tunnel and around the canister, - to resist chemical conversion for a long period of time, - not to cause any significant chemical conversion of the buffer surrounding the canister. Investigations and tests of backfill material and techniques have been running in the Swedish underground laboratory, Aspo HRL, since 1996. In the first test, Field Test of Tunnel Backfilling, the objectives were to test the manufacturing of backfill material, to develop and test a backfilling technique and to investigate what densities could be achieved with different backfill materials in the field. Horizontal layers were applied and compacted by a roller in 0.2 m thick layers to 1.5 m from the floor. The rest of the tunnel was backfilled with inclined layers. Five different backfill materials were tested; TBM-muck, TBM-muck crushed to a maximum grain size of 20 mm and crushed TBM-muck mixed with 10, 20 and 30% MX-80 bentonite. The main conclusions from these tests were that the technique for manufacturing backfill material and for backfilling the tunnel were suitable but that the horizontal backfill layers were sensitive to wet conditions, that the backfilling equipment needed to be improved to better reach the areas close to the rock walls and roof and that the durability of the equipment needed to be improved. For the continued development for the Backfill and Plug Test and the Prototype Repository it was decided that the backfilling should be made with inclined layers in the entire cross section of the tunnel in order to decrease the sensitivity to water inflow. The backfilling equipment was improved; two new compactors, the so-called slope compactor and the so

  3. Development of a tunnel backfilling concept for nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Gunnarsson, D.; Borgesson, L. [Clay Technology AB, Ideon, Lund (Sweden)

    2003-07-01

    In the main concept for disposal of the Swedish Nuclear Waste (KBS-3V) it is vital that the drifts can be backfilled with sufficiently good material at high density to fulfill the following requirements: - to obstruct upwards swelling of bentonite from the deposition holes, - to prevent or restrict the water flow in the tunnel and around the canister, - to resist chemical conversion for a long period of time, - not to cause any significant chemical conversion of the buffer surrounding the canister. Investigations and tests of backfill material and techniques have been running in the Swedish underground laboratory, Aspo HRL, since 1996. In the first test, Field Test of Tunnel Backfilling, the objectives were to test the manufacturing of backfill material, to develop and test a backfilling technique and to investigate what densities could be achieved with different backfill materials in the field. Horizontal layers were applied and compacted by a roller in 0.2 m thick layers to 1.5 m from the floor. The rest of the tunnel was backfilled with inclined layers. Five different backfill materials were tested; TBM-muck, TBM-muck crushed to a maximum grain size of 20 mm and crushed TBM-muck mixed with 10, 20 and 30% MX-80 bentonite. The main conclusions from these tests were that the technique for manufacturing backfill material and for backfilling the tunnel were suitable but that the horizontal backfill layers were sensitive to wet conditions, that the backfilling equipment needed to be improved to better reach the areas close to the rock walls and roof and that the durability of the equipment needed to be improved. For the continued development for the Backfill and Plug Test and the Prototype Repository it was decided that the backfilling should be made with inclined layers in the entire cross section of the tunnel in order to decrease the sensitivity to water inflow. The backfilling equipment was improved; two new compactors, the so-called slope compactor and the so

  4. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 3

    International Nuclear Information System (INIS)

    Johansen, K.; Donnelly, K.J.; Gee, J.H.; Green, B.J.; Nathwani, J.S.; Quinn, A.M.; Rogers, B.G.; Stevenson, M.A.; Dunford, W.E.; Tamm, J.A.

    1985-12-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second such assessment was completed in 1984 and is documented in the Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1-4. This, the third volume of the report, summarizes the pre-closure environmental and safety assessments completed by Ontario Hydro for Atomic Energy of Canada Limited. The preliminary results and their sigificance are discussed. 85 refs

  5. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 4

    International Nuclear Information System (INIS)

    Wuschke, D.M.; Gillespie, P.A.; Mehta, K.K.; Henrich, W.F.; LeNeveu, D.M.; Guvanasen, V.M.; Sherman, G.R.; Donahue, D.C.; Goodwin, B.W.; Andres, T.H.

    1985-12-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second such assessment was performed in 1984 and is documented in the Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1-4. This volume, entitled Post-Closure Assessment, describes the methods, models and data used to perform the second post-closure assessment. The results are presented and their significance is discussed. Conclusions and planned improvements are listed. 72 refs

  6. Human health considerations in the assessment of Canadian concept for the disposal of nuclear fuel wastes

    International Nuclear Information System (INIS)

    Baweja, A.S.; Tracy, B.L.; Ahier, B.; Bartlett, S.

    1996-01-01

    In 1978, AECL was mandated by the government of Ontario and the federal government to find a permanent disposal solution for spent nuclear fuels. Canada opted for disposal in plutonic rocks of the Canadian shield. The Canadian concept calls for disposal in crystalline rocks at a depth of 500 to 1000 m below the surface. The spent fuel would be contained in a canister, the canister would be emplaced in a vault containing clay-based buffer materials, and the cavity would be backfilled and sealed with natural materials. A Federal Environmental Assessment Review Panel was formed in 1992 to assess the concept for disposal of the spent fuel. In this paper a brief discussion of the human health impacts of the proposed concept is presented. Our assessment is based on the information provided by AECL, namely, the main EIS document, a summary and nine other supporting documents

  7. Phased reversibility under the current French disposal concept

    International Nuclear Information System (INIS)

    Hoorelbeke, J.-M.

    2000-01-01

    The French law of 30 December 1991 and the implementing decrees provide for taking into account the reversibility in the study of geological disposal. This takes place within the framework of a 15 year research program. The research in this field implies both the assessment of technological possibilities for retrieving waste packages safely from the repository and the assessment of the consequence of delaying the closure of the repositories on the long term safety. This research program aims at proposing to the decision makers, by the year 2006, an open range of relevant options with regards to reversibility. (author)

  8. Performance Assessment Modeling and Sensitivity Analyses of Generic Disposal System Concepts.

    Energy Technology Data Exchange (ETDEWEB)

    Sevougian, S. David; Freeze, Geoffrey A.; Gardner, William Payton; Hammond, Glenn Edward; Mariner, Paul

    2014-09-01

    directly, rather than through simplified abstractions. It also a llows for complex representations of the source term, e.g., the explicit representation of many individual waste packages (i.e., meter - scale detail of an entire waste emplacement drift). This report fulfills the Generic Disposal System Analysis Work Packa ge Level 3 Milestone - Performance Assessment Modeling and Sensitivity Analyses of Generic Disposal System Concepts (M 3 FT - 1 4 SN08080 3 2 ).

  9. Concept and programme open-quotes Radioactive waste disposal in geological formations of Ukraineclose quotes

    International Nuclear Information System (INIS)

    Khrushchov, D.P.; Umanets, M.P.; Yakovlev, Eu.A.

    1994-01-01

    The concept and the programme open-quotes Radioactive waste disposal in geological formations of Ukraineclose quotes have been compiled. On the base of specialized criterions the evaluation of the territory of Ukraine was carried out, three geological regions and three types of geological formations favourable for RAW disposal have been selected. The programme of R ampersand D investigations includes three stages: preparatory (1993-1995), preparatory - experimental (1995-2004) and preparation of construction (2005-2010)

  10. Comparing technical concepts for disposal of Belgian vitrified HLW

    International Nuclear Information System (INIS)

    Bel, J.; Bock, C. de; Boyazis, J.P.

    2004-01-01

    The choice of a suitable repository design for different categories of radioactive waste is an important element in the decisional process that will eventually lead to the waste disposal in geological ground layers during the next decades. Most countries are in the process of elaborating different technical solutions for their EBS '. Considering possible design alternatives offers more flexibility to cope with remaining uncertainties and allows optimizing some elements of the EBS in the future. However, it is not feasible to continue carrying out detailed studies for a large number of alternative design options. At different stages in the decisional process, choices, even preliminary ones, have to be made. Although the impact of different stakeholders (regulator, waste agencies, waste producers, research centers,...) in making these design choices can differ from one country to another, the choices should be based on sound, objective, clear and unambiguous justification grounds. Moreover, the arguments should be carefully reported and easy to understand by the decision makers. ONDRAF/NIRAS recently elaborated three alternative designs for the disposal of vitrified HLW. These three designs are briefly described in the next section. A first series of technological studies pointed out that the three options are feasible. It would however be unreasonable to continue R and D work on all three alternatives in parallel. It is therefore planned to make a preliminary choice of a reference design for the vitrified HLW in 2003. This selection will depend on the way the alternative design options can be evaluated against a number of criteria, mainly derived from general repository design requirements. The technique of multi-criteria analysis (MCA) will be applied as a tool for making the optimum selection, considering all selection criteria and considering different strategic approaches. This paper describes the used methodology. The decision on the actual selection will be

  11. Pulp fiction - The volunteer concept (or how not to site additional LLRW disposal capacity)

    International Nuclear Information System (INIS)

    Burton, D.A.

    1995-01-01

    Experiences of compacts and of individual states throughout the nation indicate that low-level radioactive waste disposal siting processes, based from the beginning upon the volunteer concept are fraught with problems. Most apparent among these problems is that the volunteer concept does not lead to scientifically and technically based siting endeavors. Ten years have passed since the Amendments Act of 1985, and no compact or state has been - successful in providing for new LLRW disposal capacity. That failure can be traced in part to the reliance upon the volunteer concept in siting attempts. If success is to be achieved, the future direction for LLRW management must focus on three areas: first, a comprehensive evaluation of all LLRW management options, including reduction of waste generated and on-site storage; secondly, a comprehensive evaluation of the current as well as projected waste stream, to determine the amount of disposal capacity actually needed; and, finally, sound scientifically and technically based siting processes

  12. Microbial issues pertaining to the Canadian concept for the disposal of nuclear fuel waste

    International Nuclear Information System (INIS)

    Stroes-Gascoyne, S.; West, J.M.

    1994-03-01

    AECL Research is developing a concept for the permanent disposal of nuclear fuel waste in plutonic rock of the Canadian Shield. The Federal Environmental Assessment Review Panel has issued a set of guidelines to be used by AECL Research in preparing an Environmental Impact Statement (EIS) for this concept. These guidelines require that the EIS address a number of microbiological factors and their potential to affect the integrity of the multiple barrier system on which the disposal concept is based. This report formulates a number of views and positions on microbiological factors that could influence the performance of a disposal vault in plutonic rock. Microbiological factors discussed include the presence and survival of microbes, biofilms, corrosion, biodegradation (of emplaced materials), gas production, geochemical changes, radionuclides migration, colloid formation, mutation, pathogens and methylation. Not all issues can be fully resolved with the current state of knowledge. Studies being performed to underscore and strengthen current knowledge are briefly discussed. (author). 92 refs., 1 tab

  13. Pulp fiction - The volunteer concept (or how not to site additional LLRW disposal capacity)

    Energy Technology Data Exchange (ETDEWEB)

    Burton, D.A. [Heartland Operation to Protect the Environment, Inc., Auburn, NE (United States)

    1995-12-31

    Experiences of compacts and of individual states throughout the nation indicate that low-level radioactive waste disposal siting processes, based from the beginning upon the volunteer concept are fraught with problems. Most apparent among these problems is that the volunteer concept does not lead to scientifically and technically based siting endeavors. Ten years have passed since the Amendments Act of 1985, and no compact or state has been - successful in providing for new LLRW disposal capacity. That failure can be traced in part to the reliance upon the volunteer concept in siting attempts. If success is to be achieved, the future direction for LLRW management must focus on three areas: first, a comprehensive evaluation of all LLRW management options, including reduction of waste generated and on-site storage; secondly, a comprehensive evaluation of the current as well as projected waste stream, to determine the amount of disposal capacity actually needed; and, finally, sound scientifically and technically based siting processes.

  14. Criteria and technical concept for demonstrating greater confinement disposal of radioactive wastes at Arid Western Sites

    International Nuclear Information System (INIS)

    Hunter, P.H.

    1981-01-01

    This report summarizes the work of two documents; the Criteria for Greater Confinement of Radioactive Wastes at Arid Western Sites, NVO-234, March 1981, (within this report, referred to as the GCDF Criteria Document); and the Draft Technical Concept for a Test of Greater Confinement Disposal of Radioactive Waste in Unsaturated Media at the Nevada Test Site, FBDU-343-004, June 1981, (referred within this report as the Technical Concept for the GCDF). For the past two years, Ford, Bacon and Davis has been performing technical services for the Department of Energy at the Nevada Test Site in development of defense low-level waste management concepts, including the greater confinement disposal concept with particular application to arid sites. The investigations have included the development of Criteria for Greater Confinement Disposal, NVO-234, which we published in May of this year; then the draft for the technical concept for greater confinement disposal, published in June; leading up to the point where we are now. The final technical concept and design specifications should be published imminently. The document is prerequisite to the actual construction and implementation of the demonstration facility this fiscal year

  15. AECL's concept for the disposal of nuclear fuel waste and the importance of its implementation

    International Nuclear Information System (INIS)

    Allan, C.J.

    1993-07-01

    Since 1978, Canada has been investigating a concept for permanently dealing with the nuclear fuel waste from Canadian CANDU (Canada Deuterium Uranium) nuclear generating stations. The concept is based on disposing of the waste in a vault excavated 500 to 1000 m deep in intrusive igneous rock of the Canadian Shield. AECL Research will soon be submitting an environmental impact statement (EIS) on the concept for review by a Panel through the federal environmental assessment and review process (EARP). In accordance with AECL Research's mandate and in keeping with the detailed requirements of the review Panel, AECL Research has conducted extensive studies on a wide variety of technical and socio-economic issues associated with the concept. If the concept is accepted, we can and should continue our responsible approach and take the next steps towards constructing a disposal facility for Canada's used nuclear fuel waste

  16. Considerations in managing the assessment of the Canadian nuclear fuel waste disposal concept

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Gillespie, P.A.; Whitaker, S.H.

    1992-01-01

    This paper reports that in developing a concept for disposal of Canada's nuclear fuel waste, AECL has faced challenges because the acceptability of the concept must be established before a site is selected, no agency has been made responsible for implementing the concept if it is selected, and many stakeholders in the review must be satisfied if the concept is to be accepted. The challenges have thus far been met by a program that is well-integrated technically and administratively. However, interactions with stakeholders reviewing the concept present a problem in communication. The authors believe the nature of the nuclear fuel waste disposal issue calls for a cooperative rather than an adversarial approach to problem solving to efficiently deal with the requirements of all the stakeholders

  17. Canada's high-level nuclear waste disposal concept and its evaluation process

    International Nuclear Information System (INIS)

    Sheng, Grant; Shemilt, L.W.

    2004-01-01

    The concept of disposing high-level nuclear waste in granitic rocks in the Canadian Shield, developed by Atomic Energy of Canada Limited (AECL), is anticipated to undergo a national public review within two years. The disposal concept, its documentation, and its process of evaluation, including the role of the public, government and the scientific/engineering community, are summarized. A Technical Advisory Committee (TAC) has provided external peer review of the Program since 1979 and its findings are published in annual reports which are publicly available. (author)

  18. Scenario analysis for the postclosure assessment of the Canadian concept for nuclear fuel waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Goodwin, B W; Stephens, M E; Davison, C C; Johnson, L H; Zach, R

    1994-12-01

    AECL Research has developed and evaluated a concept for disposal of Canada`s nuclear fuel waste involving deep underground disposal of the waste in intrusive igneous rock of the Canadian Shield. The postclosure assessment of this concept focusses on the effects on human health and the environment due to potential contaminant releases into the biosphere after the disposal vault is closed. Both radiotoxic and chemically toxic contaminants are considered. One of the steps in the postclosure assessment process is scenario analysis. Scenario analysis identifies factors that could affect the performance of the disposal system and groups these factors into scenarios that require detailed quantitative evaluation. This report documents a systematic procedure for scenario analysis that was developed for the postclosure assessment and then applied to the study of a hypothetical disposal system. The application leads to a comprehensive list of factors and a set of scenarios that require further quantitative study. The application also identifies a number of other factors and potential scenarios that would not contribute significantly to environmental and safety impacts for the hypothetical disposal system. (author). 46 refs., 3 tabs., 3 figs., 2 appendices.

  19. Scenario analysis for the postclosure assessment of the Canadian concept for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Goodwin, B.W.; Stephens, M.E.; Davison, C.C.; Johnson, L.H.; Zach, R.

    1994-12-01

    AECL Research has developed and evaluated a concept for disposal of Canada's nuclear fuel waste involving deep underground disposal of the waste in intrusive igneous rock of the Canadian Shield. The postclosure assessment of this concept focusses on the effects on human health and the environment due to potential contaminant releases into the biosphere after the disposal vault is closed. Both radiotoxic and chemically toxic contaminants are considered. One of the steps in the postclosure assessment process is scenario analysis. Scenario analysis identifies factors that could affect the performance of the disposal system and groups these factors into scenarios that require detailed quantitative evaluation. This report documents a systematic procedure for scenario analysis that was developed for the postclosure assessment and then applied to the study of a hypothetical disposal system. The application leads to a comprehensive list of factors and a set of scenarios that require further quantitative study. The application also identifies a number of other factors and potential scenarios that would not contribute significantly to environmental and safety impacts for the hypothetical disposal system. (author). 46 refs., 3 tabs., 3 figs., 2 appendices

  20. Assessing the performance of the Nagra HLW disposal concept

    International Nuclear Information System (INIS)

    Smith, P.; Zuidema, P.; McKinley, I.G.

    1995-01-01

    This article outlines the procedures used in safety assessment and illustrates their application in evaluating the performance of a high-level waste repository. Nagra's general safety assessment methodology has five main components: formulating the aims of the analysis, defining the safety concept, scenario development, consequence analysis and interpretation of results. A safety analysis based on conservative assumptions shows that the engineered barriers of the high-level waste repository are very effective in preventing release of radionuclides; this alone is sufficient to ensure that regulatory requirements can be met. The function of the host rock is to provide a favourable environment for the engineered barrier system. (author) 8 figs

  1. CMS cavern inspection robot

    CERN Document Server

    Ibrahim, Ibrahim

    2017-01-01

    Robots which are immune to the CMS cavern environment, wirelessly controlled: -One actuated by smart materials (Ionic Polymer-Metal Composites and Macro Fiber Composites) -One regular brushed DC rover -One servo-driven rover -Stair-climbing robot

  2. Intracranial cavernous angioma

    International Nuclear Information System (INIS)

    Yuhi, Fumiaki; Gondou, Masazumi; Sasahira, Masahiro; Ichitsubo, Hidenori; Asakura, Tetsuhiko.

    1986-01-01

    The present authors have experienced 2 cases of intracranial cavernous angioma. Of these cases, one was admitted because of generalized convulsions, while the other was admitted because of headache. In both cases, neither plain X-ray films nor carotid angiography showed any abnormality, but computerized tomography (CT) revealed a slightly high-density area which was not enhanced with contrast media. Histologically, the tumors had many vascular cavities with walls lined with a single layer of endothelial cells and had no neural tissue between the vascular cavities; therefore, they were diagnosed as cases of cavernous angioma. The authors discussed the radiological findings of the intracranial cavernous angioma with a review of the literature and stressed the role of computerized tomography in the diagnosis of cavernous angioma. (author)

  3. Liabilities for the decommissioning and disposal in the nuclear area. Analysis and concept of reformation

    International Nuclear Information System (INIS)

    Meyer, Bettina

    2012-01-01

    The contribution under consideration examines the adequacy of the reserves for decommissioning / dismantling and disposal in order to finance long-term tasks. A reform concept is presented. The two key components of the reformation are the establishment of a public fund for the long-term obligations and a stronger insolvency protection of medium-term nuclear liabilities.

  4. A new shape design method of salt cavern used as underground gas storage

    International Nuclear Information System (INIS)

    Wang, Tongtao; Yan, Xiangzhen; Yang, Henglin; Yang, Xiujuan; Jiang, Tingting; Zhao, Shuai

    2013-01-01

    Graphical abstract: Safety factor contours of four salt cavern gas storages after running 10 years. Highlights: ► We propose a new model to design the shape of salt cavern gas storage. ► The concepts of slope instability and pressure arch are introduced into the shape design. ► The max. gas pressure determines the shapes and dimensions of cavern lower structure. ► The min. gas pressure decides the shapes and dimensions of cavern upper structure. - Abstract: A new model used to design the shape and dimension of salt cavern gas storage is proposed in the paper. In the new model, the cavern is divided into two parts, namely the lower and upper structures, to design. The concepts of slope instability and pressure arch are introduced into the shape design of the lower and upper structures respectively. Calculating models are established according to the concepts. Field salt cavern gas storage in China is simulated as examples, and its shape and dimension are proposed. The effects of gas pressure, friction angle and cohesion of rock salt on the cavern stability are discussed. Moreover, the volume convergence, displacement, plastic volume rate, safety factor, and effective strain are compared with that of three other existing shapes salt caverns to validate the performance of newly proposed cavern. The results show that the max. gas pressure determines the shape and dimension of cavern lower structure, while the min. gas pressure decides that of cavern upper structure. With the increase of friction angle and cohesion of rock salt, the stability of salt cavern is increased. The newly proposed salt cavern gas storage has more notable advantages than the existing shapes of salt cavern in volume convergence, displacement, plastic volume rate, safety factor, and effective strain under the same conditions

  5. Basic concept on safety regulation for land disposal of low level radioactive solid wastes

    International Nuclear Information System (INIS)

    1985-01-01

    As to the land disposal of low level radioactive solid wastes, to which the countermeasures have become the urgent problem at present, it is considered to be a realistic method to finally store the solid wastes concentratedly outside the sites of nuclear power stations and others, and effort has been exerted by those concerned to realize it. Besides, as for extremely low level radioactive solid wastes, the measures of disposing them corresponding to the radioactivity level are necessary, and the concrete method has been examined. The Committee on Safety Regulation for Radioactive Wastes has discussed the safety regulation for those since April, 1984, and the basic concept on the safety regulation was worked up. It is expected that the safety of the land disposal of low level radioactive solid wastes can be ensured when the safety regulation is carried out in conformity with this basic concept. The present status of the countermeasures to the land disposal of low level radioactive solid wastes is shown. As the concrete method, the disposal in shallow strate has been generally adopted. At present, the plan for the final storage in Aomori Prefecture is considered, and it will be started with the first stage of four-stage control. (Kako, I.)

  6. German concept and status of the disposal of spent fuel elements from German research reactors

    International Nuclear Information System (INIS)

    Komorowski, K.; Storch, S.; Thamm, G.

    1995-01-01

    Eight research reactors with a power ≥ 100 kW are currently being operated in the Federal Republic of Germany. These comprise three TRIGA-type reactors (power 100 kW to 250 kW), four swimming-pool reactors (power 1 MW to 10 MW) and one DIDO type reactor (power 23 MW). The German research reactors are used for neutron scattering for basic research in the field of solid state research, neutron metrology, for the fabrication of isotopes and for neutron activation analysis for medicine and biology, for investigating the influence of radiation on materials and for nuclear fuel behavior. It will be vital to continue current investigations in the future. Further operation of the German research reactors is therefore indispensable. Safe, regular disposal of the irradiated fuel elements arising now and in future operation is of primary importance. Furthermore, there are several plants with considerable quantities of spent fuel, the safe disposal of which is a matter of urgency. These include above all the VKTA facilities in Rossendorf and also the TRIGA reactors, where disposal will only be necessary upon decommissioning. The present paper report is concerned with the disposal of fuel from the German research reactors. It briefly deals with the situation in the USA since the end of 1988, describes interim solutions for current disposal requirements and then mainly concentrates on the German disposal concept currently being prepared. This concept initially envisages the long-term (25--50 years) dry interim storage of fuel elements in special containers in a central German interim store with subsequent direct final disposal without reprocessing of the irradiated fuel

  7. A new safety concept for geological disposal in Japan (II) - 59357

    International Nuclear Information System (INIS)

    Kitayama, Kazumi

    2012-01-01

    This paper provides further discussion of a new defence-in-depth safety concept that was presented at ICEM09[1]. The basic idea is that it is rational to assume that the performance of passive engineered barriers with suitably chosen characteristics and the natural barrier will maintain their safety functions for a sufficiently long time due to geochemical buffering occurring deep underground, The approach can be used to enhance and embed public understanding of the long-term safety of geological disposal. This paper summarizes the logic of the approach focusing on the following topics, which are the basic themes of the new safety concept. 1. Applicability of the defence-in-depth concept to the geological disposal of radioactive waste; 2. Natural Analogue approach to explaining the long-term behaviour of the barriers; and 3. Approach for the Social Dialogue with stakeholder, which is the most important issue for site selection. (authors)

  8. Natural analogs in support of the Canadian concept for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Cramer, Jan.

    1994-08-01

    The assessment of the long-term safety and performance of the Canadian concept for disposal of nuclear fuel waste is a unique and challenging undertaking, because the predictions have to be made for time periods in the range of 10 4 to 10 6 a into the future. The data used for the assessment modelling is in large part based on observations from short-term laboratory and field experiments. Natural analogs can provide a reference for the safety assessment, providing both useful data and a qualitative illustration of the interaction of processes and materials in complex natural systems. This report reviews the available natural analog information used in support of the Canadian concept, with particular emphasis on the disposal of used CANDU (CANada Deuterium Uranium) fuel. The introduction gives a definition of natural analogs and an overview of the various types of analogs and analog studies. The review is broken down into sections pertaining to the major components of the disposal system: the vault, the geosphere and the biosphere. Specific examples are given for each. In addition, a section deals with several comprehensive natural systems that contain a number of features and processes similar to the disposal concept and that are under study by a number of countries as part of their waste management programs. (author). 224 refs., 11 tabs., 2 figs

  9. Natural analogs in support of the Canadian concept for nuclear fuel waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Cramer, Jan

    1994-08-01

    The assessment of the long-term safety and performance of the Canadian concept for disposal of nuclear fuel waste is a unique and challenging undertaking, because the predictions have to be made for time periods in the range of 10{sup 4} to 10{sup 6} a into the future. The data used for the assessment modelling is in large part based on observations from short-term laboratory and field experiments. Natural analogs can provide a reference for the safety assessment, providing both useful data and a qualitative illustration of the interaction of processes and materials in complex natural systems. This report reviews the available natural analog information used in support of the Canadian concept, with particular emphasis on the disposal of used CANDU (CANada Deuterium Uranium) fuel. The introduction gives a definition of natural analogs and an overview of the various types of analogs and analog studies. The review is broken down into sections pertaining to the major components of the disposal system: the vault, the geosphere and the biosphere. Specific examples are given for each. In addition, a section deals with several comprehensive natural systems that contain a number of features and processes similar to the disposal concept and that are under study by a number of countries as part of their waste management programs. (author). 224 refs., 11 tabs., 2 figs.

  10. Concept and Planning of Site Preparation for Radioactive Waste Disposal in Jawa and Surrounding Area

    International Nuclear Information System (INIS)

    Heru Sriwahyuni; Sastrowardoyo, Pratomo B.; Teddy Sumantri; Dewi Susilowati; Hendra Adhi Pratama; Syarmufni, A.

    2008-01-01

    Concept and planning for radioactive waste disposal in Jawa and surrounding area have been done. These activities were part of the investigation for preparation of repository location in Jawa. In this report, the summary of previous sitting activities, the waste inventory in Radioactive Waste Technology Centre, and list of important factors for sitting on radioactive waste disposal location. Several potential areas such as Karawang, Subang, Majalengka, Rembang, Tuban, Madura will be the focus for next activities. The result will be part of activities report regarding the preparation of repository location in Jawa and surrounding area, that will be used as recommendation prior to radioactive waste management policy. (author)

  11. Cerebral Cavernous Malformation and Hemorrhage

    Science.gov (United States)

    ... Text Size: SMALL • LARGE Cerebral Cavernous Angioma and Hemorrhage By Jack Hoch; Reviewed by Dr. Issam Awad ... for years, the mechanism by which these lesions hemorrhage remains poorly understood. Hemorrhage Types Since cavernous angiomas ...

  12. The nuclear waste containment and some aspects of the deep disposal concept

    International Nuclear Information System (INIS)

    Felix, B.; Thorner, P.; Raimbault, P.; Beaulieu, F.

    1995-01-01

    The French agency for the management of nuclear waste, ANDRA, is in charge of investigating the feasibility of deep disposal of high level waste in at least two types of geologic formation, leading to the validation of disposal concepts with and without retrievability. Plans to build two underground laboratories are afoot. Meanwhile, parametric modelling studies have been performed, with interesting results, some of which are shown here in graphic form. It is proved that if the overpack surrounding waste containers can be made to last for a thousand years, the dose resulting from Sr-90 and Cs-137 is nil. Conversely, the dose from actinides such as americium and Th-229 is largely unaffected by the package, being determined by their own low solubilities and underground water flow. Temperature rise in a granite host formation was modelled as a function of the distance between disposal boreholes. Finite element two dimensional calculations of water flow through backfill were also performed. 1 ref., 8 figs

  13. Study of mined storage caverns

    International Nuclear Information System (INIS)

    1975-06-01

    All available information concerning 75 mined storage caverns as well as the investigative techniques utilized to determine the feasibility of a cavern site is presented. Potential new storage caverns may be for products such as high or low vapor pressure petroleum products, other chemical products, aid industrial or nuclear waste

  14. Nuclear fuel waste management and disposal concept: Report. Federal environmental assessment review process

    International Nuclear Information System (INIS)

    1998-01-01

    The Canadian concept for disposing CANDU reactor waste or high-level nuclear wastes from reprocessing involves underground disposal in sealed containers emplaced in buffer-filled and sealed vaults 500--1,000 meters below ground, in plutonic rock of the Canadian Shield. This document presents the report of a panel whose mandate was to review this concept (rather than a specific disposal project at a specific site) along with a broad range of related policy issues, and to conduct that review in five provinces (including reviews with First Nations groups). It first outlines the review process and then describes the nature of the problem of nuclear waste management. It then presents an overview of the concept being reviewed, its implementation stages, performance assessment analyses performed on the concept, and implications of a facility based on that concept (health, environmental, social, transportation, economic). The fourth section examines the criteria by which the safety and acceptability of the concept should be evaluated. This is followed by a safety and acceptability evaluation from both technical and social perspectives. Section six proposes future steps for building and determining acceptability of the concept, including an Aboriginal participation process, creation of a Nuclear Fuel Waste Management Agency, and a public participation process. The final section discusses some issues outside the panel's mandate, such as energy policy and renewable energy sources. Appendices include a chronology of panel activities, a review of radiation hazards, comparison between nuclear waste management and the management of other wastes, a review of other countries' approaches to long-term management of nuclear fuel wastes, and details of a siting process proposed by the panel

  15. Surveying the ATLAS cavern

    CERN Multimedia

    Laurent Guiraud

    2000-01-01

    The cathedral-like cavern into which the ATLAS experiment will be lowered and installed forms a vital part of the engineering work at CERN in preparation for the new LHC accelerator. This cavern, being measured by surveyors in these images, will have one of the largest spans of any man-made underground structure. The massive 46X25X25 cubic metre detector will be the largest of its type in the world when it is completed for the LHC start-up in 2008.

  16. Examination on rational disposal concept, layout, and methods of molding and settling for high level radioactive waste

    International Nuclear Information System (INIS)

    Toyota, Masatoshi

    1998-01-01

    As for the concept of disposing high level radioactive waste in the place of disposal, the method of securing safety by isolating the waste from human environment with the combination of artificial barriers and natural barriers has been adopted. At present in Japan, Power Reactor and Nuclear Fuel Development Corporation has considered the concept of disposal, but it is considered to be necessary to review it from the viewpoints of the uncertainty in safety characteristics, the possibility of realizing construction and settlement, economical efficiency and others. Recently, the investigation of the rational disposal concept has been advanced jointly with Dr. McKinley. The conditions to be considered for artificial barriers at the time of reviewing the disposal concept are described on bentonite buffer and carbon steel overpack enclosing glass-solidified body. As the disposal concept, the private plan of Toyota and that of Toyota and McKinley are shown. Also the layout for settling two modules each in horizontal adits on both sides of the connecting tunnel is proposed. The methods of molding and settling the engineered barrier system are explained. This disposal concept can reduce uncertainty, heighten safety and reduce the cost. (K.I.)

  17. Pilot abandonment test of a very deep gas storage salt cavern

    International Nuclear Information System (INIS)

    Durup, J.G.; Vidal, F.; Rolin, C.

    2007-01-01

    As a result of knowledge gained initially from a series of succinct sealed well and cavern field tests performed in the late 1980's and early 1990's by Gaz de France (EZ58; EZ53), issues related to the long term abandonment of salt caverns became more focused. The tests were performed in cooperation with Ecole Polytechnique (France) and were partially funded by the Solution Mining Research Institute (USA). The long-term abandonment (sealing or plugging) of a solution-mined cavern in a salt formation that has been used for mineral production, hydrocarbon storage, or waste disposal has been a contemporary topic for many years. Sealing and abandonment of caverns in salt formations differs from sealing of an oil and gas well principally for two reasons: - cavern wells are generally completed with much larger casings than oil and gas exploration and production wells; - the cavern fluid pressure rises after sealing. The first difference is not a significant deterrent to effective cavern sealing and abandonment. Essentially all of the uncertainties and complexities associated with cavern sealing and abandonment are a direct result of the second difference - the fact that the cavern fluid pressure rises through time. After a short introduction to solution mining of salt caverns and their use as underground gas storages, the paper will first discuss the factors affecting cavern fluid pressure increase after sealing. The second part of the paper will highlight the practical impacts of these factors on a deep salt cavern abandonment experiment (Cavern TE02; 1500 meters deep), currently being performed on the natural gas storage of Tersanne operated for over 35 years by Gaz de France. (authors)

  18. State workshop on shallow land burial and alternative disposal concepts: proceedings

    International Nuclear Information System (INIS)

    1984-10-01

    Three of the major conclusions reached by state participants were the following: (1) Significant data gaps and information needs have to be addressed before timely state decisionmaking can be accomplished. State participants felt a generic cost/risk/benefit analysis for all viable alternatives would be useful and might best be performed by the federal government on behalf of the states. (2) Recognizing the imprecision in summarizing overall attitudes of the workshop participants, alternative disposal concepts that appear to be the most favorably perceived when rank ordered by critical factors are augered holes with liners, belowground vaults, earth mounded concrete bunkers, aboveground vaults and mined cavities. (3) The public appears to place greater confidence in disposal methods that incorporate man-made engineered barriers because of some past problems at closed shallow land burial facilities. Concern was expressed by workshop participants that the public may not consider the perceived risks associated with shallow land burial to be acceptable. In addition to the four 10 CFR Part 61, Subpart C performance objectives, public acceptance of risk was considered to be a critical factor by state officials in selecting a disposal technology. The states should take the lead in pursuing development-oriented analyses, such as detailed concept engineering and economic feasibility studies. It is not within the purview of NRC responsibility to undertake such studies

  19. Generic repository concept for RBMK-1500 spent nuclear fuel disposal in crystalline rocks in Lithuania

    International Nuclear Information System (INIS)

    Poskas, P.; Brazauskaite, A.; Narkunas, E.; Smaizys, A.; Sirvydas, A.

    2006-01-01

    During 2002-2005 investigations on possibilities to dispose of spent nuclear fuel (SNF) in Lithuania were performed with support of Swedish experts. Disposal concept for RBMK-1500 SNF in crystalline rocks in Lithuania is based on Swedish KBS-3 concept with SNF emplacement into the copper canister with cast iron insert. The bentonite and its mixture with crushed rock are also foreseen as buffer and backfill material. In this paper modelling results on thermal, criticality and other important disposal characteristics for RBMK-1500 SNF fuel emplaced in copper canisters are presented. Based on thermal calculations, the distances between the canisters and between the tunnels were justified. Criticality calculations for the canister with fresh fuel with 2.8 % 235 U enrichment demonstrated that effective neutron multiplication factor k eff values are less than allowable value of 0.95. Dose calculations have shown that total equivalent dose rate from the canister with 50 years stored RBMK-1500 SNF is rather high and is defined mainly by the γ radiation. (author)

  20. An underground research tunnel for the validation of high-level radioactive waste disposal concept

    International Nuclear Information System (INIS)

    Kwon, S.; Park, S. I.; Park, J. H.; Cho, W. J.; Han, P. S.

    2005-01-01

    In order to dispose of high-level radioactive waste(HLW) safely in geological formations, it is necessary to assess the feasibility, safety, appropriateness, and stability of the disposal concept at an underground research site, which is constructed in the same geological formation as the host rock. In this study, minimum requirements and the conceptual design for an efficient construction of a small scale URL, which is named URT, were derived based on a literature review. To confirm the validity of the conceptual design for construction at KAERI, a geological survey including a seismic refraction survey, electronic resistivity survey, borehole drilling, and in situ and laboratory tests were carried out. Based on the results, it was possible to design URT effectively with a consideration of the site characterization. The construction of URT was started in May 2005 and the first stage of the construction of the access tunnel could be successfully completed in Aug. 2005

  1. Disposal Of Spent Fuel In Salt Using Borehole Technology: BSK 3 Concept

    Energy Technology Data Exchange (ETDEWEB)

    Fopp, Stefan; Graf, Reinhold [GNS Gesellschaft fuer Nuklear-Service mbH, Hollestrasse 7A, D-45127 Essen (Germany); Filbert, Wolfgang [DBE TECHNOLOGY GmbH, Eschenstrasse 55, D-31224 Peine (Germany)

    2008-07-01

    The BSK 3 concept was developed for the direct disposal of spent fuel in rock salt. It is based on the conditioning of fuel assemblies and inserting fuel rods into a steel canister which can be placed in vertical boreholes. The BSK 3 canister is suitable for spent fuel rods from 3 PWR or 9 BWR fuel assemblies. The emplacement system developed for the handling and disposal of BSK 3 canisters comprises a transfer cask which provides appropriate shielding during the transport and emplacement process, a transport cart, and an emplacement device. Using the emplacement device the transfer cask will be positioned onto the top of the borehole lock. The presentation describes the development and the design of the transfer cask and the borehole lock. A technically feasible and safe design for the transfer cask and the borehole lock was found regarding the existing safety requirements for radiation shielding, heat dissipation and handling procedure. (authors)

  2. Reference spent fuel and its characteristics for the concept development of a deep geological disposal system

    International Nuclear Information System (INIS)

    Kang, C. H.; Choi, J. W.; Ko, W. I.; Lee, Y. M.; Park, J. H.; Hwang, Y. S.; Kim, S. K.

    1997-09-01

    The total amount of spent fuel arisen from the nuclear power plant to be planned by 2010 at the basis of the long-term power development plan announced by MOTIE (Ministry of Trade, Industry and Energy Resource) in 1995 is estimated to derive the disposal capacity of a deep geological repository is derived. The reference spent fuel whose characteristics could be planned is selected by analysing the characteristic data such as initial enrichment, discharge burnup, geometry, dimension, gross weight, etc. Also isotopic concentration, radioactivity, decay heat, hazard index and radiation intensity of a reference spent fuel are quantitatively identified and summarized in order to apply in the concept developing works of a deep geological disposal system. (author). 12 refs., 24 tabs., 14 figs

  3. Reference spent fuel and its characteristics for the concept development of a deep geological disposal system

    Energy Technology Data Exchange (ETDEWEB)

    Kang, C. H.; Choi, J. W.; Ko, W. I.; Lee, Y. M.; Park, J. H.; Hwang, Y. S.; Kim, S. K.

    1997-09-01

    The total amount of spent fuel arisen from the nuclear power plant to be planned by 2010 at the basis of the long-term power development plan announced by MOTIE (Ministry of Trade, Industry and Energy Resource) in 1995 is estimated to derive the disposal capacity of a deep geological repository is derived. The reference spent fuel whose characteristics could be planned is selected by analysing the characteristic data such as initial enrichment, discharge burnup, geometry, dimension, gross weight, etc. Also isotopic concentration, radioactivity, decay heat, hazard index and radiation intensity of a reference spent fuel are quantitatively identified and summarized in order to apply in the concept developing works of a deep geological disposal system. (author). 12 refs., 24 tabs., 14 figs.

  4. An overview of microbial research related to high-level nuclear waste disposal with emphasis on the Canadian concept for the disposal of nuclear fuel waste

    International Nuclear Information System (INIS)

    Stroes-Gascoyne, S.; West, J.M.

    1995-01-01

    Current research on the effects of microbiology on nuclear waste disposal, carried out in a number of countries, is summarized. Atomic Energy of Canada Limited has developed a concept for the permanent disposal of nuclear fuel waste in Canada. A program was initiated in 1991 to address and quantify the potential effects of microbial action on the integrity of the multibarrier system on which the disposal concept is based. This microbial program focuses on answering specific questions in areas such as the survival of bacteria under relevant radiation and desiccation conditions; growth and mobility of microbes in compacted clay buffer materials and the potential consequences for container corrosion and microbial gas production; the presence and activity of microbes in deep granitic groundwaters; and the effects of biofilms on radionuclide migration in the geosphere. (author)

  5. Advances in the self-burial concept for deep geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Logan, S.E.

    1996-01-01

    The self-burial concept for deep geological disposal of high-level radioactive waste seeks to utilize the radioactive decay heat emitted by the wastes to melt rock and allow descent by gravity into crystalline rock for isolation. Logan developed the governing equations for the self-disposal process in a paper published in 1973 and 1974 showing that moderate waste concentrations in capsules 1 to 2 m in diameter could descend through granite or basalt to considerable depths, in some cases grater than 10 km. Safety considerations related to filling, handling, and initial cooling of such large capsules prior to release, plus the severe container material environment, has prevented use of the concept. Byalko in Russia recently proposed using a sulfur-filled borehole as a conduit for conveying small capsules down to an accumulation zone at a safe depth of several kilometers. This advance in the self-burial concept overcomes previous problems with self-burial. First, capsules of 0.3 m or less in diameter are relatively simple to fill and handle. Second, investigations indicate that once emplaced at an initial accumulation depth, rock-melting can proceed without an enveloping waste container

  6. Final disposal of radioactive wastes in Switzerland: concept and overview of Project Guarantee 1985

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The validity of the operational licences of the existing Swiss nuclear power plants (NPP) Beznau I and II, Muehleberg, Goesgen and Leibstadt after 31st. December 1985 is, because of official requirements, dependent on the demonstration of permanent, safe management and final disposal of radioactive waste. For this purpose, the NPP companies have to prepare a so-called guarantee project and present this to the Bundesrat for review. The appropriate investigations and research have been carried out by Nagra (National Cooperative for the Storage of Radioactive Waste). The 1985 Project Gewaehr (Guarantee) is described in an eight volume report NGB 85-01 to 85-08 and individual research projects are reported on in separate NTB-series reference reports. The present volume NGB 85-01 takes the form of a self-contained project overview in which the concepts for nuclear waste management are described, the contents of the remaining volumes NGB 85-02 to 85-08 are summarized and Project conclusions are drawn from Project Gewaehr 1985. Project Gewaehr 1985 covers two repository types: Type C repository for high-level and certain alpha-containing intermediate-level waste, and Type B repository for all remaining intermediate- and low-level waste. The Project shows in detail that technical feasibility of final disposal can be assumed given presently available methods, that the technical safety barriers show a high level of efficiency and that suitable geological options are available to ensure long-term safety in Switzerland as the concept is defined by official requirements. The Project safety analyses show that the chosen disposal concepts assure the protection of mankind and the environment under all realistically anticipated conditions

  7. Penile cavernous hemangioma

    Directory of Open Access Journals (Sweden)

    Abdelmoughit ECHCHAOUI

    2015-06-01

    Full Text Available Hemangiomas are benign lesions that occur in any part of the body in newborns or in young patients, they are typically capillary or cavernous. Cavernous hemangioma of the penis is extremely rare; and its etiology is not completely understood. Treatment options (surgical excision, laser therapy or sclerotherapy… are controversial and are required if pain, cosmetic defect and/or bleeding during intercourse.                                                  We report a case of a 26 years old man presented with a five years history of a painless lesion on his penis. Physical examination showed an ovoid, solid, 1 x 2 mm in size on the dorsum of penis (Panel A and two elevated irregular lesions on the ventral side (Panel B. The lesions were compressive, nonpulsatile and bluish-red in color with strawberry like appearance. Biopsy and histopathological examination of the lesion revealed a gaping and communicating vessels proliferated in the superficial and medium dermis which is pathognomonic for cavernous hemangioma (Panel C and D. Given the small size, the large number of the lesions, the young age, and the ulceration risk during intercourse if skin graft after excision, Neodymium: YAG laser coagulation was recommended to get a good cosmetic results and sexual function satisfaction.

  8. Radioactive Waste Disposal Pilot Plant concept for a New Mexico site

    International Nuclear Information System (INIS)

    Weart, W.D.

    1976-01-01

    Twenty years of investigation have shown that disposal of nuclear wastes in deep salt formations is the surest means of isolating these wastes from the biosphere for the extremely long period of time required. A large scale demonstration of this capability will soon be provided by a Radioactive Waste Disposal Pilot Plant (RWDPP) to be developed in southeastern New Mexico. Initially, the pilot plant will accept only ERDA generated waste; high level waste from the commercial power reactor fuel cycle will eventually be accommodated in the pilot plant and the initial RWDPP design will be compatible with this waste form. Selection of a specific site and salt horizon will be completed in June 1976. Conceptual design of the RWDPP and assessment of its environmental impact will be completed by June 1977. Construction is expected to start in 1978 with first waste accepted in 1982. The present concept develops disposal areas for all nuclear waste types in a single salt horizon about 800 meters deep. This single level can accommodate all low level and high level waste generated in the United States through the year 2010. A major constraint on the RWDPP design is the ERDA requirement that all waste be ''readily'' retrievable during the duration of pilot plant operation

  9. Genetics Home Reference: cerebral cavernous malformation

    Science.gov (United States)

    ... Additional NIH Resources (1 link) National Institute of Neurological Disorders and Stroke Educational Resources (7 links) Boston Children's Hospital: Cavernous Malformations Disease InfoSearch: Cerebral Cavernous Malformation ...

  10. Instability risk analysis and risk assessment system establishment of underground storage caverns in bedded salt rock

    Science.gov (United States)

    Jing, Wenjun; Zhao, Yan

    2018-02-01

    Stability is an important part of geotechnical engineering research. The operating experiences of underground storage caverns in salt rock all around the world show that the stability of the caverns is the key problem of safe operation. Currently, the combination of theoretical analysis and numerical simulation are the mainly adopts method of reserve stability analysis. This paper introduces the concept of risk into the stability analysis of underground geotechnical structure, and studies the instability of underground storage cavern in salt rock from the perspective of risk analysis. Firstly, the definition and classification of cavern instability risk is proposed, and the damage mechanism is analyzed from the mechanical angle. Then the main stability evaluating indicators of cavern instability risk are proposed, and an evaluation method of cavern instability risk is put forward. Finally, the established cavern instability risk assessment system is applied to the analysis and prediction of cavern instability risk after 30 years of operation in a proposed storage cavern group in the Huai’an salt mine. This research can provide a useful theoretical base for the safe operation and management of underground storage caverns in salt rock.

  11. Robotics and remote handling concepts for disposal of high-level nuclear waste

    International Nuclear Information System (INIS)

    McAffee, Douglas; Raczka, Norman; Schwartztrauber, Keith

    1997-01-01

    This paper summarizes preliminary remote handling and robotic concepts being developed as part of the US Department of Energy's (DOE) Yucca Mountain Project. The DOE is currently evaluating the Yucca Mountain Nevada site for suitability as a possible underground geologic repository for the disposal of high level nuclear waste. The current advanced conceptual design calls for the disposal of more than 12,000 high level nuclear waste packages within a 225 km underground network of tunnels and emplacement drifts. Many of the waste packages may weigh as much as 66 tonnes and measure 1.8 m in diameter and 5.6 m long. The waste packages will emit significant levels of radiation and heat. Therefore, remote handling is a cornerstone of the repository design and operating concepts. This paper discusses potential applications areas for robotics and remote handling technologies within the subsurface repository. It also summarizes the findings of a preliminary technology survey which reviewed available robotic and remote handling technologies developed within the nuclear, mining, rail and industrial robotics and automation industries, and at national laboratories, universities, and related research institutions and government agencies

  12. "Tepid" Geysers above salt caverns

    Science.gov (United States)

    Bérest, Pierre; Brouard, Benoît; Zakharov, Vassily

    2018-06-01

    The formation of a brine geyser erupting from the wellhead of a large underground salt cavern is described. In most cases, the brine outflow from an opened cavern is slow; it results from the cavern creep closure and the thermal expansion of the cavern brine. These two processes are smooth; however, the brine outflow often is bumpy, as it is modulated by atmospheric pressure variations that generate an elastic increase (or decrease) of both cavern and brine volumes. In addition, when the flow is fast enough, the brine thermodynamic behavior in the wellbore is adiabatic. The cold brine expelled from the cavern wellhead is substituted with warm brine entering the borehole bottom, resulting in a lighter brine column. The brine outflow increases. In some cases, the flow becomes so fast that inertia terms must be taken into account. A geyser forms, coming to an end when the pressure in the cavern has dropped sufficiently. A better picture is obtained when head losses are considered. A closed-form solution can be reached. This proves that two cases must be distinguished, depending on whether the cold brine initially contained in the wellbore is expelled fully or not. It can also be shown that geyser formation is a rare event, as it requires both that the wellbore be narrow and that the cavern be very compressible. This study stemmed from an actual example in which a geyser was observed. However, scarce information is available, making any definite interpretation difficult. xml:lang="fr"

  13. Investigation of underground caverns

    International Nuclear Information System (INIS)

    Nolte, E.; Lichter, D.

    1979-01-01

    By means of a probe the condition of the boundary surfaces, other parameters, or the contents of the caverns, e.g. in salt rock may be investigated for ultimate storage of radioactive waste. The probe is hanging on a measuring cable designed as a suspending wire leading to a driving and remote-control mechanism and to evaluation units standing on the surface. At the lower end of the probe an extensionarm is hinged as supporting arm for the testing equipment. The supporting arm can be rotated about the probe axis. As testing equipment e.g. ultrasonic probes, lasers, temperature and moisture sensors may be used. (RW) [de

  14. Brain stem cavernous angioma

    International Nuclear Information System (INIS)

    Delcarpio-O'Donovan, R.; Melanson, D.; Tampieri, D.; Ethier, R.

    1988-01-01

    Twenty-two cases of cavernous angioma of the brain stem were definitely diagnosed by means of magnetic resonance (MR) imaging. In many cases, the diagnosis had remained elusive for several years. Clinically, some cases behaved like multiple sclerosis or brain stem tumor. Others, usually associated with bleeding, caused increased intracranial pressure or subarachnoid hemorrhage. The diagnostic limitations of computed tomography in the posterior fossa are well known. Angiography fails to reveal abnormalities, since this malformation has neither a feeding artery nor a draining vein. Diagnosticians' familiarity with the MR appearance of this lesion may save patients from invasive diagnostic studies and potentially risky treatment

  15. Survey and analysis of the domestic technology level for the concept development of high level waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Chang Sun; Kim, Byung Su; Song, Jae Hyok [Seoul National University, Seoul (Korea); Park, Kwang Hon; Hwang, Ju Ho; Park, Sung Hyun; Lee, Jae Min [Kyunghee University, Seoul (Korea); Han, Joung Sang; Kim, Ku Young [Yonsei University, Seoul (Korea); Lee, Jae Ki; Chang, Jae Kwon [Hangyang University, Seoul (Korea)

    1998-09-01

    The objectives of this study are the analysis of the status of HLW disposal technology and the investigation of the domestic technology level. The study has taken two years to complete with the participation of forty five researchers. The study was mainly carried out through means of literature surveys, collection of related data, visits to research institutes, and meetings with experts in the specific fields. During the first year of this project, the International Symposium on the Concept Development of the High Level Waste Disposal System was held in Taejon, Korea in October, 1997. Eight highly professed foreign experts whose fields of expertise projected to the area of high level waste disposal were invited to the symposium. This study is composed of four major areas; disposal system design/construction, engineered barrier characterization, geologic environment evaluation and performance assessment and total safety. A technical tree scheme of HLW disposal has been illustrated according to the investigation and an analysis for each technical area. For each detailed technology, research projects, performing organization/method and techniques that are to be secured in the order of priority are proposed, but the suggestions are merely at a superfluous level of propositional idea due to the reduction of the budget in the second year. The detailed programs on HLW disposal are greatly affected by governmental HLW disposal policy and in this study, the primary decisions to be made in each level of HLW disposal enterprise and a rough scheme are proposed. (author). 20 refs., 97 figs., 33 tabs.

  16. Fully engineered shallow trench design concepts for disposal of low and intermediate level radioactive waste

    International Nuclear Information System (INIS)

    Locke, J.

    1984-09-01

    In this report, the results of the reviews of design concepts, waste arisings and release mechanisms are described. The basic principles of radiological protection and the proposed strategy for land disposal in the UK are outlined. The essential features of engineered trenches are described with some discussion of the likely material choices and their influence on nuclide release. The radiological protection criteria adopted in this study is that the overall risk of serious health effects arising from any release of radioactivity from a shallow engineered trench should always be less than 10 -6 per annum, which corresponds to a received dose of 0.1 mSv/yr. This approach to radiological protection takes account of the two components of risk of health detriment to future generations; namely the probability that a release of radionuclides will occur and the probability that the subsequent radiation doses will give rise to deleterious effects. A compilation is presented of the waste streams and expected volumes and activities that may be designated for LAND 2 disposal and an initial estimate of the associated nuclide inventory is given. (author)

  17. The Cigar Lake uranium deposit: Analog information for Canada's nuclear fuel waste disposal concept

    International Nuclear Information System (INIS)

    Cramer, J.J.

    1995-05-01

    The Cigar Lake uranium deposit, located in northern Saskatchewan, has many features that parallel those being considered within the Canadian concept for disposal of nuclear fuel waste. The study of these natural structures and processes provides valuable insight toward the eventual design and site selection of a nuclear fuel waste repository. The main feature of this analog is the absence of any indication on the surface of the rich uranium ore 450 m below. This shows that the combination of natural barriers has been effective in isolating the uranium ore from the surface environment. More specifically, the deposit provides analog information relevant to the stability of UO 2 fuel waste, the performance of clay-based and general aspects of water-rock interaction. The main geotechnical studies on this deposit focus on the evolution of groundwater compositions in the deposit and on their redox chemistry with respect to the uranium, iron and sulphide systems. This report reviews and summarizes the analog information and data from the Cigar Lake analog studies for the processes and scenarios expected to occur in the disposal system for used nuclear fuel proposed in Canada. (author). 45 refs., 10 figs

  18. Crop - a project for comparative description of national concepts for disposal of radioactive waste

    International Nuclear Information System (INIS)

    Pusch, R.; Svemar, Ch.

    2003-01-01

    Nine partners representing Sweden (SKB), Belgium (SCK-CEN). Finland (POSIVA). France (Andra). Germany (GRS), Switzerland (NAGRA), Spain (ENRESA). Canada (OPG), and the US (DOECBFO) participate in the EC-supported project CROP, which is the synonym for Cluster Repository Project and aims at describing the various repository concepts for identifying similarities and differences. The ambition is to assist designers and modelers in the development of the respective concepts. Design, construction and instrumentation of underground laboratories (URLs) and forthcoming repositories as well as modeling the engineered performance of national repository concepts in crystalline rock, salt and clay are defined and compared. The depth of location of the repositories is different - 250 to 1000 m- and also the design: the multi-barrier philosophy is proposed for disposal in all types of rock but for salt the geological medium is considered to be the major barrier. The minimum time for effective isolation of the waste differs among national programs (E4 to E6 years) and so is the effort of modeling physical and chemical degradation of the engineered barrier system (EBS), which consists of canisters, embedding buffer and backfill, and plugs. CROP is focusing on the buffer and backfill and shaft, tunnel and borehole seals including plugs. The temperature in the near-field is a most important factor for the repository performance. It will be in the interval 90-110 deg C for crystalline rock and clay, and up to 200 deg C for salt in the close vicinity of the waste according to the concepts, attenuating with increased distance from it. The heat and temperature gradient affects the groundwater flow and rock strain and thereby the evolution of the EBS in the first few hundred years and they are determinants of the chemical stability and hence required dimensions of the engineered barriers. Both the short- and long-term performance of the EBS are significantly affected by the groundwater

  19. Caverns for neutrino physicists

    International Nuclear Information System (INIS)

    Duffaut, P.

    2005-01-01

    Since more than 20 years, particle physicists are using underground facilities to catch cosmic neutrinos and to get rid of other parasitic cosmic radiations. The observation of significant numbers of neutrinos requires the use of large volume caverns at important depths. This article presents such existing facilities in the US, France, Italy, UK, Spain, Japan (Kamioka), Russia and India and the different projects in competition for the setting up of a mega-ton detector with a volume of 1 million m 3 of water (DUSEL project in the US, MEMPHYS project in France, Hyperkamiokande in Japan). Several suitable underground spaces are available in these countries (abandoned mines, tunnels) but each has its advantages and drawbacks in terms of rock mechanics, access and seismicity. (J.S.)

  20. Concept study: Use of grout vaults for disposal of long-length contaminated equipment

    International Nuclear Information System (INIS)

    Clem, D.K.

    1994-01-01

    Study considers the potential for use of grout vaults for disposal of untreated long length equipment removed from waste tanks. Looks at ways to access vaults, material handling, regulatory aspects, and advantages and disadvantages of vault disposal

  1. Canister design concepts for disposal of spent fuel and high level waste

    Energy Technology Data Exchange (ETDEWEB)

    Patel, R.; Punshon, C.; Nicholas, J.; Bastid, P.; Zhou, R.; Schneider, C.; Bagshaw, N.; Howse, D.; Hutchinson, E. [TWI Ltd, Cambridge, (United Kingdom); Asano, R. [Hitachi Zosen Corporation, Osaka (Japan); King, S. [Integrity Corrosion Consulting Ltd, Calgary, Alberta (Canada)

    2012-10-15

    As part of its long-term plans for development of a repository for spent fuel (SF) and high level waste (HLW), Nagra is exploring various options for the selection of materials and design concepts for disposal canisters. The selection of suitable canister options is driven by a series of requirements, one of the most important of which is providing a minimum 1000 year lifetime without breach of containment. One candidate material is carbon steel, because of its relatively low corrosion rate under repository conditions and because of the advanced state of overall technical maturity related to construction and fabrication. Other materials and design options are being pursued in parallel studies. The objective of the present study was to develop conceptual designs for carbon steel SF and HLW canisters along with supporting justification. The design process and outcomes result in design concepts that deal with all key aspects of canister fabrication, welding and inspection, short-term performance (handling and emplacement) and long-term performance (corrosion and structural behaviour after disposal). A further objective of the study is to use the design process to identify the future work that is required to develop detailed designs. The development of canister designs began with the elaboration of a number of design requirements that are derived from the need to satisfy the long-term safety requirements and the operational safety requirements (robustness needed for safe handling during emplacement and potential retrieval). It has been assumed based on radiation shielding calculations that the radiation dose rate at the canister surfaces will be at a level that prohibits manual handling, and therefore a hot cell and remote handling will be needed for filling the canisters and for final welding operations. The most important canister requirements were structured hierarchically and set in the context of an overall design methodology. Conceptual designs for SF canisters

  2. Canister design concepts for disposal of spent fuel and high level waste

    International Nuclear Information System (INIS)

    Patel, R.; Punshon, C.; Nicholas, J.; Bastid, P.; Zhou, R.; Schneider, C.; Bagshaw, N.; Howse, D.; Hutchinson, E.; Asano, R.; King, S.

    2012-10-01

    As part of its long-term plans for development of a repository for spent fuel (SF) and high level waste (HLW), Nagra is exploring various options for the selection of materials and design concepts for disposal canisters. The selection of suitable canister options is driven by a series of requirements, one of the most important of which is providing a minimum 1000 year lifetime without breach of containment. One candidate material is carbon steel, because of its relatively low corrosion rate under repository conditions and because of the advanced state of overall technical maturity related to construction and fabrication. Other materials and design options are being pursued in parallel studies. The objective of the present study was to develop conceptual designs for carbon steel SF and HLW canisters along with supporting justification. The design process and outcomes result in design concepts that deal with all key aspects of canister fabrication, welding and inspection, short-term performance (handling and emplacement) and long-term performance (corrosion and structural behaviour after disposal). A further objective of the study is to use the design process to identify the future work that is required to develop detailed designs. The development of canister designs began with the elaboration of a number of design requirements that are derived from the need to satisfy the long-term safety requirements and the operational safety requirements (robustness needed for safe handling during emplacement and potential retrieval). It has been assumed based on radiation shielding calculations that the radiation dose rate at the canister surfaces will be at a level that prohibits manual handling, and therefore a hot cell and remote handling will be needed for filling the canisters and for final welding operations. The most important canister requirements were structured hierarchically and set in the context of an overall design methodology. Conceptual designs for SF canisters

  3. AECB staff response to the environmental impact statement on the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    1995-07-01

    The Environmental Impact Statement (EIS) on the Concept for Disposal of Canada's Nuclear Fuel Waste was released in October 1994 (AECL,1994) in response to the guidelines issued in 1992 by a Panel formed to evaluate this concept (Federal Environmental Assessment Review Panel, 1992). This response is primarily a statement of deficiencies and thus focuses on the negative aspects of the EIS. The staff review of the EIS was based on the AECB mandate, which is to protect human health and the environment and as such was focused on technical issues in the EIS. These were performance assessment of the multiple barrier system, environmental impacts, concept feasibility, siting, transport and safety as well as general issues of regulatory policy and criteria. The EIS and its supporting documentation have been the sole basis used to judge whether AECB staff expectations of the EIS have been met. The staff response (Part II) considers whether an issue is addressed appropriately and adequately, while taking account of the generic and preliminary nature of the concept. The overall conclusion that AECB staff have drawn from the technical review of the EIS is that the EIS, by itself, does not adequately demonstrate the case for deep geological disposal for nuclear fuel waste. However, AECB staff believe that the EIS information, in combination with a variety of generic national and international assessments, has provided confidence that the deep geological disposal concept is safe and viable. 74 refs

  4. AECB staff response to the environmental impact statement on the concept for disposal of Canada`s nuclear fuel waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The Environmental Impact Statement (EIS) on the Concept for Disposal of Canada`s Nuclear Fuel Waste was released in October 1994 (AECL,1994) in response to the guidelines issued in 1992 by a Panel formed to evaluate this concept (Federal Environmental Assessment Review Panel, 1992). This response is primarily a statement of deficiencies and thus focuses on the negative aspects of the EIS. The staff review of the EIS was based on the AECB mandate, which is to protect human health and the environment and as such was focused on technical issues in the EIS. These were performance assessment of the multiple barrier system, environmental impacts, concept feasibility, siting, transport and safety as well as general issues of regulatory policy and criteria. The EIS and its supporting documentation have been the sole basis used to judge whether AECB staff expectations of the EIS have been met. The staff response (Part II) considers whether an issue is addressed appropriately and adequately, while taking account of the generic and preliminary nature of the concept. The overall conclusion that AECB staff have drawn from the technical review of the EIS is that the EIS, by itself, does not adequately demonstrate the case for deep geological disposal for nuclear fuel waste. However, AECB staff believe that the EIS information, in combination with a variety of generic national and international assessments, has provided confidence that the deep geological disposal concept is safe and viable. 74 refs.

  5. User's manual for the CC3 computer models of the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    Dougan, K.D.; Wojciechowski, L.C.

    1995-06-01

    Atomic Energy of Canada Limited (AECL) is assessing a concept for disposing of CANDU reactor fuel waste in a vault deep in plutonic rock of the Canadian Shield. A computer program called the Systems Variability Analysis Code (SYVAC) has been developed as an analytical tool for the postclosure (long-term) assessment of the concept, and for environmental assessments of other systems. SYVAC3, the third generation of the code, is an executive program that directs repeated simulation of the disposal system, which is represented by the CC3 (Canadian Concept, generation 3) models comprising a design-specific vault, a site-specific geosphere and a biosphere typical of the Canadian Shield. (author). 23 refs., 7 tabs., 21 figs

  6. Source term for the bounding assessment of the Canadian nuclear fuel waste disposal concept

    International Nuclear Information System (INIS)

    Flavelle, P.

    1996-02-01

    This is the second in a series to derive the bounds of the post-closure hazard of the Canadian nuclear fuel waste disposal concept, based on the premise that it is unnecessary to predict accurately the real hazard if the bounding hazard can be shown to be acceptable. In this report a reference used (Bruce A fuel, 865 GJ/kgU average burnup) is used to derive the source term for contaminant releases from the emplacement canisters. This requires development of a container failure function which defines the age of the fuel when the canister is perforated and flooded. The source term is expressed as the time-dependent fractional release rate from the used fuel or as the time-dependent contaminant concentrations in the canister porewater. It is derived as the superposition of an instant release, comprising the upper bound of the gap and grain boundary inventory in the used fuel, and the long-term dissolution of the used fuel matrix. Several dissolution models (stoichiometric dissolution/preferential leaching) under different conditions (matrix solubility limited/ unlimited; oxidizing/ reducing solubility limits; groundwater flow/ no flow) are evaluated and the one resulting in the highest release rate/ highest porewater concentration is adopted as the bounding case. Comparisons between the models are made on the basis of the potential ingestion hazard of the canister porewater, to account for differences in the hazard of different radionuclides. (author) 20 refs., 4 tabs., 9 figs

  7. Reference concepts for the final disposal of LWR spent fuel and other high activity wastes in Spain

    International Nuclear Information System (INIS)

    Huertas, F.; Ulibarri, A.

    1993-01-01

    Studies over the last three years have been recently concluded with the selection of a reference repository concept for the final disposal of spent fuel and other high activity wastes in deep geological formations. Two non-site specific preliminary designs, at a conceptual level, have been developed; one considers granite as the host rock and the other rock salt formations. The Spanish General Radioactive Waste Program also considers clay as a potential host rock for HLW deep disposal; conceptualization for a deep repository in clay is in the initial phase of development. The salt repository concept contemplates the disposal of the HLW in self-shielding casks emplaced in the drifts of an underground facility, excavated at a depth of 850 m in a bedded salt formation. The Custos Type I(7) cask admits up to seven intact PWR fuel assemblies or 21 of BWR type. The final repository facilities are planned to accept a total of 20,000 fuel assemblies (PWR and BWR) and 50 vitrified waste canisters over a period of 25 years. The total space needed for the surface facilities amounts to 322,000 m 2 , including the rock salt dump. The space required for the underground facilities amounts to 1.2 km 2 , approximately. The granite repository concept contemplates the disposal of the HLW in carbon steel canisters, embedded in a 0.75 m thick buffer of swelling smectite clay, in the drifts of an underground facility, excavated at a depth of 55 m in granite. Each canister can host 3 PWR or 9 BWR fuel assemblies. For this concept the total number of canisters needed amounts to 4,860. The space required for the surface and underground facilities is similar to that of the salt concept. The technical principles and criteria used for the design are discussed, and a description of the repository concept is presented

  8. The huge ATLAS cavern now fully excavated

    CERN Multimedia

    2002-01-01

    Excavation of the ATLAS cavern is now complete! At the end of two years' work involving a tremendous technical challenge, the civil engineering contractors have succeeded in digging out one of the biggest experimental caverns in the world. Bravo!

  9. HMCBG processes related to the steel components in the KBS-3H disposal concept

    International Nuclear Information System (INIS)

    Johnson, Lawrence; Marschall, Paul; Wersin, Paul; Gribi, Peter

    2008-05-01

    An analysis of the Hydro-Mechanical-Chemical-microBiological processes affected by Gas (HMCBG) related to the steel components of the KBS-3H disposal concept has been performed. The outcome of this study is foreseen to contribute to the KBS-3H Process Report for a repository for spent fuel sited at Olkiluoto. Three different design options for KBS-3H are currently being studied (open tunnel option, two variants of tight distance block option). While the details of the design may influence the short to medium term performance, it is found that the medium to long-term evolution of KBS-3H is not significantly affected by the chosen design option, provided the distance blocks behave according to design. Under repository conditions, the corrosion of the supercontainer will be fairly rapid. Complete conversion of Fe0 to oxidised Fe 2+ /Fe 3+ species may occur within a few thousands of years. The main corrosion products will be magnetite and, depending on the groundwater composition, also iron sulphide and perhaps siderite. Furthermore, corrosion-derived Fe(II) may react with the clay to form Fe(II)-rich silicates. The supercontainer environment will thus experience a volume change and some loss of plasticity of the buffer between the supercontainer and the rock wall may occur. This might promote bacterial activity at the supercontainer surface, which would lead to an enhancement of localised corrosion and probably to destabilisation of the magnetite layer. Previous investigations indicate, however, that there will be no relevant bacterial activity in the main part of the buffer by virtue of its small pore sizes and low water activity. In the course of time, the swelling pressure of bentonite will be affected by a number of processes, including magnetite formation, geochemical degradation, intrusion of bentonite into void space either initially present or created by relative displacement of distance blocks and supercontainer, and by subsequent bentonite erosion. The

  10. HMCBG processes related to the steel components in the KBS-3H disposal concept

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Lawrence; Marschall, Paul; Wersin, Paul (National Cooperative for the Disposal of Radioactive Waste, Nagra, Wettingen (Switzerland)); Gribi, Peter (SandR Consult GmbH, Baden (Switzerland))

    2008-05-15

    An analysis of the Hydro-Mechanical-Chemical-microBiological processes affected by Gas (HMCBG) related to the steel components of the KBS-3H disposal concept has been performed. The outcome of this study is foreseen to contribute to the KBS-3H Process Report for a repository for spent fuel sited at Olkiluoto. Three different design options for KBS-3H are currently being studied (open tunnel option, two variants of tight distance block option). While the details of the design may influence the short to medium term performance, it is found that the medium to long-term evolution of KBS-3H is not significantly affected by the chosen design option, provided the distance blocks behave according to design. Under repository conditions, the corrosion of the supercontainer will be fairly rapid. Complete conversion of Fe0 to oxidised Fe2+/Fe3+ species may occur within a few thousands of years. The main corrosion products will be magnetite and, depending on the groundwater composition, also iron sulphide and perhaps siderite. Furthermore, corrosion-derived Fe(II) may react with the clay to form Fe(II)-rich silicates. The supercontainer environment will thus experience a volume change and some loss of plasticity of the buffer between the supercontainer and the rock wall may occur. This might promote bacterial activity at the supercontainer surface, which would lead to an enhancement of localised corrosion and probably to destabilisation of the magnetite layer. Previous investigations indicate, however, that there will be no relevant bacterial activity in the main part of the buffer by virtue of its small pore sizes and low water activity. In the course of time, the swelling pressure of bentonite will be affected by a number of processes, including magnetite formation, geochemical degradation, intrusion of bentonite into void space either initially present or created by relative displacement of distance blocks and supercontainer, and by subsequent bentonite erosion. The expected

  11. Uncertainties about the safety of disposal leading to a wish to keep alternatives open. Discussion on the concepts 'storage' ('wait and see') vs. 'disposal' and 'retrievable disposal' vs. 'definitive disposal'

    International Nuclear Information System (INIS)

    Norrby, S.

    2000-01-01

    Uncertainties about the safety of final disposal may lead to unwillingness to take decisions about waste management issues that may seem to be non-reversible. This has lead to proposals that we should wait with decisions on final measures and instead store the waste for some period of time. Also the possibility of retrieval may lead to decisions not to go for permanent disposal but instead to retrievable disposal. These aspects and the pros and cons are discussed both from a more general perspective and also with some reflections from the Swedish programme for nuclear waste management and disposal. (author)

  12. Design concept of a knowledge management system of geological disposal technology

    International Nuclear Information System (INIS)

    Osawa, Hideaki; Umeki, Hiroyuki; Makino, Hitoshi; Takase, H.; Mckinley, I.G.; Okubo, H.

    2008-01-01

    JAEA is developing a 'Knowledge Management System' for vast quantities of data or information arising from various sources relevant to the geological disposal programs in Japan. The geological disposal project is taking a stepwise approach to selecting a disposal site and, to the approval and licensing, construction, operation and closure of a repository. It is a long-term project required approximately 100 years. In this paper, in order to structuralize, as knowledge, the results of R and D on geological disposal technologies of high-level radioactive wastes, the knowledge management approach was first reviewed. The paper is followed by descriptions of the technical characteristics, procedure to carry out a plan, and education of geological disposal technologies such as knowledge management etc. The structuring of the knowledge base and the knowledge management system including the construction of safety case were described. (S. Ohno)

  13. Fat in the normal cavernous sinus

    International Nuclear Information System (INIS)

    Hosoya, Takaaki; Kera, Masahiro; Suzuki, Toshifumi; Yamaguchi, Koichi

    1986-01-01

    The cavernous sinuses of 17 patients examined by metrizamide CT cisternography with 1.5 mm-thick silces were reviewed. Most of the cavernous sinuses contained fatty components. Anterior lateral end and posterior end of the cavernous sinus are the comon sites where the fat is visible. (orig.)

  14. Geothermal characteristics in Korean peninsula for the disposal concept of high level radioactive waste

    International Nuclear Information System (INIS)

    Bae, Dae Seok; Kim, Chun Soo; Kim, Jin Woong; Han, Kyung Won; Chun, Kwan Sik

    2001-04-01

    In order to review the state-of-the-art of geothermal conditions and to supply the references for the concept development of high level radioactive waste disposal at deep geological formation in Korea. The existing data for the heat flow and geothermal gradient were evaluated and summarized over 300m in depth, which are mainly of the hot spring area. The heat flow in Korean peninsula is recorded as about 69mW/m 2 and has no significant differences, in general. This value is regarsed as similar as the average value over Korean peninsula, of 71mW/m 2 . This means The high geothermal anomalies are distributed around the south-western part of Korea and mainly covered with volcanic rocks. And, this value is within the range of the heat flow in Korean peninsula, as 50-80mW/m 2 . The geothermal gradient in each rock type are also shown a similar pattern by depth in Korea as belows. The sedimentary rock area: 25.34 deg C/km The plutonic rock area: 25.24 deg C/km (mainly granites) The metamorphic rock area: 23.56 deg C/km And, the geothermal gradient was measured as about 30 deg C/km around north- eastern part of Korea in 1996, where is distributed with granites. These values has been evaluated according to the existing data, which were mainly from the records of hot spring, in general. However, these properties would be abe to a propper references consideration with the low geothermal and areal characteristics of Korean peninsular. In the following stages, it is suggested that geothermal characteristics should be evaluated for the preferred host rocks

  15. The surface water model for assessing Canada's nuclear fuel waste disposal concept

    International Nuclear Information System (INIS)

    Bird, G.A.; Stephenson, M.; Cornett, R.J.

    1993-01-01

    Canada's Nuclear Fuel Waste Management Program (NFWMP) is investigating the concept of disposal of nuclear fuel waste in a vault excavated deep in crystalline rock on the Canadian Shield. Probabilistic vault, geosphere, and biosphere models are implemented using Monte Carlo simulation techniques to trace nuclides transported in groundwater to the surface environment and humans far into the future. This paper describes the surface water submodel and its parameter values, sensitivity analysis, and validation. The surface water model is a simple, time-dependent, mass balance model of a lake that calculates radioactive and stable isotope contaminant concentrations in lake water and sediment. These concentrations are input to the other submodels and used to predict the radiological dose to humans and other biota. Parameter values in the model are based on the literature and the author's own data, and are generic to Canadian Shield lakes. Most parameters are represented by log normally distributed probability density functions. Sensitivity analysis indicates that nuclide concentrations in lake water and sediment are governed primarily by hydrological flushing with catchment area being the most important parameter. When catchment area is held constant lake area and nuclide transfer rate from water to sediment strongly influence concentrations in both water and sediment. For volatile nuclides, gaseous evasion also has a marked influence on concentrations in both water and sediment, whereas sedimentation rate strongly influences sediment nuclide concentrations. Validation tests demonstrate that the models predictions for 60 Co, 134 Cs, 3 H, P, Cd and Ca are consistent with empirical data when uncertainties are taken into account

  16. Technical feasibility of a concept radioactive waste disposal facility in Boom clay in the Netherlands

    International Nuclear Information System (INIS)

    Vardon, P.J.; Hicks, M.A.; Fokker, P.A.; Fokkens, J.H.

    2012-01-01

    Document available in extended abstract form only. The current management strategy in the Netherlands for radioactive waste is interim storage for approximately 100 years, followed by final deep geological disposal. At present, both Boom Clay and Salt formations are being considered and investigated via the OPERA (Onderzoeks Programma Eindberging Radioactief Afval) and CORA (Commissie Opberging Radioactief Afval) research programmes respectively, instigated by COVRA (Centrale Organisatie Voor Radioactief Afval). This paper outlines the on-going investigation into the initial technical feasibility of a high-level radioactive waste disposal facility, located within a stratum of Boom Clay, as part of the OPERA research programme. The feasibility study is based on the current Belgian Super-container concept, incorporating specific features relevant to the Netherlands, including the waste inventory and possible future glaciation. The repository is designed to be situated at approximately 500 m depth in a Boom Clay stratum of approximately 100 m thickness, and will co-host vitrified High Level Waste (HLW), spent fuel from research reactors, non-heat generating HLW, Low and Intermediate Level Waste (LILW) and depleted uranium. The total footprint is designed to be 3050 m by 1300 m, and will be segregated by waste type. The waste will be stored in drifts drilled perpendicular to the main galleries and will vary in length and diameter depending upon waste type. The repository life-cycle can be considered in three phases: (i) the pre-operation phase, including the conceptual development, site investigation and selection, design and construction; (ii) the operational phase, including waste emplacement and any period of time prior to closure; and (iii) the post-operational phase. The research on the technical feasibility of the repository will investigate whether the repository can be constructed and whether it is able to perform the appropriate safety functions and meet

  17. Simulation of HTM processes in buffer-rock barriers based on the French HLW disposal concept

    International Nuclear Information System (INIS)

    Li, Xiaoshuo; Roehlig, Klaus-Juergen; Zhang, Chunliang

    2012-01-01

    Document available in extended abstract form only. The main objectives of this paper are to gain experience with modelling and analysis of HTM processes in clay rock and bentonite buffer surrounding heat-generating radioactive waste. The French concept for HLW disposal in drifts with backfilled bentonite buffer considered in numerical calculations which are carried out by using the computer code CODE-BRIGHT developed by the Technical University of Catalonia in Barcelona. The French repository designed by ANDRA is located in the middle of the Callovo-Oxfordian argillaceous formation (COX) of 250 m thickness at a depth of 500 to 630 m below the surface. The French concept has been simplified at this simulation work. A drift is considered to be excavated at a depth of 500 m below the surface. It has a diameter of 2.2 m and a length of 20 m. A large volume of the rock mass around the drift is taken into account by an axisymmetric model of 100 m radius and 100 m length. In fact, this model represents a cylindrical rock-buffer-system with the central axis of the containers, as shown in Figure 1. Some points are selected in the buffer and the rock along the radial line (dash yellow line) in the middle of the drift for recording HTM parameters with time. The display and analysis of the results at this paper are chiefly along this line. The simulation work has been divided to two time steps. At the first step, the drift excavation and ventilation is simulated by reducing the stress normal to the drift wall down to zero and circulating gas along the drift wall with relative humidity of 85 %. Following the drift excavation and ventilation, the HLW containers and the bentonite are emplaced in the drift as the second step of the simulation. This is simulated by simultaneously applying the initial conditions of the buffer and the decayed heat emitting from the waste containers as thermal boundary conditions. Two materials (Clay rock and bentonite buffer) are taken into account

  18. Metastases in the cavernous synus

    International Nuclear Information System (INIS)

    Victoria Fernandez, C.; Gonzalez Patino, E.; Pereiro Zabala, I.; Lopez Vazquez, M.D.; Cascallar Caneda, L.; Porto Vazquez, M.C.

    1993-01-01

    We report four cases of metastases in the cavernous synus in patients with primary tumors of parotid gland, lymphatic system, breast and colon. In spite of the similarity in the presentation clinic, the diagnosis wasn't carried out in all the cases with the required celerity, specially in the case of the first presentation of metastasis disease. Three of them response. We analyze the clinic and radiologic data characteristical in cavernous synus metastases, highliting the importance of diagnostic techniques, facilitating as soon as possible the suitable treatment. (Author)

  19. A structural behavior study of rock caverns considering the effects of discontinuities

    International Nuclear Information System (INIS)

    Kim, Jhin Wung; Kim, Sun Hoon; Seo, Jeong Moon; Choi, Kyu Seop; Kim, Dae Hong; Lee, Kyung Jin; Choi, In Gil; Lee, Dong Yong

    1990-06-01

    The objective of this study is to understand the effects of discontinuities within rock masses on the structural behavior of underground rock caverns for radioactive waste disposal, and then develop a computer program for the structural analysis of rock caverns considering these effect of discontinuities. The behavior of rock masses, such as strength, deformation modes, ect., is very difficult to predict because discontinuities in the form of microcracks or joints are randomly distributed within rock masses. Discontinuties existing around the rock cavern for underground radioactive waste disposal may become the main transport pathways of radionuclides, and reduce the strength of rock masses eventually causing the rock cavern structure unstable. Therefore, a comprehensive understanding of the mechanical properties and behavior of discontinuous rock masses and an improvement of structural analysis methods are essential in order to understand the behavior of underground rock cavern structures properly in order to design safe and economic understanding the behavior of discontinuous rock masses is essential. Therfore, this study includes literature review on mechanical properties of and computational models for discontinuous rock masses, and on structures. Then, bases on the engineering judgement a suitable selection and slight modifications on computational models and analysis methods have been made before developing the structural analysis computer program for underground radioactive waste disposal structures. (author)

  20. Hydrocarbon storage caverns overhaul: A case study

    Energy Technology Data Exchange (ETDEWEB)

    McDougall, N. [Bayer Inc., Sarnia, ON (Canada)

    1998-09-01

    Case studies of four hydrocarbon storage cavern overhauls by Bayer Inc., of Sarnia during the period 1993 to 1997 were reviewed and the lessons learned were discussed. Discussions included inspection requirements for each of the caverns, the logistics and planning plant production around the cavern outages, site and cavern preparation, including removal of the casing slips from the well heads. It was emphasized that cavern overhauls can be expensive operations, unless preceded by proper planning. The largest variable cost is likely to be rig time at about $ 2,000 per day. Planning for the unexpected with thoughtful contingencies can reduce costs and avoid expensive delays.

  1. Quantitative Assessment of the Potential Significance of Colloids to the KBS-3 Disposal Concept

    International Nuclear Information System (INIS)

    Klos, R.A.; White, M.J.; Wickham, S.M.; Bennett, D.G.; Hicks, T.W.

    2002-06-01

    Colloids are minute particles in the size range 1 nm to 1 μm that can remain suspended in water, and may influence radionuclide transport in radioactive waste disposal systems. Galson Sciences Ltd (GSL) has undertaken a quantitative assessment of the impact that colloid-facilitated radionuclide transport may have on the performance of the Swedish KBS-3 concept for disposal of high-level radioactive waste and spent fuel. This assessment has involved the evaluation and application of SKI's colloid transport model, COLLAGE II, modelling of km-scale Pu transport at the Nevada Test Site (NTS), USA, and identification of circumstances under which colloid-facilitated transport could be important for a KBS-3-type environment. Colloids bearing traces of plutonium from the BENHAM underground nuclear test have been detected in samples obtained from Nevada Test Site (NTS) groundwater wells 1.3 km from the detonation point. Plutonium is generally fairly immobile in groundwater systems, and it has been suggested that colloids may have caused the plutonium from the BENHAM test to be transported 1.3 km in only 30 years. This hypothesis has been tested by modelling plutonium transport in a fracture with similar characteristics to those present in the vicinity of the BENHAM test. SKI's colloid transport code, COLLAGE II, considers radionuclide transport in a one-dimensional planar fracture and represents radionuclide-colloid sorption and desorption assuming first-order, linear kinetics. Recently published data from both the ongoing NTS site investigation and from the associated Yucca Mountain Project have been used to define a COLLAGE II dataset. The kinetics of radionuclide-colloid sorption and desorption have been found to be crucial in explaining the transport of plutonium associated with colloids, as inferred at the NTS. Specifically, it has been found that for plutonium to have been transported by colloids over the full 1.3 km transport path, it is likely that the plutonium

  2. Geologic and hydrologic considerations for various concepts of high-level radioactive waste disposal in conterminous United States

    International Nuclear Information System (INIS)

    Ekren, E.B.; Dinwiddie, G.A.; Mytton, J.W.; Thordarson, W.; Weir, J.E. Jr.; Hinrichs, E.N.; Schroder, L.J.

    1974-01-01

    The purpose of this investigation is to evaluate and identify which geohydrologic environments in conterminous United States are best suited for various concepts or methods of underground disposal of high-level radioactive wastes and to establish geologic and hydrologic criteria that are pertinent to high-level waste disposal. The unproven methods of disposal include (1) a very deep drill hole (30,000 to 50,000 ft or 9,140 to 15,240 m), (2) a matrix of (an array of multiple) drill holes (1,000 to 20,000 ft or 305 to 6,100 m), (3) a mined chamber (1,000 to 10,000 ft or 305 to 3,050 m), (4) a cavity with separate manmade structures (1,000 to 10,000 ft or 305 to 3,050 m), and (5) an exploded cavity (2,000 to 20,000 ft or 610 to 6,100 m). Areas considered to be unsuitable for waste disposal are those where seismic risk is high, where possible sea-level rise would inundate potential sites, where high topographic relief coincides with high frequency of faults, where there are unfavorable ground-water conditions, and where no suitable rocks are known to be present to depths of 20,000 feet (6,100 m) or more, and where these strata either contain large volumes of ground water or have high oil and gas potential

  3. Development of the Korean Reference Vertical Disposal System Concept for Spent Fuels

    International Nuclear Information System (INIS)

    Lee, J.Y.; Cho, D.K.; Kim, S.G.; Choi, H.J.; Choi, J.W.; Hahn, P.S.

    2006-01-01

    The development of a deep geologic disposal system for the spent fuel from nuclear power plants has been carried out since this program was launched at 1997 in Korea. In ' this paper, a pre-conceptual design of the Korean Reference HLW Vertical disposal System (KRS-V1) is presented. Though no site for the underground repository has yet been specified in Korea, a generic site with granitic rock is considered for reference HLW repository design. Depth of the repository is assumed to be 500 meters. The repository consists of the disposal area, technical rooms with four shafts to connect them to the ground level in the controlled area and technical rooms with an access tunnel and three shafts to connect them to the ground level in the uncontrolled area. Disposal area consists of disposal tunnels, panel tunnels and a central tunnel. The repository will be excavated, operated and backfilled in several phases including an Underground Research Laboratory (URL) phase. The result of this preliminary conceptual design will be used for an evaluation of the feasibility, analyses of the long term safety, information for public communication and a cost estimation etc. (authors)

  4. Identification of contaminants of concern for the postclosure assessment of the concept for the disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    Goodwin, B.W.; Mehta, K.K.

    1994-03-01

    The concept for the disposal of Canada's nuclear fuel waste involves the isolation of irradiated fuel in corrosion-resistant containers emplaced din din a vault located deep in crystalline rock of the Canadian Shield. To estimate potential impacts on members of a critical group far into the future, a postclosure assessment evaluates the long-term safety of the concept. Although the nuclear fuel waste from CANDU (Canada Deuterium Uranium) power generating stations contains several hundreds of potentially toxic radionuclides and chemical elements (referred to as contaminants), many of these would not lead to significant impacts. This report provides an upper bound on estimated radiation dose and chemical toxicity effects on humans from all potentially toxic contaminants, and it identifies those that require detailed consideration in the postclosure assessment. This report also examines the origins and properties of the contaminants. Properties of interest include radioactive half-life, inventory, mobility in groundwaters and sorption on rock, degree of toxicity, and precursors and progeny (or parents and daughters) for members of a decay chain. The report considers how these properties affect the behaviour of different contaminants in different parts of the disposal system. The discussion leads to suggested methods of treatment of different contaminants when simulating their fate within the disposal system. In particular, recommendations are made on how the actinide decay chains can be simplified for study in the postclosure assessment. (author). 56 refs., 22 tabs., 12 figs

  5. Novel Technique for the UX15 Cavern Vault Support System

    CERN Document Server

    Rammer, H

    2000-01-01

    The overall LHC project schedule requires the civil engineering work to begin before the final LEP shutdown. The new caverns for the ATLAS experiment will be built in and around the existing underground structures at point 1. In order to make the best possible use of the time available for the LHC civil engineering before the shutdown of LEP, a particular arrangement for the construction of the UX15 cavern vault has been developed. The basic concept of this arrangement consists of the excavation of the cavern top heading and the installation of the concrete vault immediately afterwards, prior to the subsequent bench excavation after LEP shutdown. A temporary support of the dead weight of the concrete roof will be achieved by the suspension of the roof by 38 no. pre-stressed ground anchors of 225 tons capacity each. This support system will work up to the construction of the cavern base slab and walls and the completion of the permanent concrete lining.

  6. Implementation of the Borehole Disposal Concept for Sealed Radioactive Sources in Ghana

    International Nuclear Information System (INIS)

    Glover, Eric T.

    2016-01-01

    Results from BDC Scoping Tool: • The capsule fails after 49300 years. • The plume arrives at a well 100m away from the disposal borehole after 49621 years with peak dose of 4E-4 Sv/y. • The scoping tool considers groundwater pathway as an advective transport with no sorption. • This implies that, the peak dose that a receptor will receive via ingestion of contaminated water or inhalation of gas for all cases is below the dose constraint of 0.3mSv/y. • The results from the scoping tool suggest that the capsule and the disposal container will provide enough containment for the disposal system being considered at the proposed site.

  7. The Swedish concept for disposal of waste arising from the operation of nuclear power plants

    International Nuclear Information System (INIS)

    Carlsson, J.

    1996-01-01

    The Swedish nuclear power programme consists of 12 reactors producing 50% of the electricity in Sweden. It is stated by law that a waste producer has to make sure a safe handling and disposal of his radioactive waste. SKB is performing necessary activities on behalf of the waste producers. A system is in operation today that will manage all the radioactive waste produced in the country. The system consists of a transportation system, a final repository for operational waste and an interim storage facility for spent fuel. What remains to be built is an encapsulation plant for the spent fuel and a deep repository for final disposal of spent fuel and other long lived waste. All costs for managing and disposal of radioactive waste is paid by the owners of the nuclear power utilities. (author) 9 figs

  8. Investigations of possibilities to dispose of spent nuclear fuel in Lithuania: a model case. Volume 2, Concept of Repository in Crystalline Rocks

    International Nuclear Information System (INIS)

    Motiejunas, S.; Poskas, P.

    2005-01-01

    The aim is to present the generic repository concept in crystalline rocks in Lithuania and cost assessment of the disposal of spent nuclear fuel and long-lived intermediate level waste in this repository. Due to limited budget of this project the repository concept development for Lithuania was based mostly on the experience of foreign countries. In this Volume a review of the existing information on disposal concept in crystalline rocks from various countries is presented. Described repository concept for crystalline rocks in Lithuania covers repository layout, backfill, canister, construction materials and auxiliary buildings. Costs calculations for disposal of spent nuclear fuel and long-lived intermediate-level wastes from Ignalina NPP are presented too. Thermal, criticality and other important disposal evaluations for RBMK-1500 spent nuclear fuel emplaced in copper canister were performed and described

  9. Numerical estimation of structural integrity of salt cavern wells.

    NARCIS (Netherlands)

    Orlic, B.; Thienen-Visser, K. van; Schreppers, G.J.

    2016-01-01

    Finite element analyses were performed to estimate axial deformation of cavern wells due to gas storage operations in solution-mined salt caverns. Caverns shrink over time due to salt creep and the cavern roof subsides potentially threatening well integrity. Cavern deformation, deformation of salt

  10. AECB staff response to the environmental impact statement on the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    1995-07-01

    The Environmental Impact Statement on the Concept for Disposal of Canada's Nuclear Fuel Waste was released in October 1994 in response to the guidelines issued in 1992 by a panel formed to evaluate this concept (Federal Environmental Assessment Review Panel, 1992). This response is primarily a statement of deficiencies and thus focuses on the negative aspects of the Environmental Impact Statement (EIS). The staff review of the EIS was based on the AECB mandate, which is to protect human health and the environment and as such was focused on technical issues in the EIS. These were performance assessment of the multiple barrier system, environmental impacts, concept feasibility, siting, transport and safety as well as general issues o f regulatory policy and criteria. 30 refs

  11. Angiographic patterns of carotid-cavernous fistulas

    International Nuclear Information System (INIS)

    Georgieva, G.; Jekova, M.; Genov, P.; Hadjidekov, V.

    2006-01-01

    Full text: The aim of the study is to present our experience in angiographic evaluation of carotid-cavernous fistulas. 8 patients with carotid-cavernous fistula (6 men and 2 women, range of age from 15 to 62) are included in the study out of all undergone cerebral angiography for a four year period (1996 - 2000). All patients underwent CT brain examination, two out of 8 - MRI. Visualization of ipsi- and contra lateral cavernous sinus and ophthalmic vein dilatation are assessed. In all cases the communication between the internal carotid artery and the cavernous sinus has been assessed as direct. Near simultaneous visualization of the home internal carotid artery, the dilated ipsilateral cavernous sinus and dilated superior ophthalmic vein is found in 2 patients, simultaneous visualization of both cavernous sinuses - in two. In 1 patient the early visualization of the cavernous sinus through the fistula enabled visualization of ipsilateral main internal carotid artery from the contra lateral circulation through the communicating arteries.In 1 excessive contralateral cavernous sinus and contralateral superior ophthalmic vein dilatation is detected. In other 1 excessive flow to dilated ipsilateral cavernous sinus lead insufficient circulation in distal vessels. Digital subtraction Angiography remains the most suitable imaging method in carotid-cavernous fistula assessment regarding type of communication and level of following vessels morphology changes

  12. Concept and Idea-Project for Yugoslav Low and Intermediate level Radioactive Waste Materials Final Disposal Facility

    International Nuclear Information System (INIS)

    Peric, A.

    1997-01-01

    Encapsulation of rad waste in a mortar matrix and displacement of such solidified waste forms into the shallow land burial system, engineered trench system type is suggested concept for the final disposal of low and intermediate level rad waste. The mortar-rad waste mixtures are cured in containers of either concrete or metal for an appropriate period of time, after which solidified rad waste-mortar monoliths are then placed in the engineered trench system, parallelepiped honeycomb structure. Trench consists of vertical barrier-walls, bottom barrier-floors, surface barrier-caps and permeable-reactive walls. Surroundings of the trench consists of buffer barrier materials, mainly clay. Each segment of the trench is equipped with the independent drainage system, as a part of the main drainage. Encapsulation of each filled trench honeycomb segment is performed with concrete cap. Completed trench is covered with impermeable plastic foil and soil leaner, preferably clay. Paper presents an overview of the final disposal facility engineered trench system type. Advantages in comparison with other types of final disposal system are given. (author)

  13. A concept for a station for the encapsulation of vitrified highly radioactive waste into containers for final disposal

    International Nuclear Information System (INIS)

    Anon

    1984-09-01

    The report presents a concept and plans for a station for the encapsulation of vitrified highly radioactive waste into containers for final disposal. The process steps, the layout of the station, the main components of equipment and the sequence of operations under normal conditions are described. The station is designed for vitrified waste from reprocessing. The volume of the waste packages is 150 l, and each package contains the equivalent of 1.33 tonne HM of fuel. The radionuclide activity of the waste corresponds to spent fuel with a decay time of 40 years from discharge from the reactor. It is assumed that after transport under normal conditions the steel shell enclosing the waste is gastight and its surface is free of contamination. The containers for final disposal are made of cast steel and have the form of hollow cylinders with hemispherical ends; their overall length is 2 m and their overall diameter 0.94 m. The station is so designed that the whole procedure, from supply of the transport containers containing the waste to the delivery of the full final disposal containers, is carried out by remote control behind radiation screens in an area isolated from the environment. Containers that do not fulfill the quality control requirements can be improved or repaired in a special rework cell without interfering with the further normal operation of the plant. (author)

  14. Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    1994-01-01

    This report describes the many fundamental issues relating to the strategy being proposed by Atomic Energy of Canada Limited for the long-term management of nuclear fuel waste. It discusses the need for a method for disposal of nuclear fuel waste that would permanently protect human health and the natural environment and that would not unfairly burden future generations. It also describes the background and mandate of the Nuclear Fuel Waste Management Program in Canada.

  15. Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-01

    This report describes the many fundamental issues relating to the strategy being proposed by Atomic Energy of Canada Limited for the long-term management of nuclear fuel waste. It discusses the need for a method for disposal of nuclear fuel waste that would permanently protect human health and the natural environment and that would not unfairly burden future generations. It also describes the background and mandate of the Nuclear Fuel Waste Management Program in Canada.

  16. Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-01

    This report describes the many fundamental issues relating to the strategy being proposed by Atomic Energy of Canada Limited for the long-term management of nuclear fuel waste. It discusses the need for a method for disposal of nuclear fuel waste that would permanently protect human health and the natural environment and that would not unfairly burden future generations. It also describes the background and mandate of the Nuclear Fuel Waste Management Program in Canada.

  17. A reference container concept for spent fuel disposal: structural safety for dimensioning of the reference container

    International Nuclear Information System (INIS)

    Choi, Jongwon; Kwon, Sangki; Kang, Chulhyung; Kwon, Youngjoo

    2002-01-01

    This paper presents the mechanical and thermal stress analysis of a disposal canister to provide basic information for dimensioning the canister and configuration of the canister components. The structural stress analysis is carried out using a finite element analysis code, NISA, and focused on the structural strength of the canister against the expected external pressures due to the swelling of the bentonite buffer and the hydrostatic head, and the thermal load build up in the container

  18. MR findings of septic cavernous sinus thrombosis

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyeong Lae; Lee, Nam Joon; Lee, Jung Hee; Pyo, Hyeon Soon; Eo, Geun; Kim, Kyo Nam; Kim, Young Soon; Kim, Jang Min [Kwang Myung Sung Ae Hospital, Kwang Myung (Korea, Republic of); Lee, Don Young [Korea University Anam Hospital, Seoul (Korea, Republic of)

    2000-08-01

    To evaluate the MR findings of septic thrombosis of the cavernous sinus. Eleven MR images of six patients with septic cavernous sinus thrombosis obtained over a five-year period and proven clinically or radiologically were retrospectively reviewed. The contour and enhancement pattern of the cavernous sinus, changes in the internal carotid artery, orbit, pituitary gland and sphenoid sinus, and intracranial abnormalities were analyzed and compared with the findings of follow-up studies. In all six patients, contrast study revealed asymmetrical enlargement of the ipsilateral cavernous sinus and multiple irregular filling defects within it. Narrowing of the cavernous portion of the ipsilateral internal carotid artery was noted in five patients, upward displacement of the ipsilateral internal carotid artery in four, ipsilateral proptosis with engorgement of the superior ophthalmic vein in two, pituitary enlargement in five, and inflammatory change in the sphenoid sinus in six. Associated intracranial abnormalities included edema and enhancement in the meninx, temporal lobe, or pons adjacent to the cavernous sinus in four patients, hydrocephalus in one, and cerebral infarction in one. Follow-up MR imaging indicated that the extent of asymmetrical enlargement of the cavernous sinus, filling defects within it, as seen on contrast study, and enlarged pituitary glands had all decreased, without significant interval change. MR imaging is useful in the diagnosis of septic cavernous sinus thrombosis. Asymmetrical enlargement of the cavernous sinus, multiple irregular filling defect within it, as seen on contrast study, and changes in the internal carotid artery are characteristic findings. (author)

  19. Reinforcement of the concrete base slab of the ATLAS cavern

    CERN Multimedia

    Maximilien Brice

    2002-01-01

    Photo 02: UX15 cavern, preparation for concreting of base slab first lift. Photo 05: UX15 cavern, placing of reinforcement for base slab first lift. Photo 07: UX15 cavern, preparation for concreting of base slab first lift. Photo 09: UX15 cavern, placing of reinforcement for base slab first lift. Photo 10: UX15 cavern, view into PX14 shaft above. Photo 12: UX15 cavern, temporary access platform of RB16 tunnel. Photo 15: UJ17 chamber, invert excavation.

  20. The role of colloids and suspended particles in radionuclide transport in the Canadian concept for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Vilks, P.

    1994-02-01

    AECL Research is developing a concept for the permanent disposal of nuclear fuel waste in a deep engineered vault in plutonic rock of the Canadian Shield and is preparing an Environmental Impact Statement (EIS) to document its case for the acceptability of the disposal concept. This report, one in a series of supporting documents for the EIS, addresses the role of particles in radionuclide transport. It summarizes our studies of natural particles in groundwater and presents the arguments used to justify the omission of particle-facilitated transport in the geosphere model that is based on the Whiteshell Research Area (WRA) and used in the postclosure assessment study case. Because radiocolloids formed in the vault will not be able to migrate through the clay buffer, radiocolloid formation in the geosphere will be determined by the sorption of radionuclides onto particles in groundwater. These particles consist of typical fracture-lining minerals, such as clays, micas and quartz; precipitated particles, such as colloidal silica and Fe-Si oxyhydroxides; and organic particles. In groundwater from the WRA, the average concentrations of colloids and suspended particles are 0.34 and 1.4 mg/L respectively. Particle-facilitated transport is not included in the geosphere model because the concentrations of particles in groundwater from the WRA are too low to have a significant impact on radionuclide transport. (author). 92 refs., 11 tabs., 13 figs

  1. Modeling of nuclear waste disposal by rock melting

    International Nuclear Information System (INIS)

    Heuze, F.E.

    1982-04-01

    Today, the favored option for disposal of high-level nuclear wastes is their burial in mined caverns. As an alternative, the concept of deep disposal by rock melting (DRM) also has received some attention. DRM entails the injection of waste, in a cavity or borehole, 2 to 3 kilometers down in the earth crust. Granitic rocks are the prime candidate medium. The high thermal loading initially will melt the rock surrounding the waste. Following resolidification, a rock/waste matrix is formed, which should provide isolation for many years. The complex thermal, mechanical, and hydraulic aspects of DRM can be studied best by means of numerical models. The models must accommodate the coupling of the physical processes involved, and the temperature dependency of the granite properties, some of which are subject to abrupt discontinuities, during α-β phase transition and melting. This paper outlines a strategy for such complex modeling

  2. Programmer's guide for the CC3 computer models of the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    Dougan, K.D.

    1996-11-01

    Atomic Energy of Canada Limited (AECL) is assessing a concept for disposing of CANDU reactor fuel waste in a vault deep in plutonic rock of the Canadian Shield. A computer program called the Systems Variability Analysis Code (SYVAC) was developed as an analytical tool for the postclosure (long-term) assessment of the concept, and for environmental assessments of other systems. SYVAC3, the third generation of the code, is an executive program that directs repeated simulation of the disposal system, which is described by the CC3 (Canadian Concept, generation 3) model. The CC3 model is comprised of the disposal vault submodel, the local geosphere submodel and the biosphere submodel. The CC3 Proarammer's Guide describes the programming philosophy and programming conventions not covered in the project standards. The guide includes a description of the overall logic for the CC3 vault, geosphere, and biosphere submodels. Each of the CC3 submodels is also isolated from the other two submbdels to create autonomous or 'stand-alone' submodels. The techniques used to isolate a CC3 submodel, and in particular to determine the submodells input and output data interface, are described. Structure charts are provided for the CC3 model and stand-alone submodels. This guide is meant as a companion document to the CC3 User's Manual. This guide does not describe how to use the CC3 software. The user should consult the CC3 User's Manual to determine how to configure, compile, link, and run the CC3 source code, as well as how to modify the data in the input files. It is intended that the CC3 code version CC305 be executed with SYVAC3 version SV309 and the Modelling Algorithm Library (ML3) version ML303, both developed for the assessment of the concept. SYVAC3-CC3-ML3 (also referred to as 'SC3') can be run on any platform containing an ANSI FORTRAN 77 compliant compiler. Recommended hardware environments are specified in the CC3 User's Manual. (author)

  3. Concept and problems on modernization of existing points for radioactive waste disposal in Belarus

    International Nuclear Information System (INIS)

    Zhemzhurov, Michail

    1999-01-01

    At present Belarus has no operating nuclear power plants (NPP) on its territory, the works with fissile materials carried out at the available nuclear and physical benches have been stopped. But not long ago a research reactor IRT-M with the capacity of 5000 kw was under operation from 1962 to 1986 at the Institute of Nuclear Power Engineering, now reorganized (located in Sosny settlement, 10 kilometers from Minsk-city), and a prototype of a small-sized mobile NPP with electric capacity of 630 kw was tested in 1985-1987, as well as a whole complex of nuclear and technical benches were into service, such as large-scale reactor loop plants for testing fuel elements and critical assemblies. About 1000 industrial, medical, scientific and research institutions use radioactive materials and the devices containing them in Belarus. Annually about 8000 kg of RAW and 6000 units of the spent sources of ionizing radiation (SIR) are generated by these enterprises which are to be obligatory disposed. Annual disposal of such RAW and SIR constitutes 10-50 tons with activity of 1-5).103 Ci. The paper presents the recommendations on extraction, reprocessing and conditioning of radioactive waste from the existing storages when PDWD reconstruction which have been developed with using the created computer database on the stored RAW

  4. The Swedish Concept for Disposal of Spent Nuclear Fuel: Differences Between Vertical and Horizontal Waste Canister Emplacement

    International Nuclear Information System (INIS)

    Bennett, D.G.; Hicks, T.W.

    2005-10-01

    The Swedish Nuclear Power Inspectorate (SKI) is preparing for the review of licence applications related to the disposal of spent nuclear fuel. The Swedish Nuclear Fuel and Waste Management Company (SKB) refers to its proposals for the disposal of spent nuclear fuel as the KBS-3 concept. In the KBS-3 concept, SKB plans that, after 30 to 40 years of interim storage, spent fuel will be disposed of at a depth of about 500 m in crystalline bedrock, surrounded by a system of engineered barriers. The principle barrier to radionuclide release is a cylindrical copper canister. Within the copper canister, the spent fuel is supported by a cast iron insert. Outside the copper canister is a layer of bentonite clay, known as the buffer, which is designed to provide mechanical protection for the canisters and to limit the access of groundwater and corrosive substances to their surfaces. The bentonite buffer is also designed to sorb radionuclides released from the canisters, and to filter any colloids that may form within the waste. SKB is expected to base its forthcoming licence applications on a repository design in which the waste canisters are emplaced in vertical boreholes (KBS-3V). However, SKB has also indicated that it might be possible and, in some respects, beneficial to dispose of the waste canisters in horizontal tunnels (KBS-3H). There are many similarities between the KBS-3V and KBS-3H designs. There are, however, uncertainties associated with both of the designs and, when compared, both possess relative advantages and disadvantages. SKB has identified many of the key factors that will determine the evolution of a KBS-3H repository and has plans for research and development work in many of the areas where the differences between the KBS-3V and KBS-3H designs mean that they could be significant in terms of repository performance. With respect to the KBS-3H design, key technical issues are associated with: 1. The accuracy of deposition drift construction. 2. Water

  5. Arachnoid cyst in cavernous sinus: case report

    International Nuclear Information System (INIS)

    Lim, Hyoung Gun; Yoo, Won Jong; Jung, So Lyung; Lee, Hae Gui; Lim, Hyun Wook; Im, Soo Ah

    2002-01-01

    Arachnoid cyst of the cavernous sinus is very rare. When present, its anatomic location frequently gives rise to cranial nerve palsy. We report a case of arachnoid cyst of the cavernous sinus in a 38-year-old man with impaired eyeball movement and diplopia

  6. Arachnoid cyst in cavernous sinus: case report

    International Nuclear Information System (INIS)

    Lim, Hyoung Gun; Yoo, Won Jong; Jung, So Lyung; Lee, Hae Giu; Lim, Hyun Wook; Im, Soo Ah

    2002-01-01

    Arachnoid cyst of the cavernous sinus is very rare. When present, its anatomic location frequently gives rise to cranial nerve palsy. We report a case of arachnoid cyst of the cavernous sinus in a 38-year-old man with impeder eyeball movement and diplopia

  7. Arachnoid cyst in cavernous sinus: case report

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Hyoung Gun; Yoo, Won Jong; Jung, So Lyung; Lee, Hae Giu; Lim, Hyun Wook; Im, Soo Ah [The Catholic University of Kore College of Medicine, Puchun (Korea, Republic of)

    2002-12-01

    Arachnoid cyst of the cavernous sinus is very rare. When present, its anatomic location frequently gives rise to cranial nerve palsy. We report a case of arachnoid cyst of the cavernous sinus in a 38-year-old man with impeder eyeball movement and diplopia.

  8. A 12-year cavern abandonment test

    Directory of Open Access Journals (Sweden)

    Brouard B.

    2010-06-01

    Full Text Available In 1997-1998, an abandonment test was performed in a 950-m deep, 8000-m3 salt cavern operated by GDF SUEZ at Etrez, France. In this relatively small brine-filled cavern, which had been kept idle for 15 years before the test, thermal equilibrium was reached. A special system was designed to monitor leaks, which proved to be exceedingly small. In these conditions, brine permeation and cavern creep closure are the only factors to play significant roles in pressure evolution. This test strongly suggested that obtaining an equilibrium pressure such that the effects of these two factors were exactly equal would be reached in the long term. Four years later, pressure monitoring in the closed cavern resumed. Pressure evolution during the 2002-2009 period confirmed that cavern brine pressure will remain constant and significantly smaller than geostatic pressure in the long term, precluding any risk of fracturing and brine seepage to the overburden layers.

  9. Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site

    International Nuclear Information System (INIS)

    Cochran, J.R.; Brown, T.J.; Stockman, H.W.; Gallegos, D.P.; Conrad, S.H.; Price, L.L.

    1997-09-01

    This report documents a preliminary evaluation of the ability of the greater confinement disposal boreholes at the Nevada Test Site to provide long-term isolation of radionuclides from the disposal of vitrified byproduct material. The byproduct material is essentially concentrated residue from processing uranium ore that contains a complex mixture of radionuclides, many of which are long-lived and present in concentrations greater than 100,000 picoCuries per gram. This material has been stored in three silos at the fernald Environmental Management Project since the early 1950s and will be vitrified into 6,000 yd 3 (4,580 m 3 ) of glass gems prior to disposal. This report documents Sandia National Laboratories' preliminary evaluation for disposal of the byproduct material and includes: the selection of quantitative performance objectives; a conceptual model of the disposal system and the waste; results of the modeling; identified issues, and activities necessary to complete a full performance assessment

  10. De minimis concepts in radioactive waste disposal. Considerations in defining de minimis quantities of solid radioactive waste for uncontrolled disposal by incineration and landfill

    International Nuclear Information System (INIS)

    1983-02-01

    This document deals with recommendations addressed to those national authorities wishing to dispose of low level radioactive waste into the terrestrial environment, on how de minimis levels or quantities can be derived. The only radioactive materials covered here are declared solid radioactive wastes of very low activity which are controlled up to the point where deliberate control is lost, or wastes below a level that requires regulatory control. As regards the disposal sites, these wastes are not intended to be disposed of in fully controlled disposal facilities, such as repositories located in shallow land, rock cavities, etc. On the other hand, it is considered that these materials should not be disposed of in any place, but should be handled like other municipal wastes. Among the different techniques available, only two are considered in this document, namely a sanitary landfill facility, and an urban incineration plant

  11. The Role of Temperature in the Safety Case for High-Level Radioactive Waste Disposal: A Comparison of Design Concepts

    Directory of Open Access Journals (Sweden)

    Joachim Heierli

    2017-06-01

    Full Text Available The disposal of heat-generating radioactive waste in deep underground facilities requires a sparing use of spatial resources on the one side and favorable temperature conditions over the project lifetime on the other side. Under heat-sensitive conditions, these goals run in opposite directions and therefore a balance of some kind must be found. Often the elected strategy is to determine the size of the repository by capping the temperatures in the near-field, thus setting an upper limit to the deterioration of barrier materials. Alternatively, the spatial resources available in the siting area can be used to further reduce temperatures as long as supplementary benefits are returned from doing so. Using analytical modeling of the heat flow in the circumambient rock of a repository for high-level waste and spent fuel, this contribution examines possible obstacles in substantiating the safety case, namely the retrievability of waste during the operational lifetime of the facility, the representativeness of pilot disposal areas for monitoring, and the effect of thermal anomalies underground. The results indicate that there are, amongst the visited criteria, several benefits to the temperature-optimizing strategy over the prevailing space-optimizing concepts. The right balance between saving spatial resources and obtaining optimal temperature conditions is yet to be found.

  12. Very deep hole concept: evaluation of an alternative for nuclear waste disposal

    International Nuclear Information System (INIS)

    O'Brien, M.T.; Cohen, L.H.; Narasimhan, T.N.; Simkin, T.L.; Wollenberg, H.A.; Brace, W.F.; Green, S.; Pratt, H.P.

    1979-07-01

    One proposal for disposing of radioactive waste is to put it in drill holes or mined cavities so deep that the waste would be effectively isolated from the surface. Even if radioisotopes escaped from the disposal canister, they would be removed from the circulating groundwater system by sorption and/or chemical reaction in their transit on very long paths to the surface. This report summarizes the feasibilities and costs of making deep holes and deep mine shafts; estimates probable technological advances by the year 2000; presents thermal history and thermally induced stress calculations based on several assumptions regarding age of waste and density of emplacement; and summarizes lack of knowledge that bear upon the isolation of waste at great depth. In strong rock, present technology would probably enable us to drill a hole 20 cm in diameter to a depth of 11 km and sink a shaft 10 m in diameter to about 4.4 km. By the year 2000, with advancement of technology, holes of 15 km depth and 20 cm diameter could be drilled, and shafts of 6.4 km or deeper could be sunk. The heat output of 5.5-year-old spent fuel and 6.5-year-old reprocessed waste is used to calculate temperature increases and stress buildings in the surrounding rocks. Some waste configurations may cause unacceptably high temperature increases; indeed, limitations on temperatures reached will in some cases limit the packing density of waste canisters and/or require longer cooling of the waste before emplacement. Sealing boreholes and shafts for significant times, i.e. 1,000 to 100,000 years presents additional problems. The casing or ling of the borehole or shaft would have to be removed in the region where seals are constructed, or the lining material would have to be designed to function as an integral part of the long-term seal. Sealing fractures in the rock around the borehole or shaft will be quite important

  13. Aspects of governance in the practical implementation of the concept of reversibility for deep geological disposal. Report no. 308

    International Nuclear Information System (INIS)

    Reaud, C.; Schieber, C.; Schneider, T.; Gadbois, S.; Heriard Dubreuil, G.

    2010-01-01

    The European project COWAM in Practice (CIP) was aimed to lead for three years (2007-2009) a process of monitoring, analyzing and evaluating the governance linked with radioactive waste management. This project, in cooperation with a research group and stakeholders, was conducted in parallel in 5 European countries (Spain, France, United Kingdom, Romania, Slovenia). In France, the issue of reversibility for a deep geological disposal was introduced in the Act of December 30, 1991 on the possible options to manage radioactive waste. The Act of June 28, 2006 relative to sustainable management of materials and radioactive waste confirmed the option, by calling for a reversible waste disposal facility in a deep geological formation to be designed. The main issue is no longer to justify the adoption of reversibility, but to investigate the practical procedures for its implementation. The French stakeholder Group 4 involved in the European project COWAM In Practice (CIP) had identified several subjects for investigation: - The different aspects associated with the practical implementation of reversible disposal: technical aspects, and aspects relative to monitoring, safety and expertise, in terms of legal, financial, administrative and political, etc. responsibility related to the notion of reversibility. - The stakes of governance related to the processes of assessment and decision-making - The roles of local stakeholders in these processes. The analysis conducted by CEPN in cooperation with the French stakeholder group, facilitated by Mutadis, showed that the practical implementation of reversibility aims to maintain a capacity of choice between three options: to continue to maintain the reversibility, to retrieve packages or to initiate the closure of all or part the disposal facility. Maintaining this choice in the long term implies setting up specific institutional, financial and decision-making systems,etc,. that need to be jointly developed in advance by all the

  14. Preliminary safety concept for disposal of the very low level radioactive waste in Romania.

    Science.gov (United States)

    Niculae, O; Andrei, V; Ionita, G; Duliu, O G

    2009-05-01

    In Romania, there are certain nuclear installations in operation or under decommissioning, all of them representing an important source of very low level waste (VLLW). This paper presents an overview on the approach of the VLLW management in Romania, focused on those resulted from the nuclear power plants decommissioning. At the same time, the basic elements of safety concept, together with some safety evaluations concerning VLLW repository are presented and discussed too.

  15. Alternative concepts for treatment and disposal of Hanford site high-level waste in tanks

    Energy Technology Data Exchange (ETDEWEB)

    Claghorn, R.D.; Powell, W.J.

    1994-12-01

    Some innovative approaches have recently been proposed that may have significant schedule, cost, or environmental advantages which could improve the current HLW program strategy. Three general categories of alternative concepts are now under consideration: (1) process/product alternatives, (2) facility layout options, and (3) contracting strategies. This report compares the alternate approaches to the current program baseline to illustrate their potential significance and to identify the risks associated with each approach.

  16. Alternative concepts for treatment and disposal of Hanford site high-level waste in tanks

    International Nuclear Information System (INIS)

    Claghorn, R.D.; Powell, W.J.

    1994-12-01

    Some innovative approaches have recently been proposed that may have significant schedule, cost, or environmental advantages which could improve the current HLW program strategy. Three general categories of alternative concepts are now under consideration: (1) process/product alternatives, (2) facility layout options, and (3) contracting strategies. This report compares the alternate approaches to the current program baseline to illustrate their potential significance and to identify the risks associated with each approach

  17. Rock cavern storage of spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Won Jin; Kim, Kyung Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kwon, Sang Ki [Inha University, Incheon (Korea, Republic of)

    2015-12-15

    The rock cavern storage for spent fuel has been assessed to apply in Korea with reviewing the state of the art of the technologies for surface storage and rock cavern storage of spent fuel. The technical feasibility and economic aspects of the rock cavern storage of spent fuel were also analyzed. A considerable area of flat land isolated from the exterior are needed to meet the requirement for the site of the surface storage facilities. It may, however, not be easy to secure such areas in the mountainous region of Korea. Instead, the spent fuel storage facilities constructed in the rock cavern moderate their demands for the suitable site. As a result, the rock cavern storage is a promising alternative for the storage of spent fuel in the aspect of natural and social environments. The rock cavern storage of spent fuel has several advantages compared with the surface storage, and there is no significant difference on the viewpoint of economy between the two alternatives. In addition, no great technical difficulties are present to apply the rock cavern storage technologies to the storage of domestic spent fuel.

  18. Production, consumption and transport of gases in deep geological repositories according to the Swiss disposal concept

    International Nuclear Information System (INIS)

    Diomidis, N; Cloet, V.; Leupin, O.X.; Marschall, P.; Poller, A.; Stein, M.

    2016-12-01

    In a deep geological repository for radioactive waste, in absence of oxygen and in presence of water, corrosion of various metals and alloys will lead to the formation of hydrogen. If present, organic materials may slowly degrade and generate carbon dioxide, methane and other gaseous species. Depending on local conditions, gaseous species can be consumed by chemical reactions and by microbial activity. If the resulting rate of gas generation exceeds the rate of migration of dissolved gas molecules in the pores of the engineered barriers or the host rock, the solubility limit of the gas will eventually be exceeded and the formation of a discrete gas phase will occur. Gases could continue to accumulate until the pressure becomes sufficient to be released in gaseous form. This report deals with the evolution of gas-related processes that can influence the long-term behaviour and safety of low- and intermediate-level waste (L/ILW) and high-level waste (HLW) repositories in Opalinus Clay. The main aim is to present a synthesis of processes and phenomena related to repository-produced gases and to assess their influence on repository performance. A current overview of gas sources, reactions and interactions, generation, consumption, and transport is provided. Furthermore, current scientific understanding is used to define safety function indicators and criteria, which are employed to evaluate the potential influence of repository-generated gas on safety-relevant properties of engineered and natural barriers. The assessment of gas generation, consumption and transport is addressed separately for the HLW and the L/ILW deep geological repositories. The employed methodology, which is common for both repository types, consists of the description and quantification of the potential gas sources, which include the waste, barrier components such as disposal canisters and other gas-generating repository components, and of the processes and reactions leading to the generation or

  19. Production, consumption and transport of gases in deep geological repositories according to the Swiss disposal concept

    Energy Technology Data Exchange (ETDEWEB)

    Diomidis, N; Cloet, V.; Leupin, O.X.; Marschall, P.; Poller, A.; Stein, M.

    2016-12-15

    In a deep geological repository for radioactive waste, in absence of oxygen and in presence of water, corrosion of various metals and alloys will lead to the formation of hydrogen. If present, organic materials may slowly degrade and generate carbon dioxide, methane and other gaseous species. Depending on local conditions, gaseous species can be consumed by chemical reactions and by microbial activity. If the resulting rate of gas generation exceeds the rate of migration of dissolved gas molecules in the pores of the engineered barriers or the host rock, the solubility limit of the gas will eventually be exceeded and the formation of a discrete gas phase will occur. Gases could continue to accumulate until the pressure becomes sufficient to be released in gaseous form. This report deals with the evolution of gas-related processes that can influence the long-term behaviour and safety of low- and intermediate-level waste (L/ILW) and high-level waste (HLW) repositories in Opalinus Clay. The main aim is to present a synthesis of processes and phenomena related to repository-produced gases and to assess their influence on repository performance. A current overview of gas sources, reactions and interactions, generation, consumption, and transport is provided. Furthermore, current scientific understanding is used to define safety function indicators and criteria, which are employed to evaluate the potential influence of repository-generated gas on safety-relevant properties of engineered and natural barriers. The assessment of gas generation, consumption and transport is addressed separately for the HLW and the L/ILW deep geological repositories. The employed methodology, which is common for both repository types, consists of the description and quantification of the potential gas sources, which include the waste, barrier components such as disposal canisters and other gas-generating repository components, and of the processes and reactions leading to the generation or

  20. Accelerator-driven system design concept for disposing of spent nuclear fuels

    International Nuclear Information System (INIS)

    Gohar, Y.; Cao, Y.; Kellogg, R.; Merzari, E.

    2015-01-01

    At present, the US SNF (Spent Nuclear Fuel) inventory is growing by about 2,000 metric tonnes (MT) per year from the current operating nuclear power plants to reach about 70,000 MT by 2015. This SNF inventory contains about 1% transuranics (700 MT), which has about 115 MT of minor actinides. Accelerator-driven systems utilising proton accelerators with neutron spallation targets and subcritical blankets can be utilised for transmuting these transuranics, simultaneously generating carbon free energy, and significantly reducing the capacity of the required geological repository storage facility for the spent nuclear fuels. A fraction of the SNF plutonium can be used as a MOX fuel in the current/future thermal power reactors and as a starting fuel for future fast power reactors. The uranium of the spent nuclear fuel can be recycled for use in future nuclear power plants. This paper shows that only four to five accelerator-driven systems operating for less than 33 full power years can dispose of the US SNF inventory expected by 2015. In addition, a significant fraction of the long-lived fission products will be transmuted at the same time. Each system consists of a proton accelerator with a neutron spallation target and a subcritical assembly. The accelerator beam parameters are 1 GeV protons and 25 MW beam power, which produce 3 GWt in the subcritical assembly. A liquid metal (lead or lead-bismuth eutectic) spallation target is selected because of design advantages. This target is located at the centre of the subcritical assembly to maximise the utilisation of spallation neutrons. Because of the high power density in the target material, the target has its own coolant loop, which is independent of the subcritical assembly coolant loop. Mobile fuel forms with transuranic materials without uranium are considered in this work with liquid lead or lead-bismuth eutectic as fuel carrier

  1. Long-term interim storage concepts with conditioning strategies ensuring compatibility with subsequent disposal or reprocessing

    International Nuclear Information System (INIS)

    Moitrier, C.; Tirel, I.; Villard, C.

    2000-01-01

    The objective of the CEA studies carried out under research topic 3 (long-term interim storage) of the 1991 French radioactive waste management law is to demonstrate the industrial feasibility of a comprehensive, flexible interim storage facility by thoroughly evaluating and comparing all the basic components of various interim storage concepts. In this context, the CEA is considering reference solutions or concepts based on three primary components (the package, the interim storage facility and the site) suitable for determining the specifications of a very long-term solution. Some aspects are examined in greater detail, such as the implementation of long-term technologies, conditioning processes ensuring the absence of water and contamination in the facility, or allowance for radioactive decay of the packages. The results obtained are continually compiled in reports substantiating the design options. These studies should also lead to an overall economic assessment in terms of the capital and operating cost requirements, thereby providing an additional basis for selecting the design options. The comparison with existing industrial facilities highlights the technical and economic progress represented by the new generation of interim storage units. (authors)

  2. ATLAS cavern magnetic field calculations

    International Nuclear Information System (INIS)

    Vorojtsov, S.B.; Vorozhtsov, A.S.; Butin, F.; Price, M.

    2000-01-01

    A new approach has been adopted in an attempt to produce a complete ATLAS cavern B-field map using a more precise methodological approach (variable magnetisation, depending on the external field) and the latest design taking into account of the structural elements. The basic idea was to produce a dedicated basic TOSCA model and then to insert a series of ferromagnetic structure elements to monitor the perturbative effect on the basic field map. Eventually, it was found: the bedplate field perturbation is an order of magnitude above the permissible level; manufacturing of the bedplates from nonmagnetic material or careful evaluation of their field contribution in the event reconstruction codes is required; the field value at the rack positions is higher than the permissible one; the final position of racks should be chosen taking into account the detailed magnetic field distribution

  3. Derivation and application of an analytical rock displacement solution on rectangular cavern wall using the inverse mapping method.

    Directory of Open Access Journals (Sweden)

    Mingzhong Gao

    Full Text Available Rectangular caverns are increasingly used in underground engineering projects, the failure mechanism of rectangular cavern wall rock is significantly different as a result of the cross-sectional shape and variations in wall stress distributions. However, the conventional computational method always results in a long-winded computational process and multiple displacement solutions of internal rectangular wall rock. This paper uses a Laurent series complex method to obtain a mapping function expression based on complex variable function theory and conformal transformation. This method is combined with the Schwarz-Christoffel method to calculate the mapping function coefficient and to determine the rectangular cavern wall rock deformation. With regard to the inverse mapping concept, the mapping relation between the polar coordinate system within plane ς and a corresponding unique plane coordinate point inside the cavern wall rock is discussed. The disadvantage of multiple solutions when mapping from the plane to the polar coordinate system is addressed. This theoretical formula is used to calculate wall rock boundary deformation and displacement field nephograms inside the wall rock for a given cavern height and width. A comparison with ANSYS numerical software results suggests that the theoretical solution and numerical solution exhibit identical trends, thereby demonstrating the method's validity. This method greatly improves the computing accuracy and reduces the difficulty in solving for cavern boundary and internal wall rock displacements. The proposed method provides a theoretical guide for controlling cavern wall rock deformation failure.

  4. Microbial induced corrosion in French concept of nuclear waste underground disposal

    International Nuclear Information System (INIS)

    Feron, D.; Crusset, D.

    2014-01-01

    The objective of this paper is to give a short overview of how the bacteria, that may influence the corrosion behaviour of metals and alloys, are taken into account in the French concept of geological repository. It is important to underline that microbial induced corrosion is not a new corrosion phenomena but the presence of bacteria may modify (increase or decrease) anodic or cathodic corrosion reactions. In aerobic conditions, high corrosion rates may be obtained due to the bio-oxidation of pyrites. Under anaerobic conditions (longer period), bacteria may have negative (localised corrosion) or positive (consumption of hydrogen) effects. The mixed conditions (with and without oxygen) may be the most dangerous period for localised corrosion of metals and alloys due to the coupling and galvanic corrosion phenomena enhanced by aerobic and anaerobic bacteria. The first conclusions lead to consider that MIC is a 'short term' issue rather than a long term one. (authors)

  5. Transient behaviour of deep underground salt caverns

    International Nuclear Information System (INIS)

    Karimi-Jafari, M.

    2007-11-01

    This work deals with the transient behaviour of deep underground salt caverns. It has been shown that a cavern is a complex system, in which there are mechanical, thermal, chemical and hydraulic evolutions. The importance of the transient evolutions, particularly the role of the 'reverse' creep in the interpretation of the tightness test in a salt cavern is revealed. Creep is characterized by a formulation of the behaviour law which presents the advantage, in a practical point of view, to only have a reduced number of parameters while accounting of the essential of what it is observed. The initiation of the rupture in the effective traction in a salt cavern rapidly pressurized is discussed. A model fitted to a very long term behaviour (after abandonment) is developed too. In this case too, a lot of phenomena, more or less coupled, occur, when the existing literature took only into account some phenomena. (O.M.)

  6. Liabilities for the decommissioning and disposal in the nuclear area. Analysis and concept of reformation; Rueckstellungen fuer Rueckbau und Entsorgung im Atombereich. Analyse und Reformkonzept

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Bettina [Umweltministerium Schleswig-Holstein, Kiel (Germany)

    2012-06-15

    The contribution under consideration examines the adequacy of the reserves for decommissioning / dismantling and disposal in order to finance long-term tasks. A reform concept is presented. The two key components of the reformation are the establishment of a public fund for the long-term obligations and a stronger insolvency protection of medium-term nuclear liabilities.

  7. Civil Engineering in the ATLAS cavern

    CERN Multimedia

    Laurent Guiraud

    2000-01-01

    Ghostly figures can be seen wandering the cavern that will eventually house the ATLAS experiment, part of the LHC at CERN. Quite fitting since the detector will hunt the illusive 'ghostly' particles, such as the Higgs boson and dark matter. These engineers are excavating the huge cavern that has to be anchored from above as the detector will fill so much space that there is no room for support pillars.

  8. Digging a cavern for a titan

    CERN Multimedia

    Patrice Loiez

    1999-01-01

    Civil engineers work 100 m underground near the France-Swiss border on the cavern that will soon house ATLAS, one of the experiments on CERN's new LHC accelerator. All personnel and equipment must be lowered by crane down the access shaft. When completed this cavern will have one of the largest spans constructed at 35 m, which required the roof to be supported by large steel anchors buried in concrete.

  9. Characteristics and treatment of cavernous malformations

    International Nuclear Information System (INIS)

    Takagi, Kenji; Ishida, Mitsuaki; Okabe, Hidetoshi; Nozaki, Kazuhiko

    2013-01-01

    Cavernous malformations are clusters of dilated sinusoidal channels with thin walls devoid of elastin and smooth muscle. They have no intervening brain tissue. They occur both in sporadic and familial forms. The genes responsible for cavernous malformations have been identified. Recent reports show that mutations of these responsible genes are involved not only in familial but also in sporadic forms. Germline and somatic mutations may occur before cavernous malformations develop (two-hit mechanism). Two patterns, with mulberry-like and hematoma-like appearances, are seen intraoperatively, and from histological findings, mulberry-like appearance may change into hematoma-like one by intralesional hemorrhage. Cavernous malformation treatments include open surgery and radiosurgery. Open surgery is usually chosen for the treatment of symptomatic hemorrhagic cavernous malformations because post-radiosurgical annual bleeding risks at the early phase seem to be higher than those of open surgery. If open surgery has a high risk because of lesion location, radiosurgery becomes an effective alternative treatment. Brainstem cavernous malformations have high annual bleeding and re-bleeding incidence, so if the lesion is accessible with low risk, open surgery is recommended. (author)

  10. Sequestration of CO2 in salt caverns

    International Nuclear Information System (INIS)

    Dusseault, M.B.; Rothenburg, L.; Bachu, S.

    2002-01-01

    The greenhouse effect is thought to be greatly affected by anthropogenic and naturally generated gases, such as carbon dioxide. The reduction of greenhouse gas emissions in the atmosphere could be effected through the permanent storage of carbon dioxide in dissolved salt caverns. A large number of suitable salt deposits are located in Alberta, especially the Lotsberg Salt of east-central Alberta. A major advantage of this deposit is its proximity to present and future point sources of carbon dioxide associated with fossil fuel development projects. Using the perspective of the long term fate of the stored carbon dioxide, the authors presented the characteristics of the Lotsberg Salt and the overlying strata. A high level of security against leakage and migration of the gas back to the biosphere is ensured by several features discussed in the paper. The authors propose a procedure that would be applicable for the creation, testing, and filling of a salt cavern. Achieving a long term prediction of the behavior of the cavern during slow closure, coupled to the pressure and volume behavior of the gas within the cavern represents the critical factor. The authors came up with an acceptable prediction by using a semi-analytical model. The use of salt caverns for the permanent sequestration of carbon dioxide has not yet faced technical obstacles that would prevent it. The authors argue that sequestration of carbon dioxide in salt caverns represents an environmentally acceptable option in Alberta. 11 refs., 3 figs

  11. User`s manual for the CC3 computer models of the concept for disposal of Canada`s nuclear fuel waste

    Energy Technology Data Exchange (ETDEWEB)

    Dougan, K D; Wojciechowski, L C

    1995-06-01

    Atomic Energy of Canada Limited (AECL) is assessing a concept for disposing of CANDU reactor fuel waste in a vault deep in plutonic rock of the Canadian Shield. A computer program called the Systems Variability Analysis Code (SYVAC) has been developed as an analytical tool for the postclosure (long-term) assessment of the concept, and for environmental assessments of other systems. SYVAC3, the third generation of the code, is an executive program that directs repeated simulation of the disposal system, which is represented by the CC3 (Canadian Concept, generation 3) models comprising a design-specific vault, a site-specific geosphere and a biosphere typical of the Canadian Shield. (author). 23 refs., 7 tabs., 21 figs.

  12. Alternative waste management concept for medium and low level wastes by in-situ solidification

    International Nuclear Information System (INIS)

    Kraemer, R.

    1982-01-01

    Since 1976, a German R and D project has been carried out to find an alternative concept for the treatment and disposal of MLW and LLW arising mainly in the planned German reprocessing plant and other nuclear facilities (LWR, fuel fabrication, R and D establishments). The main feature of this concept is an in-situ solidification of preconditioned waste granules in large salt caverns located in the deep geological underground, thus avoiding such non-radioactive ballast as lost concrete shielding and container material. (orig./RW)

  13. Consequences of the safety requirement retrieval on existing disposal concepts and requirements to new concepts. Final report; Auswirkungen der Sicherheitsanforderungen Rueckholbarkeit auf existierende Einlagerungskonzepte und Anforderungen an neue Konzepte. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Bollingerfehr, W.; Herold, P.; Doerr, S.; Filbert, W. [DBE Technology GmbH, Peine (Germany)

    2014-02-15

    In summer 2013 the German Federal Parliament (Bundestag) has restarted the search or a final repository site for high-level radioactive wastes by law. The study is concerned with the consequences of retrieval as additional safety requirement for disposal concepts. Based to the actual knowledge the study concludes that for all possible host rocks (salt, clay and crystalline rock) retrieval is technically possible. Considerable planning effort will be necessary to allow the demonstration of technical feasibility and the reliability of retrieval concepts.

  14. Dose concepts and the achievability of protection for the disposal of long-lived solid waste according to ICRP

    International Nuclear Information System (INIS)

    Sugier, A.; Schneider, Th.

    2010-01-01

    excess of risk resulting from the exposure of the involved population. In this perspective, ICRP has considered it was neither its responsibility nor a wise position to establish evolutionary scenarios for the health of future generations, which would be among the requirements for converting this general appreciation into an actual prediction of health effects. For long-term situations the relevant concept is potential exposure although the situation is planned. According to ICRP 103, long lived waste disposal should be dealt with as a planned exposure situation, and the resulting exposures in the long term should be considered as potential exposures. This leads to the use of a risk constraint in implementing the optimisation principle, which implies the consideration of the dose and the associated probability of occurrence for each process or event corresponding to the scenario of exposure. The same level of protection should be achieved for future generations as for present generations. The position of the ICRP on the interpretation of the quote by ICRP 81 that 'individuals and populations in the future should be afforded at least at the same level of protection from actions taken today as is the current generation' is that the risk resulting from the evolution of the disposal system should be as low as reasonably achievable below a selected risk constraint. In the demonstration of compliance (performance assessment), which may differ when dealing with natural processes vs. human intrusion, the objective is not to attempt to estimate a radiation detriment for future individuals but rather to test the weaknesses and the robustness of the disposal system. The goal is to compare disposal options. Calculated doses to future individuals should be regarded as indicators of safety. In ICRP 103 it is stated that 'in the decision-making process, owing to the increasing uncertainties, giving less weight to very low doses and to doses received in the distant future could be

  15. DURAL CAROTID-CAVERNOUS FISTULAS

    Directory of Open Access Journals (Sweden)

    Barbara Cvenkel

    2002-12-01

    Full Text Available Background. Dural carotid-cavernous sinus fistulas (CCF are communications fed by meningeal branches of the intracavernous internal carotid artery (ACI or/and external carotid artery (ACE. In contrast to typical CCF, the arteriovenous shunting of blood is usually low flow and low pressure. Spontaneous dural CCF are more common in postmenopausal women. Aetiology is unknown, but congenital malformation or rupture of thin-walled dural arteries within venous sinuses is believed to be the cause.Case reports. 3 cases lacking the typical clinical signs of CCF who had been treated as chronic conjunctivitis, myositis of the extraocular muscle and orbital pseudotumour are presented. Clinical presentation depends on the direction and magnitude of fistular flow and on the anatomy of the collateral branches. If increased blood flow is directed anteriorly in ophthalmic veins the signs of orbito-ocular congestion are present (»redeyed shunt syndrome«. Drainage primarly in the inferior petrosal sinus may cause painful oculomotor and abducens palsies without signs of ocular congestion (»white-eyed shunt syndrome«. Also different therapeutic approaches as well as possible complications are described.Conclusions. For definite diagnosis angiography is obligatory and is also therapeutic as one third to one half of dural CCF close spontaneously. Because of potential severe eye and systemic complications, surgical intervention is indicated only in cases with uncontrolled secondary glaucoma and hypoxic retinopathy.

  16. Analysis of cavern stability at the West Hackberry SPR site.

    Energy Technology Data Exchange (ETDEWEB)

    Ehgartner, Brian L.; Sobolik, Steven Ronald

    2009-05-01

    This report presents computational analyses that simulate the structural response of caverns at the Strategic Petroleum Reserve (SPR) West Hackberry site. The cavern field comprises 22 caverns. Five caverns (6, 7, 8, 9, 11) were acquired from industry and have unusual shapes and a history dating back to 1946. The other 17 caverns (101-117) were leached according to SPR standards in the mid-1980s and have tall cylindrical shapes. The history of the caverns and their shapes are simulated in a three-dimensional geomechanics model of the site that predicts deformations, strains, and stresses. Future leaching scenarios corresponding to oil drawdowns using fresh water are also simulated by increasing the volume of the caverns. Cavern pressures are varied in the model to capture operational practices in the field. The results of the finite element model are interpreted to provide information on the current and future status of subsidence, well integrity, and cavern stability. The most significant results in this report are relevant to Cavern 6. The cavern is shaped like a bowl with a large ceiling span and is in close proximity to Cavern 9. The analyses predict tensile stresses at the edge of the ceiling during repressuization of Cavern 6 following workover conditions. During a workover the cavern is at low pressure to service a well. The wellhead pressures are atmospheric. When the workover is complete, the cavern is repressurized. The resulting elastic stresses are sufficient to cause tension around the edge of the large ceiling span. With time, these stresses relax to a compressive state because of salt creep. However, the potential for salt fracture and propagation exists, particularly towards Cavern 9. With only 200 ft of salt between the caverns, the operational consequences must be examined if the two caverns become connected. A critical time may be during a workover of Cavern 9 in part because of the operational vulnerabilities, but also because dilatant damage is

  17. Social Sustainability of Provinces in China: A Data Envelopment Analysis (DEA Window Analysis under the Concepts of Natural and Managerial Disposability

    Directory of Open Access Journals (Sweden)

    Toshiyuki Sueyoshi

    2017-11-01

    Full Text Available Natural and managerial disposability are two important strategic concepts, whose priorities are economic prosperity and environmental protection, respectively. This study defines social sustainability as the simultaneous achievement of economic prosperity and environmental protection, and then assesses the degree of social sustainability across provinces in China. In addition, this study combines the concepts of natural and managerial disposability with Data Envelopment Analysis window analysis. The method allows for frontier shifts among different time periods and thus can provide more stable and reliable results. This method is applied to assess the energy and environmental performances across the provinces of China during 2003–2014, and provides detailed information about provincial variations, which are valuable and important to policy makers (especially for those in local governments. This study identifies three important findings. First, there were no significant improvements in China’s environmental performance during the analysis periods, since, historically, the governments have not paid enough attention to environmental protection. Second, there are increasing trends in the provincial gaps regarding the environmental performance. In this regard, the central government should help the poor provinces to protect the environment. Third, there are significant differences between the results obtained under natural disposability and those obtained under managerial disposability, since they have different priorities regarding the operational and the environmental performances. Thus, significant contributions can be made by eco-technology progress combined with managerial performance improvements by business leaders and policy makers. This can be a new policy direction for the Chinese government.

  18. Emerging concepts and requirements for the long-term management of non-radioactive hazardous wastes - would geological disposal be an appropriate solution for some of these wastes

    International Nuclear Information System (INIS)

    Rein, K. von

    1994-01-01

    This work deals with the emerging concepts and requirements for the long-term management of non-radioactive hazardous wastes. After some generalities on the pollution of natural environment and the legislations taken by the swedish government the author tries to answer to the question : would geological disposal be an appropriate solution for the non-radioactive hazardous wastes? Then is given the general discussion of the last three articles concerning the background to current environmental policies and their implementation and more particularly the evolution and current thoughts about environmental policies, the managing hazardous activities and substances and the emerging concepts and requirements for the long-term management of non-radioactive hazardous wastes. Comments and questions concerning the similarity or otherwise between the present position of radioactive waste disposal and the background to current environmental policies are indicated. (O.L.)

  19. Indirect carotid- cavernous fistula — embolisation using the superior ...

    African Journals Online (AJOL)

    Kurt

    MD, FRCS (C). Division of Neurosurgery. Royal University Hospital. University of Saskatchewan. Saskatoon. Canada. Fig .1a. Left common carotid angiogram, AP view, showing the carotid-cavernous fistula. Note opaci- fication of the left cavernous sinus (arrow) and fill- ing of the right cavernous sinus (double arrows).

  20. Cavernous transformation of the portal vein

    International Nuclear Information System (INIS)

    Lehotska, V.; Dostalova, K.; Durkovsky, A.; Samal, V.

    1995-01-01

    In this contribution, the authors give an account of a rare case of a cavernous transformation of the portal vein that may have originated secondarily in a proliferative hematogenous disease with a polyglobulia and thrombosis in the periferal blood count as well as development of portal hypertension of a prehepatal type. The state of hyper-coagulation in a myeloproliferative disease may have lead to a chronic thrombosis of the portal vein with a subsequent malformation of the portal vein in terms of a cavernous transformation of the portal vein. The case is an interesting one because of the discrepancy between the gravity of the thrombotic complication and slightness of the symptoms in the clinical picture. The authors point out the importance of ultrasonography and computed tomography examination following the intravenous application of a water solution of a contrast medium in a morphologic diagnosing of a rare complication of a chronic thrombotic clot of the portal vein - the cavernous transformation. (authors)

  1. Underground disposal of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-08-15

    Disposal of low- and intermediate-level radioactive wastes by shallow land burial, emplacement in suitable abandoned mines, or by deep well injection and hydraulic fracturing has been practised in various countries for many years. In recent years considerable efforts have been devoted in most countries that have nuclear power programmes to developing and evaluating appropriate disposal systems for high-level and transuranium-bearing waste, and to studying the potential for establishing repositories in geological formations underlaying their territories. The symposium, organized jointly by the IAEA and OECD's Nuclear Energy Agency in cooperation with the Geological Survey of Finland, provided an authoritative account of the status of underground disposal programmes throughout the world in 1979. It was evidence of the experience that has been gained and the comprehensive investigations that have been performed to study various options for the underground disposal of radioactive waste since the last IAEA/NEA symposium on this topic (Disposal of Radioactive Waste into the Ground) was held in 1967 in Vienna. The 10 sessions covered the following topics: National programme and general studies, Disposal of solid waste at shallow depth and in rock caverns, underground disposal of liquid waste by deep well injection and hydraulic fracturing, Disposal in salt formations, Disposal in crystalline rocks and argillaceous sediments, Thermal aspects of disposal in deep geological formations, Radionuclide migration studies, Safety assessment and regulatory aspects.

  2. Assessment of management alternatives for LWR wastes. Volume 8. Cost and radiological impact associated with near-surface disposal of reactor waste (Spanish concept)

    International Nuclear Information System (INIS)

    Alamo Berna, S.; Sanchez Delgado, N.

    1993-01-01

    This report deals with the determination of the cost and the radiological impact associated with a near-surface disposal site (Spanish concept) for low and medium-level radioactive waste generated during operation of a 20 GWe nuclear park composed of LWRs for 30 years. This study is part of an overall theoretical exercise aimed at evaluating a selection of management routes for LWR waste based on economical and radiological criteria

  3. Assessment of management alternatives for LWR wastes. Volume 7. Cost and radiological impact associated with near-surface disposal of reactor waste (French concept)

    International Nuclear Information System (INIS)

    Malherbe, J.

    1993-01-01

    This report deals with the determination of the cost and the radiological impact associated with a near-surface disposal site (French concept) for low and medium-level radioactive waste generated during operation of a 20 GWe nuclear park composed of LWRs for 30 years. This study is part of an overall theoretical exercise aimed at evaluating a selection of management routes for LWR waste based on economical and radiological criteria

  4. Systematic Evaluation of Salt Cavern Well Integrity

    Science.gov (United States)

    Roberts, B. L.; Lord, D. L.; Lord, A. S.; Bettin, G.; Sobolik, S. R.; Park, B. Y.

    2017-12-01

    The U.S. Strategic Petroleum Reserve (SPR) holds a reserve of crude oil ( 700 million barrels) to help ease any interruptions in oil import to the United States. The oil is stored in a set of 63 underground caverns distributed across four sites along the U.S. Gulf Coast. The caverns were solution mined into salt domes at each of the four sites. The plastic nature of the salt is beneficial for the storage of crude oil as it heals any fractures that may occur in the salt. The SPR is responsible for operating and maintaining the nearly 120 wells used to access the storage caverns over operational lifetimes spanning decades. Salt creep can induce deformation of the well casing which must be remediated to insure cavern and well integrity. This is particularly true at the interface between the plastic salt and the rigid caprock. The Department of Energy, the SPR Management and Operations contractor, and Sandia National Laboratories has developed a multidimensional well-grading system for the salt cavern access wells. This system is designed to assign numeric grades to each well indicating its risk of losing integrity and remediation priority. The system consists of several main components which themselves may consist of sub-components. The main components consider such things as salt cavern pressure history, results from geomechanical simulations modeling salt deformation, and measurements of well casing deformation due to salt creep. In addition, the geology of the salt domes and their overlying caprock is also included in the grading. These multiple factors are combined into summary values giving the monitoring and remediation priority for each well. Sandia National Laboratories is a multimission laboratory managed and operated by National Technology and Engineering Solutions of Sandia LLC, a wholly owned subsidiary of Honeywell International Inc. for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-NA0003525.

  5. Analysis of cavern stability at the Bryan Mound SPR site.

    Energy Technology Data Exchange (ETDEWEB)

    Ehgartner, Brian L.; Sobolik, Steven Ronald

    2009-04-01

    This report presents computational analyses that simulate the structural response of caverns at the Strategic Petroleum Reserve Bryan Mound site. The cavern field comprises 20 caverns. Five caverns (1, 2, 4, and 5; 3 was later plugged and abandoned) were acquired from industry and have unusual shapes and a history dating back to 1946. The other 16 caverns (101-116) were leached according to SPR standards in the mid-1980s and have tall cylindrical shapes. The history of the caverns and their shapes are simulated in a 3-D geomechanics model of the site that predicts deformations, strains, and stresses. Future leaching scenarios due to oil drawdowns using fresh water are also simulated by increasing the volume of the caverns. Cavern pressures are varied in the model to capture operational practices in the field. The results of the finite element model are interpreted to provide information on the current and future status of subsidence, well integrity, and cavern stability. The most significant result in this report is relevant to caverns 1, 2, and 5. The caverns have non-cylindrical shapes and have potential regions where the surrounding salt may be damaged during workover procedures. During a workover the normal cavern operating pressure is lowered to service a well. At this point the wellhead pressures are atmospheric. When the workover is complete, the cavern is repressurized. The resulting elastic stresses are sufficient to cause tension and large deviatoric stresses at several locations. With time, these stresses relax to a compressive state due to salt creep. However, the potential for salt damage and fracturing exists. The analyses predict tensile stresses at locations with sharp-edges in the wall geometry, or in the case of cavern 5, in the neck region between the upper and lower lobes of the cavern. The effects do not appear to be large-scale, however, so the only major impact is the potential for stress-induced salt falls in cavern 5, potentially leading to

  6. Cavernous haemangioma mimicking as clitoral hypertrophy

    Directory of Open Access Journals (Sweden)

    Sajid Nayyar

    2014-01-01

    Full Text Available Haemangioma is the most common benign neoplasm of infantile age. It is most commonly located in head and neck region, trunk and extremities but very rarely it can be located at clitoris. However, it is very important to differentiate clitoral haemangioma from enlargement of the clitoris secondary to androgen excess. Only four cases of clitoromegaly caused by cavernous haemangioma have been reported in the literature so far. Herein, we report our experience with a 10-year-old girl who presented with clitoromegaly and normal hormonal assay that turned out to be clitoral cavernous haemangioma after histopathological examination of the clitoral mass.

  7. Low-level radioactive waste disposal in the United States: An overview of current commercial regulations and concepts

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.

    1993-08-01

    Commercial low-level radioactive waste disposal in the United States is regulated by the US Nuclear Regulatory Commission (NRC) under 10 CFR 61 (1991). This regulation was issued in 1981 after a lengthy and thorough development process that considered the radionuclide concentrations and characteristics associated with commercial low-level radioactive waste streams; alternatives for waste classification; alternative technologies for low-level radioactive waste disposal; and data, modeling, and scenario analyses. The development process also included the publication of both draft and final environmental impact statements. The final regulation describes the general provisions; licenses; performance objectives; technical requirements for land disposal; financial assurances; participation by state governments and Indian tribes; and records, reports, tests, and inspections. This paper provides an overview of, and tutorial on, current commercial low-level radioactive waste disposal regulations in the United States

  8. Safety assessment for radwaste disposal in Korea: Pt. 1

    International Nuclear Information System (INIS)

    Suh, I.S.; Park, H.H.; Han, K.W.; Hahn, P.S.

    1986-01-01

    A simplified safety analysis code has been established in order to provide a basic methodology for the preliminary selection of a disposal method. The disposal type selection is prerequisite to meet the requirements of low and intermediate level radwaste management program in Korea. The code covers resaturation and leaching, migration through fracture-porous media transport such that the rock cavern disposal option can be evaluated compared with that of shallow land burial

  9. Modeling deformation processes of salt caverns for gas storage due to fluctuating operation pressures

    Science.gov (United States)

    Böttcher, N.; Nagel, T.; Goerke, U.; Khaledi, K.; Lins, Y.; König, D.; Schanz, T.; Köhn, D.; Attia, S.; Rabbel, W.; Bauer, S.; Kolditz, O.

    2013-12-01

    In the course of the Energy Transition in Germany, the focus of the country's energy sources is shifting from fossil to renewable and sustainable energy carriers. Since renewable energy sources, such as wind and solar power, are subjected to annual, seasonal, and diurnal fluctuations, the development and extension of energy storage capacities is a priority in German R&D programs. Common methods of energy storage are the utilization of subsurface caverns as a reservoir for natural or artificial fuel gases, such as hydrogen, methane, or the storage of compressed air. The construction of caverns in salt rock is inexpensive in comparison to solid rock formations due to the possibility of solution mining. Another advantage of evaporite as a host material is the self-healing capacity of salt rock. Gas caverns are capable of short-term energy storage (hours to days), so the operating pressures inside the caverns are fluctuating periodically with a high number of cycles. This work investigates the influence of fluctuating operation pressures on the stability of the host rock of gas storage caverns utilizing numerical models. Therefore, we developed a coupled Thermo-Hydro-Mechanical (THM) model based on the finite element method utilizing the open-source software platform OpenGeoSys. Our simulations include the thermodynamic behaviour of the gas during the loading/ unloading of the cavern. This provides information on the transient pressure and temperature distribution on the cavern boundary to calculate the deformation of its geometry. Non-linear material models are used for the mechanical analysis, which describe the creep and self-healing behavior of the salt rock under fluctuating loading pressures. In order to identify the necessary material parameters, we perform experimental studies on the mechanical behaviour of salt rock under varying pressure and temperature conditions. Based on the numerical results, we further derive concepts for monitoring THM quantities in the

  10. Imaging diagnosis of dural and direct cavernous carotid fistulae

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Daniela dos; Monsignore, Lucas Moretti; Nakiri, Guilherme Seizem; Cruz, Antonio Augusto Velasco e; Colli, Benedicto Oscar; Abud, Daniel Giansante, E-mail: danisantos2404@gmail.com [Universidade de Sao Paulo (HCFMRP/USP), Ribeirao Preto, SP (Brazil). Faculdade de Medicina. Hospital das Clinicas

    2014-07-15

    Arteriovenous fistulae of the cavernous sinus are rare and difficult to diagnose. They are classified into dural cavernous sinus fistulae or direct carotid-cavernous fistulae. Despite the similarity of symptoms between both types, a precise diagnosis is essential since the treatment is specific for each type of fistula. Imaging findings are remarkably similar in both dural cavernous sinus fistulae and carotid-cavernous fistulae, but it is possible to differentiate one type from the other. Amongst the available imaging methods (Doppler ultrasonography, computed tomography, magnetic resonance imaging and digital subtraction angiography), angiography is considered the gold standard for the diagnosis and classification of cavernous sinus arteriovenous fistulae. The present essay is aimed at didactically presenting the classification and imaging findings of cavernous sinus arteriovenous fistulae. (author)

  11. Historical Cavern Floor Rise for All SPR Sites

    Energy Technology Data Exchange (ETDEWEB)

    Moriarty, Dylan Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-09-01

    The Strategic Petroleum Reserve (SPR) contains the largest supply is the largest stockpile of government-owned emergency crude oil in the world. The oil is stored in multiple salt caverns spread over four sites in Louisiana and Texas. Cavern infrastructure near the bottom of the cavern can be damaged from vertical floor movement. This report presents a comprehensive history of floor movements in each cavern. Most of the cavern floor rise rates ranged from 0.5-3.5 ft/yr, however, there were several caverns with much higher rise rates. BH103, BM106, and BH105 had the three highest rise rates. Information from this report will be used to better predict future vertical floor movements and optimally place cavern infrastructure. The reasons for floor rise are not entirely understood and should be investigated.

  12. Subdural hematoma from a cavernous malformation.

    Science.gov (United States)

    Schmitt, Anne J; Mitha, Alim P; Germain, Rasha; Eschbacher, Jennifer; Spetzler, Robert F

    2014-01-01

    To present a case of a cavernous malformation presenting with a subdural hematoma. A 27-year-old woman was admitted with progressively worsening headache, vomiting, weakness, and word-finding difficulties 1 week after she was discharged from an outside hospital, where she was managed conservatively for a presumed traumatic subdural hematoma. Computed tomography revealed an enlarging subacute left hemispheric subdural hematoma for which she underwent drill craniostomy. Postprocedural magnetic resonance imaging showed a posterior left temporal lobe mass consistent with a cavernous malformation juxtaposed with the subdural hematoma. Craniotomy for resection of the lesion was performed. She had an uncomplicated postoperative course and experienced a good recovery. The signs and symptoms, diagnostic imaging, and intraoperative findings suggest that the subdural hematoma was caused by extralesional hemorrhage of the cavernous malformation, which is a rare finding associated with these malformations. The clinical course, radiologic, and intraoperative findings suggest that the subdural hemorrhage was caused by extralesional hemorrhage of the cavernous malformation. Copyright © 2014 Elsevier Inc. All rights reserved.

  13. Air quality in the Carlsbad cavern

    International Nuclear Information System (INIS)

    Cheng, Yung-Seng; Chen, Tou-Rong; Wasiolek, P.T.

    1994-01-01

    The air quality in the Carlsbad Cavern has been investigated, but there are no reports on radon progeny and aerosols. The purpose of this experiment was to determine the activity size distribution of radon progeny and the air exchange rate inside the Cavern. Teams from ITRI and New Mexico Institute of Mining and Technology (NMT) conducted the field study in July 1994. The ITRI graded diffusion battery (GDB) was used to determine the activity size distribution, progeny concentration, equilibrium factor, and unattached fraction of the radon progeny. The design, calibration, and performance of the GDB have been described. For this study, each stage of the GDB contained one stainless steel screen, with the mesh sizes arranged in a series of 30, 50, 145, 200, and 635 mesh from the air inlet to the outlet. A 47-nm type A/E glass fiber filter was used to collect all particles that penetrated the screens. The flow rate was 5 L/min. The average ventilation rate in the cavern is 0.0026 V/hr. Our results showed that the cavern atmosphere may be quite different from other underground environments. The atmosphere in the summer is stable and relatively free of airborne particles, partly due to the extremely slow air exchange rate

  14. Vascular permeability in cerebral cavernous malformations

    DEFF Research Database (Denmark)

    Mikati, Abdul G; Khanna, Omaditya; Zhang, Lingjiao

    2015-01-01

    Patients with the familial form of cerebral cavernous malformations (CCMs) are haploinsufficient for the CCM1, CCM2, or CCM3 gene. Loss of corresponding CCM proteins increases RhoA kinase-mediated endothelial permeability in vitro, and in mouse brains in vivo. A prospective case-controlled observ...

  15. The ATLAS cavern in the spotlight

    CERN Multimedia

    On Wednesday, 4th June, the President of the Swiss Confederation, Pascal Couchepin, inaugurated the world's largest experimental cavern, which is to house the ATLAS detector in 2007, and announced Switzerland's gift to CERN of the "Palais de l'Equilibre".

  16. Special people visit the ATLAS cavern

    CERN Multimedia

    Muriel

    ATLAS has been host to many important visitors lately. Here are a selected few: Professor Stephen Hawking visits the ATLAS cavern On Tuesday 26 September 2006 the ATLAS Collaboration was honoured by a very special visit to the detector in the underground cavern. We were pleased to guide Professor Stephen Hawking, the famous cosmologist holding the post of Lucasian Professor of Mathematics at Cambridge University (position held by Isaac Newton in the 17th century), on a tour of the ATLAS pit and the LHC tunnel. The visit was accompanied by a few colleagues from the CERN Theory group, and was only possible thanks to the professional assistance of Olga Beltramello and Bernard Lebegue, who had also taken care of all the necessary preparatory work in the cavern. Professor Hawking was very keen to check for himself the status of the detector installation, and he admired, in particular, the spectacular TGC big wheel on side C. (left) Stephen Hawking in the ATLAS cavern side-C (right) and in the LHC tunnel...

  17. A concept to combine DOE waste minimization goals with commercial utility needs for a universal container system for spent nuclear fuel storage, transportation, and disposal

    International Nuclear Information System (INIS)

    Falci, F.P.; Smith, M.L.; Sorenson, K.B.

    1993-01-01

    The concept of storing, transporting, and disposing of spent fuel using a single package has obvious advantages. Coupling this concept with using contaminated scrap metal from the EM Complex will help reduce a significant portion of waste that would otherwise need to be packaged, stored, and disposed of as low level radioactive waste. Assuming a material of cost of $1 per pound for 800,000 tons of metal needed for universal containers, the potential material cost savings from manufacturing these containers from what would otherwise be a waste product is about $1.5 billion. Clearly, this concept is novel and has significant obstacles that need to be addressed and overcome; particularly in the regulatory arena. However, the potential benefits warrant the evaluation of the proposal on several fronts. DOE OCRWM should seriously consider the universal cask concept for management of spent fuel. DOE EM should pursue the development of melting contaminated scrap for the manufacture of casks. Finally, EM and OCRWM should cooperate on the evaluation of using EM contaminated scrap metal for the manufacture of universal casks for OCRWM spent fuel

  18. Identification of contaminants of concern for the postclosure assessment of the concept for the disposal of Canada`s nuclear fuel waste

    Energy Technology Data Exchange (ETDEWEB)

    Goodwin, B W; Mehta, K K

    1994-03-01

    The concept for the disposal of Canada`s nuclear fuel waste involves the isolation of irradiated fuel in corrosion-resistant containers emplaced din din a vault located deep in crystalline rock of the Canadian Shield. To estimate potential impacts on members of a critical group far into the future, a postclosure assessment evaluates the long-term safety of the concept. Although the nuclear fuel waste from CANDU (Canada Deuterium Uranium) power generating stations contains several hundreds of potentially toxic radionuclides and chemical elements (referred to as contaminants), many of these would not lead to significant impacts. This report provides an upper bound on estimated radiation dose and chemical toxicity effects on humans from all potentially toxic contaminants, and it identifies those that require detailed consideration in the postclosure assessment. This report also examines the origins and properties of the contaminants. Properties of interest include radioactive half-life, inventory, mobility in groundwaters and sorption on rock, degree of toxicity, and precursors and progeny (or parents and daughters) for members of a decay chain. The report considers how these properties affect the behaviour of different contaminants in different parts of the disposal system. The discussion leads to suggested methods of treatment of different contaminants when simulating their fate within the disposal system. In particular, recommendations are made on how the actinide decay chains can be simplified for study in the postclosure assessment. (author). 56 refs., 22 tabs., 12 figs.

  19. Retrievability - a matter of public acceptance? Reflections on the public review of the proposed nuclear fuel waste disposal concept in Canada

    International Nuclear Information System (INIS)

    Riverin, G.

    2000-01-01

    Environmental assessment has been used as a planning tool in Canada for almost three decades. Public participation, one of its fundamental principles, is at the heart of environmental assessment in our country. To date, approximately 12 large projects related to nuclear energy have been the subject of public reviews by independent panels of experts appointed by the Government of Canada. These include: the development of uranium mines in Northern Saskatchewan; the construction and operation of two CANDU reactors in New-Brunswick, the second of which was never constructed; proposed uranium hexafluoride refineries in Ontario and Saskatchewan; expansion of a dry storage facility for nuclear spent fuel in Quebec; and decommissioning of uranium mine tailings areas in Ontario. All of the assessments mentioned above were conducted under the environmental assessment regimes of 1975 and 1984 that preceded the Canadian Environmental Assessment Act (1995). One of the public reviews of particular interest to this workshop is that of the proposed concept for deep geological disposal of nuclear fuel waste in Canada. This paper focuses exclusively on the public review of the Nuclear Fuel Waste Disposal Concept developed by Atomic Energy of Canada Limited (AECL), particularly as it relates to public acceptance of retrievability. The paper first describes the historical context in which AECL's concept was developed prior to the public review. It then briefly outlines the changes in the societal context that occurred between the time when decisions were made to proceed with the development of the concept in 1978 and the time when public hearings were held in 1996-1997 and the panel report was presented to the government in 1998. It also provides a short description of the concept itself. The paper then presents a discussion of the arguments used by the public in the panel review, arguments, which demonstrate a decrease in confidence in a concept lacking effective postclosure

  20. Preclosure probabilistic assessment of the Canadian concept for used fuel disposal focussing on key radionuclides and exposure pathways for routine emissions

    International Nuclear Information System (INIS)

    Russell, S.B.

    1996-01-01

    The Canadian Nuclear Fuel Waste Management Program was initiated in 1978 to develop a concept for safe disposal of nuclear fuel waste (intact used nuclear fuel or high-level waste from any future reprocessing of used fuel) from CANDU reactors. The concept includes the immobilization of nuclear fuel waste and emplacement of the waste in an engineered vault, deep underground in a stable rock formation within the Canadian Shield. In 1994, AECL submitted an environmental and safety assessment of the disposal concept in the form of an Environmental Impact Statement or EIS for regulatory, scientific and public reviews. Ontario Hydro's contribution to the EIS included the preclosure assessment consisting of the safety and environmental implications of the construction, operation and decommissioning (closure) of a conceptual used-fuel disposal centre (UFDC), plus transportation of used fuel from storage at reactor sites to the UFDC. In the EIS, the environmental impact from routine emissions from the UFDC during the operation phase was calculated in a deterministic mode using single-valued constants representing the geometric mean or the average value of the input parameters in the preclosure model PREAC (Preclosure Radiological Environmental Assessment Code). A qualitative estimate of the range of uncertainty associated with the preclosure model dose predictions was about an order of magnitude based on a review of the expected range of input parameter values. This paper examines the time-behaviour of the preclosure system and provides a quantitative estimate of the uncertainty, as determined through the use of probabilistic techniques, associated with the potential radiological impact from the same chronic UFDC radionuclide emissions during the preclosure phase. The individual dose to a member of the critical group assumed to be living near the UFDC has been assessed for selected key radionuclides and exposure pathways identified in the EIS. The purpose of this post

  1. The association of carotid cavernous fistula with Graves′ ophthalmopathy

    Directory of Open Access Journals (Sweden)

    Ozlem Celik

    2013-01-01

    Full Text Available Graves′ ophthalmopathy (GO is one of the frequent manifestations of the disorder which is an inflammatory process due to fibroblast infiltration, fibroblast proliferation and accumulation of glycosaminoglycans. Eye irritation, dryness, excessive tearing, visual blurring, diplopia, pain, visual loss, retroorbital discomfort are the symptoms and they can mimic carotid cavernous fistulas. Carotid cavernous fistulas are abnormal communications between the carotid arterial system and the cavernous sinus. The clinical manifestations of GO can mimic the signs of carotid cavernous fistulas. Carotid cavernous fistulas should be considered in the differential diagnosis of the GO patients especially who are not responding to the standard treatment and when there is a unilateral or asymmetric eye involvement. Here we report the second case report with concurrent occurrence of GO and carotid cavernous fistula in the literature.

  2. The association of carotid cavernous fistula with Graves’ ophthalmopathy

    Science.gov (United States)

    Celik, Ozlem; Buyuktas, Deram; Islak, Civan; Sarici, A Murat; Gundogdu, A Sadi

    2013-01-01

    Graves’ ophthalmopathy (GO) is one of the frequent manifestations of the disorder which is an inflammatory process due to fibroblast infiltration, fibroblast proliferation and accumulation of glycosaminoglycans. Eye irritation, dryness, excessive tearing, visual blurring, diplopia, pain, visual loss, retroorbital discomfort are the symptoms and they can mimic carotid cavernous fistulas. Carotid cavernous fistulas are abnormal communications between the carotid arterial system and the cavernous sinus. The clinical manifestations of GO can mimic the signs of carotid cavernous fistulas. Carotid cavernous fistulas should be considered in the differential diagnosis of the GO patients especially who are not responding to the standard treatment and when there is a unilateral or asymmetric eye involvement. Here we report the second case report with concurrent occurrence of GO and carotid cavernous fistula in the literature. PMID:23571267

  3. Cavernous angioma associated with ipsilateral hippocampal sclerosis

    International Nuclear Information System (INIS)

    Okujava, M.; Ebner, A.; Schmitt, J.; Woermann, F.G.

    2002-01-01

    We report two cases with extratemporal cavernous angioma (CA) and coexisting ipsilateral hippocampal sclerosis. Classically dual pathology is defined as the association of hippocampal sclerosis with an extrahippocampal lesion. Subtle changes in hippocampus might be overlooked in the presence of an unequivocal extrahippocampal abnormality. Seizure outcome after epilepsy surgery in cases with dual pathology is less favourable if only one of the lesions is removed. Dual pathology must always be considered in diagnostic imaging of patients with intractable epilepsy and CA. (orig.)

  4. Cavernous angioma associated with ipsilateral hippocampal sclerosis

    Energy Technology Data Exchange (ETDEWEB)

    Okujava, M [Institute of Radiology and Interventional Diagnostics, Tbilisi (Georgia); Ebner, A; Schmitt, J; Woermann, F G [Bethel Epilepsy Centre, Mara Hospital, Bielefeld (Germany)

    2002-07-01

    We report two cases with extratemporal cavernous angioma (CA) and coexisting ipsilateral hippocampal sclerosis. Classically dual pathology is defined as the association of hippocampal sclerosis with an extrahippocampal lesion. Subtle changes in hippocampus might be overlooked in the presence of an unequivocal extrahippocampal abnormality. Seizure outcome after epilepsy surgery in cases with dual pathology is less favourable if only one of the lesions is removed. Dual pathology must always be considered in diagnostic imaging of patients with intractable epilepsy and CA. (orig.)

  5. Design and operation problems related to water curtain system for underground water-sealed oil storage caverns

    Directory of Open Access Journals (Sweden)

    Zhongkui Li

    2016-10-01

    Full Text Available The underground water-sealed storage technique is critically important and generally accepted for the national energy strategy in China. Although several small underground water-sealed oil storage caverns have been built in China since the 1970s, there is still a lack of experience for large-volume underground storage in complicated geological conditions. The current design concept of water curtain system and the technical instruction for system operation have limitations in maintaining the stability of surrounding rock mass during the construction of the main storage caverns, as well as the long-term stability. Although several large-scale underground oil storage projects are under construction at present in China, the design concepts and construction methods, especially for the water curtain system, are mainly based on the ideal porosity medium flow theory and the experiences gained from the similar projects overseas. The storage projects currently constructed in China have the specific features such as huge scale, large depth, multiple-level arrangement, high seepage pressure, complicated geological conditions, and high in situ stresses, which are the challenging issues for the stability of the storage caverns. Based on years' experiences obtained from the first large-scale (millions of cubic meters underground water-sealed oil storage project in China, some design and operation problems related to water curtain system during project construction are discussed. The drawbacks and merits of the water curtain system are also presented. As an example, the conventional concept of “filling joints with water” is widely used in many cases, as a basic concept for the design of the water curtain system, but it is immature. In this paper, the advantages and disadvantages of the conventional concept are pointed out, with respect to the long-term stability as well as the safety of construction of storage caverns. Finally, new concepts and principles

  6. Necrotizing Fasciitis of the Nose Complicated with Cavernous Sinus Thrombosis

    Directory of Open Access Journals (Sweden)

    D. Swaminath

    2014-01-01

    Full Text Available Necrotizing fasciitis is a rapidly progressive life threatening bacterial infection of the skin, the subcutaneous tissue, and the fascia. We present a case of necrotizing fasciitis involving the nose complicated by cavernous sinus thrombosis. Few cases of septic cavernous sinus thrombosis have been reported to be caused by cellulitis of the face but necrotizing fasciitis of the nose is rare. It is very important to recognize the early signs of cavernous thrombosis. Treatment for septic cavernous sinus thrombosis is controversial but early use of empirical antibiotics is imperative.

  7. Allowable pillar to diameter ratio for strategic petroleum reserve caverns.

    Energy Technology Data Exchange (ETDEWEB)

    Ehgartner, Brian L.; Park, Byoung Yoon

    2011-05-01

    This report compiles 3-D finite element analyses performed to evaluate the stability of Strategic Petroleum Reserve (SPR) caverns over multiple leach cycles. When oil is withdrawn from a cavern in salt using freshwater, the cavern enlarges. As a result, the pillar separating caverns in the SPR fields is reduced over time due to usage of the reserve. The enlarged cavern diameters and smaller pillars reduce underground stability. Advances in geomechanics modeling enable the allowable pillar to diameter ratio (P/D) to be defined. Prior to such modeling capabilities, the allowable P/D was established as 1.78 based on some very limited experience in other cavern fields. While appropriate for 1980, the ratio conservatively limits the allowable number of oil drawdowns and hence limits the overall utility and life of the SPR cavern field. Analyses from all four cavern fields are evaluated along with operating experience gained over the past 30 years to define a new P/D for the reserve. A new ratio of 1.0 is recommended. This ratio is applicable only to existing SPR caverns.

  8. MRI findings of intracranial cavernous malformations

    International Nuclear Information System (INIS)

    Han, Byoung Hee; Kim, Dong Ik; Cho, Yong Kuk

    1995-01-01

    To analyze the variable MRI features and clinical significance of intracranial cavernous malformations. Forty patients(mean age 35.4) with cavernous malformation were evaluated by MRI. Eleven patients were surgically confirmed. Cavernous malformations were divided into four categories on the basis of the MR imaging characteristics, especially on T2-weighted image. Type I lesion was defined as an extralesional subacute hemorrhage outside the low signal rim, type II as an intralesional hemorrhage surrounded by low signal rim, type III lesion as an intralesional thrombosis with variegated central core surrounded by low signal rim, and type IV lesion as a focal old hemorrhagic core with small low signal intensity. Type IV was further divided into IVa and IVb, whether the lesion has small iso-or hypersignal central core (IVa) or not (IVb). Follow-up MRI was evaluated in 12 patients who were managed conservatively. Follow-up intervals ranged from 2 weeks to 29 months (mean 6 months). Total 80 lesions were detected in 40 patients. Multiple lesions were noted in 10 patients. The topography of the cavernous malformations was supratentorial in 75% and infratentorial in 23%. There were 10 lesions in type I, 15 in type II, 21 in type III, 14 in type IVa, and 20 in type IVb. Type I lesions mainly showed mass effect and edema. Type III lesions showed minimal contrast enhancements in 7 lesions on delayed images. Type II lesions showed the characteristics of both type I and type III lesions. On follow up images, decrease in size in 5, change of type in 7, rebleeding in 2 and no change in 12 lesions were demonstrated. Hemorrhage, edema and mass effect were combined in the cases of rebleeding. On follow-up study, the estimated risk of bleeding was 32.3%/person-year and 13.7%/lesion-year. Cavernous malformations show as variable appearance, on MR imaging suggesting variable stages of evolution. The MR morphologic classification and evaluation of secondary findings are helpful to

  9. Safety evaluation of geological disposal concepts for low and medium-level wastes in rock-salt (Pacoma project)

    International Nuclear Information System (INIS)

    Prij, J.; Van Dalen, A.; Roodbergen, H.A.; Slagter, W.; Van Weers, A.W.; Zanstra, D.A.; Glasbergen, P.; Koester, H.W.; Lembrechts, J.F.; Nijhof-Pan, I.; Slot, A.F.M.

    1991-01-01

    In the framework of the Performance Assessment of Confinements for MLW and Alpha Waste (PACOMA) the disposal options dealing with rock-salt are studied by GSF and ECN (with subcontract to RIVM). The overall objectives of these studies are to develop and demonstrate procedures for the radiological safety assessment of a deep repository in salt formations. An essential objective is to show how far appropriate choices of the repository design parameters can improve the performances of the whole system. The research covers two waste inventories (the Dutch OPLA and the PACOMA reference inventory), two disposal techniques (conventional and solution mining) and three types of formations (salt dome, pillow and bedded salt). An important part of the research has been carried out in the socalled VEOS project within the framework of the Dutch OPLA study. The methodology used in the consequence analysis is a deterministic one. The models and calculation tools used to perform the consequence analysis are the codes: EMOS, METROPOL and BIOS. The results are expressed in terms of dose rates and doses to individuals as well as to groups. Detailed information with respect to the input data and the results obtained with the three codes is given in three annexes to this final report

  10. Commercial potential of natural gas storage in lined rock caverns (LRC)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    The geologic conditions in many regions of the United States will not permit the development of economical high-deliverability gas storage in salt caverns. These regions include the entire Eastern Seaboard; several northern states, notably Minnesota and Wisconsin; many of the Rocky Mountain States; and most of the Pacific Northwest. In late 1997, the United States Department of Energy (USDOE) Federal Energy Technology Center engaged Sofregaz US to investigate the commercialization potential of natural gas storage in Lined Rock Caverns (LRC). Sofregaz US teamed with Gaz de France and Sydkraft, who had formed a consortium, called LRC, to perform the study for the USDOE. Underground storage of natural gas is generally achieved in depleted oil and gas fields, aquifers, and solution-mined salt caverns. These storage technologies require specific geologic conditions. Unlined rock caverns have been used for decades to store hydrocarbons - mostly liquids such as crude oil, butane, and propane. The maximum operating pressure in unlined rock caverns is limited, since the host rock is never entirely impervious. The LRC technology allows a significant increase in the maximum operating pressure over the unlined storage cavern concept, since the gas in storage is completely contained with an impervious liner. The LRC technology has been under development in Sweden by Sydkraft since 1987. The development process has included extensive technical studies, laboratory testing, field tests, and most recently includes a storage facility being constructed in southern Sweden (Skallen). The LRC development effort has shown that the concept is technically and economically viable. The Skallen storage facility will have a rock cover of 115 meters (375 feet), a storage volume of 40,000 cubic meters (250,000 petroleum barrels), and a maximum operating pressure of 20 MPa (2,900 psi). There is a potential for commercialization of the LRC technology in the United States. Two regions were studied

  11. Commercial potential of natural gas storage in lined rock caverns (LRC); FINAL

    International Nuclear Information System (INIS)

    NONE

    1999-01-01

    The geologic conditions in many regions of the United States will not permit the development of economical high-deliverability gas storage in salt caverns. These regions include the entire Eastern Seaboard; several northern states, notably Minnesota and Wisconsin; many of the Rocky Mountain States; and most of the Pacific Northwest. In late 1997, the United States Department of Energy (USDOE) Federal Energy Technology Center engaged Sofregaz US to investigate the commercialization potential of natural gas storage in Lined Rock Caverns (LRC). Sofregaz US teamed with Gaz de France and Sydkraft, who had formed a consortium, called LRC, to perform the study for the USDOE. Underground storage of natural gas is generally achieved in depleted oil and gas fields, aquifers, and solution-mined salt caverns. These storage technologies require specific geologic conditions. Unlined rock caverns have been used for decades to store hydrocarbons - mostly liquids such as crude oil, butane, and propane. The maximum operating pressure in unlined rock caverns is limited, since the host rock is never entirely impervious. The LRC technology allows a significant increase in the maximum operating pressure over the unlined storage cavern concept, since the gas in storage is completely contained with an impervious liner. The LRC technology has been under development in Sweden by Sydkraft since 1987. The development process has included extensive technical studies, laboratory testing, field tests, and most recently includes a storage facility being constructed in southern Sweden (Skallen). The LRC development effort has shown that the concept is technically and economically viable. The Skallen storage facility will have a rock cover of 115 meters (375 feet), a storage volume of 40,000 cubic meters (250,000 petroleum barrels), and a maximum operating pressure of 20 MPa (2,900 psi). There is a potential for commercialization of the LRC technology in the United States. Two regions were studied

  12. Recovery of opthalmoplegia associated with cavernous sinus dural arteriovenous fistulas after transvenous cavernous sinus packing

    Energy Technology Data Exchange (ETDEWEB)

    Xianli, Lv; Chuhan, Jiang; Youxiang, Li; Xinjian, Yang [Beijing Neurosurgical institute, Beijing Tiantan Hospital, Capital Medical University, 6, Tiantan Xili, Chongwen, Beijing (China); Wu Zhongxue, E-mail: ttyyzjb@sina.co [Beijing Neurosurgical institute, Beijing Tiantan Hospital, Capital Medical University, 6, Tiantan Xili, Chongwen, Beijing (China)

    2010-08-15

    Background: We report the recovery of ophthalmoplegia in 11 patients with cavernous sinus dural arteriovenous fistula (CSDAVF) after sinus packing at follow-up. Methods: Of 18 patients with CSDAVF treated with transvenous cavernous sinus packing between August 2002 and December 2007 at Beijing Tiantan Hospital, there were 9 patients with initial CNIII or CNVI dysfunction and 2 patients with CNVI dysfunction immediately after cavernous sinus packing selected and reevaluated. Results: Of 11 patients with CNIII or CNVI palsy, recovery was complete in 10. In 1 patient, complete CNVI palsy was unchanged because the CSDAVF was not cured. There were 6 men and 5 women with a mean age of 52.9 years. In 5 patients, CNVI palsy was associated with chemosis, proptosis and pulsatile tinnitus. Timing of treatment after onset of symptoms was from 4 to 35 days in 9 patients. All CSDAVFs were Barrow type D. Mean follow-up after treatment was 17.7 months (range, 2-54 months). Conclusion: CSDAVF-induced CNIII or CNVI palsies can be cured after cavernous sinus packing transvenously in most patients.

  13. Recovery of opthalmoplegia associated with cavernous sinus dural arteriovenous fistulas after transvenous cavernous sinus packing

    International Nuclear Information System (INIS)

    Lv Xianli; Jiang Chuhan; Li Youxiang; Yang Xinjian; Wu Zhongxue

    2010-01-01

    Background: We report the recovery of ophthalmoplegia in 11 patients with cavernous sinus dural arteriovenous fistula (CSDAVF) after sinus packing at follow-up. Methods: Of 18 patients with CSDAVF treated with transvenous cavernous sinus packing between August 2002 and December 2007 at Beijing Tiantan Hospital, there were 9 patients with initial CNIII or CNVI dysfunction and 2 patients with CNVI dysfunction immediately after cavernous sinus packing selected and reevaluated. Results: Of 11 patients with CNIII or CNVI palsy, recovery was complete in 10. In 1 patient, complete CNVI palsy was unchanged because the CSDAVF was not cured. There were 6 men and 5 women with a mean age of 52.9 years. In 5 patients, CNVI palsy was associated with chemosis, proptosis and pulsatile tinnitus. Timing of treatment after onset of symptoms was from 4 to 35 days in 9 patients. All CSDAVFs were Barrow type D. Mean follow-up after treatment was 17.7 months (range, 2-54 months). Conclusion: CSDAVF-induced CNIII or CNVI palsies can be cured after cavernous sinus packing transvenously in most patients.

  14. Integrated Disposal Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Located near the center of the 586-square-mile Hanford Site is the Integrated Disposal Facility, also known as the IDF.This facility is a landfill similar in concept...

  15. α-waste conditioning concepts on the basis of waste arisings, actinide distribution and their influence on final disposal products

    International Nuclear Information System (INIS)

    Krause, H.; Scheffler, K.

    1978-01-01

    Among the wastes arising from the reprocessing and Pu-fuel element fabrication plants, only seven waste streams contain the major part of the actinides going into the radioactive waste. It is shown that the liquid α-waste from fuel element fabrication, the high level liquid waste, and the active fraction of the medium level liquid waste can be incorporated into borosilicate glass. Wet combustion of solid burnable waste allows a relatively easy and complete recovery of plutonium. Leached hulls, sludges from feed clarification and solid non-combustible wastes can be incorporated into concrete. These treatment methods guarantee that only relatively small amounts of high quality α-bearing residues have to be disposed of

  16. Centrifuge and laboratory tests, modelling the penetrator concept for the disposal of HGW in deep ocean sediments

    International Nuclear Information System (INIS)

    Savvidou, C.; Schofield, A.N.

    1986-12-01

    The report is a summary of the work carried out at Cambridge University Engineering Department to investigate the geotechnical aspects of the subseabed disposal of heat generating waste. The problem of heat transfer and coupled consolidation around a heat source was studied both experimentally and numerically. Calculations of the temperature and pore pressure changes in the soil around a cylindrical heat source were made and verified by both laboratory tests and by centrifuge modelling at 100 times earth's gravity. It was shown that conduction was the major heat transfer process. The high velocity penetration of soil by projectiles was modelled on the Cambridge Geotechnical Centrifuge and this was followed by centrifuge tests in which there was subsequent heating of the projectile after firing. These dynamic tests showed that the projectile produced high pore pressures within the soil, which were quickly dissipated. (author)

  17. Status of work on the final repository concept concerning direct disposal of spent fuel rods in fuel rod casks (BSK)

    International Nuclear Information System (INIS)

    Filbert, W.; Wehrmann, J.; Bollingerfehr, W.; Graf, R.; Fopp, S.

    2008-01-01

    The reference concept in Germany on direct final storage of spent fuel rods is the burial of POLLUX containers in the final repository salt dome. The POLLUX container is self-shielded. The final storage concept also includes un-shielded borehole storage of high-level waste and packages of compacted waste. GNS has developed a spent fuel container (BSK-3) for unshielded borehole storage with a mass of 5.2 tons that can carry the fuel rods of three PWR reactors of 9 BWR reactors. The advantages of BSK storage include space saving, faster storage processes, less requirements concerning technical barriers, cost savings for self-shielded casks.

  18. Benign mass in tonsil- cavernous hemangioma.

    Science.gov (United States)

    Joseph, Sumitha; Prakash, M; Mohammed, Hafida K; Govar, Aberna

    2013-10-01

    Cavernous hemangioma is also called as 'ANGIOMA CAVERNOSUM' or 'CAVERNOMA' as benign lesion of blood vessels. They are similar to strawberry hemangioma but deeply situated. Although most often associated with skin it is also sometimes found in mucous membrane, brain and the viscera. The diagnosis of hemangiomas is mainly based on clinical evaluation . Isolated hemangiomas in the tonsillar tissue is a rare occurance. In this we report had a case of adult tonsillar hemangioma of left side associated with recurrent tonsillitis . He was effectively managed surgically without any complications.

  19. Cavernous hemangioma of the knee - case report

    OpenAIRE

    Weiss, Marcin; Dolata, Tomasz; Weiss, Waldemar; Maksymiak, Martyna; Kałużny, Krystian; Kałużna, Anna; Zukow, Walery; Hagner Derengowska, Magdalena

    2018-01-01

    Weiss Marcin, Dolata Tomasz, Weiss Waldemar, Maksymiak Martyna, Kałużny Krystian, Kałużna Anna, Zukow Walery, Hagner‑Derengowska Magdalena. Cavernous hemangioma of the knee - case report. Journal of Education, Health and Sport. 2018;8(4):318-325. eISNN 2391-8306. DOI http://dx.doi.org/10.5281/zenodo.1226645 http://ojs.ukw.edu.pl/index.php/johs/article/view/5438 The journal has had 7 points in Ministry of Science and Higher Education parametric evalu...

  20. Sewage sludge disposal at the city of Duesseldorf - Conception of co-combustion in a coal power plant; Klaerschlammentsorgung der Stadt Duesseldorf - Konzeption der Mitverbrennung im Kraftwerk

    Energy Technology Data Exchange (ETDEWEB)

    Lindert, M. [Umweltamt der Landeshauptstadt Duesseldorf (Germany); Hansmann, G. [Stadtwerke Duesseldorf AG (Germany); Mittmann, H. [Kanal- und Wasserbauamt der Landeshauptstadt Duesseldorf (Germany); Goertz, W. [Umweltamt der Landeshauptstadt Duesseldorf (Germany)

    1995-11-01

    Simultaneously to the enlargement of the biological wastewater treatment plants in Germany the amount of sludges increased. For the reuse or disposal of these sludges different methods - from agricultural use to incineration - are applied. For the city of Duesseldorf it became necessary to outline a new conception for the sludge disposal. A number of methods has been considered, showing that co-incineration in a coal-power-plant appears to be practicable under the circumstances found in Duesseldorf. Hence the effects of such a co-incineration on the emissions and the composition of solid waste materials of the power plant have been investigated in the course of an experimental operation. These experiments show that coincineration of the sludge also has advantages from the ecological point of view. (orig.) [Deutsch] Mit dem Ausbau der biologischen Klaeranlagen in Deutschland stieg in den letzten Jahren auch die Menge des anfallenden Klaerschlamms. Zur Verwertung bzw. Entsorgung dieses Schlammes werden unterschiedliche Verfahren - von der landwirtschaftlichen Verwertung bis zur Verbrennung - herangezogen. Fuer die Stadt Duesseldorf ergab sich die Notwendigkeit, die Klaerschlammentsorgung neu zu konzipieren. Verschiedene Varianten wurden geprueft, wobei die Mitverbrennung in der Schmelzkammerfeuerung eines Steinkohlekraftwerkes unter den in Duesseldorf herrschenden Randbedingungen praktikabel erschien. Daher wurden die Auswirkungen einer solchen Mitverbrennung auf das Emissionsverhalten und die Zusammensetzung der festen Reststoffe des Kraftwerks waehrend eines Probebetriebes untersucht. Die Versuche zeigen, dass die Mitverbrennung auch aus oekologischer Sicht Vorteile aufweist. (orig.)

  1. Beta adrenergic receptors in human cavernous tissue

    Energy Technology Data Exchange (ETDEWEB)

    Dhabuwala, C.B.; Ramakrishna, C.V.; Anderson, G.F.

    1985-04-01

    Beta adrenergic receptor binding was performed with /sup 125/I iodocyanopindolol on human cavernous tissue membrane fractions from normal tissue and transsexual procedures obtained postoperatively, as well as from postmortem sources. Isotherm binding studies on normal fresh tissues indicated that the receptor density was 9.1 fmoles/mg. with a KD of 23 pM. Tissue stored at room temperature for 4 to 6 hours, then at 4C in saline solution for 19 to 20 hours before freezing showed no significant changes in receptor density or affinity, and provided evidence for the stability of postmortem tissue obtained within the same time period. Beta receptor density of 2 cavernous preparations from transsexual procedures was not significantly different from normal control tissues, and showed that high concentrations of estrogen received by these patients had no effect on beta adrenergic receptor density. Displacement of /sup 125/iodocyanopindolol by 5 beta adrenergic agents demonstrated that 1-propranolol had the greatest affinity followed by ICI 118,551, zinterol, metoprolol and practolol. When the results of these displacement studies were subjected to Scatfit, non- linear regression line analysis, a single binding site was described. Based on the relative potency of the selective beta adrenergic agents it appears that these receptors were of the beta 2 subtype.

  2. Small hepatocellular carcinoma versus small cavernous hemangioma

    International Nuclear Information System (INIS)

    Choi, B.I.; Park, H.W.; Kim, S.H.; Han, M.C.; Kim, C.W.

    1989-01-01

    To determine the optimal pulse sequence for detection and differential diagnosis of small hepatocellular carcinomas and cavernous hemangiomas less than 5 cm in diameter, the authors have analyzed spin-echo (SE) images of 15 small hepatocellular carcinomas and 31 small cavernous hemangiomas obtained at 2.0 T. Pulse sequences used included repetition times (TRs) of 500 and 2,000 msec and echo times (TEs) of 30,60,90,120,150, and 180 msec. Mean tumor-liver contrast-to-noise ratios on the SE 2,000/60 (TR msec/TE msec) sequence were 23.90 ± 16.33 and 62.10 ± 25.94 for small hepatocellular carcinomas and hemangiomas, respectively, and were significantly greater than for all other pulse sequences. Mean tumor-liver signal intensity ratios on the SE 2,000/150 sequence were 2.34 ± 1.72 and 6.04 ± 2.72 for small hepatocellular carcinomas and hemangiomas, respectively, and were significantly greater than for all other pulse sequences in hemangiomas

  3. Strategic petroleum reserve caverns casing damage update 1997

    Energy Technology Data Exchange (ETDEWEB)

    Munson, D.E.; Molecke, M.A.; Neal, J.T. [and others

    1998-01-01

    Hanging casing strings are used for oil and brine transfer in the domal salt storage caverns of the Strategic Petroleum Reserve (SPR). Damage to these casings is of concern because hanging string replacement is costly and because of implications on cavern stability. Although the causes of casing damage are not always well defined, many events leading to damage are assumed to be the result of salt falls impacting the hanging strings. However, in some cases, operational aspects may be suspected. The history of damage to hanging strings is updated in this study to include the most recent events. Potential general domal and local operational and material factors that could influence the tendency for caverns to have salt falls are examined in detail. As a result of this examination, general factors, such as salt dome anomalies and crude type, and most of the operational factors, such as geometry, location and depressurizations, are not believed to be primary causes of casing damage. Further analysis is presented of the accumulation of insolubles during cavern solutioning and accumulation of salt fall material on the cavern floor. Inaccuracies in sump geometry probably make relative cavern insolubles contents uncertain. However, determination of the salt fall accumulations, which are more accurate, suggest that the caverns with the largest salt fall accumulations show the greatest number of hanging string events. There is good correlation between the accumulation rate and the number of events when the event numbers are corrected to an equivalent number for a single hanging string in a quiescent, operating cavern. The principal factor that determines the propensity for a cavern to exhibit this behavior is thought to be the effect of impurity content on the fracture behavior of salt.

  4. Interaction between rock, bentonite buffer and canister. FEM calculations of some mechanical effects on the canister in different disposal concepts

    International Nuclear Information System (INIS)

    Boergesson, L.

    1992-07-01

    An important task of the buffer of highly compacted bentonite is to offer a mechanical protection to the canister. This role has been investigated by a number of finite element calculations using the complex elasto plastic material models for the bentonite that have been developed on the basis of laboratory tests and adapted to the code ABAQUS. The following main functions and scenarios have been investigated for some different canister types and repository concepts: - The effect of the water and swelling pressure, - The effect of a rock shear perpendicular to the canister axis, - The effect of creep in the copper after a rock shear displacement, - The thermomechanical effects when an initially saturated buffer is used

  5. Aspects of governance in the practical implementation of the concept of reversibility for deep geological disposal. Report no. 308; Stockage geologique de dechets radioactifs: mise en oeuvre pratique du concept de reversibilite et gouvernance. Rapport no. 308

    Energy Technology Data Exchange (ETDEWEB)

    Reaud, C.; Schieber, C.; Schneider, T.; Gadbois, S.; Heriard Dubreuil, G.

    2010-07-01

    The European project COWAM in Practice (CIP) was aimed to lead for three years (2007-2009) a process of monitoring, analyzing and evaluating the governance linked with radioactive waste management. This project, in cooperation with a research group and stakeholders, was conducted in parallel in 5 European countries (Spain, France, United Kingdom, Romania, Slovenia). In France, the issue of reversibility for a deep geological disposal was introduced in the Act of December 30, 1991 on the possible options to manage radioactive waste. The Act of June 28, 2006 relative to sustainable management of materials and radioactive waste confirmed the option, by calling for a reversible waste disposal facility in a deep geological formation to be designed. The main issue is no longer to justify the adoption of reversibility, but to investigate the practical procedures for its implementation. The French stakeholder Group 4 involved in the European project COWAM In Practice (CIP) had identified several subjects for investigation: - The different aspects associated with the practical implementation of reversible disposal: technical aspects, and aspects relative to monitoring, safety and expertise, in terms of legal, financial, administrative and political, etc. responsibility related to the notion of reversibility. - The stakes of governance related to the processes of assessment and decision-making - The roles of local stakeholders in these processes. The analysis conducted by CEPN in cooperation with the French stakeholder group, facilitated by Mutadis, showed that the practical implementation of reversibility aims to maintain a capacity of choice between three options: to continue to maintain the reversibility, to retrieve packages or to initiate the closure of all or part the disposal facility. Maintaining this choice in the long term implies setting up specific institutional, financial and decision-making systems,etc,. that need to be jointly developed in advance by all the

  6. Cavernous hemangioma of the thoracic spinal cord

    International Nuclear Information System (INIS)

    Wang, A.M.; Lin, J.C.T.; Morris, J.H.; Fischer, E.G.; Petersen, R.

    1988-01-01

    A 25-year-old woman presented with a four-year history of progressive right-lower-extremity weakness and atrophy and a left hemisensory deficit was found. Metrizamide-enhanced spinal CT scan showed an intramedullary lesion at the level of T1-T2; this had expanded the cord in fusiform fashion but showed no evidence of a cystic component. Surgical resection was performed and the pathological diagnosis was cavernous hemangioma. Two and one-half years later, her left hemisensory deficit was worsening and a spinal MRI showed high signal intensity mass in the region of the previous surgery consistent with chronic hematoma which was re-evacuated with some improvement in the patient's neurological condition. (orig.)

  7. Neuronavigation for the resection of cavernous angiomas.

    Science.gov (United States)

    Du, G; Zhou, L

    1999-08-01

    To introduce the use of the StealthStation neuronavigator combined with preoperative computerized tomography (CT) in resection of intracranial cavernous angiomas (CAs). The StealthStation neuronavigator was used to provide a realtime correlation of the operating field and the computerized images in 6 patients with CAs. All patients suffered from epileptic seizures. Four patients underwent keyhole surgery and 2 underwent small skin-flap craniotomy. The mean follow-up was 4.5 months. With the guidance of neuronavigator, lesionectomy associated with removal of hemosiderin deposition, gliosis and calcification was performed precisely. The mean fiducial error was from 1.65 mm to 4.53 mm, the predicted accuracy at 10 cm was between 1.82 mm and 3.28 mm, and the sustained accuracy ranged from 0.50 mm to 3.45 mm. The StealthStation neuronavigator is reliable and accurate in the resection of CAs.

  8. [Cavernous haemangiomas: hearing and vestibular inaugural symptoms].

    Science.gov (United States)

    Dumas, G; Schmerber, S

    2004-11-01

    Cavernous haemangiomas (cavernomas)(CH) are relatively rare (2% of cranial tumoral pathology) vascular malformations mostly observed in the central nervous system. Their most common topographical site in brain stem is midline in the pons, for which clinical course may mimic symptoms of peripheral origin (sudden deafness, fluctuating hearing loss, Meniere-like vertigo). To establish the correlation between the clinical manifestations of hearing and balance disturbance and the anatomical site within the pons of cavernous haemangiomas, and to describe their clinical features, and the findings on auditory brainstem response (ABR) and magnetic resonance imaging (MRI). To propose a literature review about CH and its implications. We made a retrospective review of the histories of three patients aged 24, 44 and 45 years, diagnosed as having cavernomas of the brainstem in which audiometric evaluation, videonystagmography (VNG), ABR and imaging techniques lead to the diagnosis of intracranial cavernoma. The clinical and radiological files were reviewed and a direct relationship between symptoms and localization was found in all 3 patients, especially in relation to our understanding of the auditory and vestibular pathways within the brainstem. The literature regarding cavernomas of the pons is reviewed and the clinical, neuroimage, pathological, natural course and management aspects of the disease are discussed. We recommend the use of cerebral MRI for initial diagnosis which shows a typical rosette-like appearance with a heterogeneous signal on T2-weighted images, along with follow-up and investigation into similar profiles among family members. At present there is no consensus about the treatment to follow when cavernomas are located in the brain stem. There is no specific medical treatment for this condition, and surgery is indicated only exceptionally. Anticoagulant therapy, platelet-dispersing medication and violent sports activities are contraindicated.

  9. Therapeutic surprise! Photodynamic therapy for cavernous haemangioma of the disc

    Directory of Open Access Journals (Sweden)

    Mahesh P Shanmugam

    2017-01-01

    Full Text Available Purpose: To report the response of cavernous haemangioma of the disc to PDT. Methods and Patients: A 32 years old lady presented to us with complaints of sudden onset of blurry vision in her right eye. What seemed initially as polypoidal choroidal vasculopathy turned out as cavernous haemangioma of the disc after pneumatic displacement of the sub-retinal haeme. She was treated with PDT as she was prone to recurrent haemorrhage from the lesion due to her low platelet count. Results: Complete regression of the cavernous haemangioma was noted as early as the second week itself and remained regressed for 4 months. Conclusion: PDT can be safe option for patients presenting with symptomatic cavernous haemangioma of the disc or retina.

  10. Intracranial cavernous hemangiomas: a case report and bibliographic review

    International Nuclear Information System (INIS)

    Shiguihara, L.C.M.; Granero, P.C.; Gianotti, I.A.; Lederman, H.M.; Seixas, M.T.

    1992-01-01

    This is a case report of intracranial cavernous hemangioma that presented with macrocrania. A large, spontaneously hyperdense area with mass effect on CT was seen. This is a rare vascular malformation evolving the CNS in pediatrics. (author)

  11. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Allan, C.J.

    1993-01-01

    The Canadian concept for nuclear fuel waste disposal is based on disposing of the waste in a vault excavated 500-1000 m deep in intrusive igneous rock of the Canadian Shield. The author believes that, if the concept is accepted following review by a federal environmental assessment panel (probably in 1995), then it is important that implementation should begin without delay. His reasons are listed under the following headings: Environmental leadership and reducing the burden on future generations; Fostering public confidence in nuclear energy; Forestalling inaction by default; Preserving the knowledge base. Although disposal of reprocessing waste is a possible future alternative option, it will still almost certainly include a requirement for geologic disposal

  12. Development of technical information database for high level waste disposal

    International Nuclear Information System (INIS)

    Kudo, Koji; Takada, Susumu; Kawanishi, Motoi

    2005-01-01

    A concept design of the high level waste disposal information database and the disposal technologies information database are explained. The high level waste disposal information database contains information on technologies, waste, management and rules, R and D, each step of disposal site selection, characteristics of sites, demonstration of disposal technology, design of disposal site, application for disposal permit, construction of disposal site, operation and closing. Construction of the disposal technologies information system and the geological disposal technologies information system is described. The screen image of the geological disposal technologies information system is shown. User is able to search the full text retrieval and attribute retrieval in the image. (S.Y. )

  13. Cerebral cavernous malformations. Serial magnetic resonance imaging findings in patients with and without gamma knife surgery

    International Nuclear Information System (INIS)

    Yoon Pyeong-Ho; Kim, Dong-Ik; Jeon Pyoung; Ryu, Young-Hoon; Hwang, Geum-Joo; Park, Sang-Joon

    1998-01-01

    To classify the cerebral cavernous malformations and to investigate the natural history of cavernous malformations according to the classification, 41 patients with 61 cavernous malformations (40 cavernous malformations from 22 patients treated with gamma knife surgery) were regularly followed up using MR imaging for a mean period of 25.5 months in treated cavernous malformations and 20.7 months in untreated cavernous malformations, respectively. Cavernous malformations were classified into four types. Follow-up MR images were analyzed to evaluate changes in size, signal intensity, rebleeding, and perilesional adverse reaction of irradiation. A total of 61 cavernous malformations including 17 in type I, 23 in type II, 10 in type III, and 11 in type IV showed usual degradation of blood product in 22 cavernous malformations, no change in shape and signal intensity in 31 cavernous malformations, and eight cavernous malformations with rebleedings in the serial MR images. In these eight cavernous malformations with rebleedings, six occurred in type II and two in type III, but none in type I or IV. Rebleedings were more frequent in type II than in other types. Adverse reaction of irradiation was observed in five of 22 patients treated with gamma knife surgery. Although most cerebral cavernous malformations showed evolution of hemorrhage or no change in size or shape on follow-up MR images, cerebral cavernous malformations represented as mixture of subacute and chronic hemorrhage with hemosiderin rim (type II) have a higher frequency to rebleed than other types of cerebral cavernous malformations. Cerebral cavernous malformations represented as hemosiderin deposition without central core (type IV) have a lower tendency to rebleed than other types and do not need any treatment. Most of the adverse reaction of irradiation after gamma knife surgery around cavernous malformations are transient findings and are considered to be perilesional edema. (K.H)

  14. Features of Bayou Choctaw SPR caverns and internal structure of the salt dome.

    Energy Technology Data Exchange (ETDEWEB)

    Munson, Darrell E.

    2007-07-01

    The intent of this study is to examine the internal structure of the Bayou Choctaw salt dome utilizing the information obtained from graphical representations of sonar survey data of the internal cavern surfaces. Many of the Bayou Choctaw caverns have been abandoned. Some existing caverns were purchased by the Strategic Petroleum Reserve (SPR) program and have rather convoluted histories and complex cavern geometries. In fact, these caverns are typically poorly documented and are not particularly constructive to this study. Only two Bayou Choctaw caverns, 101 and 102, which were constructed using well-controlled solutioning methods, are well documented. One of these was constructed by the SPR for their use while the other was constructed and traded for another existing cavern. Consequently, compared to the SPR caverns of the West Hackberry and Big Hill domes, it is more difficult to obtain a general impression of the stratigraphy of the dome. Indeed, caverns of Bayou Choctaw show features significantly different than those encountered in the other two SPR facilities. In the number of abandoned caverns, and some of those existing caverns purchased by the SPR, extremely irregular solutioning has occurred. The two SPR constructed caverns suggest that some sections of the caverns may have undergone very regular solutioning to form uniform cylindrical shapes. Although it is not usually productive to speculate, some suggestions that point to the behavior of the Bayou Choctaw dome are examined. Also the primary differences in the Bayou Choctaw dome and the other SPR domes are noted.

  15. Indirect carotid cavernous fistula mimicking ocular myasthenia.

    Science.gov (United States)

    Leishangthem, Lakshmi; Satti, Sudhakar Reddy

    2017-10-19

    71-year-old woman with progressive left-sided, monocular diplopia and ptosis. Her symptoms mimicked ocular myasthenia, but she had an indirect carotid cavernous fistula (CCF). She was diagnosed with monocular myasthenia gravis (negative acetylcholinesterase antibody) after a positive ice test and started on Mestinon and underwent a thymectomy complicated by a brachial plexus injury. Months later, she developed left-sided proptosis and ocular bruit. She was urgently referred to neuro-interventional surgery and was diagnosed with an indirect high-flow left CCF, which was treated with Onyx liquid and platinum coil embolisation. Mestinon was discontinued. Her ophthalmic symptoms resolved. However, she was left with a residual left arm and hand hemiparesis and dysmetria secondary to a brachial plexus injury. Indirect CCF usually can present with subtle and progressive symptoms leading to delayed diagnosis or misdiagnosis. It is important for ophthalmologists to consider this differential in a patient with progressive ocular symptoms. © BMJ Publishing Group Ltd (unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  16. Gallium scintigraphy in a case of septic cavernous sinus thrombosis

    International Nuclear Information System (INIS)

    Palestro, C.J.; Malat, J.; Gladstone, A.G.; Richman, A.H.

    1986-01-01

    Septic cavernous sinus thrombosis, a relatively uncommon disease entity, frequently can be fatal. Early diagnosis is imperative in order that appropriate treatment be instituted. A 59-year-old woman who was admitted to our institution with complaints of diplopia, blurred vision and fevers that developed following a tooth extraction is presented. Initial CT and lumbar puncture on the day of admission were totally normal. A repeat CT performed 48 hours after admission, on the same day as gallium imaging, demonstrated findings consistent with cavernous sinus thrombosis. Gallium imaging demonstrated intense uptake in the left cavernous sinus and left orbit as well as moderately increased activity in the right cavernous sinus and orbit, confirming infection. The patient was treated with antibiotics, and repeat CT and gallium imaging were performed ten days later, both of which demonstrated near total resolution of the disease process. Conceivably, if gallium imaging had been initiated on the day of admission it may have been the first study to demonstrate an infectious process in the cavernous sinus. Gallium imaging should be considered as a diagnostic tool in the noninvasive workup of this entity

  17. Waste package/engineered barrier system design concepts for the direct disposal of spent fuel in the potential United States' repository at Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Stahl, D.; Harrison, D.J.

    1993-01-01

    The goal of the US Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) waste package development program is to design a waste package and associated engineered barrier system (EBS) that meets the applicable regulatory requirements for safe disposal of spent nuclear fuel and solidified high-level waste (HLW) in a geologic repository. Attainment of this goal relies on a multi-barrier approach, the unsaturated nature of the Yucca Mountain site, consideration of technical alternatives, and sufficient resolution of technical and regulatory uncertainties. To accomplish this, an iterative system engineering approach will be used. The NWPA of 1982 limits the content of the first US repository to 70,000 metric tons of heavy metal (MTHM). The DOE Mission Plan describes the implementation of the provisions of the NWPA for the waste management system. The Draft 1988 approach will involve selecting candidate designs, evaluating them against performance requirements, and then selecting one or two preferred designs for further detailed evaluation and final design. The reference design of the waste package described in the YMP Site Characterization Plan is a thin-walled, vertical borehole-emplaced waste package with an air gap between the package and the rock wall. The reference design appeared to meet the design requirement. However, the degree of uncertainty was large. This uncertainty led to considering several more-robust design concepts during the Advanced Conceptual Design phase of the program that include small, drift-emplaced packages and higher capacity, drift-emplaced packages, both partially and totally self-shielded. Metallic as well as ceramic materials are being considered

  18. Treatment and final disposal of nuclear waste. Programme for encapsulation, deep geological disposal, and research, development and demonstration

    International Nuclear Information System (INIS)

    1995-09-01

    Programs for RD and D concerning disposal of radioactive waste are presented. Main topics include: Design, testing and manufacture of canisters for the spent fuels; Design of equipment for deposition of waste canisters; Material and process for backfilling rock caverns; Evaluation of accuracy and validation of methods for safety analyses; Development of methods for defining scenarios for the safety analyses. 471 refs, 67 figs, 21 tabs

  19. Treatment and final disposal of nuclear waste. Programme for encapsulation, deep geological disposal, and research, development and demonstration

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    Programs for RD and D concerning disposal of radioactive waste are presented. Main topics include: Design, testing and manufacture of canisters for the spent fuels; Design of equipment for deposition of waste canisters; Material and process for backfilling rock caverns; Evaluation of accuracy and validation of methods for safety analyses; Development of methods for defining scenarios for the safety analyses. 471 refs, 67 figs, 21 tabs.

  20. Disposal safety

    International Nuclear Information System (INIS)

    Bartlett, J.W.

    International consensus does not seem to be necessary or appropriate for many of the issues concerned with the safety of nuclear waste disposal. International interaction on the technical aspects of disposal has been extensive, and this interaction has contributed greatly to development of a consensus technical infrastructure for disposal. This infrastructure provides a common and firm base for regulatory, political, and social actions in each nation

  1. Waste disposal

    International Nuclear Information System (INIS)

    Neerdael, B.; Marivoet, J.; Put, M.; Verstricht, J.; Van Iseghem, P.; Buyens, M.

    1998-01-01

    The primary mission of the Waste Disposal programme at the Belgian Nuclear Research Centre SCK/CEN is to propose, develop, and assess solutions for the safe disposal of radioactive waste. In Belgium, deep geological burial in clay is the primary option for the disposal of High-Level Waste and spent nuclear fuel. The main achievements during 1997 in the following domains are described: performance assessment, characterization of the geosphere, characterization of the waste, migration processes, underground infrastructure

  2. Radiological features of childhood giant cavernous malformations

    Energy Technology Data Exchange (ETDEWEB)

    Ozgen, Burce; Senocak, Efsun; Oguz, Kader K. [Hacettepe University, Department of Radiology, Faculty of Medicine, Ankara (Turkey); Soylemezoglu, Figen [Hacettepe University, Department of Pathology, School of Medicine, Ankara (Turkey); Akalan, Nejat [Hacettepe University, Department of Neurosurgery, School of Medicine, Ankara (Turkey)

    2011-04-15

    Giant cavernous malformations (GCM) are very large, low-flow vascular malformations, which usually have atypical imaging features and are commonly misdiagnosed preoperatively as neoplasms or vascular malformations. These lesions have mostly been reported in children. As cavernomas show different features in children compared to adults, we evaluated the imaging features of pediatric GCMs in order to help in the preoperative diagnosis of these malformations. Brain MR studies of nine children (mean age of 4 years; 8 months-9 years) with biopsy-proven GCM were retrospectively evaluated. We defined GCMs as cavernomas of {>=}4 cm. Lesions were evaluated regarding their size, location, signal characteristics, general appearance (uni/multilocular) as well as regarding the presence of mass effect, edema, and fluid-fluid levels and were classified according to the Mottolese classification of pediatric cavernomas. Lesion locations were parietal (n = 5), frontal (n = 2), temporal, and intraventricular. Seven lesions were in the periventricular region (with five in the periatrial region). Six patients had T1 hyperintense multilobulated lesions with ''bubbles of blood'' appearance and three patients had heterogeneous lesions with reticular core. All lesions had mass effect, edema (marked in four cases), and peripheral hemosiderin rim. Fluid-fluid levels were also common (n = 7). Most of our lesions (six of nine) were classified as type IIIA, two as type IIIC, and one as type IA. In children, a GCM should be considered in case of very large hemorrhagic intra-axial mass with ''bubbles of blood'' multicystic appearance, surrounding hemosiderin ring, fluid-fluid levels, and accompanying edema-mass effect, especially in the periatrial location. (orig.)

  3. Grid scale energy storage in salt caverns

    Energy Technology Data Exchange (ETDEWEB)

    Crotogino, Fritz; Donadei, Sabine [KBB Underground Technologies GmbH, Hannover (Germany)

    2009-07-01

    Fossil energy sources require some 20% of the annual consumption to be stored to secure emergency cover, peak shaving, seasonal balancing, etc. Today the electric power industry benefits from the extreme high energy density of fossil fuels. This is one important reason why the German utilities are able to provide highly reliable grid operation at a electric power storage capacity at their pumped hydro power stations of less then 1 hour (40 GWh) related to the total load in the grid - i.e. only 0,06% related to natural gas. Along with the changeover to renewable wind based electricity production this ''outsourcing'' of storage services to fossil fuels will decline. One important way out will be grid scale energy storage. The present discussion for balancing short term wind and solar power fluctuations focuses primarily on the installation of Compressed Air Energy Storages (CAES) in addition to existing pumped hydro plants. Because of their small energy density, these storage options are, however, generally not suitable for balancing for longer term fluctuations in case of larger amounts of excess wind power or even seasonal fluctuations. Underground hydrogen storages, however, provide a much higher energy density because of chemical energy bond - standard practice since many years. The first part of the article describes the present status and performance of grid scale energy storages in geological formations, mainly salt caverns. It is followed by a compilation of generally suitable locations in Europe and particularly Germany. The second part deals with first results of preliminary investigations in possibilities and limits of offshore CAES power stations. (orig.)

  4. Lined rock caverns for the storage of hazardous waste

    International Nuclear Information System (INIS)

    Semprich, S.; Speidel, S.R.; Schneider, H.J.

    1987-01-01

    For reasons of environmental protection the storage of hazardous waste in unlined rock caverns is possible to a very limited extent only. Therefore, the authors have recently developed technologies for the lining and sealing of rock caverns. In the process, sealing systems of synthetic materials or metals have proved suitable. Synthetic materials can be used in the form of either sheets or coatings with various materials such as epoxy resins, polyethylenes etc. being used. Metal sealings consist of thin sheets or foils which are either welded or bonded. In either case, the structural design must provide for a leakage control possibility. The article describes the design principles, the structural and operational aspects as well as the control measures with regard to the planning and execution of lined rock caverns for the storage of hazardous waste

  5. Optical Coherence Tomography Angiography of Retinal Cavernous Hemangioma.

    Science.gov (United States)

    Pierro, Luisa; Marchese, Alessandro; Gagliardi, Marco; Bandello, Francesco

    2017-08-01

    Retinal cavernous hemangioma is a rare, benign, retinal tumor characterized by angiomatous proliferation of vessels within the inner retina or the optic disc.1 Here we report a case of retinal cavernous hemangioma on the margin of the optic disc in the right eye of a 61-year-old asymptomatic female. The lesion was studied with multimodal imaging which included structural optical coherence tomography, fluorescein angiography, blue fundus auto-fluorescence, optical coherence tomography angiography (OCTA) (DRI OCT Triton; Topcon, Tokyo, Japan) and visual field examination. Blood circulation inside retinal cavernous hemangioma lesion is typically low-stagnant.2 However, OCTA demonstrated blood flow inside the lesion, illustrating its vascular circulation.3 Visual field was within the normal limits, except from a slight enlargement of the blind spot. [Ophthalmic Surg Lasers Imaging Retina. 2017;48:684-685.]. Copyright 2017, SLACK Incorporated.

  6. Radioactive waste and special waste disposal in salt domes - phoney waste management solutions

    International Nuclear Information System (INIS)

    Grimmel, E.

    1990-01-01

    The paper tries to make aware of the fact that an indefinite safe disposal of anthropogeneous wastes in underground repositories is impossible. Suspicion is raised that the Gorleben-Rambow salt dome has never been studied for its suitability as a repository, but that it was simply taken for granted. Safety analyses are meant only to conceal uncertainty. It is demanded to immediately opt out of the ultimate disposal technique for radioactive and special wastes in salt caverns. (DG) [de

  7. Tolerance of cranial nerves of the cavernous sinus to radiosurgery

    International Nuclear Information System (INIS)

    Tishler, R.B.; Loeffler, J.S.; Alexander, E. III; Kooy, H.M.; Lunsford, L.D.; Duma, C.; Flickinger, J.C.

    1993-01-01

    Stereotactic radiosurgery is becoming a more accepted treatment option for benign, deep seated intracranial lesions. However, little is known about the effects of large single fractions of radiation on cranial nerves. This study was undertaken to assess the effect of radiosurgery on the cranial nerves of the cavernous sinus. The authors examined the tolerance of cranial nerves (II-VI) following radiosurgery for 62 patients (42/62 with meningiomas) treated for lesions within or near the cavernous sinus. Twenty-nine patients were treated with a modified 6 MV linear accelerator (Joint Center for Radiation Therapy) and 33 were treated with the Gamma Knife (University of Pittsburgh). Three-dimensional treatment plans were retrospectively reviewed and maximum doses were calculated for the cavernous sinus and the optic nerve and chiasm. Median follow-up was 19 months (range 3-49). New cranial neuropathies developed in 12 patients from 3-41 months following radiosurgery. Four of these complications involved injury to the optic system and 8 (3/8 transient) were the result of injury to the sensory or motor nerves of the cavernous sinus. There was no clear relationship between the maximum dose to the cavernous sinus and the development of complications for cranial nerves III-VI over the dose range used (1000-4000 cGy). For the optic apparatus, there was a significantly increased incidence of complications with dose. Four of 17 patients (24%) receiving greater than 800 cGy to any part of the optic apparatus developed visual complications compared with 0/35 who received less than 800 cGy (p = 0.009). Radiosurgery using tumor-controlling doses of up to 4000 cGy appears to be a relatively safe technique in treating lesions within or near the sensory and motor nerves (III-VI) of the cavernous sinus. The dose to the optic apparatus should be limited to under 800 cGy. 21 refs., 4 tabs

  8. Neuroradiological diagnosis and interventional therapy of carotid cavernous fistulas

    International Nuclear Information System (INIS)

    Struffert, T.; Engelhorn, T.; Doelken, M.; Doerfler, A.; Holbach, L.

    2008-01-01

    Carotid cavernous fistulas are pathologic connections between the internal and/or external carotid artery and the cavernous sinus. According to Barrow one can distinguish between direct (high flow) and indirect (low flow) fistulas, whereby direct fistulas are often traumatic while indirect fistulas more frequently occur spontaneously in postmenopausal women. Diagnosis can easily be established using MRI and angiography, which allow exact visualization of the anatomy of fistulas to plan the interventional neurological therapy that in recent years has replaced surgical therapy. This article provides an overview on imaging findings, diagnosis using MRI and angiography as well as interventional treatment strategies. (orig.) [de

  9. An evaluation on the disposal alternatives for low- and intermediate- level radwaste (II)

    International Nuclear Information System (INIS)

    Park, Hun Hwee; Han, Kyung Won; Hahn, Pil Soo; Lee, Han Soo; Cho, Won Jin; Lee, Jae Dwan; Park, Chung Kyun; Lee, Myung Joo; Choi, Heui Joo; Lee, Youn Myoung

    1988-02-01

    An evaluation on the radioactive waste disposal alternatives for the low-and intermediate level wastes being produced from nuclear power generation and radioisotope application was carried out in view of the radiological safety, socio-political aspects and repository construction economics. Three types of possible alternatives-sample shallow land disposal method, engineered shallow land disposal method and engineered rock cavern disposal method are investigated. The safety assessment consists of radiological dose calculation and nonradiological impacts which is expressed as total number of injuries and fatalities during construction, operation and transportation. The sociopolitical assessment is done in terms of site conditions including easiness for land acquisition, technical feasibility and public acceptance. The economic assessment is performed by cost comparison regarding land acquisition, construction, operation and closure for each alternatives. The evaluation shows that engineered rock cavern disposal method has remarkable favour in safety than others. And also an integrated evaluation using AHP results the engineered rock cavern disposal method as the most favorable option

  10. Reversible deep disposal

    International Nuclear Information System (INIS)

    2009-10-01

    This presentation, given by the national agency of radioactive waste management (ANDRA) at the meeting of October 8, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), describes the concept of deep reversible disposal for high level/long living radioactive wastes, as considered by the ANDRA in the framework of the program law of June 28, 2006 about the sustainable management of radioactive materials and wastes. The document presents the social and political reasons of reversibility, the technical means considered (containers, disposal cavities, monitoring system, test facilities and industrial prototypes), the decisional process (progressive development and blocked off of the facility, public information and debate). (J.S.)

  11. Cerebral cavernous angioma. 16 cases. Aspects in CT and MR

    International Nuclear Information System (INIS)

    Pina, J.I.; Medrano, J.; Lasierra, R.; Benito, J.L. de; Feijoo, R.; Fernandez, J.A.; Villavieja, J.L.

    1995-01-01

    The cerebral cavernous angioma (CA) is included in the group of cerebral malformations that can not be detected angiographically. We present the retrospective study of 16 patients, diagnosed as having CA, comparing the data provided by CT and MR, as well as the contribution of cerebral angiography. (Author) 25 refs

  12. Carotid-cavernous fistula after functional endoscopic sinus surgery.

    Science.gov (United States)

    Karaman, Emin; Isildak, Huseyin; Haciyev, Yusuf; Kaytaz, Asim; Enver, Ozgun

    2009-03-01

    Carotid-cavernous fistulas (CCFs) are anomalous communications between the carotid arterial system and the venous cavernous sinus. They can arise because of spontaneous or trauma causes. Most caroticocavernous fistulas are of spontaneous origin and unknown etiology. Spontaneous CCF may also be associated with cavernous sinus pathology such as arteriosclerotic changes of the arterial wall, fibromuscular dysplasia, or Ehler-Danlos syndrome. Traumatic CCFs may occur after either blunt or penetrating head trauma. Their clinical presentation is related to their size and to the type of venous drainage, which can lead to a variety of symptoms, such as visual loss, proptosis, bruit, chemosis, cranial nerve impairment, intracranial hemorrhage (rare), and so on. Treatment by endovascular transarterial embolization with electrolytically detachable coils is a very effective method for CCF with good outcomes. Carotid-cavernous fistulas have been rarely reported after craniofacial surgery and are uncommon pathologies in otolaryngology practice. In this study, we report a 40-year-old woman with CCF secondary to blunt trauma of functional endoscopic sinus surgery.

  13. NA62 cavern and sub-detectors 2017

    CERN Multimedia

    Graham, Connor

    2017-01-01

    The NA62 cavern, with the completed detector, during breaks in data taking in July 2017. Pictures from 05-07-17 by Dan Protopopescu and pictures from 08-07-17 by Connor Graham (Both Glasgow-affiliated). Includes pictures of the whole experiment, safety systems and sub-detector elements.

  14. Value of gamma knife radiosurgery for tumors invading cavernous sinus

    International Nuclear Information System (INIS)

    Jokura, Hidefumi; Yoshimoto, Takashi

    1999-01-01

    The usefulness of radiosurgery for cavernous sinus tumors was evaluated based on our experience and recent published reports from other institutes. Twenty-six meningiomas involving the cavernous sinus were treated by radiosurgery. The length of follow-up average 3 years. Tumors regressed in 40% and remained stable in 56% of cases. A total of 96% of the tumors were controlled with only a few minor complications. We believe surgical resection to reduce the volume of the tumor without causing new neurological deficits, followed by radiosurgery on the tumor located in the cavernous sinus is the best choice in many cases. Twenty-five pituitary adenomas with cavernous sinus invasion were treated by a combination of transsphenoidal removal and radiosurgery. All the tumors are controlled in terms of volume during the follow-up (average of 34 months). There were no new neurological deficits, including visual disturbance. Hormone elevation was able to be corrected at an early stage without pituitary insufficiency more by radiosurgery than by fractionated radiation. However, to obtain good results by radiosurgery, it must be preceded by complete surgical decompression of optic nerves and chiasma from the tumor. (author)

  15. Estimating the distribution of salt cavern squeeze using subsidence measurements

    NARCIS (Netherlands)

    Fokker, P.A.; Visser, J.

    2014-01-01

    We report a field study on solution mining of magnesium chloride from bischofite layers in the Netherlands at depths between 1500 and 1850 m. Subsidence that was observed in the area is due to part of the brine production being realized by cavern squeeze; some of which were connccted. Wc used an

  16. Simulation of Cavern Formation and Karst Development Using Salt

    Science.gov (United States)

    Kent, Douglas C.; Ross, Alex R.

    1975-01-01

    A salt model was developed as a teaching tool to demonstrate the development of caverns and karst topography. Salt slabs are placed in a watertight box to represent fractured limestone. Erosion resulting from water flow can be photographed in time-lapse sequence or demonstrated in the laboratory. (Author/CP)

  17. Fat deposition in the cavernous sinus in Cushing disease

    International Nuclear Information System (INIS)

    Bachow, T.B.; Hesselink, J.R.; Aaron, J.O.; Davis, K.R.; Taveras, J.M.

    1984-01-01

    Fat density in the cavernous sinus on computed tomography (CT) is described in 6 out of 16 (37.5%) patients with Cushing disease. This finding may aid in making a specific diagnosis in patients with a pituitary mass. It was not seen in 30 random CT studies of the sella; however, supra seller fat was incidentally noted in the patient with acromegaly

  18. Valuation of gas stored in salt cavern facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bond, Michael A. [St. Mary' s University, TX (United States); Grant, Floyd H. [Purdue University, IN (United States)

    2008-07-01

    Since natural gas production is relatively inelastic towards demand in the short term, underground storage is used as a buffer against periods of high demand. Of the three most common storage facility types, depleted reservoirs, aquifers and manmade salt caverns, the latter is the most costly to develop. The challenge then is to maximize profits through efficient operation, well-timed injection and withdrawal of gas. The valuation of a commodity in storage is a challenging problem and has been the subject of study for decades. We investigate selected existing valuation approaches and look for ways to leverage salt-cavern-specific physical characteristics for financial advantage. The basis for our valuation is the Black-Scholes model for pricing options. Then, applying Monte-Carlo methods and simulation, we model combinations of characteristics in multi-cavern facilities and their impact on profitability. We describe the theory behind our work and our analytical framework and provide numerical results of our analysis. Our approach offers increased efficiency in salt-cavern gas storage facility operations. (author)

  19. Fat deposition in the cavernous sinus in Cushing disease

    Energy Technology Data Exchange (ETDEWEB)

    Bachow, T.B.; Hesselink, J.R.; Aaron, J.O.; Davis, K.R.; Taveras, J.M.

    1984-10-01

    Fat density in the cavernous sinus on computed tomography (CT) is described in 6 out of 16 (37.5%) patients with Cushing disease. This finding may aid in making a specific diagnosis in patients with a pituitary mass. It was not seen in 30 random CT studies of the sella; however, supra seller fat was incidentally noted in the patient with acromegaly.

  20. Analysis of SPR salt cavern remedial leach program 2013.

    Energy Technology Data Exchange (ETDEWEB)

    Weber, Paula D.; Gutierrez, Karen A.; Lord, David L.; Rudeen, David Keith

    2013-09-01

    The storage caverns of the US Strategic Petroleum Reserve (SPR) exhibit creep behavior resulting in reduction of storage capacity over time. Maintenance of oil storage capacity requires periodic controlled leaching named remedial leach. The 30 MMB sale in summer 2011 provided space available to facilitate leaching operations. The objective of this report is to present the results and analyses of remedial leach activity at the SPR following the 2011 sale until mid-January 2013. This report focuses on caverns BH101, BH104, WH105 and WH106. Three of the four hanging strings were damaged resulting in deviations from normal leach patterns; however, the deviations did not affect the immediate geomechanical stability of the caverns. Significant leaching occurred in the toes of the caverns likely decreasing the number of available drawdowns until P/D ratio criteria are met. SANSMIC shows good agreement with sonar data and reasonably predicted the location and size of the enhanced leaching region resulting from string breakage.

  1. A Case of Brainstem Cavernous Angioma Presenting with Persistent Hiccups

    Directory of Open Access Journals (Sweden)

    Mohammad Ali Arami

    2010-07-01

    Full Text Available "nIntractable hiccup most be considered as a symptom of underlying serious pathologies. We report a case of medulla oblongata cavernous angima presented with persistant hiccup and without any improvement during routine nonpharmacologic and pharmacologic treatment regimns. The patient is under our follow up visits and surgery is very high risk for this young girl.

  2. Primary extradural leiomyosarcoma involving cavernous sinus in an immunocompetent patient

    Directory of Open Access Journals (Sweden)

    Hanni V Gulwani

    2014-01-01

    Full Text Available Intracranial leiomyosarcoma (LMS are uncommon malignancies and usually encountered after systemic metastases. Limited cases of primary intracranial LMSs have been reported in the literature. It mostly affects immunocompromised individuals in association with Epstein-Barr virus infection. This is the unusual first case being reported of primary LMS in immunocompetent patient with involvement of cavernous sinus.

  3. Waste disposal

    International Nuclear Information System (INIS)

    2005-01-01

    Radioactive waste, as a unavoidable remnant from the use of radioactive substances and nuclear technology. It is potentially hazardous to health and must therefore be managed to protect humans and the environment. The main bulk of radioactive waste must be permanently disposed in engineered repositories. Appropriate safety standards for repository design and construction are required along with the development and implementation of appropriate technologies for the design, construction, operation and closure of the waste disposal systems. As backend of the fuel cycle, resolving the issue of waste disposal is often considered as a prerequisite to the (further) development of nuclear energy programmes. Waste disposal is therefore an essential part of the waste management strategy that contributes largely to build confidence and helps decision-making when appropriately managed. The International Atomic Energy Agency provides assistance to Member States to enable safe and secure disposal of RW related to the development of national RWM strategies, including planning and long-term project management, the organisation of international peer-reviews for research and demonstration programmes, the improvement of the long-term safety of existing Near Surface Disposal facilities including capacity extension, the selection of potential candidate sites for different waste types and disposal options, the characterisation of potential host formations for waste facilities and the conduct of preliminary safety assessment, the establishment and transfer of suitable technologies for the management of RW, the development of technological solutions for some specific waste, the building of confidence through training courses, scientific visits and fellowships, the provision of training, expertise, software or hardware, and laboratory equipment, and the assessment of waste management costs and the provision of advice on cost minimisation aspects

  4. Disposal options for radioactive waste

    International Nuclear Information System (INIS)

    Olivier, J.P.

    1991-01-01

    On the basis of the radionuclide composition and the relative toxicity of radioactive wastes, a range of different options are available for their disposal. Practically all disposal options rely on confinement of radioactive materials and isolation from the biosphere. Dilution and dispersion into the environment are only used for slightly contaminated gaseous and liquid effluents produced during the routine operation of nuclear facilities, such as power plants. For the bulk of solid radioactive waste, whatever the contamination level and decay of radiotoxicity with time are, isolation from the biosphere is the objective of waste disposal policies. The paper describes disposal approaches and the various techniques used in this respect, such as shallow land burial with minimum engineered barriers, engineered facilities built at/near the surface, rock cavities at great depth and finally deep geologic repositories for long-lived waste. The concept of disposing long-lived waste into seabed sediment layers is also discussed, as well as more remote possibilities, such as disposal in outer space or transmutation. For each of these disposal methods, the measures to be adopted at institutional level to reinforce technical isolation concepts are described. To the extent possible, some comments are made with regard to the applicability of such disposal methods to other hazardous wastes. (au)

  5. Report on radioactive waste disposal

    International Nuclear Information System (INIS)

    1993-01-01

    The safe management of radioactive wastes constitutes an essential part of the IAEA programme. A large number of reports and conference proceedings covering various aspects of the subject have been issued. The Technical Review Committee on Underground Disposal (February 1988) recommended that the Secretariat issue a report on the state of the art of underground disposal of radioactive wastes. The Committee recommended the need for a report that provided an overview of the present knowledge in the field. This report covers the basic principles associated with the state of the art of near surface and deep geological radioactive waste disposal, including examples of prudent practice, and basic information on performance assessment methods. It does not include a comprehensive description of the waste management programmes in different countries nor provide a textbook on waste disposal. Such books are available elsewhere. Reviewing all the concepts and practices of safe radioactive waste disposal in a document of reasonable size is not possible; therefore, the scope of this report has been limited to cover essential parts of the subject. Exotic disposal techniques and techniques for disposing of uranium mill tailings are not covered, and only brief coverage is provided for disposal at sea and in the sea-bed. The present report provides a list of references to more specialized reports on disposal published by the IAEA as well as by other bodies, which may be consulted if additional information is sought. 108 refs, 22 figs, 2 tabs

  6. Waste management in ancient Greece from the Homeric to the Classical period: concepts and practices of waste, dirt, recycling and disposal

    OpenAIRE

    Lindenlauf, A.

    2000-01-01

    This doctoral thesis has two purposes. First, it develops a universally applicable model for the analysis of waste disposal and recycling practices. This model synthesises Schiffer's behavioural analysis of the formation processes of the archaeological record with the history, sociology and anthropology of conceptualisations of dirt. Second, it shows how this model may be applied to ancient Greece. In the tradition of material culture studies, it aims to challenge the entrenche...

  7. The french low-level waste disposal site 'Centre de l'Aube'. A ten years process, from geological concept to waste deliveries

    International Nuclear Information System (INIS)

    Fernique, J.C.

    1993-01-01

    The 'Centre de la Manche', first French low-level waste disposal site opened in 1969 and will enter the institutional control period around 1994. A creation process for a new disposal was initiated in 1981 when ANDRA prepared a general radioactive waste management Program and presented it to the High Council for Nuclear Safety and Information. After acceptance of the Program, a national site screening was made, based on a conceptual geological model designed from the experience. In 1984, the Minister of Industry announced the pre-selection of 3 counties out of the inventory for preliminary studies that allowed to select l' Aube as a potential site for the new French disposal 'Centre de l'Aube'. The different steps of the process and procedure that brought to the acceptance of the first packages in January 1992 is presented in the paper, as well as the experience recently gained since that date. This additional know-how and expertise is made available by Andra through agreements already existing with various Countries like, among others, Spain, the United States, and Mexico

  8. Cataract surgery in a case of carotid cavernous fistula

    Science.gov (United States)

    Nair, Akshay Gopinathan; Praveen, Smita Vittal; Noronha, Veena Olma

    2014-01-01

    A carotid-cavernous fistula (CCF) is an abnormal communication between the cavernous sinus and the carotid arterial system. The ocular manifestations include conjunctival chemosis, proptosis, globe displacement, raised intraocular pressure and optic neuropathy. Although management of CCF in these patients is necessary, the ophthalmologist may also have to treat other ocular morbidities such as cataract. Cataract surgery in patients with CCF may be associated with many possible complications, including suprachoroidal hemorrhage. We describe cataract extraction surgery in 60-year-old female with bilateral spontaneous low-flow CCF. She underwent phacoemulsification via a clear corneal route under topical anesthesia and had an uneventful postoperative phase and recovered successfully. Given the various possible ocular changes in CCF, one must proceed with an intraocular surgery with caution. In this communication, we wish to describe the surgical precautions and the possible pitfalls in cataract surgery in patients with CCF. PMID:25370401

  9. Sensitivity of storage field performance to geologic and cavern design parameters in salt domes.

    Energy Technology Data Exchange (ETDEWEB)

    Ehgartner, Brian L. (Sandia National Laboratories, Albuquerque, NM); Park, Byoung Yoon

    2009-03-01

    A sensitivity study was performed utilizing a three dimensional finite element model to assess allowable cavern field sizes for strategic petroleum reserve salt domes. A potential exists for tensile fracturing and dilatancy damage to salt that can compromise the integrity of a cavern field in situations where high extraction ratios exist. The effects of salt creep rate, depth of salt dome top, dome size, caprock thickness, elastic moduli of caprock and surrounding rock, lateral stress ratio of surrounding rock, cavern size, depth of cavern, and number of caverns are examined numerically. As a result, a correlation table between the parameters and the impact on the performance of storage field was established. In general, slower salt creep rates, deeper depth of salt dome top, larger elastic moduli of caprock and surrounding rock, and a smaller radius of cavern are better for structural performance of the salt dome.

  10. Long term storage of finished gasolines in large salt caverns

    Energy Technology Data Exchange (ETDEWEB)

    Koenig, J.W.J. [German Strategic Petroleum Reserve, Hamburg (Germany)

    1995-05-01

    Strategic oil stocking requires large low cost storage facilities. Crude oil has been held in very large salt mines and/or artificially made salt caverns for many years, notably in Europe and the USA. Following crude oil, gasoils and refinery light feed stocks have been tried also. Military organisations tried jet fuel and early cases of underground aviation gasoline storage in steel tanks have been reported.

  11. Endovascular treatment of carotid-cavernous vascular lesions

    Directory of Open Access Journals (Sweden)

    GUILHERME BRASILEIRO DE AGUIAR

    Full Text Available ABSTRACT Objective: to evaluate the endovascular treatment of vascular lesions of the cavernous segment of the internal carotidartery (ICA performed at our institution. Methods: we conducted a descriptive, retrospective and prospective study of patients with aneurysms of the cavernous portion of the ICA or with direct carotid-cavernous fistulas (dCCF undergoing endovascular treatment. Results: we included 26 patients with intracavernous aneurysms and ten with dCCF. All aneurysms were treated with ICA occlusion. Those with dCCF were treated with occlusion in seven cases and with selective fistula occlusion in the remaining three. There was improvement of pain and ocular proptosis in all patients with dCCF. In patients with intracavernous aneurysms, the incidence of retro-orbital pain fell from 84.6% to 30.8% after treatment. The endovascular treatment decreased the dysfunction of affected cranial nerves in both groups, especially the oculomotor one. Conclusion: the endovascular treatment significantly improved the symptoms in the patients studied, especially those related to pain and oculomotor nerve dysfunction.

  12. [A case of multiple cavernous angioma with dementia].

    Science.gov (United States)

    Kariya, S; Kawahara, M; Suzumura, A

    2000-10-01

    We reported a 65-year-old man who developed dementia since 50 years of age. His consciousness was clear but he was indifferent to his illness. Also, the luck of attention was recognized when we underwent examinations and the result of intellectual test varied every time we performed. His memory function was almost normal on the examination which was performed when he was cooperative. Magnetic resonance imaging (MRI) disclosed multiple tiny lesions (more than 130 in all) in cerebrum, brainstem, cerebellum and spinal cord. These lesions were compatible with multiple cavernous angioma. Most of lesions manifested high-density area on cranial CT. Though the multiplicity of foci indicated the possibility of familial occurrence, he was considered to be a sporadic case on his lineage investigation and the brain MRI of his only son. In this case, neither headache nor seizures which were known as the major clinical features of intracerebral cavernous angioma was observed. He was diagnosed as having white matter dementia characterized by attentional dysfunction, decrement of volition and less memory disturbance. We speculated that he developed symptomatic dementia by the sum of multiple minor degeneration, especially in frontal lobe white matter, caused by repeated minor bleeding from cavernous angiomas.

  13. Gas hydrates in gas storage caverns; Gashydrate bei der Gaskavernenspeicherung

    Energy Technology Data Exchange (ETDEWEB)

    Groenefeld, P. [Kavernen Bau- und Betriebs-GmbH, Hannover (Germany)

    1997-12-31

    Given appropriate pressure and temperature conditions the storage of natural gas in salt caverns can lead to the formation of gas hydrates in the producing well or aboveground operating facilities. This is attributable to the stored gas becoming more or less saturated with water vapour. The present contribution describes the humidity, pressure, and temperature conditions conducive to gas hydrate formation. It also deals with the reduction of the gas removal capacity resulting from gas hydrate formation, and possible measures for preventing hydrate formation such as injection of glycol, the reduction of water vapour absorption from the cavern sump, and dewatering of the cavern sump. (MSK) [Deutsch] Bei der Speicherung von Erdgas in Salzkavernen kann es unter entsprechenden Druck- und Temperaturverhaeltnissen zur Gashydratbildung in den Foerdersonden oder obertaegigen Betriebseinrichtungen kommen, weil sich das eingelagerte Gas mehr oder weniger mit Wasserdampf aufsaettigt. Im Folgenden werden die Feuchtigkeits-, Druck- und Temperaturbedingungen, die zur Hydratbildung fuehren erlaeutert. Ebenso werden die Verringerung der Auslagerungskapazitaet durch die Hydratbildung, Massnahmen zur Verhinderung der Hydratbildung wie die Injektion von Glykol, die Verringerung der Wasserdampfaufnahme aus dem Kavernensumpf und die Entwaesserung der Kavernensumpfs selbst beschrieben.

  14. Waste Disposal

    International Nuclear Information System (INIS)

    Neerdael, B.; Marivoet, J.; Put, M.; B-Verstricht, J.; Van Iseghem, P.; Buyens, M.

    1998-01-01

    This contribution describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 1997 in three topical areas are reported on: performance assessments, waste forms/packages and near-and far field studies

  15. Advanced Gas Storage Concepts: Technologies for the Future

    Energy Technology Data Exchange (ETDEWEB)

    Freeway, Katy (PB-KBB Inc.); Rogers, R.E. (Mississippi State University); DeVries, Kerry L.; Nieland, Joel D.; Ratigan, Joe L.; Mellegard, Kirby D. (RESPEC)

    2000-02-01

    This full text product includes: 1) A final technical report titled Advanced Underground Gas Storage Concepts, Refrigerated-Mined Cavern Storage and presentations from two technology transfer workshops held in 1998 in Houston, Texas, and Pittsburgh, Pennsylvania (both on the topic of Chilled Gas Storage in Mined Caverns); 2) A final technical report titled Natural Gas Hydrates Storage Project, Final Report 1 October 1997 - 31 May 1999; 3) A final technical report titled Natural Gas Hydrates Storage Project Phase II: Conceptual Design and Economic Study, Final Report 9 June - 10 October 1999; 4) A final technical report titled Commerical Potential of Natural Gas Storage in Lined Rock Caverns (LRC) and presentations from a DOE-sponsored workshop on Alternative Gas Storage Technologies, held Feb 17, 2000 in Pittsburgh, PA; and 5) Phase I and Phase II topical reports titled Feasibility Study for Lowering the Minimum Gas Pressure in Solution-Mined Caverns Based on Geomechanical Analyses of Creep-Induced Damage and Healing.

  16. Impact of corrosion-derived iron on the bentonite buffer within the KBS-3H disposal concept. The Olkiluoto site as case study

    International Nuclear Information System (INIS)

    Wersin, P.; Birgersson, M.; Olsson, S.; Karnland, O.; Snellman, M.

    2007-12-01

    Steel components are unstable in EBS (Engineered Barrier System) environments. They will corrode to fairly insoluble corrosion products, such as magnetite, and also react with the smectitic matrix of the bentonite buffer. In this study, the impact of reduced iron on the buffer's stability has been assessed within the framework of the KBS-H concept. Our work includes two parts. In the first part, available data from experimental and modelling studies have been compiled and interpreted. In the second part, a relatively simple geochemical modelling exercise on the iron-bentonite interaction in the current KBS-3H disposal system has been performed using Olkiluoto as test case. The iron in this case stems from the perforated supercontainer steel shell foreseen to be emplaced around the buffer material. The iron-bentonite interaction under reducing conditions may involve different processes including sorption, redox and dissolution / precipitation reactions, the details of which are not yet understood. One process to consider is the sorption of corrosion-derived Fe(II). This process is fast and leads to strong binding of Fe(II) at the smectite surface. Whether this sorption reaction is accompanied by a redox and surface precipitation reaction is presently not clear. A further process to consider under very reducing conditions is the reduction of structural Fe(III) in the clay which may destabilise the montmorillonite structure. The process of greatest relevance for the buffer's performance is montmorillonite transformation in contact with reduced iron. This process is very slow and experimentally difficult to investigate. Current data suggest that the transformation process may either lead to a Fe-rich smectite (e.g. saponite) or to a non-swelling clay (berthierine or chlorite). In addition, cementation due to precipitation of iron corrosion products or of SiO 2 resulting from montmorillonite transformation may occur. Physical properties of the buffer may in principle be

  17. Impact of corrosion-derived iron on the bentonite buffer within the KBS-3H disposal concept. The Olkiluoto site as case study

    Energy Technology Data Exchange (ETDEWEB)

    Wersin, P. (Gruner AG, Basel (Switzerland)); Birgersson, M.; Olsson, S.; Karnland, O. (Clay Technology, Lund (Sweden)); Snellman, M. (Saanio and Riekkola Oy, Helsinki (Finland))

    2007-12-15

    Steel components are unstable in EBS (Engineered Barrier System) environments. They will corrode to fairly insoluble corrosion products, such as magnetite, and also react with the smectitic matrix of the bentonite buffer. In this study, the impact of reduced iron on the buffer's stability has been assessed within the framework of the KBS-H concept. Our work includes two parts. In the first part, available data from experimental and modelling studies have been compiled and interpreted. In the second part, a relatively simple geochemical modelling exercise on the iron-bentonite interaction in the current KBS-3H disposal system has been performed using Olkiluoto as test case. The iron in this case stems from the perforated supercontainer steel shell foreseen to be emplaced around the buffer material. The iron-bentonite interaction under reducing conditions may involve different processes including sorption, redox and dissolution / precipitation reactions, the details of which are not yet understood. One process to consider is the sorption of corrosion-derived Fe(II). This process is fast and leads to strong binding of Fe(II) at the smectite surface. Whether this sorption reaction is accompanied by a redox and surface precipitation reaction is presently not clear. A further process to consider under very reducing conditions is the reduction of structural Fe(III) in the clay which may destabilise the montmorillonite structure. The process of greatest relevance for the buffer's performance is montmorillonite transformation in contact with reduced iron. This process is very slow and experimentally difficult to investigate. Current data suggest that the transformation process may either lead to a Fe-rich smectite (e.g. saponite) or to a non-swelling clay (berthierine or chlorite). In addition, cementation due to precipitation of iron corrosion products or of SiO{sub 2} resulting from montmorillonite transformation may occur. Physical properties of the buffer may

  18. Impact of corrosion-derived iron on the bentonite buffer within the KBS-3H disposal concept. The Olkiluoto site as case study

    International Nuclear Information System (INIS)

    Wersin, Paul; Birgersson, Martin; Olsson, Siv; Karnland, Ola; Snellman, Margit

    2008-05-01

    Steel components are unstable in EBS environments. They will corrode to fairly insoluble corrosion products, such as magnetite, and also react with the smectitic matrix of the bentonite buffer. In this study, the impact of reduced iron on the buffer's stability has been assessed within the framework of the KBS-H concept. Our work includes two parts. In the first part, available data from experimental and modelling studies have been compiled and interpreted. In the second part, a relatively simple geochemical modelling exercise on the iron-bentonite interaction in the current KBS-3H disposal system has been performed using Olkiluoto as test case. The iron in this case stems from the perforated supercontainer steel shell foreseen to be emplaced around the buffer material. The iron-bentonite interaction under reducing conditions may involve different processes including sorption, redox and dissolution/precipitation reactions, the details of which are not yet understood. One process to consider is the sorption of corrosion-derived Fe(II). This process is fast and leads to strong binding of Fe(II) at the smectite surface. Whether this sorption reaction is accompanied by a redox and surface precipitation reaction is presently not clear. A further process to consider under very reducing conditions is the reduction of structural Fe(III) in the clay which may destabilise the montmorillonite structure. The process of greatest relevance for the buffer's performance is montmorillonite transformation in contact with reduced iron. This process is very slow and experimentally difficult to investigate. Current data suggest that the transformation process may either lead to a Fe-rich smectite (e.g. saponite) or to a non-swelling clay (berthierine or chlorite). In addition, cementation due to precipitation of iron corrosion products or of SiO 2 resulting from montmorillonite transformation may occur. Physical properties of the buffer may in principle be affected by montmorillonite

  19. Impact of corrosion-derived iron on the bentonite buffer within the KBS-3H disposal concept. The Olkiluoto site as case study

    Energy Technology Data Exchange (ETDEWEB)

    Wersin, Paul (National Cooperative for the Disposal of Radioactive Waste, Nagra, Wettingen (Switzerland)); Birgersson, Martin; Olsson, Siv; Karnland, Ola (Clay Technology AB, Lund (Sweden)); Snellman, Margit (Saanio and Riekkola Oy, Helsinki (Finland))

    2008-05-15

    Steel components are unstable in EBS environments. They will corrode to fairly insoluble corrosion products, such as magnetite, and also react with the smectitic matrix of the bentonite buffer. In this study, the impact of reduced iron on the buffer's stability has been assessed within the framework of the KBS-H concept. Our work includes two parts. In the first part, available data from experimental and modelling studies have been compiled and interpreted. In the second part, a relatively simple geochemical modelling exercise on the iron-bentonite interaction in the current KBS-3H disposal system has been performed using Olkiluoto as test case. The iron in this case stems from the perforated supercontainer steel shell foreseen to be emplaced around the buffer material. The iron-bentonite interaction under reducing conditions may involve different processes including sorption, redox and dissolution/precipitation reactions, the details of which are not yet understood. One process to consider is the sorption of corrosion-derived Fe(II). This process is fast and leads to strong binding of Fe(II) at the smectite surface. Whether this sorption reaction is accompanied by a redox and surface precipitation reaction is presently not clear. A further process to consider under very reducing conditions is the reduction of structural Fe(III) in the clay which may destabilise the montmorillonite structure. The process of greatest relevance for the buffer's performance is montmorillonite transformation in contact with reduced iron. This process is very slow and experimentally difficult to investigate. Current data suggest that the transformation process may either lead to a Fe-rich smectite (e.g. saponite) or to a non-swelling clay (berthierine or chlorite). In addition, cementation due to precipitation of iron corrosion products or of SiO{sub 2} resulting from montmorillonite transformation may occur. Physical properties of the buffer may in principle be affected by

  20. Preliminary long-term stability criteria for compressed air energy storage caverns in salt domes

    Energy Technology Data Exchange (ETDEWEB)

    Thoms, R.L.; Martinez, J.D.

    1978-08-01

    Air storage caverns, which are an essential and integral component of a CAES plant, should be designed and operated so as to perform satisfactorily over the intended life of the overall facility. It follows that the long-term ''stability'' of air storage caverns must be considered as a primary concern in projecting the satisfactory operation of CAES facilities. As used in the report, ''stability'' of a storage cavern implies the extent to which an acceptable amount of cavern storage volume can be utilized with routine maintenance for a specified time interval, e.g., 35 years. In this context, cavern stability is relative to both planned utilization and time interval of operation. The objective of the study was to review the existing literature and consult knowledgeable workers in the storage industry, and then report state-of-the-art findings relative to long-term stability of compressed air energy storage caverns in salt domes. Further, preliminary cavern stability criteria were to be presented in a form consistent with the amount of information available on cavern performance in salt domes. Another objective of the study was to outline a methodology for determining the long-term stability of site-specific CAES cavern systems in salt domes.

  1. Geotechnical issues and guidelines for storage of compressed air in excavated hard rock caverns

    Energy Technology Data Exchange (ETDEWEB)

    Allen, R.D.; Doherty, T.J.; Fossum, A.F.

    1982-04-01

    The results of a literature survey on the stability of excavated hard rock caverns are presented. The objective of the study was to develop geotechnical criteria for the design of compressed air energy storage (CAES) caverns in hard rock formations. These criteria involve geologic, hydrological, geochemical, geothermal, and in situ stress state characteristics of generic rock masses. Their relevance to CAES caverns, and the identification of required research areas, are identified throughout the text. This literature survey and analysis strongly suggests that the chief geotechnical issues for the development and operation of CAES caverns in hard rock are impermeability for containment, stability for sound openings, and hydrostatic balance.

  2. Technical considerations in the design of near surface disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    2001-11-01

    Good design is an important step towards ensuring operational as well as long term safety of low and intermediate level waste (LILW) disposal. The IAEA has produced this report with the objective of outlining the most important technical considerations in the design of near surface disposal facilities and to provide some examples of the design process in different countries. This guidance has been developed in light of experience gained from the design of existing near surface disposal facilities in a range of Member States. In particular the report provide information on design objective, design requirements, and design phases. The report focuses on: near surface disposal facilities accepting solidified LILW; disposal facilities on or just below the ground surface, where the final protective covering is of the order of a few metres thick; and disposal facilities several tens of metres below the ground surface (including rock cavern type facilities)

  3. Underground disposal of radioactive wastes

    International Nuclear Information System (INIS)

    1981-01-01

    This report is an overview document for the series of IAEA reports dealing with underground waste disposal to be prepared in the next few years. It provides an introduction to the general considerations involved in implementing underground disposal of radioactive wastes. It suggests factors to be taken into account for developing and assessing waste disposal concepts, including the conditioned waste form, the geological containment and possible additional engineered barriers. These guidelines are general so as to cover a broad range of conditions. They are generally applicable to all types of underground disposal, but the emphasis is on disposal in deep geological formations. Some information presented here may require slight modifications when applied to shallow ground disposal or other types of underground disposal. Modifications may also be needed to reflect local conditions. In some specific cases it may be that not all the considerations dealt with in this book are necessary; on the other hand, while most major considerations are believed to be included, they are not meant to be all-inclusive. The book primarily concerns only underground disposal of the wastes from nuclear fuel cycle operations and those which arise from the use of isotopes for medical and research activities

  4. Microbial issues pertaining to the canadian concept for the disposal of nuclear fuel waste. Questions a examiner quant aux microbes lors du developpement du concept canadien de stockage permanent des dechets de combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Stroes-Gascoyne, S.; West, J.M.

    1994-01-01

    This report formulates a number of views and positions on microbiological factors that could influence the performance of a disposal vault in plutonic rock. Microbiological factors discussed include the presence and survival of microbes, biofilms, corrosion, biodegradation (of emplaced materials), gas production, geochemical changes, radionuclide migration, colloid formation, mutation, pathogens and methylation. Not all issues can be fully resolved with the current state of knowledge. Studies being performed to underscore and strengthen current knowledge are briefly discussed.

  5. Waste disposal

    CERN Multimedia

    2006-01-01

    We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container. type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3). nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.). building concerned. details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting o...

  6. Waste disposal

    CERN Multimedia

    2006-01-01

    We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container; type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3); nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.); building concerned; details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting...

  7. Geomechanical Analysis and Design Considerations for Thin-Bedded Salt Caverns. Final Report

    International Nuclear Information System (INIS)

    Michael S. Bruno

    2005-01-01

    The bedded salt formations located throughout the United States are layered and interspersed with non-salt materials such as anhydrite, shale, dolomite and limestone. The salt layers often contain significant impurities. GRI and DOE have initialized this research proposal in order to increase the gas storage capabilities by providing operators with improved geotechnical design and operating guidelines for thin bedded salt caverns. Terralog has summarized the geologic conditions, pressure conditions, and critical design factors that may lead to: (1) Fracture in heterogeneous materials; (2) Differential deformation and bedding plane slip; (3) Propagation of damage around single and multiple cavern; and (4) Improved design recommendations for single and multiple cavern configurations in various bedded salt environments. The existing caverns within both the Permian Basin Complex and the Michigan and Appalachian Basins are normally found between 300 m to 1,000 m (1,000 ft to 3,300 ft) depth depending on local geology and salt dissolution depth. Currently, active cavern operations are found in the Midland and Anadarko Basins within the Permian Basin Complex and in the Appalachian and Michigan Basins. The Palo Duro and Delaware Basins within the Permian Basin Complex also offer salt cavern development potential. Terralog developed a number of numerical models for caverns located in thin bedded salt. A modified creep viscoplastic model has been developed and implemented in Flac3D to simulate the response of salt at the Permian, Michigan and Appalachian Basins. The formulation of the viscoplastic salt model, which is based on an empirical creep law developed for Waste Isolation Pilot Plant (WIPP) Program, is combined with the Drucker-Prager model to include the formation of damage and failure. The Permian salt lab test data provided by Pfeifle et al. 1983, are used to validate the assumptions made in the material model development. For the actual cavern simulations two

  8. Overview of low level waste disposal facility costs

    International Nuclear Information System (INIS)

    Saverot, P.M.

    1995-01-01

    Economics and uncertainty go hand-in-hand and it is too soon to have conclusive data on the life cycle costs of a disposal facility. While LLW volumes from are decreasing year after year, the effect of the projected LLW volumes from decommissioning may have a significant impact on the final unit costs. This overview recognizes that countries see LLW disposal costs differently depending on the scale of their programs and on the geographical, political and economic frameworks within which they operate. The reasons for the cost differences arise from a number of factors: differences in designs and in technologies (near surface engineered vault, enhanced shallow land burial, silo type caverns,...), disposal capacities, programmatic and regulatory requirements, organizational, managerial and institutional frameworks, contractual arrangements, etc. Comparison of actual project costs, if done incorrectly, can lead to invalid conclusions and little purpose would be served by so doing since cost variations reflect the reality faced by each country

  9. Review of applicable technology: solution mining of caverns in salt domes to serve as repositories for radioactive wastes

    International Nuclear Information System (INIS)

    1976-01-01

    There is an abundance of salt domes in the Gulf Coastal region. Advances in leaching technology and cavern shape control make it possible to build large caverns with configurations approaching teardrops, cylinders, and spheres. Fenix and Scisson has designed and constructed several dozen caverns in sizes up to three million barrels (16.8 million cubic feet). It is now within current technological bounds to evacuate the brine left in the cavern following construction, dehumidify the cavern atmosphere and supply conditioned cavern ventilation. The state-of-the-art in drilling large diameter holes has advanced to the point that it is now possible to drill 120-in. holes as deep as 6,000 ft and 144-in. holes to lesser depths. Additional research is needed in the area of cavern stability. Cavern shrinkage rates are known to increase with depth because of lower salt strengths at higher pressures and temperatures

  10. HLW disposal dilemma

    International Nuclear Information System (INIS)

    Andrei, V.; Glodeanu, F.

    2003-01-01

    The radioactive waste is an inevitable residue from the use of radioactive materials in industry, research and medicine, and from the operation of generating electricity nuclear power stations. The management and disposal of such waste is therefore an issue relevant to almost all countries. Undoubtedly the biggest issue concerning radioactive waste management is that of high level waste. The long-lived nature of some types of radioactive wastes and the associated safety implications of disposal plans have raised concern amongst those who may be affected by such facilities. For these reasons the subject of radioactive waste management has taken on a high profile in many countries. Not one Member State in the European Union can say that their high level waste will be disposed of at a specific site. Nobody can say 'that is where it is going to go'. Now, there is a very broad consensus on the concept of geological disposal. The experts have little, if any doubt that we could safely dispose of the high level wastes. Large sectors of the public continue to oppose to most proposals concerning the siting of repositories. Given this, it is increasingly difficult to get political support, or even political decisions, on such sites. The failure to advance to the next step in the waste management process reinforces the public's initial suspicion and resistance. In turn, this makes the political decisions even harder. In turn, this makes the political decisions even harder. The management of spent fuel from nuclear power plant became a crucial issue, as the cooling pond of the Romanian NPP is reaching saturation. During the autumn of 2000, the plant owner proceeded with an international tendering process for the supply of a dry storage system to be implemented at the Cernavoda station to store the spent fuel from Unit 1 and eventually from Unit 2 for a minimum period of 50 years. The facility is now in operation. As concern the disposal of the spent fuel, the 'wait and see

  11. Disposal facility data for the interim performance

    International Nuclear Information System (INIS)

    Eiholzer, C.R.

    1995-01-01

    The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

  12. Analysis of cavern and well stability at the West Hackberry SPR site using a full-dome model.

    Energy Technology Data Exchange (ETDEWEB)

    Sobolik, Steven R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-08-01

    This report presents computational analyses that simulate the structural response of caverns at the Strategic Petroleum Reserve (SPR) West Hackberry site. The cavern field comprises 22 caverns. Five caverns (6, 7, 8, 9, 11) were acquired from industry and have unusual shapes and a history dating back to 1946. The other 17 caverns (101-117) were leached according to SPR standards in the mid-1980s and have tall cylindrical shapes. The history of the caverns and their shapes are simulated in a three-dimensional geomechanics model of the site that predicts deformations, strains, and stresses. Future leaching scenarios corresponding to oil drawdowns using fresh water are also simulated by increasing the volume of the caverns. Cavern pressures are varied in the model to capture operational practices in the field. The results of the finite element model are interpreted to provide information on the current and future status of subsidence, well integrity, and cavern stability. The most significant results in this report are relevant to Cavern 6. The cavern is shaped like a bowl with a large ceiling span and is in close proximity to Cavern 9. The analyses predict tensile stresses at the edge of the ceiling during repressurization of Cavern 6 following workover conditions. During a workover the cavern is at low pressure to service a well. The wellhead pressures are atmospheric. When the workover is complete, the cavern is repressurized. The resulting elastic stresses are sufficient to cause tension around the edge of the large ceiling span. With time, these stresses relax to a compressive state because of salt creep. However, the potential for salt fracture and propagation exists, particularly towards Cavern 9. With only 200 feet of salt between the caverns, the operational consequences must be examined if the two caverns become connected. A critical time may be during a workover of Cavern 9 in part because of the operational vulnerabilities, but also because dilatant damage

  13. Efficiency analyses of the CANDU spent fuel repository using modified disposal canisters for a deep geological disposal system design

    International Nuclear Information System (INIS)

    Lee, J.Y.; Cho, D.K.; Lee, M.S.; Kook, D.H.; Choi, H.J.; Choi, J.W.; Wang, L.M.

    2012-01-01

    Highlights: ► A reference disposal concept for spent nuclear fuels in Korea has been reviewed. ► To enhance the disposal efficiency, alternative disposal concepts were developed. ► Thermal analyses for alternative disposal concepts were performed. ► From the result of the analyses, the disposal efficiency of the concepts was reviewed. ► The most effective concept was suggested. - Abstract: Deep geological disposal concept is considered to be the most preferable for isolating high-level radioactive waste (HLW), including nuclear spent fuels, from the biosphere in a safe manner. The purpose of deep geological disposal of HLW is to isolate radioactive waste and to inhibit its release of for a long time, so that its toxicity does not affect the human beings and the biosphere. One of the most important requirements of HLW repository design for a deep geological disposal system is to keep the buffer temperature below 100 °C in order to maintain the integrity of the engineered barrier system. In this study, a reference disposal concept for spent nuclear fuels in Korea has been reviewed, and based on this concept, efficient alternative concepts that consider modified CANDU spent fuels disposal canister, were developed. To meet the thermal requirement of the disposal system, the spacing of the disposal tunnels and that of the disposal pits for each alternative concept, were drawn following heat transfer analyses. From the result of the thermal analyses, the disposal efficiency of the alternative concepts was reviewed and the most effective concept suggested. The results of these analyses can be used for a deep geological repository design and detailed analyses, based on exact site characteristics data, will reduce the uncertainty of the results.

  14. Geological disposal of high-level radioactive wastes. Historical perspective and contemporary issues

    International Nuclear Information System (INIS)

    Ahn, Joonhong

    2013-01-01

    The contemporary concept on the geological disposal of radioactive wastes, the position of Japan in the world stream of geological disposal, and the ideal aspect of the Japanese geological disposal after the Fukushima accident are described. (M.H.)

  15. Pregnancy-related spinal epidural capillary-cavernous haemangioma: magnetic resonance imaging and differential diagnosis

    International Nuclear Information System (INIS)

    Hakan, T.; Berkman, M.Z.; Demir, M.K.; Aker, F.V.

    2007-01-01

    Full text: Epidural haemangiomas are very rare tumours of the spine. Only a few case reports have been published and most of them were cavernous or capillary. To the best of our knowledge, we report the first case of a histologically confirmed epidural capillary-cavernous haemangioma of the thoracic spine presented in the MRI

  16. Electrical properties of air in the Carlsbad Caverns

    International Nuclear Information System (INIS)

    Wilkening, M.; Romero, V.

    1980-01-01

    Radon 222 and its daughter product concentrations in the Carlsbad Caverns are higher than in outdoor air by a factor of several hundred. The effects of the radiation from these substances on the electrical properties of air in the cave have been studied. The rate of ion-pair production, the ion density, and the electrical conductivity are much higher in the Cave than in outdoor air. The mobility of the ions is less than outdoors due to the high humidity and low condensation nuclei concentration. A small net space charge produces a barely detectable electric field of the order of one percent of the earth's fair weather field

  17. Adrenal cavernous hemangioma: MRI, CT, and US appearance

    International Nuclear Information System (INIS)

    Marotti, M.; Sucic, Z.; Krolo, I.; Dimanovski, J.; Klaric, R.; Ferencic, Z.; Karapanda, N.; Babic, N.; Pavlekovic, K.

    1997-01-01

    Two cases of rare adrenal cavernous hemangiomas are reported, one imaged with conventional X-ray techniques, US, CT, and MRI, and the other with US and CT. The CT technique clearly demonstrated calcifications and the internal structure of the lesions in both cases and peripheral rim enhancement on the postcontrast scan in one patient. Although MRI demonstrated accurately the complex nature of the lesion, the inability to visualize the calcified areas do not allow to make a specific histologic diagnosis. (orig.). With 8 figs

  18. An interesting case of angiogenesis in cavernous hemangioma

    Directory of Open Access Journals (Sweden)

    Dipankar Das

    2016-01-01

    Full Text Available Cavernous hemangioma is the most common orbital tumor in adult. There is lot of literatures for clinicopathological features of this tumor. These tumors had been studied for the model of angiogenesis in many of the experimental setups. We present a case of 34-year-old male with this tumor in the left eye with computerized tomography evidence. Postsurgical laboratory findings gave interesting evidence of tumor angiogenesis with tumor endothelial cells and sprouting of the small vessels endothelial cells. Podosome rosette could be conceptualized from the characteristic patterns seen in the tumor.

  19. [Pontine cavernous angioma (cavernoma) with initial ENT manifestations].

    Science.gov (United States)

    Pino Rivero, V; González Palomino, A; Pantoja Hernández, C G; Trinidad Ruíz, G; Marqués Rebollo, L; Blasco Huelva, A

    2006-01-01

    We report the case of a 22 years old female who consulted us for facial parestesias, hearing loss in right ear and sudden tinnitus. Her audiometry showed an unilateral discreet sensorineural hipoacusia and the cranial IRM, a mass of 20 mm diameter in right pontine region and bulbus informed as cavernous angioma with signs of recent bleeding. The patient was sent to Neurosurgery but she refused the intervention. The risk of hemorrhage in the cavernomas is estimated at 0.25% to 1.6% per year and represents the main reason to advise a surgical treatment.

  20. Shallow land disposal of radioactive waste

    International Nuclear Information System (INIS)

    1987-01-01

    The application of basic radiation protection concepts and objectives to the disposal of radioactive wastes requires the development of specific reference levels or criteria for the radiological acceptance of each type of waste in each disposal option. This report suggests a methodology for the establishment of acceptance criteria for the disposal of low-level radioactive waste containing long-lived radionuclides in shallow land burial facilities

  1. General criteria for radioactive waste disposal

    International Nuclear Information System (INIS)

    Maxey, M.N.; Musgrave, B.C.; Watkins, G.B.

    1979-01-01

    Techniques are being developed for conversion of radioactive wastes to solids and their placement into repositories. Criteria for such disposal are needed to assure protection of the biosphere. The ALARA (as low as reasonably achievable) principle should be applicable at all times during the disposal period. Radioactive wastes can be categorized into three classes, depending on the activity. Three approaches were developed for judging the adequacy of disposal concepts: acceptable risk, ore body comparison, and three-stage ore body comparison

  2. Specified radioactive waste final disposal act

    International Nuclear Information System (INIS)

    Yasui, Masaya

    2001-01-01

    Radioactive wastes must be finally and safely disposed far from human activities. Disposal act is a long-range task and needs to be understood and accepted by public for site selection. This paper explains basic policy of Japanese Government for final disposal act of specified radioactive wastes, examination for site selection guidelines to promote residential understanding, general concept of multi-barrier system for isolating the specific radioactive wastes, and research and technical development for radioactive waste management. (S. Ohno)

  3. Concepts and data-collection techniques used in a study of the unsaturated zone at a low-level radioactive-waste disposal site near Sheffield, Illinois

    Science.gov (United States)

    Healy, R.W.; DeVries, M.P.; Striegl, Robert G.

    1986-01-01

    A study of water and radionuclide movement through the unsaturated zone is being conducted at the low level radioactive waste disposal site near Sheffield, Illinois. Included in the study are detailed investigations of evapotranspiration, movement of water through waste trench covers, and movement of water and radionuclides (dissolved and gaseous) from the trenches. An energy balance/Bowen ratio approach is used to determine evapotranspiration. Precipitation, net radiation, soil-heat flux, air temperature and water vapor content gradients, wind speed, and wind direction are measured. Soil water tension is measured with tensiometers which are connected to pressure transducers. Meteorological sensors and tensiometers which are connected to pressure transducers. Meteorological sensors and tensiometers are monitored with automatic data loggers. Soil moisture contents are measured through small-diameter access tubes with neutron and gamma-ray attenuation gages. Data beneath the trenches are obtained through a 130-meter-long tunnel which extends under four of the trenches. Water samples are obtained with suction lysimeters, and samples of the geologic material are obtained with core tubes. These samples are analyzed for radiometric and inorganic chemistry. Gas samples are obtained from gas piezometers and analyzed for partial pressures of major constituents, Radon-222, tritiated water vapor, and carbon-14 dioxide. (USGS)

  4. Cavernous sinus hemangioma: a fourteen year single institution experience.

    Science.gov (United States)

    Bansal, Sumit; Suri, Ashish; Singh, Manmohan; Kale, Shashank Sharad; Agarwal, Deepak; Sharma, Manish Singh; Mahapatra, Ashok Kumar; Sharma, Bhawani Shankar

    2014-06-01

    Cavernous sinus hemangioma (CSH) is a rare extra-axial vascular neoplasm that accounts for 2% to 3% of all cavernous sinus tumors. Their location, propensity for profuse bleeding during surgery, and relationship to complex neurovascular structures are factors which present difficulty in excising these lesions. The authors describe their experience of 22 patients with CSH over 14 years at a tertiary care center. Patients were managed with microsurgical resection using a purely extradural transcavernous approach (13 patients) and with Gamma Knife radiosurgery (GKRS; Elekta AB, Stockholm, Sweden) (nine patients). Retrospective data analysis found headache and visual impairment were the most common presenting complaints, followed by facial hypesthesia and diplopia. All but one patient had complete tumor excision in the surgical series. Transient ophthalmoparesis (complete resolution in 6-8 weeks) was the most common surgical complication. In the GKRS group, marked tumor shrinkage (>50% tumor volume reduction) was achieved in two patients, slight shrinkage in five and no change in two patients, with symptom improvement in the majority of patients. To our knowledge, we describe one of the largest series of CSH managed at a single center. Although microsurgical resection using an extradural transcavernous approach is considered the treatment of choice in CSH and allows complete excision with minimal mortality and long-term morbidity, GKRS is an additional tool for treating residual symptomatic lesions or in patients with associated comorbidities making surgical resection unsuitable. Copyright © 2013. Published by Elsevier Ltd.

  5. Cavern background measurement with the ATLAS RPC system

    CERN Document Server

    Aielli, G; The ATLAS collaboration

    2012-01-01

    The measurement of cavern background has been carried out systematically since the beginning of LHC, as soon as the luminosity produced a detectable signal, from L = 10^28 cm^2s^1 of the early 2010 operation up to L=10^28 cm^2s^1 at the end of 2011 proton-proton run, which is just 1/3 of the nominal LHC luminosity. The reason for this is to early foresee the running condition for the detector for the nominal LHC luminosity and beyond, in view of the super-LHC upgrade. Background Montecarlo calculations have been validated against data and the background map analysis pointed out hotspots due to localized cracks in the radiation shielding. The RPCs participated to this effort since the earliest stages providing an accurate correlation between luminosity and background, a 3D background map in the barrel region and a direct measurement of the cavern activation. Moreover due to the high sensitivity and very good signal to noise ratio of the proposed method, based on the gap current, the measurement was provided in...

  6. Cavern background measurement with the ATLAS RPC system

    CERN Document Server

    Aielli, G; The ATLAS collaboration

    2012-01-01

    The measurement of cavern background has been carried out systematically since the beginning of LHC, as soon as the luminosity produced a detectable signal, from L=1028 cm-2s-1 of the early 2010 operation up to L=3.5x1033 cm-2s-1 at the end of 2011 proton-proton run, which is just 1/3 of the nominal LHC luminosity. The reason for this is to early foresee the running condition for the detector for the nominal LHC luminosity and beyond, in view of the super-LHC upgrade. Background Montecarlo calculations have been validated against data and the background map analysis pointed out hotspots due to localized cracks in the radiation shielding. The RPCs participated to this effort since the earliest stages providing an accurate correlation between luminosity and background, a 3D background map in the barrel region and a direct measurement of the cavern activation. Moreover due to the high sensitivity and very good signal to noise ratio of the proposed method, based on the gap current, the measurement was provided in...

  7. Nitrogen Monitoring of West Hackberry 117 Cavern Wells

    Energy Technology Data Exchange (ETDEWEB)

    Bettin, Giorgia [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lord, David L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-02-01

    U.S. Strategic Petroleum Reserve (SPR) oil storage cavern West Hackberry 117 was tested under extended nitrogen monitoring following a successful mechanical integrity test in order to validate a newly developed hydrostatic column model to be used to differentiate between normal "tight" well behavior and small-leak behavior under nitrogen. High resolution wireline pressure and temperature data were collected during the test period and used in conjunction with the hydrostatic column model to predict the nitrogen/oil interface and the pressure along the entire fluid column from the bradenhead flange nominally at ground surface to bottom of brine pool. Results here and for other SPR caverns have shown that wells under long term nitrogen monitoring do not necessarily pressurize with a relative rate (P N2 /P brine) of 1. The theoretical relative pressure rate depends on the well configuration, pressure and the location of the nitrogen-oil interface and varies from well to well. For the case of WH117 the predicted rates were 0.73 for well A and 0.92 for well B. The measured relative pressurization rate for well B was consistent with the model prediction, while well A rate was found to be between 0.58-0.68. A number of possible reasons for the discrepancy between the model and measured rates of well A are possible. These include modeling inaccuracy, measurement inaccuracy or the possibility of the presence of a very small leak (below the latest calculated minimum detectable leak rate).

  8. Waste and Disposal: Demonstration

    International Nuclear Information System (INIS)

    Neerdael, B.; Buyens, M.; De Bruyn, D.; Volckaert, G.

    2002-01-01

    Within the Belgian R and D programme on geological disposal, demonstration experiments have become increasingly important. In this contribution to the scientific report 2001, an overview is given of SCK-CEN's activities and achievements in the field of large-scale demonstration experiments. In 2001, main emphasis was on the PRACLAY project, which is a large-scale experiment to demonstrate the construction and the operation of a gallery for the disposal of HLW in a clay formation. The PRACLAY experiment will contribute to enhance understanding of water flow and mass transport in dense clay-based materials as well as to improve the design of the reference disposal concept. In the context of PRACLAY, a surface experiment (OPHELIE) has been developed to prepare and to complement PRACLAY-related experimental work in the HADES Underground Research Laboratory. In 2001, efforts were focussed on the operation of the OPHELIE mock-up. SCK-CEN also contributed to the SELFRAC roject which studies the self-healing of fractures in a clay formation

  9. Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

    International Nuclear Information System (INIS)

    Lee, Seunghee; Kim, Juyoul

    2017-01-01

    Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • 14 C, 226 Ra, 241 Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing 14 C, 226 Ra and 241 Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10 −7 mSv/yr, for both disposal options and satisfied the regulatory limit of 0.1 mSv/yr. However, in the

  10. Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seunghee; Kim, Juyoul, E-mail: gracemi@fnctech.com

    2017-03-15

    Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • {sup 14}C, {sup 226}Ra, {sup 241}Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing {sup 14}C, {sup 226}Ra and {sup 241}Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10{sup −7} mSv/yr, for both disposal options and satisfied the regulatory limit

  11. Whither nuclear waste disposal?

    International Nuclear Information System (INIS)

    Cotton, T.A.

    1990-01-01

    With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site

  12. Whither nuclear waste disposal?

    Energy Technology Data Exchange (ETDEWEB)

    Cotton, T A [JK Research Associates, Silver Spring, MD (United States)

    1990-07-01

    With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site.

  13. Improvement in Visual Symptomatology after Endovascular Treatment of Cavernous Carotid Aneurysms: A Multicenter Study.

    Science.gov (United States)

    Drazin, Doniel; Choulakian, Armen; Nuño, Miriam; Gandhi, Ravi; Edgell, Randall C; Alexander, Michael J

    2013-06-01

    Aneurysms arising from the cavernous internal carotid artery (CCAs) pose technical challenges for surgical management and such patients are frequently referred for endovascular treatment. These aneurysms often produce a variety of neurological deficits, primarily those related to oculoparesis. Our purpose was to determine the visual and neurological outcome of patients with treated CCAs. We reviewed the medical records and angiograms for patients who underwent endovascular treatment for CCAs at three academic medical centers. The following outcomes were analyzed: angiographic assessment, visual improvement and outcome at 3 months using Glasgow Outcome Scale (GOS). Thirty-four patients (mean age 54.7 years) were treated for CCAs. The mean aneurysm size was 14.2 mm (range: 3-45 mm), and fourteen patients (41.2%) required stent assistance. Twenty-one aneurysms (61.8%) were completely occluded; nine aneurysms (26.6%) had near-complete occlusion; 4 aneurysms (11.8%) had partial occlusion. Seven patients (20.6%) required retreatment. Fifteen of the 34 patients (44.1%) presented with visual symptoms, while only eight patients had residual visual symptomatology at follow-up (44.1% vs. 23.5%; p=0.02). Patients that presented with visual symptoms (N=15) had a mean aneurysm size of 24.5 mm, while those without visual symptoms (N=19) had a size of 7.5 mm (p=0.001). Follow-up GOS was good (4-5) in 29 patients (90.6%). No thromboembolic complications were observed. One patient died (3.1%) of an unrelated cause. Most patients in this multicenter series improved or remained stable after treatment. The results of this study indicate that endovascular treatment may improve the outcome of visual symptoms in patients with large cavernous aneurysms with low periprocedural morbidity. MJA is a consultant for Stryker and Codman. AC receives a Cordis Endovascular Fellowship Training Grant and a Stryker Endovascular Neurosurgery Post-graduate Fellow Grant. Dr. Drazin: Conception and Design

  14. Literature Survey Concerning the Feasibility of Remedial Leach for Select Phase I Caverns

    Energy Technology Data Exchange (ETDEWEB)

    Weber, Paula D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Flores, Karen A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lord, David L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    Bryan Mound 5 ( BM5 ) and West Hackberry 9 ( WH9 ) have the potential to create a significant amount of new storage space should the caverns be deemed "leach - ready". This study discusses the original drilling history of the caverns, surrounding geology, current stability, and, based on this culmination of data, makes a preliminary assessment of the leach potential for the cavern. The risks associated with leaching BM5 present substantial problems for the SPR . The odd shape and large amount of insoluble material make it difficult to de termine whether a targeted leach would have the desired effect and create useable ullage or further distort the shape with preferential leaching . T he likelihood of salt falls and damaged or severed casing string is significant . In addition, a targeted le ach would require the relocation of approximately 27 MMB of oil . Due to the abundance of unknown factors associated with this cavern, a targeted leach of BM5 is not recommended. A targeted leaching of the neck of WH 9 could potentially eliminate or diminis h the mid - cavern ledge result ing in a more stable cavern with a more favorable shape. A better understanding of the composition of the surrounding salt and a less complicated leaching history yields more confidence in the ability to successfully leach this region. A targeted leach of WH9 can be recommended upon the completion of a full leach plan with consideration of the impacts upon nearby caverns .

  15. Assessment of the Available Drawdowns for Oil Storage Caverns at the West Hackberry SPR Site

    Energy Technology Data Exchange (ETDEWEB)

    Sobolik, Steven R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Geotechnology and Engineering Dept.

    2016-03-01

    The Department of Energy, in response to requests from the U.S. Congress, wishes to maintain an up-to-date table documenting the number of available full drawdowns of each of the caverns owned by the Strategic Petroleum Reserve. This information is important for assessing the SPR’s ability to deliver oil to domestic oil companies expeditiously if national or world events dictate a rapid sale and deployment of the oil reserves. What factors go into assessing available drawdowns? The evaluation of drawdown risks require the consideration of several factors regarding cavern and wellbore integrity and stability, including stress states caused by cavern geometry and operations, salt damage caused by dilatant and tensile stresses, the effect on enhanced creep on wellbore integrity, the sympathetic stress effect of operations on neighboring caverns. Based on the work over the past several months, a consensus has been built regarding the assessment of drawdown capabilities and risks for the SPR caverns. This paper draws upon the recently West Hackberry model upgrade and analyses to reevaluate and update the available drawdowns for each of those caverns. Similar papers for the Bryan Mound, Big Hill, and Bayou Choctaw papers will be developed as the upgrades to those analyses are completed. The rationale and documentation of the methodology is described in the remainder of this report, as are the updated estimates of available drawdowns for the West Hackberry caverns.

  16. Application of radiological exclusion and exemption principles to sea disposal. The concept of 'de minimis' for radioactive substances under the London Convention 1972

    International Nuclear Information System (INIS)

    1999-03-01

    At the first Consultative Meeting of the Contracting Parties to the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (London Convention 1972) in 1975, the IAEA submitted to the Contracting Parties the provisional definition of high level wastes not suitable for dumping at sea and the recommendations concerning low level waste dumping, thus responding to the request of the Convention. The objective of this report is to respond to the request made by the Contracting Parties at their Nineteenth Consultative Meeting in 1997. It provides guidance for making judgements on whether the radiological concepts of exclusion, or exemption without further consideration, can be applied for materials planned to be dumped or whether a specific assessment is needed

  17. Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

    International Nuclear Information System (INIS)

    2003-12-01

    Radioactive waste must be managed safely, consistent with internationally agreed safety standards. The disposal method chosen for the waste should be commensurate with the hazard and longevity of the waste. Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. The term 'near surface disposal' encompasses a wide range of design options, including disposal in engineered structures at or just below ground level, disposal in simple earthen trenches a few metres deep, disposal in engineered concrete vaults, and disposal in rock caverns several tens of metres below the surface. The use of a near surface disposal option requires design and operational measures to provide for the protection of human health and the environment, both during operation of the disposal facility and following its closure. To ensure the safety of both workers and the public (both in the short term and the long term), the operator is required to design a comprehensive waste management system for the safe operation and closure of a near surface disposal facility. Part of such a system is to establish criteria for accepting waste for disposal at the facility. The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures and in addition, to prevent or limit hazards, which could arise from non-radiological causes. Waste acceptance criteria include limits on radionuclide content concentration in waste materials, and radionuclide amounts in packages and in the repository as a whole. They also include limits on quantity of free liquids, requirements for exclusion of chelating agents and pyrophoric materials, and specifications of the characteristics of the waste containers. Largely as a result of problems encountered at some disposal facilities operated in the past, in 1985 the IAEA published guidance on generic acceptance

  18. Prediction of long-term crustal movement for geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Sasaki, Takeshi; Morikawa, Seiji; Tabei, Kazuto; Koide, Hitoshi; Tashiro, Toshiharu

    2000-01-01

    Long-term stability of the geological environment is essential for the safe geological disposal of radioactive waste, for which it is necessary to predict the crustal movement during an assessment period. As a case study, a numerical analysis method for the prediction of crustal movement in Japan is proposed. A three-dimensional elastic analysis by FEM for the geological block structure of the Kinki region and the Awaji-Rokko area is presented. Stability analysis for a disposal cavern is also investigated. (author)

  19. Clinical features and management of cavernous and venous angiomas in the head

    International Nuclear Information System (INIS)

    Tokunaga, Koji; Date, Isao

    2011-01-01

    Cerebral cavernous angiomas consist of well-circumscribed collections of thin-walled sinusoidal vascular channels lacking the intervening brain tissue. They are present in 0.4-0.8% of the population, and can occur in a sporadic or familial form. Most common symptoms are seizures, hemorrhage, and focal neurological deficits. The annual bleeding rate of the patient is reported to be 0.25%-20%. High-resolution magnetic resonance imaging (MRI) is a useful diagnostic tool with a high degree of sensitivity and specificity. Microsurgical excision of the lesion is a good treatment choice for cavernous angiomas in the brain, even in the brainstem. Although stereotactic radiosurgery may reduce the incidence of rebleeding and the frequency of seizures, its indication should be carefully investigated because of the relatively high rate of radiation-induced side effects. Less frequently, cavernous angiomas can be located at the extra-axial regions of the head, which include the cavernous sinus, the orbit, and the cranial nerves. Cavernous angiomas in the cavernous sinus pose a neurosurgical challenge due to the high vascularity and involvement of the neurovascular structures, and stereotactic radiosurgery is considered as an additional option. Surgical resection is recommended for symptomatic cavernous angiomas in the orbit; however, the rate of complications after resection is not necessarily low for cavernous angiomas within the apex. Venous angiomas are anomalies of normal venous drainage, which show characteristic appearance of the drainage system in the late phase of angiography (caput medusae). They are found either alone or in combination with other vascular malformations. Conservative treatment is recommended except for patients with a large hematoma or with a coexisting cavernous angioma. (author)

  20. Financing of radioactive waste disposal

    International Nuclear Information System (INIS)

    Reich, J.

    1989-01-01

    Waste disposal is modelled as a financial calculus. In this connection the particularity is not primarily the dimension to be expected of financial requirement but above all the uncertainty of financial requirement as well as the ecological, socio-economic and especially also the temporal dimension of the Nuclear Waste Disposal project (disposal of spent fuel elements from light-water reactors with and without reprocessing, decommissioning = safe containment and disposal of nuclear power plants, permanent isolation of radioactive waste from the biosphere, intermediate storage). Based on the above mentioned factors the author analyses alternative approaches of financing or financial planning. He points out the decisive significance of the perception of risks or the evaluation of risks by involved or affected persons - i.e. the social acceptance of planned and designed waste disposal concepts - for the achievement and assessment of alternative solutions. With the help of an acceptance-specific risk measure developed on the basis of a mathematical chaos theory he illustrates, in a model, the social influence on the financing of nuclear waste disposal. (orig./HP) [de

  1. Near-surface land disposal

    International Nuclear Information System (INIS)

    Kittel, J.H.

    1989-01-01

    The Radioactive Waste Management Handbook provides a comprehensive, systematic treatment of nuclear waste management. Near-Surface Land Disposal, the first volume, is a primary and secondary reference for the technical community. To those unfamiliar with the field, it provides a bridge to a wealth of technical information, presenting the technology associated with the near-surface disposal of low or intermediate level wastes. Coverage ranges from incipient planning to site closure and subsequent monitoring. The book discusses the importance of a systems approach during the design of new disposal facilities so that performance objectives can be achieved; gives an overview of the radioactive wastes cosigned to near-surface disposal; addresses procedures for screening and selecting sites; and emphasizes the importance of characterizing sites and obtaining reliable geologic and hydrologic data. The planning essential to the development of particular sites (land acquisition, access, layout, surface water management, capital costs, etc.) is considered, and site operations (waste receiving, inspection, emplacement, closure, stabilization, etc.) are reviewed. In addition, the book presents concepts for improved confinement of waste, important aspects of establishing a monitoring program at the disposal facility, and corrective actions available after closure to minimize release. Two analytical techniques for evaluating alternative technologies are presented. Nontechnical issues surrounding disposal, including the difficulties of public acceptance are discussed. A glossary of technical terms is included

  2. Numerical simulation for excavation and long-term behavior of large-scale cavern in soft rock

    International Nuclear Information System (INIS)

    Sawada, Masataka; Okada, Tetsuji

    2010-01-01

    Low-level radioactive waste is planned to be disposed at the depth of more than 50 m in Neogene tuff or tuffaceous sandstone. Generally there are few cracks in sedimentary soft rocks, thus it is considered to be easier to determine permeability of soft rocks than that of discontinuous rocks. On the other hand, sedimentary soft rocks show strong time-dependent behavior, and they are more sensitive to heat, groundwater, and their chemical effect. Numerical method for long-term behavior of underground facilities is necessary to their design and safety assessment. Numerical simulations for excavation of test cavern in disposal site are described in this report. Our creep model was applied to these simulations. Although it is able to reproduce the behavior of soft rock observed in laboratory creep test, simulation using parameters obtained from laboratory tests predicts much larger displacement than that of measurement. Simulation using parameters modified based on in-situ elastic wave measurement and back analysis reproduces measured displacements very well. Behavior of the surrounding rock mass during resaturation after setting of the waste and the engineered barrier system is also simulated. We have a plan to investigate chemical and mechanical interaction among soft rock, tunnel supports and engineered barriers, and to make their numerical models. (author)

  3. Ocean Disposal Site Monitoring

    Science.gov (United States)

    EPA is responsible for managing all designated ocean disposal sites. Surveys are conducted to identify appropriate locations for ocean disposal sites and to monitor the impacts of regulated dumping at the disposal sites.

  4. Waste disposal: preliminary studies

    International Nuclear Information System (INIS)

    Carvalho, J.F. de.

    1983-01-01

    The problem of high level radioactive waste disposal is analyzed, suggesting an alternative for the final waste disposal from irradiated fuel elements. A methodology for determining the temperature field around an underground disposal facility is presented. (E.G.) [pt

  5. Acute presentation of solitary spinal epidural cavernous angioma in a child

    International Nuclear Information System (INIS)

    Khalatbari, M.R.; Moharamzad, Y.; Hamidi, M.

    2013-01-01

    Solitary spinal epidural cavernous angiomas are rare lesions, especially in paediatric age group. They are infrequently considered in the differential diagnosis of spinal epidural masses in children. We report a case of solitary epidural cavernous angioma of the thoracic spine in a child presenting with acute onset of back pain and myelopathy. Magnetic resonance imaging of the thoracic spine demonstrated a posterior epidural mass at T6-T8 levels with compression of the spinal cord. Using microsurgical technique and bipolar coagulation, total excision of the lesion was achieved. Histopathological examination confirmed the diagnosis of cavernous angioma. At the five-year follow-up, there was no recurrence of the tumour. (author)

  6. Research progress in hepatic cavernous hemangiomas: a comprehensive review with graphics

    International Nuclear Information System (INIS)

    Ouyang Yong; Zhang Xuejun; Ouyang Xuehui; Chao Lumeng

    2012-01-01

    The common benign tumor of the liver, cavernous hemangioma, has already been confirmed, both embryologically and pathologically, to be not a neoplasm, but a congenital vascular malformation of the liver which is resulted from the arrested development of hepatic sinusoids at embryologic stage. This paper aims to make a comprehensive description of the cavernous hemangiomas of the liver, including the lesion's blood supply, the hemodynamics, the imaging features, the classification and its interventional therapy. The relevant example illustrations, figures and graphics are accompanied with the text in order to provide the readers with an complete and up-to-date understanding of the hepatic cavernous hemangiomas. (authors)

  7. Waste disposal developments within BNFL

    International Nuclear Information System (INIS)

    Johnson, L.F.

    1989-01-01

    British Nuclear Fuels plc has broad involvement in topics of radioactive waste generation, treatment, storage and disposal. The Company's site at Drigg has been used since 1959 for the disposal of low level waste and its facilities are now being upgraded and extended for that purpose. Since September 1987, BNFL on behalf of UK Nirex Limited has been managing an investigation of the Sellafield area to assess its suitability for deep underground emplacement of low and intermediate level radioactive wastes. An approach will be described to establish a partnership with the local community to work towards a concept of monitored, underground emplacement appropriate for each waste category. (author)

  8. Nuclear fuel waste disposal in Canada

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Gillespie, P.A.

    1990-05-01

    Atomic Energy of Canada Limited (AECL) has developed a concept for disposing of Canada's nuclear fuel waste and is submitting it for review under Federal Environmental Assessment and Review Process. During this review, AECL intends to show that careful, controlled burial 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield is a safe and feasible way to dispose of Canada's nuclear fuel waste. The concept has been assessed without identifying or evaluating any particular site for disposal. AECL is now preparing a comprehensive report based on more than 10 years of research and development

  9. Nuclear fuel waste disposal in Canada

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Gillespie, P.A.

    1990-05-01

    Atomic Energy of Canada Limited (AECL) has developed a concept for disposing of Canada's nuclear fuel waste and is submitting it for review under the Federal Environmental Assessment and Review Process. During this review, AECL intends to show that careful, controlled burial 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield is a safe and feasible way to dispose of Canada's nuclear fuel waste. The concept has been assessed without identifying or evaluating any particular site for disposal. AECL is now preparing a comprehensive report based on more than 10 years of research and development

  10. Hepatocellular carcinoma with cavernous transformation of the protal vein

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Heung Suk; Lee, Seung Ro; Hahm, Chang Kok [Hanyang University College of Medicine, Seoul (Korea, Republic of)

    1985-10-15

    Twenty cases of hepatocellular carcinoma were examined by selective celiac and superior mesenteric arteriography. Obstruction of the main portal vein due to tumor thrombus was revealed in 7 cases and 3 of these cases had cavernous transformation of the portal vein (CTPV). The authors intended in this study to evaluate CTPV group and non-CTPV group clinically and radiologically. The results obtained are as follows: 1. The duration of illness was shorter in CTPV group than non- CTPV group. 2. There was no significant difference in tumor size between two groups ,and main portion of tumor was located in the right lobe in both groups. 3. Arterio portal shunt was present in 2 of 4 cases in non-CTPV group, but was no present at all in CRPV groups. 5. There wa no significant difference in blood chemistry between two groups. 6. CTPV may play an important role maintain the hepatic blood flow.

  11. Intramedullary cavernous hemangiomas, magnetic resonance studies in four patients

    International Nuclear Information System (INIS)

    Barrena, M.R.; Guelbenzu, S.; Garcia, S.; Bertrol, V.

    1998-01-01

    Intramedullary cavernous hemangiomas are vascular malformations that can be located throughout the entire central nervous system. They are more frequently found in brain than in spinal cord, where it is only possible to diagnose them by magnetic resonance (RM): We present four cases of intramedullary spinal cord cavernoma, three of which were located in the thoracic spine and one in cervical spine. Computed tomography was ineffective in their diagnosis. However, MR disclosed there presence of well-defined tumors producing a thickening of the spinal cord. The signal was heterogeneous in both T1 and T2-weighted images. There were low signal areas due to the presence of calcium and hemosiderin and high intensity signals provoked by methemoglobin within the lesions, which were scarcely enhanced by intravenous gadolinium administration. One of the lesions presented in the form of a large intramedullary hematoma. (Author) 8 refs

  12. [Neuronavigation for the resection of intracranial cavernous angiomas].

    Science.gov (United States)

    Du, G; Zhou, L

    1999-05-01

    To evaluate the use of the Stealth Station neuronavigator in conjunction with preoperative computerized tomography (CT) in the resection of intracranial cavernous angiomas (CAs). The Stealth Station neuronavigator was used to provide real-time correlation of the operating field and computerized images in 6 patients with CAs. All of them suffered from epileptic seizures. Neuronavigation-guided lesionectomy with removal of hemosiderin deposition, gliosis and calcification in all cases was performed precisely. Mean fiducial error, predicted accuracy at 10 cm, and sustained accuracy ranged from 1.65 to 4.53 mm, 1.82 to 3.28 mm, and 0.50 to 3.45 mm, respectively. The Stealth Station neuronavigator is reliable and accurate in the resection of CAs.

  13. Observations on vapor pressure in SPR caverns : sources.

    Energy Technology Data Exchange (ETDEWEB)

    Munson, Darrell Eugene

    2010-05-01

    The oil of the Strategic Petroleum Reserve (SPR) represents a national response to any potential emergency or intentional restriction of crude oil supply to this country, and conforms to International Agreements to maintain such a reserve. As assurance this reserve oil will be available in a timely manner should a restriction in supply occur, the oil of the reserve must meet certain transportation criteria. The transportation criteria require that the oil does not evolve dangerous gas, either explosive or toxic, while in the process of transport to, or storage at, the destination facility. This requirement can be a challenge because the stored oil can acquire dissolved gases while in the SPR. There have been a series of reports analyzing in exceptional detail the reasons for the increases, or regains, in gas content; however, there remains some uncertainty in these explanations and an inability to predict why the regains occur. Where the regains are prohibitive and exceed the criteria, the oil must undergo degasification, where excess portions of the volatile gas are removed. There are only two known sources of gas regain, one is the salt dome formation itself which may contain gas inclusions from which gas can be released during oil processing or storage, and the second is increases of the gases release by the volatile components of the crude oil itself during storage, especially if the stored oil undergoes heating or is subject to biological generation processes. In this work, the earlier analyses are reexamined and significant alterations in conclusions are proposed. The alterations are based on how the fluid exchanges of brine and oil uptake gas released from domal salt during solutioning, and thereafter, during further exchanges of fluids. Transparency of the brine/oil interface and the transfer of gas across this interface remains an important unanswered question. The contribution from creep induced damage releasing gas from the salt surrounding the cavern is

  14. Management of Cerebral Cavernous Malformations: From Diagnosis to Treatment

    Directory of Open Access Journals (Sweden)

    Nikolaos Mouchtouris

    2015-01-01

    Full Text Available Cerebral cavernous malformations are the most common vascular malformations and can be found in many locations in the brain. If left untreated, cavernomas may lead to intracerebral hemorrhage, seizures, focal neurological deficits, or headaches. As they are angiographically occult, their diagnosis relies on various MR imaging techniques, which detect different characteristics of the lesions as well as aiding in planning the surgical treatment. The clinical presentation and the location of the lesion are the most important factors involved in determining the optimal course of treatment of cavernomas. We concisely review the literature and discuss the advantages and limitations of each of the three available methods of treatment—microsurgical resection, stereotactic radiosurgery, and conservative management—depending on the lesion characteristics.

  15. Emergency treatment by intravascular embolization in traumatic carotid cavernous fistula

    International Nuclear Information System (INIS)

    Tang Jun; Sun Zengtao; Liu Zuoqin; Liu Yanjun; Li Fengxin

    2006-01-01

    Objective: To discuss the method of intervenfional intravascular treatment in traumatic carotid cavernous fistula (TCCF) and the significance of clinical application in emergency. Methods: In 297 eases of TCCF, 36 cases were treated by interventional intravascular embolization by detachable balloon, embolization orificium or occlusion in one side of carotid artery. In the 36 cases, serious epistaxis occurred in 22 eases, cortical vein inflow in 9 cases, intracranial hemorrhage in 3 cases, aggravation of eyesight in 3 cases, and limb dysfunction in 2 cases. Results: Fistula was successfully embolized and internal carotid artery remained patent in 19 cases. Complete embolization of orificium or internal carotid artery was achieved in 17 eases. The serious epistaxias in 22 cases and intracranial hemorrhage in 3 cases stopped. Eyesight recovered in 2 eases and improved in 1 case. Limb dysfunction improved evidently in 2 cases. Conclusion: Intravascular embolization treatment is the first therapeutic choice for TCCF, especially in emergency. It is necessary, safe and effective. (authors)

  16. Surgical treatment of cavernous malformations involving medulla oblongata.

    Science.gov (United States)

    Zhang, Si; Lin, Sen; Hui, Xuhui; Li, Hao; You, Chao

    2017-03-01

    Surgical treatment of cavernous malformations (CMs) involving medulla oblongata is more difficult than the CMs in other sites because of the surrounding vital structures. However, the distinctive features and treatment strategies have not been well illustrated. Therefore, we enrolled a total of 19 patients underwent surgical treatment of CMs involving medulla oblongata in our hospital from August 2008 to August 2014. The clinical features, surgical management and clinical outcome of these patients were retrospectively analyzed, while our institutional surgical indications, approaches and microsurgical techniques were discussed. In our study, gross total resection was achieved in 17 patients and subtotal resection in 2. Two patients underwent emergency surgeries due to severe and progressive neurological deficits. The postoperative new-onset or worsened neurological deficits occurred in 6 patients. After a mean follow-up of 45.8±22.2months, the neurological status was improved in 10 patients and remained stable in 7. The mean modified Rankin Scale (mRS) was 2.58±1.26 preoperatively, 3.11±0.99 postoperatively and 1.84±1.42 at the recent follow-up, respectively. During the follow-up period, no rehemorrhage and recurrence occurred, and the residual lesions remained stable. We recommended surgical resection of symptomatic CMs involving medulla oblongata via optimal approaches, feasible entry zones and meticulous microsurgical techniques in attempting to achieve safe resection and favorable outcome. The clinical features, surgical indications, timing and microsurgical techniques of this special entity should be distinctive from the brainstem cavernous malformations in other sites. Copyright © 2016 Elsevier Ltd. All rights reserved.

  17. Sonographic Findings of Cavernous Hemangioma in Fatty Liver

    International Nuclear Information System (INIS)

    Hahm, Jin Kyeung; Kim, Ki Whang; Yoon, Sang Wook; Kim, Tae Hoon; Lee, Jong Tae; Yoo, Hyung Sik; Kim, Myung Jin; Ji, Hoon

    1995-01-01

    Typical cavernous hemangioma presents no diagnostic difficulty at sonography. However, in cases of atypical hemangioma, further evaluation is needed to differentiate it from malignancy. On the other hand, thcechogenicity of the lesion may be iso echo or hypoecho when it occurs in association with fatty liver. We analyzed the sonographic features of hemangioma in fatty liver. We reviewed the sonograms of 22 lesions from 19 patients. We divided the lesions into two groups; the lesion measuring less than 3cm in diameter (group I) and the lesions measuring same or greater than 3cm (group II). The lesions of each group were analyzed in terms of location, shape, distinction of margin, internal echogenicity, posterior enhancement, lateral shadowing, and peritumoral hypoechoic halo. The lesions were located in subcapsular or perivascular areain 86%. They strowed round or lobulated shape with well defined margin in 82%. Internal echo of the lesions was hypoechoic in 82% and homogeneous in 64%. Posterior enhancement was seen in 77%. The posterior wall of the lesion was distinct in 68%. There was no statistical difference in incidence of each finding described above between the two groups except the internal echogenicity(p<0.05). All of the four hyperechoic lesions measured greater than 3cmin diameter, and three of them showed uneven thickness of echogenic rind. Definitive diagnosis of hemangioma could be obtained in 82%. In remaining 18% of hemangioma, the lesions showed peripheral hypoechoic halo and lateral shadowing that made the diagnosis of hemangioma difficult. However, the possibility of hemangioma could be suggested because they showed haemangiomas internal eye-catching and posterior enhancement. Hepatic cavernous hemangioma presents with variable eye-catching as compared to the surrounding tissue when it is associated with fatty liver disease, Thus, in differentiating hemangiomas from other localized hepatic mass, other characteristics such as homogeneity of the

  18. Direct carotid cavernous fistula after submucous resection of the nasal septum.

    Science.gov (United States)

    Bizri, A R; al-Ajam, M; Zaytoun, G; al-Kutoubi, A

    2000-01-01

    A carotid cavernous fistula (CCF) is an abnormal arteriovenous anastomosis between the carotid artery and the cavernous sinus. Etiologies of this condition reported in the literature so far include facial trauma, rupture of an intracavernous aneurysm of the carotid artery, Ehler-Danlos syndrome and fibromuscular dysplasia of the cerebral arteries. Such fistulae were reported as complications of rhinoplasty, transsphenoidal surgery, embolization of cavernous sinus meningioma, and rhinocerebral mucormycosis. CCF may also occur spontaneously in children or as a congenital malformation. However, to our knowledge, submucous resection of the nasal septum has not been reported before to cause direct carotid-cavernous fistula. CT and angiographic findings are presented and a review of the literature for reported causes of CCF is made as well as a brief discussion of the possible pathophysiology.

  19. Selective occlusion of a carotid sinus cavernous fistula after transsphenoidal hypophysectomy

    International Nuclear Information System (INIS)

    Lins, E.; Dietrich, U.; Wappenschmidt, J.

    1987-01-01

    A case of carotid cavernous sinus fistula following transsphenoidal hypophysectomy is reported. A selective occlusion of the fistula with patency of the carotid artery was achieved by means of a detachable balloon catheter. (orig.) [de

  20. VACUUM THERAPY – PREVENTION OF HYPOXIA OF CAVERNOUS TISSUE PATIENTS AFTER RADICAL PROSTATECTOMY

    Directory of Open Access Journals (Sweden)

    A. E. Osadchinskii

    2018-01-01

    Full Text Available Patients, after radical prostatectomy with the use of nerve-sparing techniques, without carrying out penile rehabilitation, are at risk of forming cavernous fibrosis with the emergence of subsequent persistent erectile dysfunction. In order to minimize damage to cavernous tissue and early restoration of erectile function during the period of neuropraxia, it is necessary to ensure a sufficient level of oxygenation. The role of applying vacuum in penile rehabilitation for the prevention of hypoxia of cavernous tissue is not fully understood, due to the lack of data on the gaseous composition of the blood at the time of reaching the vacuum of erection. The purpose of this work was to review the scientific studies devoted to the study of vacuum induced penile erection in animals or humans, which indicates high results due to increased oxygenation of cavernous tissue.

  1. Vascular permeability and iron deposition biomarkers in longitudinal follow-up of cerebral cavernous malformations

    DEFF Research Database (Denmark)

    Girard, Romuald; Fam, Maged D; Zeineddine, Hussein A

    2017-01-01

    OBJECTIVE Vascular permeability and iron leakage are central features of cerebral cavernous malformation (CCM) pathogenesis. The authors aimed to correlate prospective clinical behavior of CCM lesions with longitudinal changes in biomarkers of dynamic contrast-enhanced quantitative permeability (...

  2. Transient behaviour of deep underground salt caverns; Comportement transitoire des cavites salines profondes

    Energy Technology Data Exchange (ETDEWEB)

    Karimi-Jafari, M

    2007-11-15

    This work deals with the transient behaviour of deep underground salt caverns. It has been shown that a cavern is a complex system, in which there are mechanical, thermal, chemical and hydraulic evolutions. The importance of the transient evolutions, particularly the role of the 'reverse' creep in the interpretation of the tightness test in a salt cavern is revealed. Creep is characterized by a formulation of the behaviour law which presents the advantage, in a practical point of view, to only have a reduced number of parameters while accounting of the essential of what it is observed. The initiation of the rupture in the effective traction in a salt cavern rapidly pressurized is discussed. A model fitted to a very long term behaviour (after abandonment) is developed too. In this case too, a lot of phenomena, more or less coupled, occur, when the existing literature took only into account some phenomena. (O.M.)

  3. Dural carotid cavernous sinus fistula presenting as isolated oculomotor nerve palsy: Case report

    Directory of Open Access Journals (Sweden)

    Şehnaz Arıcı

    2015-04-01

    Full Text Available Indirect (dural carotid cavernous fistula is formed by the connection between meningeal branches of the internal carotid artery and the cavernous sinüs, and low flow circulation with low pressure is occured. Proptosis, ophtalmoplegia, headache, scleral and conjuctival hyperemia expanding around the eyeball can be observed. A forty-eight year old female patient with a background of diabetes mellitus and hypertension was admitted with complaints of double vision. Isolated oculomotor nerve palsy was found in neurological examination and an indirect carotid cavernous fistula was revealed by digital subtraction angiography. Our case with carotid cavernous fistula as a rare cause of isolated oculomotor nerve palsy is worth to be reported.

  4. EXAMINE AND EVALUATE A PROCESS TO USE SALT CAVERNS TO RECEIVE SHIP BORNE LIQUEFIED NATURAL GAS

    Energy Technology Data Exchange (ETDEWEB)

    Michael M. McCall; William M. Bishop; D. Braxton Scherz

    2003-04-24

    The goal of the U.S. Department of Energy cooperative research project is to define, describe, and validate, a process to utilize salt caverns to receive and store the cargoes of LNG ships. The project defines the process as receiving LNG from a ship, pumping the LNG up to cavern injection pressures, warming it to cavern compatible temperatures, injecting the warmed vapor directly into salt caverns for storage, and distribution to the pipeline network. The performance of work under this agreement is based on U.S. Patent 5,511,905, and other U.S. and Foreign pending patent applications. The cost sharing participants in the research are The National Energy Technology Laboratory (U.S. Department of Energy), BP America Production Company, Bluewater Offshore Production Systems (U.S.A.), Inc., and HNG Storage, L.P. Initial results indicate that a salt cavern based receiving terminal could be built at about half the capital cost, less than half the operating costs and would have significantly higher delivery capacity, shorter construction time, and be much more secure than a conventional liquid tank based terminal. There is a significant body of knowledge and practice concerning natural gas storage in salt caverns, and there is a considerable body of knowledge and practice in handling LNG, but there has never been any attempt to develop a process whereby the two technologies can be combined. Salt cavern storage is infinitely more secure than surface storage tanks, far less susceptible to accidents or terrorist acts, and much more acceptable to the community. The project team developed conceptual designs of two salt cavern based LNG terminals, one with caverns located in Calcasieu Parish Louisiana, and the second in Vermilion block 179 about 50 miles offshore Louisiana. These conceptual designs were compared to conventional tank based LNG terminals and demonstrate superior security, economy and capacity. The potential for the development of LNG receiving terminals

  5. Deep borehole disposal of plutonium

    International Nuclear Information System (INIS)

    Gibb, F. G. F.; Taylor, K. J.; Burakov, B. E.

    2008-01-01

    Excess plutonium not destined for burning as MOX or in Generation IV reactors is both a long-term waste management problem and a security threat. Immobilisation in mineral and ceramic-based waste forms for interim safe storage and eventual disposal is a widely proposed first step. The safest and most secure form of geological disposal for Pu yet suggested is in very deep boreholes and we propose here that the key to successful combination of these immobilisation and disposal concepts is the encapsulation of the waste form in small cylinders of recrystallized granite. The underlying science is discussed and the results of high pressure and temperature experiments on zircon, depleted UO 2 and Ce-doped cubic zirconia enclosed in granitic melts are presented. The outcomes of these experiments demonstrate the viability of the proposed solution and that Pu could be successfully isolated from its environment for many millions of years. (authors)

  6. Flow diversion in the treatment of carotid injury and carotid-cavernous fistula after transsphenoidal surgery

    Science.gov (United States)

    Lum, Cheemum; Ahmed, Muhammad E; Glikstein, Rafael; dos Santos, Marlise P; Lesiuk, Howard; Labib, Mohamed; Kassam, Amin B

    2015-01-01

    We describe a case of iatrogenic carotid injury with secondary carotid-cavernous fistula (CCF) treated with a silk flow diverter stent placed within the injured internal carotid artery and coils placed within the cavernous sinus. Flow diverters may offer a simple and potentially safe vessel-sparing option in this rare complication of transsphenoidal surgery. The management options are discussed and the relevant literature is reviewed. PMID:26015526

  7. The superior ophthalmic vein approach for the treatment of carotid-cavernous fistulas: our first experience

    Directory of Open Access Journals (Sweden)

    Chiriac A.

    2016-06-01

    Full Text Available Complex cavernous sinus fistulae (CCF are still a technical challenge to neurovascular team. The most commonly performed treatment consists in endovascular embolization of the lesion through an arterial or venous approach. Not always these conventional routes are feasible, requiring alternative routes. We report a case of a 44-year-old woman with a complex indirect (Barrow D carotid cavernous sinus fistula treated by two interventional sessions that imposing a retrograde direct transvenous approach via the superior ophthalmic vein.

  8. Endoscope-assisted resection of cavernous angioma at the foramen of Monro: a case report

    OpenAIRE

    Matsumoto, Yuji; Kurozumi, Kazuhiko; Shimazu, Yousuke; Ichikawa, Tomotsugu; Date, Isao

    2016-01-01

    Introduction Intraventricular cavernous angiomas are rare pathological entities, and those located at the foramen of Monro are even rarer. We herein present a case of cavernous angioma at the foramen of Monro that was successfully treated by neuroendoscope-assisted surgical removal, and review the relevant literature. Case presentation A 65-year-old woman had experienced headache and vomiting for 10?days before admission to another hospital. Magnetic resonance imaging (MRI) showed a mass at t...

  9. Regional waste treatment facilities with underground monolith disposal for all low-heat-generating nuclear wastes

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1982-01-01

    An alternative system for treatment and disposal of all ''low-heat-generating'' nuclear wastes from all sources is proposed. The system, Regional Waste Treatment Facilities with Underground Monolith Disposal (RWTF/UMD), integrates waste treatment and disposal operations into single facilities at regional sites. Untreated and/or pretreated wastes are transported from generation sites such as reactors, hospitals, and industries to regional facilities in bulk containers. Liquid wastes are also transported in bulk after being gelled for transport. The untreated and pretreated wastes are processed by incineration, crushing, and other processes at the RWTF. The processed wastes are mixed with cement. The wet concrete mixture is poured into large low-cost, manmade caverns or deep trenches. Monolith dimensions are from 15 to 25 m wide, and 20 to 60 m high and as long as required. This alternative waste system may provide higher safety margins in waste disposal at lower costs

  10. Development of the safety assessment technology for the radioactive waste disposal

    International Nuclear Information System (INIS)

    Kim, Chang Lak; Choi, Kwang Sub; Cho, Chan Hee; Lee, Myung Chan; Kim, Jhin Wung

    1992-03-01

    The major goal of this project is to develop a source-term model for the safety assessment of a low- and intermediate-level radioactive waste repository as follows: 1) estimation of the arising of low- and intermediate-level radioactive wastes, 2) development of inventory data base, 3) development of a source-term code for shallow-land disposal, and 4) improvement of the REPS source-term code for rock cavern type disposal developed already in 1990 and conservative safety assessment for an imaginary repository. In addition, the source of C-14 in the inventory is assessed by two methods: decontamination factor and scaling factor. The source-term code for shallow-land disposal include the following submodels: surface water penetration into the repository, concrete degradation, corrosion of container drums, leaching of radionuclides from waste forms, and migration of radionuclides from engineered disposal facility is estimated by this code. (Author)

  11. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Petit, J.C.

    1998-04-01

    A deep gap, reflecting a persisting fear, separates the viewpoints of the experts and that of the public on the issue of the disposal of nuclear WASTES. The history of this field is that of the proliferation with time of spokesmen who pretend to speak in the name of the both humans and non humans involved. Three periods can be distinguished: 1940-1970, an era of contestation and confusion when the experts alone represents the interest of all; 1970-1990, an era of contestation and confusion when spokespersons multiply themselves, generating the controversy and the slowing down of most technological projects; 1990-, an era of negotiation, when viewpoints, both technical and non technical, tend to get closer and, let us be optimistic, leading to the overcome of the crisis. We show that, despite major differences, the options and concepts developed by the different actors are base on two categories of resources, namely Nature and Society, and that the consensus is built up through their 'hydridation'. we show in this part that the perception of nuclear power and, in particular of the underground disposal of nuclear wastes, involves a very deep psychological substrate. Trying to change mentalities in the domain by purely scientific and technical arguments is thus in vain. The practically instinctive fear of radioactivity, far from being due only to lack of information (and education), as often postulated by scientists and engineers, is rooted in archetypical structures. These were, without doubt, reactivated in the 40 s by the traumatizing experience of the atomic bomb. In addition, anthropological-linked considerations allow us to conclude that he underground disposal of wastes is seen as a 'rape' and soiling of Mother Earth. This contributes to explaining, beyond any rationality, the refusal of this technical option by some persons. However, it would naturally be simplistic and counter-productive to limit all controversy in this domain to these psychological aspects

  12. Simultaneous and sequential hemorrhage of multiple cerebral cavernous malformations: a case report.

    Science.gov (United States)

    Louis, Nundia; Marsh, Robert

    2016-02-09

    The etiology of cerebral cavernous malformation hemorrhage is not well understood. Causative physiologic parameters preceding hemorrhagic cavernous malformation events are often not reported. We present a case of an individual with sequential simultaneous hemorrhages in multiple cerebral cavernous malformations with a new onset diagnosis of hypertension. A 42-year-old white man was admitted to our facility with worsening headache, left facial and tongue numbness, dizziness, diplopia, and elevated blood pressure. His past medical history was significant for new onset diagnosis of hypertension and chronic seasonal allergies. Serial imaging over the ensuing 8 days revealed sequential hemorrhagic lesions. He underwent suboccipital craniotomy for resection of the lesions located in the fourth ventricle and right cerebellum. One month after surgery, he had near complete resolution of his symptoms with mild residual vertigo but symptomatic chronic hypertension. Many studies have focused on genetic and inflammatory mechanisms contributing to cerebral cavernous malformation rupture, but few have reported on the potential of hemodynamic changes contributing to cerebral cavernous malformation rupture. Systemic blood pressure changes clearly have an effect on angioma pressures. When considering the histopathological features of cerebral cavernous malformation architecture, changes in arterial pressure could cause meaningful alterations in hemorrhage propensity and patterns.

  13. Fractal Prediction of Grouting Volume for Treating Karst Caverns along a Shield Tunneling Alignment

    Directory of Open Access Journals (Sweden)

    Wen-Chieh Cheng

    2017-06-01

    Full Text Available Karst geology is common in China, and buried karst formations are widely distributed in Guangdong province. In the process of shield tunneling, the abundant water resources present in karst caverns could lead to the potential for high water ingress, and a subsequent in situ stress change-induced stratum collapse. The development and distribution of karst caverns should therefore be identified and investigated prior to shield tunnel construction. Grouting is an efficient measure to stabilize karst caverns. The total volume of karst caverns along the shield tunneling alignment, and its relationship with the required volume of grouts, should be evaluated in the preliminary design phase. Conventionally, the total volume of karst caverns is empirically estimated based on limited geological drilling hole data; however, accurate results are rarely obtained. This study investigates the hydrogeology and engineering geology of Guangzhou, the capital of Guangdong province, and determines the fractal characteristics of the karst caverns along the tunnel section of Guangzhou metro line no. 9. The karst grouting coefficients (VR were found to vary from 0.11 in the case of inadequate drilling holes to 1.1 in the case where adequate drilling holes are provided. A grouting design guideline was furthermore developed in this study for future projects in karst areas.

  14. Hazard assessment of the stability of a cavern roof along the coastline

    Science.gov (United States)

    Reina, A.; Lollino, P.

    2009-04-01

    This work concerns the hazard assessment about the stability of a large shallow depth cavern, located along the coastline rocky sector of Polignano town (Apulia, Southern Italy) under an intensely urbanised area. This cavern, which lies at the sea level, has been created by a prolonged process of sea erosion within a rock mass formed of a lower stratified limestone mass and an upper Gravina Calcarenite mass. The thickness of the cavern roof, which has a dome shape, is less than 10 metres in the centre. Important buildings, as hotels and private houses, are located just above the top of the roof. Erosion processes have been observed to be still active along the whole cavern due to climate factors and, in particular, to sea salt weathering and sea spray effects. In 2007 a large calcarenite block, 3 m large, fell down from the cavern roof and consequently a field investigation campaign was carried out for a rational stabilization plan in order to understand the current stability conditions of the roof and the potential failure mechanism. Therefore, a thorough geo-structural survey has firstly been carried out, together with laboratory and in-situ testing for measuring the physical and mechanical properties of the calcarenite rock and of the corresponding joints. A monitoring system has also been planned and installed in order to measure the erosional rate and the block displacements in the cavern.

  15. Mathematical model of salt cavern leaching for gas storage in high-insoluble salt formations.

    Science.gov (United States)

    Li, Jinlong; Shi, Xilin; Yang, Chunhe; Li, Yinping; Wang, Tongtao; Ma, Hongling

    2018-01-10

    A mathematical model is established to predict the salt cavern development during leaching in high-insoluble salt formations. The salt-brine mass transfer rate is introduced, and the effects of the insoluble sediments on the development of the cavern are included. Considering the salt mass conservation in the cavern, the couple equations of the cavern shape, brine concentration and brine velocity are derived. According to the falling and accumulating rules of the insoluble particles, the governing equations of the insoluble sediments are deduced. A computer program using VC++ language is developed to obtain the numerical solution of these equations. To verify the proposed model, the leaching processes of two salt caverns of Jintan underground gas storage are simulated by the program, using the actual geological and technological parameters. The same simulation is performed by the current mainstream leaching software in China. The simulation results of the two programs are compared with the available field data. It shows that the proposed software is more accurate on the shape prediction of the cavern bottom and roof, which demonstrates the reliability and applicability of the model.

  16. Principles and guidelines for radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    1988-06-01

    Four basic principles relevant to radioactive waste disposal identified. These principles cover the justification of the activity giving rise to the waste, the consideration of risk to present and future generations, the minimization of the need for intervention in the future, and the financial obligations of the licensee. The use of risk limits as opposed to dose limits associated with disposal is discussed, as are the concepts of critical group, de minimis, and ALARA, in the context of a waste disposal facility. Guidance is given on the selection of the preferred waste disposal concept from among several alternatives, and for judging proposed design improvements to the chosen concept

  17. 2005 dossier: granite. Tome: phenomenological evolution of the geologic disposal

    International Nuclear Information System (INIS)

    2005-01-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the phenomenological aspects of the geologic disposal of high-level and long-lived radioactive wastes (HLLL) in granite formations. Content: 1 - introduction: ANDRA's research program on disposal in granitic formation; 2 - the granitic environment: geologic history, French granites; 3 - HLLL wastes and disposal design concepts; 4 - identification, characterization and modeling of a granitic site: approach, geologic modeling, hydrologic and hydro-geochemical modeling, geomechanical and thermal modeling, long-term geologic evolution of a site; 5 - phenomenological evolution of a disposal: main aspects of the evolution of a repository with time, disposal infrastructures, B-type wastes disposal area, C-type wastes disposal area; spent fuels disposal area, radionuclides transfer and retention in the granitic environment; 6 - conclusions: available knowledge, methods and tools for the understanding and modeling of the phenomenological evolution of a granitic disposal site. (J.S.)

  18. Japan's exploration of vertical holes and subsurface caverns on the Moon and Mars

    Science.gov (United States)

    Haruyama, J.; Kawano, I.; Kubota, T.; Yoshida, K.; Kawakatsu, Y.; Kato, H.; Otsuki, M.; Watanabe, K.; Nishibori, T.; Yamamoto, Y.; Iwata, T.; Ishigami, G.; Yamada, T. T.

    2013-12-01

    Recently, gigantic vertical holes exceeding several tens of meters in diameter and depth were discovered on the Moon and Mars. Based on high-resolution image data, lunar holes and some Martian pits (called 'holes' hereafter) are probably skylights of subsurface caverns such as lava tubes or magma chambers. We are starting preparations for exploring the caverns through the vertical holes. The holes and subsurface caverns have high potential as resources for scientific studies. Various important geological and mineralogical processes could be uniquely and effectively observed inside these holes and subsurface caverns. The exposed fresh lava layers on the vertical walls of the lunar and Martian holes would provide information on volcanic eruption histories. The lava layers may also provide information on past magnetic fields of the celestial bodies. The regolith layers may be sandwiched between lava layers and may preserve volatile elements including solar wind protons that could be a clue to understanding past solar activities. Water molecules from solar winds or cometary/meteorite impacts may be stored inside the caverns because of mild temperatures there. The fresh lava materials forming the walls and floors of caverns might trap endogenic volatiles from magma eruptions that will be key materials for revealing the formation and early evolution of the Moon and Mars. Furthermore, the Martian subsurface caverns are highly expected to be life cradles where the temperatures are probably stable and that are free from ultra-violet and other cosmic rays that break chemical bonds, thus avoiding polymerization of molecules. Discovering extraterrestrial life and its varieties is one of our ultimate scientific purposes for exploring the lunar and Martian subsurface caverns. In addition to scientific interests, lunar and Martian subsurface caverns are excellent candidates for future lunar bases. We expect such caverns to have high potential due to stable temperatures; absence

  19. Transvenous embolization of indirect carotid-cavernous fistula via upper ophthalmic/facial vein - Case report and literature review

    International Nuclear Information System (INIS)

    Sirakov, S.; Penkov, M.; Sirakov, A.; Kamenov, B.; Todorov, Y.; Ninov, K.; Bachvarov, Ch.

    2015-01-01

    Indirect carotid-cavernous fistula or dural arterio-venous fistula of cavernous sinus is relatively rare pathologic finding. Different classifications of carotid-cavernous fistulae are proposed. Now days more and more they are treated by endovascular approach. A case of authors' practice of transvenous embolization of carotid-cavernous fistula via upper ophthalmic vein in 52 year old female is presented with review of the literature. A week later ocular symptoms of the patient regressed. Control angiography at the third month follow up does not visualize fistula. The transvenous approach in management of carotid cavernous fistulae is safe and effective in cases direct arterial approach is absent or technically impossible. Key words: Indirect Carotid-Cavernous Fistula. Embolization. Transvenous Approach

  20. Is there a dural wall between the cavernous sinus and the pituitary fossa? Anatomical and MRI findings

    International Nuclear Information System (INIS)

    Dietemann, J.L.; Diniz, R.; Reis, M. Jr.; Neugroschl, C.; Vinclair, L.; Maillot, C.

    1998-01-01

    We compared MRI studies of the sellar area and embryological and adult histological studies of the cavernous sinuses and pituitary fossa. MRI studies were performed in 50 normal subjects with coronal sections using a fast inversion-recovery sequence to demonstrate the dural walls of the cavernous sinus and pituitary fossa. With this sequence, dura mater appears as a high-signal linear structure. The lateral and superior walls of the cavernous sinus was easily identified on all studies, but demonstration of a dural wall separating the cavernous sinus from the pituitary fossa was not possible. These results correlated well with embryological and adult histological studies obtained from 14 specimens. The absence of a strong separation between the pituitary fossa and the cavernous sinus explains the high incidence of extension of pituitary tumours to the cavernous sinuses and vice versa. (orig.) (orig.)

  1. Disposal of tritiated effluents

    International Nuclear Information System (INIS)

    Hartmann, K.; Bruecher, H.

    1981-06-01

    After some introductory remarks on the origin of tritium, its properties and its behaviour in a reprocessing plant three alternative methods for the disposal of tritiated effluents produced during reprocessing are described (deep well injection, in-situ solidification, deep-sea dumping) and compared with each other under various aspects. The study is based on the concept of a 1400 t/a reprocessing plant for LWR fuel, which annually produces 3000 m 3 of tritiated waste water with a tritium content of 6.5 x 10 12 Bq/m 3 as well as a residual fission product and actinide content. An assessment of the three methods under the aspects of simplicity, reliability, safety, costs, state of development and materials handling revealed advantages in favour of 'injection', followed by 'dumping' and 'in-situ solidification'. (orig./HP) [de

  2. Management of radioactive fuel wastes: the Canadian disposal program

    International Nuclear Information System (INIS)

    Boulton, J.

    1978-10-01

    This report describes the research and development program to verify and demonstrate the concepts for the safe, permanent disposal of radioactive fuel wastes from Canadian nuclear reactors. The program is concentrating on deep underground disposal in hard-rock formations. The nature of the radioactive wastes is described, and the options for storing, processing, packaging and disposing of them are outlined. The program to verify the proposed concept, select a suitable site and to build and operate a demonstration facility is described. (author)

  3. Proposal of a SiC disposal canister for very deep borehole disposal

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heui-Joo; Lee, Minsoo; Lee, Jong-Youl; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this paper authors proposed a silicon carbide, SiC, disposal canister for the DBD concept in Korea. A. Kerber et al. first proposed the SiC canister for a geological disposal of HLW, CANDU or HTR spent nuclear fuels. SiC has some drawbacks in welding or manufacturing a large canister. Thus, we designed a double layered disposal canister consisting of a stainless steel outer layer and a SiC inner layer. KAERI has been interested in developing a very deep borehole disposal (DBD) of HLW generated from pyroprocessing of PWR spent nuclear fuel and supported the relevant R and D with very limited its own budget. KAERI team reviewed the DBD concept proposed by Sandia National Laboratories (SNL) and developed its own concept. The SNL concept was based on the steel disposal canister. The authors developed a new technology called cold spray coating method to manufacture a copper-cast iron disposal canister for a geological disposal of high level waste in Korea. With this method, 8 mm thin copper canister with 400 mm in diameter and 1200 mm in height was made. In general, they do not give any credit on the lifetime of a disposal canister in DBD concept unlike the geological disposal. In such case, the expensive copper canister should be replaced with another one. We designed a disposal canister using SiC for DBD. According to an experience in manufacturing a small size canister, the fabrication of a large-size one is a challenge. Also, welding of SiC canister is not easy. Several pathways are being paved to overcome it.

  4. Post-disposal safety assessment of toxic and radioactive waste: waste types, disposal practices, disposal criteria, assessment methods and post-disposal impacts

    International Nuclear Information System (INIS)

    Torres, C.; Simon, I.; Little, R.H.; Charles, D.; Grogan, H.A.; Smith, G.M.; Sumerling, T.J.; Watkins, B.M.

    1993-01-01

    The need for safety assessments of waste disposal stems not only from the implementation of regulations requiring the assessment of environmental effects, but also from the more general need to justify decisions on protection requirements. As waste-disposal methods have become more technologically based, through the application of more highly engineered design concepts and through more rigorous and specific limitations on the types and quantities of the waste disposed, it follows that assessment procedures also must become more sophisticated. It is the overall aim of this study to improve the predictive modelling capacity for post-disposal safety assessments of land-based disposal facilities through the development and testing of a comprehensive, yet practicable, assessment framework. This report records all the work which has been undertaken during Phase 1 of the study. Waste types, disposal practices, disposal criteria and assessment methods for both toxic and radioactive waste are reviewed with the purpose of identifying those features relevant to assessment methodology development. Difference and similarities in waste types, disposal practices, criteria and assessment methods between countries, and between toxic and radioactive wastes are highlighted and discussed. Finally, an approach to identify post-disposal impacts, how they arise and their effects on humans and the environment is described

  5. Generic Crystalline Disposal Reference Case

    Energy Technology Data Exchange (ETDEWEB)

    Painter, Scott Leroy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chu, Shaoping [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Harp, Dylan Robert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Perry, Frank Vinton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-02-20

    A generic reference case for disposal of spent nuclear fuel and high-level radioactive waste in crystalline rock is outlined. The generic cases are intended to support development of disposal system modeling capability by establishing relevant baseline conditions and parameters. Establishment of a generic reference case requires that the emplacement concept, waste inventory, waste form, waste package, backfill/buffer properties, EBS failure scenarios, host rock properties, and biosphere be specified. The focus in this report is on those elements that are unique to crystalline disposal, especially the geosphere representation. Three emplacement concepts are suggested for further analyses: a waste packages containing 4 PWR assemblies emplaced in boreholes in the floors of tunnels (KBS-3 concept), a 12-assembly waste package emplaced in tunnels, and a 32-assembly dual purpose canister emplaced in tunnels. In addition, three failure scenarios were suggested for future use: a nominal scenario involving corrosion of the waste package in the tunnel emplacement concepts, a manufacturing defect scenario applicable to the KBS-3 concept, and a disruptive glaciation scenario applicable to both emplacement concepts. The computational approaches required to analyze EBS failure and transport processes in a crystalline rock repository are similar to those of argillite/shale, with the most significant difference being that the EBS in a crystalline rock repository will likely experience highly heterogeneous flow rates, which should be represented in the model. The computational approaches required to analyze radionuclide transport in the natural system are very different because of the highly channelized nature of fracture flow. Computational workflows tailored to crystalline rock based on discrete transport pathways extracted from discrete fracture network models are recommended.

  6. Low level waste disposal

    International Nuclear Information System (INIS)

    Barthoux, A.

    1985-01-01

    Final disposal of low level wastes has been carried out for 15 years on the shallow land disposal of the Manche in the north west of France. Final participant in the nuclear energy cycle, ANDRA has set up a new waste management system from the production center (organization of the waste collection) to the disposal site including the setting up of a transport network, the development of assessment, additional conditioning, interim storage, the management of the disposal center, records of the location and characteristics of the disposed wastes, site selection surveys for future disposals and a public information Department. 80 000 waste packages representing a volume of 20 000 m 3 are thus managed and disposed of each year on the shallow land disposal. The disposal of low level wastes is carried out according to their category and activity level: - in tumuli for very low level wastes, - in monoliths, a concrete structure, of the packaging does not provide enough protection against radioactivity [fr

  7. A Probabilistic Performance Assessment Study of Potential Low-Level Radioactive Waste Disposal Sites in Taiwan

    Science.gov (United States)

    Knowlton, R. G.; Arnold, B. W.; Mattie, P. D.; Kuo, M.; Tien, N.

    2006-12-01

    For several years now, Taiwan has been engaged in a process to select a low-level radioactive waste (LLW) disposal site. Taiwan is generating LLW from operational and decommissioning wastes associated with nuclear power reactors, as well as research, industrial, and medical radioactive wastes. The preliminary selection process has narrowed the search to four potential candidate sites. These sites are to be evaluated in a performance assessment analysis to determine the likelihood of meeting the regulatory criteria for disposal. Sandia National Laboratories and Taiwan's Institute of Nuclear Energy Research have been working together to develop the necessary performance assessment methodology and associated computer models to perform these analyses. The methodology utilizes both deterministic (e.g., single run) and probabilistic (e.g., multiple statistical realizations) analyses to achieve the goals. The probabilistic approach provides a means of quantitatively evaluating uncertainty in the model predictions and a more robust basis for performing sensitivity analyses to better understand what is driving the dose predictions from the models. Two types of disposal configurations are under consideration: a shallow land burial concept and a cavern disposal concept. The shallow land burial option includes a protective cover to limit infiltration potential to the waste. Both conceptual designs call for the disposal of 55 gallon waste drums within concrete lined trenches or tunnels, and backfilled with grout. Waste emplaced in the drums may be solidified. Both types of sites are underlain or placed within saturated fractured bedrock material. These factors have influenced the conceptual model development of each site, as well as the selection of the models to employ for the performance assessment analyses. Several existing codes were integrated in order to facilitate a comprehensive performance assessment methodology to evaluate the potential disposal sites. First, a need

  8. Thermo-mechanical modelling of salt caverns due to fluctuating loading conditions.

    Science.gov (United States)

    Böttcher, N.

    2015-12-01

    This work summarizes the development and application of a numerical model for the thermo-mechanical behaviour of salt caverns during cyclic gas storage. Artificial salt caverns are used for short term energy storage, such as power-to-gas or compressed air energy storage. Those applications are characterized by highly fluctuating operation pressures due to the unsteady power levels of power plants based on renewable energy. Compression and expansion of the storage gases during loading and unloading stages lead to rapidly changing temperatures in the host rock of the caverns. This affects the material behaviour of the host rock within a zone that extends several meters into the rock mass adjacent to the cavern wall, and induces thermo-mechanical stresses and alters the creep response.The proposed model features the thermodynamic behaviour of the storage medium, conductive heat transport in the host rock, as well as temperature dependent material properties of rock salt using different thermo-viscoplastic material models. The utilized constitutive models are well known and state-of-the-art in various salt mechanics applications. The model has been implemented into the open-source software platform OpenGeoSys. Thermal and mechanical processes are solved using a finite element approach, coupled via a staggered coupling scheme. The simulation results allow the conclusion, that the cavern convergence rate (and thus the efficiency of the cavern) is highly influenced by the loading cycle frequency and the resulting gas temperatures. The model therefore allows to analyse the influence of operation modes on the cavern host rock or on neighbouring facilities.

  9. Recent activity on disposal of uranium waste

    International Nuclear Information System (INIS)

    Fujiwara, Noboru

    1999-01-01

    The concept on the disposal of uranium waste has not been discussed in the Atomic Energy Commission of Japan, but the research and development of it are carried out in the company and agency which are related to uranium waste. In this paper, the present condition and problems on disposal of uranium waste were shown in aspect of the nuclear fuel manufacturing companies' activity. As main contents, the past circumstances on the disposal of uranium waste, the past activity of nuclear fuel manufacturing companies, outline and properties of uranium waste were shown, and ideas of nuclear fuel manufacturing companies on the disposal of uranium waste were reported with disposal idea in the long-term program for development and utilization of nuclear energy. (author)

  10. High-level waste processing and disposal

    International Nuclear Information System (INIS)

    Crandall, J.L.; Krause, H.; Sombret, C.; Uematsu, K.

    1984-11-01

    Without reprocessing, spent LWR fuel itself is generally considered an acceptable waste form. With reprocessing, borosilicate glass canisters, have now gained general acceptance for waste immobilization. The current first choice for disposal is emplacement in an engineered structure in a mined cavern at a depth of 500-1000 meters. A variety of rock types are being investigated including basalt, clay, granite, salt, shale, and volcanic tuff. This paper gives specific coverage to the national high level waste disposal plans for France, the Federal Republic of Germany, Japan and the United States. The French nuclear program assumes prompt reprocessing of its spent fuels, and France has already constructed the AVM. Two larger borosilicate glass plants are planned for a new French reprocessing plant at La Hague. France plans to hold the glass canisters in near-surface storage for a forty to sixty year cooling period and then to place them into a mined repository. The FRG and Japan also plan reprocessing for their LWR fuels. Both are currently having some fuel reprocessed by France, but both are also planning reprocessing plants which will include waste vitrification facilities. West Germany is now constructing the PAMELA Plant at Mol, Belgium to vitrify high level reprocessing wastes at the shutdown Eurochemic Plant. Japan is now operating a vitrification mockup test facility and plans a pilot plant facility at the Tokai reprocessing plant by 1990. Both countries have active geologic repository programs. The United State program assumes little LWR fuel reprocessing and is thus primarily aimed at direct disposal of spent fuel into mined repositories. However, the US have two borosilicate glass plants under construction to vitrify existing reprocessing wastes

  11. Second Barrel Toroid Coil Installed in ATLAS Cavern

    CERN Multimedia

    Tappern, G.

    The second barrel toroid coil was lowered into the ATLAS Cavern on Friday, 26 November. The operation takes approximately five hours of precision crane and winch operations. Before lowering, several checks are made to ensure that no loose items have been left on the coil which would fall during the lowering down the shaft. This is a very difficult, but very important check, with the first coil in position, and partly below the shaft. After changing the winch tooling on Wednesday December 1st, the coil was lifted, rotated and placed into the feet. The girders which support the coil and the Z direction stops had all been pre-set before putting the coil in the feet. The angle is controlled by an inclinometer. When the final adjustments of position have been made, which will locate the coils at the plus/minus two mm level, the connection beams (voussoirs and struts) will be put in place; this requires a complex shimming procedure. This will lock together the two coils into the feet and forms the foundation for th...

  12. The anatomical location and laterality of orbital cavernous haemangiomas.

    Science.gov (United States)

    McNab, Alan A; Selva, Dinesh; Hardy, Thomas G; O'Donnell, Brett

    2014-10-01

    To determine the anatomical location and laterality of orbital cavernous haemangiomas (OCH). Retrospective case series. The records of 104 patients with OCH were analyzed. The anatomical location of each OCH defined by the location of a point at the centre of the lesion, and its laterality. There were 104 patients included in the study. No patient had more than one lesion. Sixteen (15.4%) were located in the anterior third of the orbit, 74 (71.2%) were in the middle third, and 14 (13.5%) in the posterior third. In the middle third, 10 of 74 (13.5%) were extraconal and 64 intraconal (86.5%), with 30 of 64 (46.9%) middle third intraconal lesions lying lateral to the optic nerve. Of 104 lesions, 56 (53.8%) were left sided, showing a trend towards a predilection for the left side (p = 0.065). If data from other published series which included data on laterality is added to our own data and analysed, 270 of 468 (57.7%) OCH occurred in the left orbit (p lateral to the optic nerve. This may reflect an origin of these lesions from the arterial side of the circulation, as there are more small arteries in the intraconal space lateral to the optic nerve than in other locations. A predilection for the left orbit remains unexplained.

  13. Cerebral cavernous malformations: natural history and clinical management.

    Science.gov (United States)

    Gross, Bradley A; Du, Rose

    2015-01-01

    Cavernous malformations (CMs) are angiographically-occult clusters of dilated sinusoidal channels that may present clinically with seizures, focal neurological deficits and/or hemorrhage. Across natural history studies, the annual hemorrhage rate ranged from 1.6-3.1% per patient-year, decreasing to 0.08-0.2% per patient-year for incidental CMs and to 0.3-0.6% for the collective group of unruptured CMs. Prior hemorrhage is a significant risk factor for subsequent CM hemorrhage. Hemorrhage clustering, particularly within the first 2 years, is an established phenomenon that may confound results of natural history studies evaluating the rate of rehemorrhage. Indeed, rehemorrhage rates for hemorrhagic CMs range from 4.5-22.9% in the literature. Surgical resection is the gold standard treatment for surgically-accessible, symptomatic CMs. Incidental CMs or minimally symptomatic, surgically inaccessible eloquent lesions may be considered for observation. Stereotactic radiosurgery is a controversial treatment approach of consideration only for cases of highly aggressive, surgically inaccessible CMs.

  14. Surgical management of cavernous malformations coursing with drug resistant epilepsy

    Directory of Open Access Journals (Sweden)

    Mario Arturo Alonso-Vanegas

    2012-01-01

    Full Text Available Cerebral cavernous malformations (CM are dynamic lesions characterized by continuous size changes and repeated bleeding. When involving cortical tissue, CM pose a significant risk for the development of drug-resistant epilepsy, which is thought to be result of an altered neuronal network caused by the lesion itself and its blood degradation products. Preoperative evaluation should comprise a complete seizure history, neurological examination, epilepsy-oriented MRI, EEG, video-EEG, completed with SPECT, PET, functional MRI and/or invasive monitoring as needed. Radiosurgery shows variable rates of seizure freedom and a high incidence of complications, thus microsurgical resection remains the optimal treatment for CM coursing with drug-resistant epilepsy.Two thirds of patients reach Engel I class at three-year follow-up, regardless of lobar location. Those with secondarily generalized seizures, a higher seizure frequency, and generalized abnormalities on preoperative or postoperative EEG, show poorer outcomes, while factors such as gender, duration of epilepsy, lesion size, age, bleeding at the time of surgery, do not correlate consistently with seizure outcome. Electrocorticography and a meticulous removal of all cortical hemosiderin –beyond pure lesionectomy– reduce the risk of symptomatic recurrences.

  15. Management of supratentorial cavernous malformations: craniotomy versus gammaknife radiosurgery.

    Science.gov (United States)

    Shih, Yang-Hsin; Pan, David Hung-Chi

    2005-02-01

    Although craniotomy is the preferred treatment for symptomatic solitary supratentorial cavernous malformation (CM), radiosurgery is also an option. Our aim was to see which of these strategies was the most effective and under what circumstances. Of the 46 patients with solitary supratentorial CM that we retrospectively studied, 24 presented with seizures, 16 with focal neurological deficits due to intracerebral hemorrhage, and 6 with both seizures and bleeding. Sixteen were treated with craniotomy and 30 with gammaknife radiosurgery (GKRS). The main outcome measures for comparing craniotomy with GKRS were the proportion of postoperative seizure-free patients and the proportion of patients in whom no rebleeding occurred. Of patients presenting with seizures with/without bleeding, a significantly higher proportion of the craniotomy group than the GKRS group became and remained seizure-free (11/14 [79%] versus 4/16 [25%]; P < 0.002), and of those presenting with bleeding with/without seizures, a somewhat (though nonsignificantly) higher proportion did not rebleed (4/4 [100%] versus 12/18 [67%]) after surgery. The remaining 2 of the 16 craniotomy patients did not rebleed and had no residual tumor at follow up. Twelve of the 30 GKRS patients had evidence of tumor regression at follow up. In the clinical management of solitary supratentorial CM, craniotomy for lesionectomy resulted in better seizure control and rebleeding avoidance than GKRS.

  16. Treatment Outcome Of Seizures Associated With Intracranial Cavernous Angiomas

    Directory of Open Access Journals (Sweden)

    Nievera Conrad C

    1999-01-01

    Full Text Available Seizures are among the typical presentations of intracranial cavernous angiomas (ICA. Twenty-one patients (age range: 2 to 53 years treated for seizures associated with ICA between 1983 and 1997 were restrospectively studied to evaluate their outcome following medical or surgical intervention. The mean interval between seizure onset and initial presentation at our institution was 7.6 years. Seizures were simple partial in 3 patients, complex partial in 15 and secondarily generalized tonic-clonic in 13. The commonest site of the lesion was the temporal lobe (52%. Multiple angiomas were observed in 5 (24% patients. Seven (32% patients were medically-managed with antiepileptic therapy and 14 (68% underwent either lesionectomy with resection of the epileptogenic zone (9 patients or temporal lobectomy (5 patients. Mean follow-up time was 4 years (range: 3 months to 14 years. Of the medically-managed patients, 3 (43% remained seizure-free whereas 4 (57% continued to have seizures with an average frequency of one per day. Of the surgically-managed patients, 12 (86% became seizure-free and 2 (14% had no more than two seizures per year. Surgery appears to be extremely effective in the management of seizures associated with ICA and should receive a strong and early consideration in patients who fail medical therapy.

  17. The disposal of Canada's nuclear fuel waste: engineering for a disposal facility

    International Nuclear Information System (INIS)

    Simmons, G.R.; Baumgartner, P.

    1994-01-01

    This report presents some general considerations for engineering a nuclear fuel waste disposal facility, alternative disposal-vault concepts and arrangements, and a conceptual design of a used-fuel disposal centre that was used to assess the technical feasibility, costs and potential effects of disposal. The general considerations and alternative disposal-vault arrangements are presented to show that options are available to allow the design to be adapted to actual site conditions. The conceptual design for a used-fuel disposal centre includes descriptions of the two major components of the disposal facility, the Used-Fuel Packaging Plant and the disposal vault; the ancillary facilities and services needed to carry out the operations are also identified. The development of the disposal facility, its operation, its decommissioning, and the reclamation of the site are discussed. The costs, labour requirements and schedules used to assess socioeconomic effects and that may be used to assess the cost burden of waste disposal to the consumer of nuclear energy are estimated. The Canadian Nuclear Fuel Waste Management Program is funded jointly by AECL and Ontario Hydro under the auspices of the CANDU Owners Group. (author)

  18. Confidence building in implementation of geological disposal

    International Nuclear Information System (INIS)

    Umeki, Hiroyuki

    2004-01-01

    Long-term safety of the disposal system should be demonstrated to the satisfaction of the stakeholders. Convincing arguments are therefore required that instil in the stakeholders confidence in the safety of a particular concept for the siting and design of a geological disposal, given the uncertainties that inevitably exist in its a priori description and in its evolution. The step-wise approach associated with making safety case at each stage is a key to building confidence in the repository development programme. This paper discusses aspects and issues on confidence building in the implementation of HLW disposal in Japan. (author)

  19. Treated Effluent Disposal Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Treated non-hazardous and non-radioactive liquid wastes are collected and then disposed of through the systems at the Treated Effluent Disposal Facility (TEDF). More...

  20. Familial cerebral cavernous haemangioma diagnosed in an infant with a rapidly growing cerebral lesion

    International Nuclear Information System (INIS)

    Ng, B.H.K.; Pereira, J.K.; Ghedia, S.; Pinner, J.; Mowat, D.; Vonau, M.

    2006-01-01

    Cavernous haemangiomas of the central nervous system are vascular malformations best imaged by MRI. They may present at any age, but to our knowledge only 39 cases in the first year of life have previously been reported. A familial form has been described and some of the underlying genetic mutations have recently been discovered. We present the clinical features and serial MRI findings of an 8-week-old boy who presented with subacute intracranial haemorrhage followed by rapid growth of a surgically proven cavernous haemangioma, mimicking a tumour. He also developed new lesions. A strong family history of neurological disease was elucidated. A familial form of cavernous haemangioma was confirmed by identification of a KRIT 1 gene mutation and cavernous haemangiomas in the patient and other family members. We stress the importance of considering cavernous haemangiomas in the context of intracerebral haemorrhage and in the differential diagnosis of rapidly growing lesions in this age group. The family history is also important in screening for familial disease

  1. Stability of interbed for salt cavern gas storage in solution mining considering cusp displacement catastrophe theory

    Directory of Open Access Journals (Sweden)

    Le Yu

    2015-03-01

    Full Text Available Cusp displacement catastrophe theory can be introduced to propose a new method about instability failure of the interbed for gas storage cavern in bedded salt in solution mining. We can calculate initial fracture drawing pace of this interbed to obtain 2D and 3D gas storage shapes at this time. Moreover, Stability evaluation of strength reduction finite element method (FEM based on this catastrophe theory can used to evaluate this interbed stability after initial fracture. A specific example is simulated to obtain the influence of the interbed depth, cavern internal pressure, and cavern building time on stability safety factor (SSF. The results indicate: the value of SSF will be lower with the increase of cavern building time in solution mining and the increase of interbed depth and also this value remains a rise with the increase of cavern internal pressure Especially, we can conclude that the second-fracture of the interbed may take place when this pressure is lower than 6 MPa or after 6 days later of the interbed after initial fracture. According to above analysis, some effective measures, namely elevating the tube up to the top of the interbed, or changing the circulation of in-and-out lines, can be introduced to avoid the negative effects when the second-fracture of the interbed may occur.

  2. Endoscope-assisted resection of cavernous angioma at the foramen of Monro: a case report.

    Science.gov (United States)

    Matsumoto, Yuji; Kurozumi, Kazuhiko; Shimazu, Yousuke; Ichikawa, Tomotsugu; Date, Isao

    2016-01-01

    Intraventricular cavernous angiomas are rare pathological entities, and those located at the foramen of Monro are even rarer. We herein present a case of cavernous angioma at the foramen of Monro that was successfully treated by neuroendoscope-assisted surgical removal, and review the relevant literature. A 65-year-old woman had experienced headache and vomiting for 10 days before admission to another hospital. Magnetic resonance imaging (MRI) showed a mass at the foramen of Monro, and obstructive hydrocephalus of both lateral ventricles. The patient was then referred to our hospital. Neurological examination on admission to our hospital showed memory disturbance (Mini-Mental State Examination 20/30) and wide-based gait. A cavernous angioma at the foramen of Monro was diagnosed based on the typical popcorn-like appearance of the lesion on MRI. The lesion was completely removed by neuroendoscope-assisted transcortical surgery with the Viewsite Brain Access System (Vycor Medical Inc., Boca Raton, FL), leading to a reduction in the size of the ventricles. The resected mass was histologically confirmed to be cavernous angioma. The patient's symptoms resolved immediately and there were no postoperative complications. Minimally invasive neuroendoscope-assisted surgery was used to successfully treat a cavernous angioma at the foramen of Monro.

  3. Multiple cavernous malformations presenting in a patient with Poland syndrome: A case report

    Directory of Open Access Journals (Sweden)

    De Salles Antonio AF

    2011-09-01

    Full Text Available Abstract Introduction Poland syndrome is a congenital disorder related to chest and hand anomalies on one side of the body. Its etiology remains unclear, with an ipsilateral vascular alteration (of unknown origin to the subclavian artery in early embryogenesis being the currently accepted theory. Cavernous malformations are vascular hamartomas, which have been linked to a genetic etiology, particularly in familial cases, which commonly present with multiple lesions. Our case report is the first to describe multiple cavernous malformations associated with Poland syndrome, further supporting the vascular etiology theory, but pointing to a genetic rather than a mechanistic factor disrupting blood flow in the corresponding vessels. Case presentation A 41-year-old Caucasian man with Poland syndrome on the right side of his body presented to our hospital with a secondary generalized seizure and was found to have multiple cavernous malformations distributed in his brain, cerebellum, and brain stem, with a predominance of lesions in the left hemisphere. Conclusion The distribution of cavernous malformations in the left hemisphere and the right-sided Poland syndrome in our patient could not be explained by a mechanistic disruption of one of the subclavian arteries. A genetic alteration, as in familial cavernous malformations, would be a more appropriate etiologic diagnosis of Poland syndrome in our patient. Further genetic and pathological studies of the involved blood vessels in patients with Poland syndrome could lead to a better understanding of the disease.

  4. Retrievable disposal - opposing views on ethics

    International Nuclear Information System (INIS)

    Selling, H.A.

    2000-01-01

    In the previous decades many research programmes on the disposal of radioactive waste have been completed in the Netherlands. The experts involved have reconfirmed their view that deep underground disposal in suitable geological formations would ensure a safe and prolonged isolation of the waste from the biosphere. Both rock salt and clay formations are considered to qualify as a suitable host rock. In 1993 the government in a position paper stated that such a repository should be designed in a way that the waste can be retrieved from it, should the need arise. In an attempt to involve stakeholders in the decision-making process, a research contract was awarded to an environmental group to study the ethical aspects related to retrievable disposal of radioactive waste. In their report which was published in its final form in January 2000 the authors concluded that retrievable disposal is acceptable from an ethical point of view. However, this conclusion was reached in the understanding that this situation of retrievability would be permanent. From the concept of equity between generations, each successive generation should be offered equal opportunities to decide for itself how to dispose of the radioactive waste. Consequently, the preferred disposal option is retrievable disposal (or long term storage) in a surface facility. Although this view is not in conformity with the ''official'' position on radioactive waste disposal, there is a benefit of having established a dialogue between interested parties in a broad sense. (author)

  5. Application and research of special waste plasma disposal technology

    International Nuclear Information System (INIS)

    Lan Wei

    2007-12-01

    The basic concept of plasma and the principle of waste hot plasma disposal technology are simply introduced. Several sides of application and research of solid waste plasma disposal technology are sumed up. Compared to the common technology, the advantages of waste hot plasma disposal technology manifest further. It becomes one of the most prospective and the most attended high tech disposal technology in particular kind of waste disposal field. The article also simply introduces some experiment results in Southwest Institute of Physics and some work on the side of importation, absorption, digestion, development of foreign plasma torch technology and researching new power sources for plasma torch. (authors)

  6. Gamma Knife radiosurgery for hemangioma of the cavernous sinus.

    Science.gov (United States)

    Lee, Cheng-Chia; Sheehan, Jason P; Kano, Hideyuki; Akpinar, Berkcan; Martinez-Alvarez, Roberto; Martinez-Moreno, Nuria; Guo, Wan-Yuo; Lunsford, L Dade; Liu, Kang-Du

    2017-05-01

    OBJECTIVE Cavernous sinus hemangiomas (CSHs) are rare vascular tumors. A direct microsurgical approach usually results in massive hemorrhage and incomplete tumor resection. Although stereotactic radiosurgery (SRS) has emerged as a therapeutic alternative to microsurgery, outcome studies are few. Authors of the present study evaluated the role of SRS for CSH. METHODS An international multicenter study was conducted to review outcome data in 31 patients with CSH. Eleven patients had initial microsurgery before SRS, and the other 20 patients (64.5%) underwent Gamma Knife SRS as the primary management for their CSH. Median age at the time of radiosurgery was 47 years, and 77.4% of patients had cranial nerve dysfunction before SRS. Patients received a median tumor margin dose of 12.6 Gy (range 12-19 Gy) at a median isodose of 55%. RESULTS Tumor regression was confirmed by imaging in all 31 patients, and all patients had greater than 50% reduction in tumor volume at 6 months post-SRS. No patient had delayed tumor growth, new cranial neuropathy, visual function deterioration, adverse radiation effects, or hypopituitarism after SRS. Twenty-four patients had presented with cranial nerve disorders before SRS, and 6 (25%) of them had gradual improvement. Four (66.7%) of the 6 patients with orbital symptoms had symptomatic relief at the last follow-up. CONCLUSIONS Stereotactic radiosurgery was effective in reducing the volume of CSH and attaining long-term tumor control in all patients at a median of 40 months. The authors' experience suggests that SRS is a reasonable primary and adjuvant treatment modality for patients in whom a CSH is diagnosed.

  7. Dynamic contrast-enhanced MRI evaluation of cerebral cavernous malformations.

    Science.gov (United States)

    Hart, Blaine L; Taheri, Saeid; Rosenberg, Gary A; Morrison, Leslie A

    2013-10-01

    The aim of this study is to quantitatively evaluate the behavior of CNS cavernous malformations (CCMs) using a dynamic contrast-enhanced MRI (DCEMRI) technique sensitive for slow transfer rates of gadolinium. The prospective study was approved by the institutional review board and was HIPPA compliant. Written informed consent was obtained from 14 subjects with familial CCMs (4 men and 10 women, ages 22-76 years, mean 48.1 years). Following routine anatomic MRI of the brain, DCEMRI was performed for six slices, using T1 mapping with partial inversion recovery (TAPIR) to calculate T1 values, following administration of 0.025 mmol/kg gadolinium DTPA. The transfer rate (Ki) was calculated using the Patlak model, and Ki within CCMs was compared to normal-appearing white matter as well as to 17 normal control subjects previously studied. All subjects had typical MRI appearance of CCMs. Thirty-nine CCMs were studied using DCEMRI. Ki was low or normal in 12 lesions and elevated from 1.4 to 12 times higher than background in the remaining 27 lesions. Ki ranged from 2.1E-6 to 9.63E-4 min(-1), mean 3.55E-4. Normal-appearing white matter in the CCM patients had a mean Ki of 1.57E-4, not statistically different from mean WM Ki of 1.47E-4 in controls. TAPIR-based DCEMRI technique permits quantifiable assessment of CCMs in vivo and reveals considerable differences not seen with conventional MRI. Potential applications include correlation with biologic behavior such as lesion growth or hemorrage, and measurement of drug effects.

  8. Stent-assisted coil embolization for cavernous carotid artery aneurysms.

    Science.gov (United States)

    Kono, Kenichi; Shintani, Aki; Okada, Hideo; Tanaka, Yuko; Terada, Tomoaki

    2014-01-01

    Internal carotid artery (ICA) occlusion with or without a bypass surgery is the traditional treatment for cavernous sinus (CS) aneurysms with cranial nerve (CN) dysfunction. Coil embolization without stents frequently requires retreatment because of the large size of CS aneurysms. We report the mid-term results of six unruptured CS aneurysms treated with stent-assisted coil embolization (SACE). The mean age of the patients was 72 years. The mean size of the aneurysms was 19.8 mm (range: 13-26 mm). Before treatment, four patients presented with CN dysfunction and two patients had no symptoms. SACE was performed under local or general anesthesia in three patients each. Mean packing density was 29.1% and tight packing was achieved. There were no neurological complications. CN dysfunction was cured in three patients (75%) and partly resolved in one patient (25%). Transient new CN dysfunction was observed in two patients (33%). Clinical and imaging follow-up ranged from 6 to 26 months (median: 16 months). Recanalization was observed in three patients (50%; neck remnant in two patients and dome filling in one patient), but no retreatment has yet been required. No recurrence of CN dysfunction has occurred yet. In summary, SACE increases packing density and may reduce requirement of retreatment with an acceptable cure rate of CN dysfunction. SACE may be a superior treatment for coiling without stents and be an alternative treatment of ICA occlusion for selected patients, such as older patients and those who require a high-flow bypass surgery or cannot receive general anesthesia.

  9. Nuclear fuel waste disposal. Canada's consultative approach

    Energy Technology Data Exchange (ETDEWEB)

    Hillier, J A.R.; Dixon, R S [AECL (Canada)

    1993-07-01

    Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

  10. Nuclear fuel waste disposal. Canada's consultative approach

    International Nuclear Information System (INIS)

    Hillier, J.A.R.; Dixon, R.S.

    1993-01-01

    Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

  11. Radiotracer studies in cavernous marble at Kamathikhairy Dam site, Pench Project (Maharashtra)

    International Nuclear Information System (INIS)

    Nath, Ravendra; Mahajan, N.M.; Vaidya, S.D.

    1982-01-01

    Radiotracer studies with tritiated water at Pench Project site conclusively proved that the cavernous marble upstream of the saddle dam is continuous with the marble occuring near the spillway portion of the main dam and that there is fast subterranean flow of water through the cavernous marble here. It is also established that this marble band upstream of the dam is interconnected with the marble band occuring in the vicinity of Pali village about 3 km downstream of the dam. Though big unclogged subterranean channels do not seem to exist in this region, which might have resulted in heavy leakage from the impounded reservoir, yet the possibility of some leakage of the water through the cavernous marble cannot be ruled out, due to the interconnection of the marble occuring upstream of the dam with the downstream marble band. (author)

  12. Navigated transcranial magnetic stimulation in preoperative planning for the treatment of motor area cavernous angiomas

    Science.gov (United States)

    Paiva, Wellingson Silva; Fonoff, Erich Talamoni; Marcolin, Marco Antonio; Bor-Seng-Shu, Edson; Figueiredo, Eberval Gadelha; Teixeira, Manoel Jacobsen

    2013-01-01

    Since the introduction of microscopic techniques, radical surgery for cavernous angiomas has become a recommended treatment option. However, the treatment of motor area cavernous angioma represents a great challenge for the surgical team. Here, we describe an approach guided by frameless neuronavigation and preoperative functional mapping with transcranial magnetic stimulation (TMS), for surgical planning. We used TMS to map the motor cortex and its relationship with the angioma. We achieved complete resection of the lesions in the surgeries, while avoiding areas of motor response identified during the preoperative mapping. We verified the complete control of seizures (Engel class 1A) in the patients with previous refractory epilepsy. Postsurgery, one patient was seizure-free without medication, and two patients required only one medication for seizure control. Thus, navigated TMS appears to be a useful tool, in preoperative planning for cavernous angiomas of the motor area. PMID:24353424

  13. Spectacular test of the fire extinguishing system in the underground cavern of the CMS experiment

    CERN Multimedia

    Maximilien Brice

    2006-01-01

    The enormous rumbling heard 100 m under the earth on Friday, 12 May, was not the start of a foam party at CMS. The Safety Team looked on from the second tier of the CMS underground cavern as it reechoed to the sound of water rushing through the two huge pipes overhead and the air was filled with a mixture of water and foam. A minute later it was a winter wonderland, as fluffy puffs of foam came shooting out of the twelve foam blowers lining the upper cavern walls on both sides. In less than two minutes 7 m3 of water mixed with a small percentage of foaming liquid, was transformed into 5600 m3 of foam and discharged into the cavern.

  14. Gd-DTPA in the evaluation of the normal and adnormal cavernous sinus

    International Nuclear Information System (INIS)

    Marks, M.P.; Thrush, A.; Enzmann, D.

    1989-01-01

    This paper reports on Gd-DTPA used in the evaluation of normal and abnormal cavernous sinus anatomy. Twenty-five normal subjects and 11 patients with cavernous sinus invasion were studied before Gd-DTPA enhancement. Normal studies were assessed for the conspicuity of the dural margins, the trigeminal cistern, and intracavernous and exiting cranial nerves. Contrast medium enhancement improved deductibility of the medical cavernous sinus margin (68% vs 38% on precontrast images) and intracavernous cranial nerves. Cranial nerves were inconsistently seen even on postcontrast images (cranial nerve III, 88%; v 1 , 36%, V 2 , 38%). On the abnormal images, contrast enhancement was beneficial in defining the relationship of tumor to parasellar structures, egress of tumor through bony foramina, and compression of the trigeminal cistern

  15. Tightness and suitability evaluation of abandoned salt caverns served as hydrocarbon energies storage under adverse geological conditions (AGC)

    International Nuclear Information System (INIS)

    Wei, Liu; Jie, Chen; Deyi, Jiang; Xilin, Shi; Yinping, Li; Daemen, J.J.K.; Chunhe, Yang

    2016-01-01

    Highlights: • Tightness conditions are set to assess use of old caverns for hydrocarbons storage. • Gas seepage and tightness around caverns are numerically simulated under AGC. • κ of interlayers act as a key factor to affect the tightness and use of salt cavern. • The threshold upper permeability of interlayers is proposed for storing oil and gas. • Three types of real application are introduced by using the tightness conditions. - Abstract: In China, the storage of hydrocarbon energies is extremely insufficient partially due to the lack of storage space, but on the other side the existence of a large number of abandoned salt caverns poses a serious threat to safety and geological environments. Some of these caverns, defined as abandoned caverns under adverse geological conditions (AGC), are expected to store hydrocarbon energies (natural gas or crude oil) to reduce the risk of potential disasters and simultaneously support the national strategic energy reserve of China. Herein, a series of investigations primarily related to the tightness and suitability of the caverns under AGC is performed. Laboratory measurements to determine the physical and mechanical properties as well as porosity and permeability of bedded salt cores from a near target cavern are implemented to determine the petro-mechanical properties and basic parameters for further study. The results show that the mechanical properties of the bedded rock salts are satisfactory for the stability of caverns. The interface between the salt and interlayers exhibits mechanical properties that are between those of rock salt and interlayers and in particular is not a weak zone. The silty mudstone interlayers have relatively high porosity and permeability, likely due to their low content of clay minerals and the presence of halite-filled cracks. The conditions for evaluating the tightness and suitability of a cavern for storing hydrocarbons are proposed, including “No tensile stress,”

  16. The borehole disposal of spent sources (BOSS)

    International Nuclear Information System (INIS)

    Heard, R.G.

    2002-01-01

    During the International Atomic Energy Agency (IAEA) Regional Training Course on 'The Management of Low-Level Radioactive Waste from Hospitals and Other Nuclear Applications' hosted by the Atomic Energy Corporation of SA Ltd. (AEC), now NECSA, during July/August 1995, the African delegates reviewed their national radioactive waste programmes. Among the issues raised, which are common to most African countries, were the lack of adequate storage facilities, lack of disposal solutions and a lack of equipment to implement widely used disposal concepts to dispose of their spent sources. As a result of this meeting, a Technical Co-operation (TC) project was launched to look at the technical feasibility and economic viability of such a concept. Phase I and II of the project have been completed and the results can be seen in three reports produced by NECSA. The Safety Assessment methodology used in the evaluation of the concept was that developed during the ISAM programme and detailed in Van Blerk's PhD thesis. This methodology is specifically developed for shallow land repositories, but was used in this case as the borehole need not be more than 100m deep and could fit into the definition of a shallow land disposal system. The studies found that the BOSS concept would be suitable for implementation in African countries as the borehole has a large capacity for sources and it is possible that an entire country's disused sources can be placed in a single borehole. The costs are a lot lower than for a shallow land trench, and the concept was evaluated using radium (226) sources as the most limiting inventory. The conclusion of the initial safety assessment was that the BOSS concept is robust, and provides a viable alternative for the disposal of radium needles. The concept is expected to provide good assurance of safety at real sites. The extension of the safety assessment to other types of spent sources is expected to be relatively straightforward. Disposal of radium needles

  17. Disposal of spent fuel from German nuclear power plants - 16028

    International Nuclear Information System (INIS)

    Graf, Reinhold; Brammer, Klaus-Juergen; Filbert, Wolfgang; Bollingerfehr, Wilhelm

    2009-01-01

    The 'direct disposal of spent fuel' as a part of the current German reference concept was developed as an alternative to spent fuel reprocessing and vitrified HLW disposal. The technical facilities necessary for the implementation of this part of the reference concept, the so called POLLUX R concept, i.e. interim storage buildings for casks containing spent fuel, a pilot conditioning facility, and a special cask 'POLLUX' for final disposal have been built. With view to a geological salt formation all handling procedures for the direct disposal of spent fuel were tested aboveground in full-scale test facilities. To optimise the reference concept, all operational steps have been reviewed for possible improvements. The two additional concepts for the direct disposal of SF are the BSK 3 concept and the DIREGT concept. Both concepts rely on borehole emplacement technology, vertical boreholes for the BSK 3 concept und horizontal boreholes for the DIREGT concept. Supported by the EU and the German Federal Ministry of Economics and Technology (BMWi), DBE TECHNOLOGY built an aboveground full-scale test facility to simulate all relevant handling procedures for the BSK 3 disposal concept. GNS (Company for Nuclear Service), representing the German utilities, provided the main components and its know-how concerning cask design and manufacturing. The test program was concluded recently after more than 1.000 emplacement operations had been performed successfully. The BSK 3 emplacement system in total comprises an emplacement device, a borehole lock, a transport cart, a transfer cask which will shuttle between the aboveground conditioning facility and the underground repository, and the BSK 3 canister itself, designed to contain the fuel rods of three PWR-fuel assemblies with a total of about 1.6 tHM. The BSK 3 concept simplifies the operation of the repository because the handling procedures and techniques can also be applied for the disposal of reprocessing residues. In addition

  18. Deep Borehole Disposal Safety Analysis.

    Energy Technology Data Exchange (ETDEWEB)

    Freeze, Geoffrey A. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Stein, Emily [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Price, Laura L. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); MacKinnon, Robert J. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Tillman, Jack Bruce [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2016-10-01

    This report presents a preliminary safety analysis for the deep borehole disposal (DBD) concept, using a safety case framework. A safety case is an integrated collection of qualitative and quantitative arguments, evidence, and analyses that substantiate the safety, and the level of confidence in the safety, of a geologic repository. This safety case framework for DBD follows the outline of the elements of a safety case, and identifies the types of information that will be required to satisfy these elements. At this very preliminary phase of development, the DBD safety case focuses on the generic feasibility of the DBD concept. It is based on potential system designs, waste forms, engineering, and geologic conditions; however, no specific site or regulatory framework exists. It will progress to a site-specific safety case as the DBD concept advances into a site-specific phase, progressing through consent-based site selection and site investigation and characterization.

  19. Ultimate storage in salt caverns / status report; Endverwahrung von Salzkavernen / Stand der Entwicklung

    Energy Technology Data Exchange (ETDEWEB)

    Crotogino, F.; Schmidt, U. [Kavernen Bau- und Betriebs-GmbH, Hannover (Germany)

    1998-12-31

    The contribution reviews the state of knowledge on final storage in salt caverns. The long-term effects of a hermetically sealed, brine-filled cavern are discussed. So far, there are no valid predictions. (orig.) [Deutsch] In dem Beitrag wird der derzeitige Kenntnis- und Diskussionsstand zur Endverwahrung von Salzkavernen zusammengefasst. Aufbauend auf den bisher vorliegenden Vorstellungen zur Soleimpraegnation bei einem Innendruck, der nahezu dem Ueberlagerungsdruck entspricht, werden die denkbaren langfristigen Auswirkungen einer vollstaendig abgeschlossenen solegefuellten Kaverne skizziert; belastbare Prognosen sind derzeit noch nicht moeglich. (orig.)

  20. Simulation of Mechanical Processes in Gas Storage Caverns for Short-Term Energy Storage

    Science.gov (United States)

    Böttcher, Norbert; Nagel, Thomas; Kolditz, Olaf

    2015-04-01

    In recent years, Germany's energy management has started to be transferred from fossil fuels to renewable and sustainable energy carriers. Renewable energy sources such as solar and wind power are subjected by fluctuations, thus the development and extension of energy storage capacities is a priority in German R&D programs. This work is a part of the ANGUS+ Project, funded by the federal ministry of education and research, which investigates the influence of subsurface energy storage on the underground. The utilization of subsurface salt caverns as a long-term storage reservoir for fossil fuels is a common method, since the construction of caverns in salt rock is inexpensive in comparison to solid rock formations due to solution mining. Another advantage of evaporate as host material is the self-healing behaviour of salt rock, thus the cavity can be assumed to be impermeable. In the framework of short-term energy storage (hours to days), caverns can be used as gas storage reservoirs for natural or artificial fuel gases, such as hydrogen, methane, or compressed air, where the operation pressures inside the caverns will fluctuate more frequently. This work investigates the influence of changing operation pressures at high frequencies on the stability of the host rock of gas storage caverns utilizing numerical models. Therefore, we developed a coupled Thermo-Hydro-Mechanical (THM) model based on the finite element method utilizing the open-source software platform OpenGeoSys. The salt behaviour is described by well-known constitutive material models which are capable of predicting creep, self-healing, and dilatancy processes. Our simulations include the thermodynamic behaviour of gas storage process, temperature development and distribution on the cavern boundary, the deformation of the cavern geometry, and the prediction of the dilatancy zone. Based on the numerical results, optimal operation modes can be found for individual caverns, so the risk of host rock damage

  1. A NOVEL PROCESS TO USE SALT CAVERNS TO RECEIVE SHIP BORNE LNG

    Energy Technology Data Exchange (ETDEWEB)

    Michael M. McCall; William M. Bishop; Marcus Krekel; James F. Davis; D. Braxton Scherz

    2005-05-31

    This cooperative research project validates use of man made salt caverns to receive and store the cargoes of LNG ships in lieu of large liquid LNG tanks. Salt caverns will not tolerate direct injection of LNG because it is a cryogenic liquid, too cold for contact with salt. This research confirmed the technical processes and the economic benefits of pressuring the LNG up to dense phase, warming it to salt compatible temperatures and then directly injecting the dense phase gas into salt caverns for storage. The use of salt caverns to store natural gas sourced from LNG imports, particularly when located offshore, provides a highly secure, large scale and lower cost import facility as an alternative to tank based LNG import terminals. This design can unload a ship in the same time as unloading at a tank based terminal. The Strategic Petroleum Reserve uses man made salt caverns to securely store large quantities of crude oil. Similarly, this project describes a novel application of salt cavern gas storage technologies used for the first time in conjunction with LNG receiving. The energy industry uses man made salt caverns to store an array of gases and liquids but has never used man made salt caverns directly in the importation of LNG. This project has adapted and expanded the field of salt cavern storage technology and combined it with novel equipment and processes to accommodate LNG importation. The salt cavern based LNG receiving terminal described in the project can be located onshore or offshore, but the focus of the design and cost estimates has been on an offshore location, away from congested channels and ports. The salt cavern based terminal can provide large volumes of gas storage, high deliverability from storage, and is simplified in operation compared to tank based LNG terminals. Phase I of this project included mathematical modeling that proved a salt cavern based receiving terminal could be built at lower capital cost, and would have significantly higher

  2. [Clinical picture and complex treatment of septic thromboses of the cavernous sinuses].

    Science.gov (United States)

    Mozhaev, S V; Zubkov, Iu N; Ponomarev, A M; Shimchenko, P Ia

    1980-07-01

    Under analysis are etiology, clinical picture and diagnosis of a septic thrombosis of cavernous sinuses in 28 patients. The authors have shown the interrelationship between local manifestations of the disease, injuries of the brain and its sheaths and septic complications (abscessing pneumonia as the most severe of them). A scheme of the complex treatment of patients with thrombosis of the cavernous sinus is proposed. The leading role in this treatment is played by intracarotid infusion of antibiotics in combination with anticoagulant drugs, vasodilatatory agents and novocaine as well as the therapy of septic complications (abscesses of the face and hairy part of the head, meningoencephalitis, pneumonia).

  3. Optimizing High Level Waste Disposal

    International Nuclear Information System (INIS)

    Dirk Gombert

    2005-01-01

    If society is ever to reap the potential benefits of nuclear energy, technologists must close the fuel-cycle completely. A closed cycle equates to a continued supply of fuel and safe reactors, but also reliable and comprehensive closure of waste issues. High level waste (HLW) disposal in borosilicate glass (BSG) is based on 1970s era evaluations. This host matrix is very adaptable to sequestering a wide variety of radionuclides found in raffinates from spent fuel reprocessing. However, it is now known that the current system is far from optimal for disposal of the diverse HLW streams, and proven alternatives are available to reduce costs by billions of dollars. The basis for HLW disposal should be reassessed to consider extensive waste form and process technology research and development efforts, which have been conducted by the United States Department of Energy (USDOE), international agencies and the private sector. Matching the waste form to the waste chemistry and using currently available technology could increase the waste content in waste forms to 50% or more and double processing rates. Optimization of the HLW disposal system would accelerate HLW disposition and increase repository capacity. This does not necessarily require developing new waste forms, the emphasis should be on qualifying existing matrices to demonstrate protection equal to or better than the baseline glass performance. Also, this proposed effort does not necessarily require developing new technology concepts. The emphasis is on demonstrating existing technology that is clearly better (reliability, productivity, cost) than current technology, and justifying its use in future facilities or retrofitted facilities. Higher waste processing and disposal efficiency can be realized by performing the engineering analyses and trade-studies necessary to select the most efficient methods for processing the full spectrum of wastes across the nuclear complex. This paper will describe technologies being

  4. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 4. Alternatives for waste isolation and disposal

    International Nuclear Information System (INIS)

    1976-05-01

    Volume IV of the five-volume report contains information on alternatives for final storage and disposal of radioactive wastes. Section titles include: basic concepts for geologic isolation; geologic storage alternatives; geologic disposal alternatives; extraterrestrial disposal; and, transmutation

  5. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 4. Alternatives for waste isolation and disposal

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Volume IV of the five-volume report contains information on alternatives for final storage and disposal of radioactive wastes. Section titles include: basic concepts for geologic isolation; geologic storage alternatives; geologic disposal alternatives; extraterrestrial disposal; and, transmutation. (JGB)

  6. Taiwan industrial cooperation program technology transfer for low-level radioactive waste final disposal - phase I.

    Energy Technology Data Exchange (ETDEWEB)

    Knowlton, Robert G.; Cochran, John Russell; Arnold, Bill Walter; Jow, Hong-Nian; Mattie, Patrick D.; Schelling, Frank Joseph Jr. (; .)

    2007-01-01

    Sandia National Laboratories and the Institute of Nuclear Energy Research, Taiwan have collaborated in a technology transfer program related to low-level radioactive waste (LLW) disposal in Taiwan. Phase I of this program included regulatory analysis of LLW final disposal, development of LLW disposal performance assessment capabilities, and preliminary performance assessments of two potential disposal sites. Performance objectives were based on regulations in Taiwan and comparisons to those in the United States. Probabilistic performance assessment models were constructed based on limited site data using software including GoldSim, BLT-MS, FEHM, and HELP. These software codes provided the probabilistic framework, container degradation, waste-form leaching, groundwater flow, radionuclide transport, and cover infiltration simulation capabilities in the performance assessment. Preliminary performance assessment analyses were conducted for a near-surface disposal system and a mined cavern disposal system at two representative sites in Taiwan. Results of example calculations indicate peak simulated concentrations to a receptor within a few hundred years of LLW disposal, primarily from highly soluble, non-sorbing radionuclides.

  7. Treatment and disposal of radioactive wastes from nuclear power plants. Program for encapsulation, deep geologic deposition and research, development and demonstration

    International Nuclear Information System (INIS)

    1995-09-01

    Programs for RD and D concerning disposal of radioactive waste are presented. Main topics include: Design, testing and manufacture of canisters for the spent fuels; Design of equipment for deposition of waste canisters; Material and process for backfilling rock caverns; Evaluation of accuracy and validation of methods for safety analyses; Development of methods for defining scenarios for the safety analyses. 471 refs, 67 figs, 21 tabs

  8. Geological disposal system development

    International Nuclear Information System (INIS)

    Kang, Chul Hyung; Kuh, J. E.; Kim, S. K. and others

    2000-04-01

    Spent fuel inventories to be disposed of finally and design base spent fuel were determined. Technical and safety criteria for a geological repository system in Korea were established. Based on the properties of spent PWR and CANDU fuels, seven repository alternatives were developed and the most promising repository option was selected by the pair-wise comparison method from the technology point of view. With this option preliminary conceptual design studies were carried out. Several module, e.g., gap module, congruent release module were developed for the overall assessment code MASCOT-K. The prominent overseas databases such as OECD/NEA FEP list were are fully reviewed and then screened to identify the feasible ones to reflect the Korean geo-hydrological conditions. In addition to this the well known scenario development methods such as PID, RES were reviewed. To confirm the radiological safety of the proposed KAERI repository concept the preliminary PA was pursued. Thermo-hydro-mechanical analysis for the near field of repository were performed to verify thermal and mechanical stability for KAERI repository system. The requirements of buffer material were analyzed, and based on the results, the quantitative functional criteria for buffer material were established. The hydraulic and swelling property, mechanical properties, and thermal conductivity, the organic carbon content, and the evolution of pore water chemistry were investigated. Based on the results, the candidate buffer material was selected

  9. Research on geological disposal

    International Nuclear Information System (INIS)

    Uchida, Masahiro

    2011-01-01

    The aims of this research are to develop criteria for reviewing acceptability of the adequacy of the result of Preliminary and Detailed Investigations submitted by the implementor, and to establish a basic policy to secure safety for safety review. In FY 2010, 13 geology/climate related events for development of acceptance criteria for reviewing the adequacy of the result of Preliminary and Detailed Investigations were extracted. And the accuracy of geophysical exploration methods necessary for the Preliminary Investigation was evaluated. Regarding the research for safety review, we developed an idea of safety concept of Japanese geological disposal, and analyzed basic safety functions to secure safety. In order to verify the groundwater flow evaluation methods developed in regulatory research, the hydrological and geochemical data at Horonobe, northern Hokkaido were obtained, and simulated result of regional groundwater flow were compared with measured data. And we developed the safety scenario of geology/climate related events categorized by geological and geomorphological properties. Also we created a system to check the quality of research results in Japan and other countries in order to utilize for safety regulation, and developed a database system to compile them. (author)

  10. Geological disposal system development

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Chul Hyung; Kuh, J. E.; Kim, S. K. and others

    2000-04-01

    Spent fuel inventories to be disposed of finally and design base spent fuel were determined. Technical and safety criteria for a geological repository system in Korea were established. Based on the properties of spent PWR and CANDU fuels, seven repository alternatives were developed and the most promising repository option was selected by the pair-wise comparison method from the technology point of view. With this option preliminary conceptual design studies were carried out. Several module, e.g., gap module, congruent release module were developed for the overall assessment code MASCOT-K. The prominent overseas databases such as OECD/NEA FEP list were are fully reviewed and then screened to identify the feasible ones to reflect the Korean geo-hydrological conditions. In addition to this the well known scenario development methods such as PID, RES were reviewed. To confirm the radiological safety of the proposed KAERI repository concept the preliminary PA was pursued. Thermo-hydro-mechanical analysis for the near field of repository were performed to verify thermal and mechanical stability for KAERI repository system. The requirements of buffer material were analyzed, and based on the results, the quantitative functional criteria for buffer material were established. The hydraulic and swelling property, mechanical properties, and thermal conductivity, the organic carbon content, and the evolution of pore water chemistry were investigated. Based on the results, the candidate buffer material was selected.

  11. No nuclear power. No disposal facility?

    Energy Technology Data Exchange (ETDEWEB)

    Feinhals, J. [DMT GmbH und Co.KG, Hamburg (Germany)

    2016-07-01

    Countries with a nuclear power programme are making strong efforts to guarantee the safe disposal of radioactive waste. The solutions in those countries are large disposal facilities near surface or in deep geological layers depending on the activity and half-life of the nuclides in the waste. But what will happen with the radioactive waste in countries that do not have NPPs but have only low amounts of radioactive waste from medical, industrial and research facilities as well as from research reactors? Countries producing only low amounts of radioactive waste need convincing solutions for the safe and affordable disposal of their radioactive waste. As they do not have a fund by an operator of nuclear power plants, those countries need an appropriate and commensurate solution for the disposal of their waste. In a first overview five solutions seem to be appropriate: (i) the development of multinational disposal facilities by using the existing international knowhow; (ii) common disposal with hazardous waste; (iii) permanent storage; (iv) use of an existing mine or tunnel; (v) extension of the borehole disposal concept for all the categories of radioactive wastes.

  12. The legal system of nuclear waste disposal

    International Nuclear Information System (INIS)

    Dauk, W.

    1983-01-01

    This doctoral thesis presents solutions to some of the legal problems encountered in the interpretation of the various laws and regulations governing nuclear waste disposal, and reveals the legal system supporting the variety of individual regulations. Proposals are made relating to modifications of problematic or not well defined provisions, in order to contribute to improved juridical security, or inambiguity in terms of law. The author also discusses the question of the constitutionality of the laws for nuclear waste disposal. Apart from the responsibility of private enterprise to contribute to safe treatment or recycling, within the framework of the integrated waste management concept, and apart from the Government's responsibility for interim or final storage of radioactive waste, there is a third possibility included in the legal system for waste management, namely voluntary measures taken by private enterprise for radioactive waste disposal. The licence to be applied for in accordance with section 3, sub-section (1) of the Radiation Protection Ordinance is interpreted to pertain to all measures of radioactive waste disposal, thus including final storage of radioactive waste by private companies. Although the terminology and systematic concept of nuclear waste disposal are difficult to understand, there is a functionable system of legal provisions contained therein. This system fits into the overall concept of laws governing technical safety and safety engineering. (orig./HSCH) [de

  13. Trial Readiness in Cavernous Angiomas With Symptomatic Hemorrhage (CASH).

    Science.gov (United States)

    Polster, Sean P; Cao, Ying; Carroll, Timothy; Flemming, Kelly; Girard, Romuald; Hanley, Daniel; Hobson, Nicholas; Kim, Helen; Koenig, James; Koskimäki, Janne; Lane, Karen; Majersik, Jennifer J; McBee, Nichol; Morrison, Leslie; Shenkar, Robert; Stadnik, Agnieszka; Thompson, Richard E; Zabramski, Joseph; Zeineddine, Hussein A; Awad, Issam A

    2018-04-11

    Brain cavernous angiomas with symptomatic hemorrhage (CASH) are uncommon but exact a heavy burden of neurological disability from recurrent bleeding, for which there is no proven therapy. Candidate drugs to stabilize the CASH lesion and prevent rebleeding will ultimately require testing of safety and efficacy in multisite clinical trials. Much progress has been made in understanding the epidemiology of CASH, and novel biomarkers have been linked to the biological mechanisms and clinical activity in lesions. Yet, the ability to enroll and risk-stratify CASH subjects has never been assessed prospectively at multiple sites. Biomarkers and other outcomes have not been evaluated for their sensitivity and reliability, nor have they been harmonized across sites. To address knowledge gaps and establish a research network as infrastructure for future clinical trials, through the Trial Readiness grant mechanism, funded by National Institute of Neurological Disorders and Stroke/National Institutes of Health. This project includes an observational cohort study to assess (1) the feasibility of screening, enrollment rates, baseline disease categorization, and follow-up of CASH using common data elements at multiple sites, (2) the reliability of imaging biomarkers including quantitative susceptibility mapping and permeability measures that have been shown to correlate with lesion activity, and (3) the rates of recurrent hemorrhage and change in functional status and biomarker measurements during prospective follow-up. We propose a harmonized multisite assessment of enrollment rates of CASH, baseline features relevant to stratification in clinical trials, and follow-up assessments of functional outcomes in relation to clinical bleeds. We introduce novel biomarkers of vascular leak and hemorrhage, with firm mechanistic foundations, which have been linked to clinical disease activity. We shall test their reliability and validity at multiple sites, and assess their changes over time

  14. Cavernous malformations isolated from cranial nerves: Unexpected diagnosis?

    Science.gov (United States)

    Rotondo, Michele; Natale, Massimo; D'Avanzo, Raffaele; Pascale, Michela; Scuotto, Assunta

    2014-11-01

    Cranial nerves (CN) cavernous malformations (CMs) are lesions that are isolated from the CNs. The authors present three cases of CN CMs, for which MR was demonstrated to be critical for management, and surgical resection produced good outcomes for the patients. Surgical removal is the recommended course of action to restore or preserve neurological function and to eliminate the risk of future haemorrhage. However, the anatomical location and the complexity of nearby neural structures can make these lesions difficult to access and remove. In this study, the authors review the literature of reported cases of CN CMs to analyse the clinical and radiographic presentations, surgical approaches and neurological outcomes. A MEDLINE/Pub Med search was performed and revealed 86 cases of CN CMs. The authors report three additional cases in this study for a total of 89 cases. CMs affecting the optic nerve (CN II), oculomotor nerve (CN III), facial/vestibule-cochlear nerves (CN VII, CN VIII) have been described. The records of three patients were reviewed with respect to the lesion locations, symptoms, surgical approaches and therapeutic considerations. Clinical and radiological follow-up results are reported. Three patients (2 females, 1 male; age range 21-37 year) presented with three CN lesions. One lesion involved CN III, one lesion involved CN VII-CN VIII, and one involved CN II. The patient with the CN III lesion had a one-month history of mild right ptosis and diplopia. The patient with the CN VII-CN VIII lesion exhibited acute hearing loss and on the left and left facial paresis. The patient with the opticchiasmatic lesion presented with acute visual deterioration on the right and a left temporal field deficit in the left eye. Pterional and orbitozygomatic craniotomies were performed for the CN III lesion and the CN II lesion, and retrosigmoid craniotomy was performed for the cerebello-pontine angle lesion. All patients experienced symptom improvement after surgery. On

  15. Siting history and current construction status of disposal facility for low and intermediate level radioactive waste in Korea

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Kikuchi, Saburo; Maruyama, Masakatsu

    2008-01-01

    Korean government decided disposal site for low and intermediate level radioactive waste (LILW), which is located at coastal area near the Wolsong nuclear power plants in Gyeong-Ju city in December. 2005, based on the result of votes of residents in four candidate sites. Since then, Korea Hydro and Nuclear Power Co., Ltd (KHNP), which is the management company of the LILW disposal facility, has carried out the preparation for construction of disposal facility and its licensing process. At the first phase, 100 thousand drums in 200 liter are planned to be disposed of in the rock cavern type disposal facility located at the depth from 80m to 130m below the sea level, and finally 800 thousand drums in 200 liter are planned to be disposed of in the site. This report shows the history of siting for the LILW disposal, the outline of design of disposal facility and current status of its construction, based on the information which was obtained mainly during our visit to the disposal site in Korea. (author)

  16. Processing and waste disposal representative for fusion breeder blanket systems

    International Nuclear Information System (INIS)

    Finn, P.A.; Vogler, S.

    1987-01-01

    This study is an evaluation of the waste handling concepts applicable to fusion breeder systems. Its goal is to determine if breeder blanket waste can be disposed of in shallow land burial, the least restrictive method under US Nuclear Regulatory regulations. The radionuclides expected in the materials used in fusion reactor blankets are described, as are plans for reprocessing and disposal of the components of different breeder blankets. An estimate of the operating costs involved in waste disposal is made

  17. Implementation and responsibility for waste disposal : AEC sets up frameworks

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The Atomic Energy Commission approved the report ''measures for treatment and disposal of radioactive waste'' made by its advisory committee; which clarifies where the legal responsibility lies in relation to the waste treatment and disposal. In principle, the waste producers, i.e. the electric power companies should be responsible for the treatment and disposal of low-level radioactive waste and the Government for regulation of the safety of waste management. Then, in connection with a LLW ultimate storage facility planned in Aomori Prefecture, the waste disposal company may be responsible for safety of the LLW management. The disposal of high-level radioactive waste is the responsibility of the Government, the waste producer being responsible for the cost. Contents are the following: organization and responsibility for treatment and disposal of radioactive waste; concept of disposal of TRU waste. (Mori, K.)

  18. Advances in Geologic Disposal System Modeling and Shale Reference Cases

    Energy Technology Data Exchange (ETDEWEB)

    Mariner, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Emily R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Frederick, Jennifer M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sevougian, S. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hammond, Glenn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-09-22

    The Spent Fuel and Waste Science and Technology (SFWST) Campaign of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (OFCT) is conducting research and development (R&D) on geologic disposal of spent nuclear fuel (SNF) and high level nuclear waste (HLW). Two high priorities for SFWST disposal R&D are design concept development and disposal system modeling (DOE 2011, Table 6). These priorities are directly addressed in the SFWST Generic Disposal Systems Analysis (GDSA) work package, which is charged with developing a disposal system modeling and analysis capability for evaluating disposal system performance for nuclear waste in geologic media (e.g., salt, granite, shale, and deep borehole disposal).

  19. Disposal of Radioactive Waste

    International Nuclear Information System (INIS)

    2011-01-01

    This Safety Requirements publication applies to the disposal of radioactive waste of all types by means of emplacement in designed disposal facilities, subject to the necessary limitations and controls being placed on the disposal of the waste and on the development, operation and closure of facilities. The classification of radioactive waste is discussed. This Safety Requirements publication establishes requirements to provide assurance of the radiation safety of the disposal of radioactive waste, in the operation of a disposal facility and especially after its closure. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. This is achieved by setting requirements on the site selection and evaluation and design of a disposal facility, and on its construction, operation and closure, including organizational and regulatory requirements.

  20. Safety studies of HLW-disposal in the Mors salt dome - Support to the salt option of the Pagis project

    International Nuclear Information System (INIS)

    Lindstroem Jensen, K.E.

    1987-01-01

    The study, which is a support to the Pagis project, covers three tasks concerning the evaluation of the Danish salt dome Mors (variant disposal site): evaluation of the human intrusion scenario where a cavern is excavated near the HLW-repository by solution mining technique. The waste is supposed to be leached during the operation period until the abandoned cavern is closed by convergence and the contaminated brine is pressed up into the overburden. Evaluation of the brine intrusion scenario, where the HLW-repository is inadvertently located close to a major brine pocket which subsequently releases its brine content through defects in the repository to the discharge stream for the catchment area. Collection and description of hydrological data of surface and deep layers (down to circa 700 metres) in the repository region. The data will be used by GSF to calculate the radionuclide migration in the geosphere

  1. Industrial feasibility study of a spent nuclear fuel package for direct deep disposal

    International Nuclear Information System (INIS)

    Le Lous, K.; Loubrieu, J.; Chupeau, J.; Serpantie, J.P.; Becle, D.; Aubry, S.

    2001-01-01

    EDF has undertaken to study the industrial feasibility of a spent nuclear fuel package meeting direct disposal requirements. In this context, a disposal concept has been defined in which packages are cooled in place until the module is finally sealed. Indeed, one of the objectives of that disposal concept is to reduce the underground area occupied by the repository. A functional analysis has been performed within the framework of that ventilated disposal concept, taking into account the phases of the package lifetime from its conditioning until the disposal post-closure phase. An industrial feasibility study is in progress, which takes into account the functional specifications and some preliminary studies. (author)

  2. The use of protective barriers to deter inadvertent human intrusion into a mined geologic facility for the disposal of radioactive waste: A review of previous investigations and potential concepts

    International Nuclear Information System (INIS)

    Tolan, T.L.

    1993-06-01

    Sandia National Laboratories is evaluating the feasibility of developing protective barrier system for the Waste Isolation Pilot Plant (WIPP) to thwart inadvertent human intrusion into this radioactive-waste disposal system for a period of 9,900 years after assumed loss of active institutional controls. The protective barrier system would be part of a series of enduring passive institutional controls whose long-term function will be to reduce the likelihood of inadvertent human activities (e.g., exploratory drilling for resources) that could disrupt the WIPP disposal system

  3. A creative therapy in treating cavernous hemangioma of penis with copper wire.

    Science.gov (United States)

    Zhang, Dong; Zhang, Haiyang; Sun, Peng; Li, Peng; Xue, Aibing; Jin, Xunbo

    2014-10-01

    Cavernous hemangiomas of penis are rare benign lesions infrequently described in the literature. No completely satisfactory treatment has been found to correct the cosmetic deformities especially the extensive hemangiomas of corpus penis. In light of the promising application of copper wire/needle in vascular malformations, we began a clinical study to investigate the safety, feasibility, and cosmetic effect of copper wire therapy in treating cavernous hemangioma of penis. Seven patients ranging in age from 12 to 32 years with penile cavernous hemangiomas entered our study from 2005 to 2011. All patients received treatments with percutaneous copper wires. Perioperative data including mean operation time, estimated blood loss, length of copper wire retention, and length of hospital stay were analyzed. All possible complications were noted, and cosmetic result was evaluated. Patients were followed up after discharge from the hospital. All operations were successful, and no obvious complications were observed. The patients were satisfied with the aesthetic results. Follow-up time ranged from 1 to 5 years. Recurrence was discovered in a patient with the largest lesion of corpus penis 2 months after the treatment. Secondary procedure was carried out with the same technique, and no lesions were found later. The shortage of studies on this topic prevented us from defining a therapeutic reference standard. The results of our study confirmed that copper wire therapy was a simple, safe, and useful option for penile cavernous hemangioma. © 2013 International Society for Sexual Medicine.

  4. Schwann cell seeded guidance tubes restore erectile function after ablation of cavernous nerves in rats.

    Science.gov (United States)

    May, F; Weidner, N; Matiasek, K; Caspers, C; Mrva, T; Vroemen, M; Henke, J; Lehmer, A; Schwaibold, H; Erhardt, W; Gänsbacher, B; Hartung, R

    2004-07-01

    Dissection of the cavernous nerves eliminates spontaneous erections. We evaluated the ability of Schwann cell seeded nerve guidance tubes to restore erections after bilateral cavernous nerve resection in rats. Sections (5 mm) of the cavernous nerve were excised bilaterally, followed by immediate bilateral microsurgical reconstruction. In 10 animals per group (20 study nerves) reconstruction was performed by genitofemoral nerve interposition, interposition of silicone tubes or interposition of silicone tubes seeded with homologous Schwann cells. As the control 10 animals (20 study nerves) underwent sham operation (positive control) and bilateral nerve ablation (without reconstruction) was performed in a further 10 (negative control). Erectile function was evaluated 3 months postoperatively by relaparotomy, electrical nerve stimulation and intracavernous pressure recording. After 3 months neurostimulation resulted in an intact erectile response in 90% (18 of 20) of Schwann cell grafts, while treatment with autologous nerves (30% or 6 of 20) or tubes only (50% or 10 of 20) was less successful (p Schwann cell grafts compared to results in the other treatment groups (p Schwann cell grafts. Schwann cell seeded guidance tubes restore erectile function after the ablation of cavernous nerves in rats and they are superior to autologous nerve grafts.

  5. Aggressive cavernous sinus dural arteriovenous fistula: Angioarchitecture analysis and embolization by various approaches

    Directory of Open Access Journals (Sweden)

    Chao-Bao Luo

    2016-03-01

    Conclusion: Aggressive CSDAVFs are associated with occlusion/stenosis of the IPS or compartment of IPS–cavernous sinus with leptomeningeal reflux. In this limited case series, aggressive CSDAVFs most presented with brainstem ischemia, followed by nonhemorrhagic/hemorrhagic stroke in the cerebrum. Embolization through various access routes is a feasible method to manage these aggressive CSDAVFs, with an acceptable level of periprocedural risks.

  6. Intramedullary cavernous angiomas of the spinal cord. Clinical characteristics of 13 lesions

    International Nuclear Information System (INIS)

    Aoyama, Takeshi; Hida, Kazutoshi; Houkin, Kiyohiro

    2011-01-01

    Magnetic resonance imaging has increased the incidence of the diagnosis of intramedullary cavernous angioma. Surgical therapy tends not to be recommended for asymptomatic lesions, but symptomatic lesions that bleed recurrently should be treated. The natural course of intramedullary cavernous angioma remains unknown and arguments have been raised against the surgical treatment of symptomatic lesions. We reviewed the clinical features of 13 intramedullary cavernous angiomas in 12 patients surgically treated between 1988 and 2009. The 7 men and 5 women were aged from 14 to 60 years, the preoperative interval ranged from 0 to 161 months, and the mean number of hemorrhages in the 13 lesions was 2.5. Sixteen operations were performed to treat the 13 lesions. The surgical approach depended on the lesion location. The outcome of patients with mild to moderate preoperative symptoms (McCormick grades I-III) was significantly better than that of patients with severe symptoms (McCormick grade IV) (p<0.05). Symptomatic intramedullary cavernous angioma tends to bleed repeatedly. The lesion should be surgically removed to avoid further deterioration due to recurrent hemorrhages. The shortest path approach should be selected based on preoperative images and complete removal should be attempted. Residual lesion may be masked by surrounding gliosis, so careful postoperative follow up is necessary. (author)

  7. Physical and Numerical Modeling of the Stability of Deep Caverns in Tahe Oil Field in China

    Directory of Open Access Journals (Sweden)

    Chao Wang

    2017-06-01

    Full Text Available Cave collapses emerge during the process of oil reservoir development, seriously affecting oil production. To reveal the collapse and failure mechanism of the carbonate cavern with a buried depth of 5600 m in Tahe Oil Field, using a self-developed ultra-high pressure model test system with the intelligent numerical control function, the model simulation material of carbonate rocks developed to carry out the 3D geo-mechanical model test. The model test and numerical results indicate that: (1 collapse and failure mechanism of the deep-buried caves mainly involve the failure mode of tensile shear. The rupture plane on the side wall is approximately parallel to the direction of maximum principal compressive stress. The V-type tension and split rupture plane then emerges. (2 In the process of forming holes in the model caverns, micro cracks are generated at the foot of the left and right side walls of the caverns, and the roof panels are constantly moving downward. The shorter the distance to the cave wall, the severer the destructiveness of the surrounding rocks will be. (3 The displacement of the top of the model cavern is relatively large and uniform, indicating that the cave roof moves downward as a whole. The area of the cavity suffering damage is 2.3 times as large as the cave span. The research results in this paper lay a solid test basis for revealing the cave collapse and failure mechanism in super depth.

  8. Detection of cavernous transformation of the portal vein by contrast-enhanced ultrasound.

    Science.gov (United States)

    Hwang, Misun; Thimm, Matthew A; Guerrerio, Anthony L

    2018-06-01

    Cavernous transformation of the portal vein can be missed on color Doppler exam or arterial phase cross-sectional imaging due to their slow flow and delayed enhancement. Contrast-enhanced ultrasound (CEUS) offers many advantages over other imaging techniques and can be used to successfully detect cavernous transformations of the portal vein. A 10-month-old female was followed for repeat episodes of hematemesis. Computed tomography angiography (CTA) and magnetic resonance arteriogram (MRA) and portal venography were performed. Color Doppler exam of the portal vein was performed followed by administration of Lumason, a microbubble US contrast agent. Magnetic resonance arteriogram, CTA, and color Doppler exam at the time of initial presentation was unremarkable without obvious vascular malformation within the limits of motion degraded exam. At 8-month follow-up, esophagogastroduodenoscopy revealed a vascular malformation in the distal esophagus which was sclerosed. At 6 month after sclerosis of the lesion, portal venography revealed occlusion of the portal vein with extensive collateralization. Color Doppler revealed subtle hyperarterialization and periportal collaterals. CEUS following color Doppler exam demonstrated extensive enhancement of periportal collaterals. Repeat color Doppler after contrast administration demonstrated extensive Doppler signal in the collateral vessels, suggestive of cavernous transformation. We describe a case of cavernous transformation of the portal vein missed on initial color Doppler, CTA and MRA, but detected with contrast-enhanced ultrasound technique.

  9. Large cavernous hemangioma of the adrenal gland: Laparoscopic treatment. Report of a case

    Directory of Open Access Journals (Sweden)

    A. Agrusa

    2015-01-01

    Conclusion: Laparoscopic adrenalectomy is considered the standard treatment in case of diagnosis of benign lesions. In this case report we discussed a large adrenal cavernous hemangioma treated with laparoscopic approach. Fundamental is the study of preoperative endocrine disorders and radiologic findings to exclude signs of malignancy.

  10. Spall formation in solution mined storage caverns based on a creep and fracture analysis

    International Nuclear Information System (INIS)

    Munson, Darrell E.

    2000-01-01

    Because of limited direct observation, understanding of the interior conditions of the massive storage caverns constructed in Gulf Coast salt domes is realizable only through predictions of salt response. Determination of the potential for formation of salt spans, leading to eventual salt falls, is based on salt creep and fracture using the Multimechanism-Deformation Coupled Fracture (MCDF) model. This is a continuum model for creep, coupled to continuum damage evolution. The model has been successfully tested against underground results of damage around several test rooms at the Waste Isolation Pilot Plant (WIPP). Model simulations, here, evaluate observations made in the Strategic Petroleum Reserve (SPR) storage caverns, namely, the accumulation of material on cavern floors and evidence of salt falls. A simulation of a smooth cavern wall indicates damage is maximum at the surface but diminishes monotonically into the salt, which suggests the source of salt accumulation is surface sluffing. If a protuberance occurs on the wall, fracture damage can form beneath the protuberance, which will eventually cause fracture, and lead to a salt fall

  11. Roentgenological investigation of cavernous sinus structure with special reference to paracavernous cranial nerves

    International Nuclear Information System (INIS)

    Tsuha, M.; Aoki, H.; Okamura, T.

    1987-01-01

    We have evaluated the anatomical structure of cavernous sinuses in parasellar blocks obtained from adult cadavers to gain clinically useful information. Ten microdissectional studies of parasellar blocks (20 sides of cavernous sinus) were carried out with special emphasis on the course of paracavernous cranial nerves (3rd to 6th). These were also examined on plain radiographs. Secondly, CT investigations of the cavernous sinuses (notably as to paracavernous cranial nerves) were undertaken in twenty clinical cases having presumed parasellar lesions and in three parasellar blocks from cadavers. The results from microdisectional studies and plain radiographs were as follows. It was found that the 3rd cranial nerve entered the lateral wall of the cavernous sinus close to the antero-inferior part of the posterior clinoid on lateral projection. The 4th cranial nerve, on the other hand, entered near the postero-inferior portion of the posterior clinoid on the same view. Variations in Parkinson's triangle were fairly often noted, although marked asymmetry was not seen in individual cases. From CT findings, it was found that a postenhanced, magnified direct coronal study was essential for identifying paracavernous cranial nerves more clearly. The 3rd and 5th cranial nerves were fairly well identified on axial and coronal projections. Careful radiological investigation including plain skull radiographs and CT seems to be of value for those who diagnose or treat parasellar lesions. (orig.)

  12. Arteriovenous Malformation in Temporal Lobe Presenting as Contralateral Ocular Symptoms Mimicking Carotid-Cavernous Fistula

    Directory of Open Access Journals (Sweden)

    Fadzillah Mohd-Tahir

    2013-01-01

    Full Text Available Aim. To report a rare case of arteriovenous malformation in temporal lobe presenting as contralateral orbital symptoms mimicking carotid-cavernous fistula. Method. Interventional case report. Results. A 31-year-old Malay gentleman presented with 2-month history of painful progressive exophthalmos of his left eye associated with recurrent headache, diplopia, and reduced vision. Ocular examination revealed congestive nonpulsating 7 mm exophthalmos of the left eye with no restriction of movements in all direction. There was diplopia in left lateral gaze. Left IOP was elevated at 29 mmHg. Left eye retinal vessels were slightly dilated and tortuous. CT scan was performed and showed right temporal arteriovenous malformation with a nidus of 3.8 cm × 2.5 cm with right middle cerebral artery as feeding artery. There was dilated left superior ophthalmic vein of 0.9 mm in diameter with enlarged left cavernous sinus. MRA and carotid angiogram confirmed right temporal arteriovenous malformation with no carotid-cavernous fistula. Most of the intracranial drainage was via left cavernous sinus. His signs and symptoms dramatically improved following successful embolisation, completely resolved after one year. Conclusion. Intracranial arteriovenous malformation is rarely presented with primary ocular presentation. Early intervention would salvage the eyes and prevent patients from more disaster morbidity or fatality commonly due to intracranial haemorrhage.

  13. Strains and stresses in the rock around and unlined hot water cavern

    Science.gov (United States)

    Rehbinder, Göran

    1984-07-01

    Hot water stored in an unlined rock cavern is an efficient energy storage. A research program has been carried out with a test plant at the city of Avesta, Sweden. The plant consists of a rock cavern, the volume of which is 15000 m3, which serves as an energy buffer in the district heating system of the city. The water is heated from a garbage incinerator located close to the cavern. During the first test period the temperature of the stored water has varied between 40°C and 95°C. The heating of the rock causes strains and stresses in the rock. The measurements show that the state in the rock does mainly respond to the average temperature and not to the fluctuations. The maximum thermal stress is 9 MPa occurring at the wall of the cavern. The heave of the ground is less than 5 mm. The development of stress and strain will continue after the first test period since thermal equilibrium was not reached during this period.

  14. High-Level Radioactive Waste: Safe Storage and Ultimate Disposal.

    Science.gov (United States)

    Dukert, Joseph M.

    Described are problems and techniques for safe disposal of radioactive waste. Degrees of radioactivity, temporary storage, and long-term permanent storage are discussed. Included are diagrams of estimated waste volumes to the year 2000 and of an artist's conception of a permanent underground disposal facility. (SL)

  15. Occipital lobe infarction: a rare presentation of bilateral giant cavernous carotid aneurysms: a case report.

    Science.gov (United States)

    Vanikieti, Kavin; Poonyathalang, Anuchit; Jindahra, Panitha; Cheecharoen, Piyaphon; Chokthaweesak, Wimonwan

    2018-02-02

    Cavernous carotid aneurysm (CCA) represents 2-9% of all intracranial aneurysms and 15% of internal carotid artery (ICA) aneurysms; additionally, giant aneurysms are those aneurysms that are > 25 mm in size. Bilateral CCAs account for 11-29% of patients and are commonly associated with structural weaknesses in the ICA wall, secondary to systemic hypertension. CCAs are considered benign lesions, given the low risk for developing major neurologic morbidities (i.e., subarachnoid hemorrhage, cerebral infarction, or carotid cavernous fistula). Moreover, concurrent presentation with posterior circulation cerebral infarction is even rarer, given different circulation territory from CCA. Here, we report on a patient with bilateral giant CCAs who presented with both typical and atypical symptoms. An 88-year-old hypertensive woman presented with acute vertical oblique binocular diplopia, followed by complete ptosis of the right eye. Ophthalmic examination showed dysfunction of the right third, fourth, and sixth cranial nerves. Further examination revealed hypesthesia of the areas supplied by the ophthalmic (V1) and maxillary (V2) branches of the right trigeminal nerve. Bilateral giant cavernous carotid aneurysms, with a concurrent subacute right occipital lobe infarction, were discovered on brain imaging and angiogram. Additionally, a prominent right posterior communicating artery (PCOM) was revealed. Seven months later, clinical improvement with stable radiographic findings was documented without any intervention. Dysfunction of the third, fourth, and sixth cranial nerves, and the ophthalmic (V 1 ) and maxillary (V 2 ) branches of the trigeminal nerves, should necessitate brain imaging, with special attention given to the cavernous sinus. Despite unilateral symptomatic presentation, bilateral lesions cannot be excluded solely on the basis of clinical findings. CCA should be included in the differential diagnosis of cavernous sinus lesions. Although rare, ipsilateral

  16. Endovascular management of dural carotid-cavernous sinus fistulas in 141 patients

    Energy Technology Data Exchange (ETDEWEB)

    Kirsch, M. [Alfried Krupp Krankenhaus, Klinik fuer Radiologie und Neuroradiologie, Essen (Germany); Universitaetsklinikum Greifswald, Institut fuer Diagnostische Radiologie und Neuroradiologie, Greifswald (Germany); Henkes, H.; Liebig, T.; Weber, W.; Golik, S.; Kuehne, D. [Alfried Krupp Krankenhaus, Klinik fuer Radiologie und Neuroradiologie, Essen (Germany); Esser, J. [Universitaetsklinikum Essen, Zentrum fuer Augenheilkunde, Essen (Germany)

    2006-07-15

    Introduction: The purpose of this study was to evaluate the single-centre experience with transvenous coil treatment of dural carotid-cavernous sinus fistulas. Methods: Between November 1991 and December 2005, a total of 141 patients (112 female) with dural carotid-cavernous sinus fistula underwent 161 transvenous treatment sessions. The patient files and angiograms were analysed retrospectively. Clinical signs and symptoms included chemosis (94%), exophthalmos (87%), cranial nerve palsy (54%), increased intraocular pressure (60%), diplopia (51%), and impaired vision (28%). Angiography revealed in addition cortical drainage in 34% of the patients. Partial arterial embolization was carried out in 23% of the patients. Transvenous treatment comprised in by far the majority of patients complete filling of the cavernous sinus and the adjacent segment of the superior and inferior ophthalmic vein with detachable coils. Complete interruption of the arteriovenous shunt was achieved in 81% of the patients. A minor residual shunt (without cortical or ocular drainage) remained in 13%, a significant residual shunt (with cortical or ocular drainage) remained in 4%, and the attempted treatment failed in 2%. There was a tendency for ocular pressure-related symptoms to resolve rapidly, while cranial nerve palsy and diplopia improved slowly (65%) or did not change (11%). The 39 patients with visual impairment recovered within the first 2 weeks after endovascular treatment. After complete interruption of the arteriovenous shunt, no recurrence was observed. The transvenous coil occlusion of the superior and inferior ophthalmic veins and the cavernous sinus of the symptomatic eye is a highly efficient and safe treatment in dural carotid-cavernous sinus fistulas. In the majority of patients a significant and permanent improvement in clinical signs and symptoms can be achieved. (orig.)

  17. 3D inkjet printed disposable environmental monitoring wireless sensor node

    KAUST Repository

    Farooqui, Muhammad Fahad; Shamim, Atif

    2017-01-01

    We propose a disposable, miniaturized, moveable, fully integrated 3D inkjet-printed wireless sensor node for large area environmental monitoring applications. As a proof of concept, we show the wireless sensing of temperature, humidity and H2S

  18. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Blomeke, J.O.

    1979-01-01

    Radioactive waste management and disposal requirements options available are discussed. The possibility of beneficial utilization of radioactive wastes is covered. Methods of interim storage of transuranium wastes are listed. Methods of shipment of low-level and high-level radioactive wastes are presented. Various methods of radioactive waste disposal are discussed

  19. Nuclear Waste Disposal Program 2016

    International Nuclear Information System (INIS)

    2016-12-01

    This comprehensive brochure published by the Swiss National Cooperative for the Disposal of Radioactive Waste (NAGRA) discusses the many important steps in the management of radioactive waste that have already been implemented in Switzerland. The handling and packaging of waste, its characterisation and inventorying, as well as its interim storage and transport are examined. The many important steps in Swiss management of radioactive waste already implemented and wide experience gained in carrying out the associated activities are discussed. The legal framework and organisational measures that will allow the selection of repository sites are looked at. The various aspects examined include the origin, type and volume of radioactive wastes, along with concepts and designs for deep geological repositories and the types of waste to be stored therein. Also, an implementation plan for the deep geological repositories, the required capacities and the financing of waste management activities are discussed as is NAGRA’s information concept. Several diagrams and tables illustrate the program

  20. Concept - or no concept

    DEFF Research Database (Denmark)

    Thorsteinsson, Uffe

    1999-01-01

    Discussion about concept in industrial companies. A method for mapping of managerial concept in specific area is shown......Discussion about concept in industrial companies. A method for mapping of managerial concept in specific area is shown...

  1. The role of performance assessment in radioactive waste disposal

    International Nuclear Information System (INIS)

    Stenhouse, M.J.

    1998-01-01

    Performance assessment has many applications in the field of radioactive waste management, none more important than demonstrating the suitability of a particular repository system for waste disposal. The role of performance assessment in radioactive waste disposal is discussed with reference to assessments performed in civilian waste management programmes. The process is, however, relevant, and may be applied directly to the disposal of defence-related wastes. When used in an open and transparent manner, performance assessment is a powerful methodology not only for convincing the authorities of the safety of a disposal concept, but also for gaining the wider acceptance of the general public for repository siting. 26 refs

  2. HLW disposal in Germany - R and D achievements and outlook

    International Nuclear Information System (INIS)

    Steininger, W.

    2006-01-01

    The paper gives a brief overview of the status of R and D on HLW disposal. Shortly addressed is the current nuclear policy. After describing the responsibilities regarding R and D for disposing of heat-generating high-level (HLW) waste (vitrified waste and spent fuel), selected projects are mentioned to illustrate the state of knowledge in disposing of waste in rock salt. Participation in international projects and programs is described to illustrate the value for the German concepts and ideas for HLW disposal in different rock types. Finally, a condensed outlook on future activities is given. (author)

  3. Methodology for the technical evaluation of disposal systems for Greater-Than-Class C low-level radioactive waste

    International Nuclear Information System (INIS)

    Lamar, D.A.; Raymond, J.R.

    1990-07-01

    This paper presents the methodology that will be used for the evaluation of alternative disposal concepts for Greater-Than-Class C low-level radioactive waste. The primary focus will be on the technical evaluation of various disposal concepts leading toward the identification of technically feasible disposal systems

  4. Successful Transarterial Embolization of a Posttraumatic Fistula Between a Posterior Communicating Artery Aneurysm and the Cavernous Sinus: A Case Report.

    Science.gov (United States)

    Jinbo, Yin; Jun, Liu; Kejie, Mou; Zheng, Zhou

    2015-01-01

    Posterior communicating artery (PCoA) aneurysm-cavernous sinus fistulae are an extremely rare complication of head injury . The treatment of PCoA aneurysm-cavernous sinus fistulae has not been well described. A 27-year-old man was admitted with a retroocular bruit and blurred vision of the left eye seven months after a severe head injury. We report the angiographic appearance of a posterior communicating artery (PCoA) aneurysm with a fistula to the cavernous sinus. This injury had been previously misinterpreted to be a PCoA aneurysm by computerized tomographic angiography (CTA). The patient was successfully treated with coils and Onyx of a fistula between the PCoA aneurysm and cavernous sinus.

  5. Use of Synthetic Nerve Grafts to Restore Cavernous Nerve Function Following Prostate Cancer Surgery: In Vitro and In Vivo Studies

    National Research Council Canada - National Science Library

    Konety, Badrinath R

    2006-01-01

    .... Schwann cell and neurona stem cells en neurite growth are being investigated. Tubulized sheets of the polymer with and without those factors/cells have been used to microsurgically replace resected cavernous nerve...

  6. Disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-01-15

    The problem of disposal can be tackled in two ways: the waste can be diluted and dispersed so that the radiation to which any single individual would be subjected would be negligible, or it can be concentrated and permanently isolated from man and his immediate environment. A variety of methods for the discharge of radioactive waste into the ground were described at the Monaco conference. They range from letting liquid effluent run into pits or wells at appropriately chosen sites to the permanent storage of high activity material at great depth in geologically suitable strata. Another method discussed consists in the incorporation of high level fission products in glass which is either buried or stored in vaults. Waste disposal into rivers, harbours, outer continental shelves and the open sea as well as air disposal are also discussed. Many of the experts at the Monaco conference were of the view that most of the proposed, or actually applied, methods of waste disposal were compatible with safety requirements. Some experts, felt that certain of these methods might not be harmless. This applied to the possible hazards of disposal in the sea. There seemed to be general agreement, however, that much additional research was needed to devise more effective and economical methods of disposal and to gain a better knowledge of the effects of various types of disposal operations, particularly in view of the increasing amounts of waste material that will be produced as the nuclear energy industry expands

  7. Disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Nuttall, K.

    1994-01-01

    In 1978, the governments of Canada and Ontario established the Nuclear Fuel Waste Management program. As of the time of the conference, the research performed by AECL was jointly funded by AECL and Ontario Hydro through the CANDU owners' group. Ontario Hydro have also done some of the research on disposal containers and vault seals. From 1978 to 1992, AECL's research and development on disposal cost about C$413 million, of which C$305 was from funds provided to AECL by the federal government, and C$77 million was from Ontario Hydro. The concept involves the construction of a waste vault 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield. Used fuel (or possibly solidified reprocessing waste) would be sealed into containers (of copper, titanium or special steel) and emplaced (probably in boreholes) in the vault floor, surrounded by sealing material (buffer). Disposal rooms might be excavated on more than one level. Eventually all excavated openings in the rock would be backfilled and sealed. Research is organized under the following headings: disposal container, waste form, vault seals, geosphere, surface environment, total system, assessment of environmental effects. A federal Environmental Assessment Panel is assessing the concept (holding public hearings for the purpose) and will eventually make recommendations to assist the governments of Canada and Ontario in deciding whether to accept the concept, and how to manage nuclear fuel waste. 16 refs., 1 tab., 3 figs

  8. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1982-01-01

    This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

  9. Subseabed disposal safety analysis

    International Nuclear Information System (INIS)

    Koplick, C.M.; Kabele, T.J.

    1982-01-01

    This report summarizes the status of work performed by Analytic Sciences Corporation (TASC) in FY'81 on subseabed disposal safety analysis. Safety analysis for subseabed disposal is divided into two phases: pre-emplacement which includes all transportation, handling, and emplacement activities; and long-term (post-emplacement), which is concerned with the potential hazard after waste is safely emplaced. Details of TASC work in these two areas are provided in two technical reports. The work to date, while preliminary, supports the technical and environmental feasibility of subseabed disposal of HLW

  10. Virtual Reality Model of the Three-Dimensional Anatomy of the Cavernous Sinus Based on a Cadaveric Image and Dissection.

    Science.gov (United States)

    Qian, Zeng-Hui; Feng, Xu; Li, Yang; Tang, Ke

    2018-01-01

    Studying the three-dimensional (3D) anatomy of the cavernous sinus is essential for treating lesions in this region with skull base surgeries. Cadaver dissection is a conventional method that has insurmountable flaws with regard to understanding spatial anatomy. The authors' research aimed to build an image model of the cavernous sinus region in a virtual reality system to precisely, individually and objectively elucidate the complete and local stereo-anatomy. Computed tomography and magnetic resonance imaging scans were performed on 5 adult cadaver heads. Latex mixed with contrast agent was injected into the arterial system and then into the venous system. Computed tomography scans were performed again following the 2 injections. Magnetic resonance imaging scans were performed again after the cranial nerves were exposed. Image data were input into a virtual reality system to establish a model of the cavernous sinus. Observation results of the image models were compared with those of the cadaver heads. Visualization of the cavernous sinus region models built using the virtual reality system was good for all the cadavers. High resolutions were achieved for the images of different tissues. The observed results were consistent with those of the cadaver head. The spatial architecture and modality of the cavernous sinus were clearly displayed in the 3D model by rotating the model and conveniently changing its transparency. A 3D virtual reality model of the cavernous sinus region is helpful for globally and objectively understanding anatomy. The observation procedure was accurate, convenient, noninvasive, and time and specimen saving.

  11. Submarine groundwater discharge into the coast revealed by water chemistry of man-made undersea liquefied petroleum gas cavern

    Science.gov (United States)

    Lee, Jin-Yong; Cho, Byung Wook

    2008-10-01

    SummaryThe occurrence of submarine groundwater discharge (SGD) as well as its supply of many nutrients and metals to coastal seawaters is now generally known. However, previous studies have focused on the chemical and radiological analysis of groundwater, surface seawater, shallow marine sediments and their pore waters, as well as the measurement of upward flow through the marine sediments, as end members of the discharge process. In this study, chemical and isotopic analysis results of marine subsurface waters are reported. These were obtained from deep boreholes of an undersea liquefied petroleum gas (LPG) storage cavern, located about 8 km off the western coast of Korea. The cavern is about 130-150 m below the sea bottom, which is covered by a 4.8-19.5 m silty clay stratum. An isotopic composition (δ 2H and δ 18O) of the marine subsurface waters falls on a mixing line between terrestrial groundwater and seawater. Vertical EC profiling at the cavern boreholes revealed the existence of a fresh water zone. An increase in the contents of ferrous iron and manganese and a decrease in levels of nitrate, bicarbonate and cavern seepage were recorded in August 2006, indicating a decreased submarine groundwater flux originating from land, mainly caused by an elevated cavern gas pressure. It is suggested in this study that the main source of fresh waters in the man-made undersea cavern is the submarine groundwater discharge mainly originating from the land.

  12. Sonar atlas of caverns comprising the U.S. Strategic Petroleum Reserve. Volume 2, Big Hill Site, Texas.

    Energy Technology Data Exchange (ETDEWEB)

    Rautman, Christopher Arthur; Lord, Anna Snider

    2007-08-01

    Downhole sonar surveys from the four active U.S. Strategic Petroleum Reserve sites have been modeled and used to generate a four-volume sonar atlas, showing the three-dimensional geometry of each cavern. This volume 2 focuses on the Big Hill SPR site, located in southeastern Texas. Volumes 1, 3, and 4, respectively, present images for the Bayou Choctaw SPR site, Louisiana, the Bryan Mound SPR site, Texas, and the West Hackberry SPR site, Louisiana. The atlas uses a consistent presentation format throughout. The basic geometric measurements provided by the down-cavern surveys have also been used to generate a number of geometric attributes, the values of which have been mapped onto the geometric form of each cavern using a color-shading scheme. The intent of the various geometrical attributes is to highlight deviations of the cavern shape from the idealized cylindrical form of a carefully leached underground storage cavern in salt. The atlas format does not allow interpretation of such geometric deviations and anomalies. However, significant geometric anomalies, not directly related to the leaching history of the cavern, may provide insight into the internal structure of the relevant salt dome.

  13. Sonar atlas of caverns comprising the U.S. Strategic Petroleum Reserve. Volume 1, Bayou Choctaw site, Louisiana.

    Energy Technology Data Exchange (ETDEWEB)

    Rautman, Christopher Arthur; Lord, Anna Snider

    2007-10-01

    Downhole sonar surveys from the four active U.S. Strategic Petroleum Reserve sites have been modeled and used to generate a four-volume sonar atlas, showing the three-dimensional geometry of each cavern. This volume 1 focuses on the Bayou Choctaw SPR site, located in southern Louisiana. Volumes 2, 3, and 4, respectively, present images for the Big Hill SPR site, Texas, the Bryan Mound SPR site, Texas, and the West Hackberry SPR site, Louisiana. The atlas uses a consistent presentation format throughout. The basic geometric measurements provided by the down-cavern surveys have also been used to generate a number of geometric attributes, the values of which have been mapped onto the geometric form of each cavern using a color-shading scheme. The intent of the various geometrical attributes is to highlight deviations of the cavern shape from the idealized cylindrical form of a carefully leached underground storage cavern in salt. The atlas format does not allow interpretation of such geometric deviations and anomalies. However, significant geometric anomalies, not directly related to the leaching history of the cavern, may provide insight into the internal structure of the relevant salt dome.

  14. Sonar atlas of caverns comprising the U.S. Strategic Petroleum Reserve. Volume 3, Bryan Mound Site, Texas.

    Energy Technology Data Exchange (ETDEWEB)

    Rautman, Christopher Arthur; Lord, Anna Snider

    2007-09-01

    Downhole sonar surveys from the four active U.S. Strategic Petroleum Reserve sites have been modeled and used to generate a four-volume sonar atlas, showing the three-dimensional geometry of each cavern. This volume 3 focuses on the Bryan Mound SPR site, located in southeastern Texas. Volumes 1, 2, and 4, respectively, present images for the Bayou Choctaw SPR site, Louisiana, the Big Hill SPR site, Texas, and the West Hackberry SPR site, Louisiana. The atlas uses a consistent presentation format throughout. The basic geometric measurements provided by the down-cavern surveys have also been used to generate a number of geometric attributes, the values of which have been mapped onto the geometric form of each cavern using a color-shading scheme. The intent of the various geometrical attributes is to highlight deviations of the cavern shape from the idealized cylindrical form of a carefully leached underground storage cavern in salt. The atlas format does not allow interpretation of such geometric deviations and anomalies. However, significant geometric anomalies, not directly related to the leaching history of the cavern, may provide insight into the internal structure of the relevant salt dome.

  15. Sonar atlas of caverns comprising the U.S. Strategic Petroleum Reserve. Volume 4, West Hackberry site, Louisiana.

    Energy Technology Data Exchange (ETDEWEB)

    Rautman, Christopher Arthur; Lord, Anna Snider

    2007-09-01

    Downhole sonar surveys from the four active U.S. Strategic Petroleum Reserve sites have been modeled and used to generate a four-volume sonar atlas, showing the three-dimensional geometry of each cavern. This volume 4 focuses on the West Hackberry SPR site, located in southwestern Louisiana. Volumes 1, 2, and 3, respectively, present images for the Bayou Choctaw SPR site, Louisiana, the Big Hill SPR site, Texas, and the Bryan Mound SPR site, Texas. The atlas uses a consistent presentation format throughout. The basic geometric measurements provided by the down-cavern surveys have also been used to generate a number of geometric attributes, the values of which have been mapped onto the geometric form of each cavern using a color-shading scheme. The intent of the various geometrical attributes is to highlight deviations of the cavern shape from the idealized cylindrical form of a carefully leached underground storage cavern in salt. The atlas format does not allow interpretation of such geometric deviations and anomalies. However, significant geometric anomalies, not directly related to the leaching history of the cavern, may provide insight into the internal structure of the relevant salt dome.

  16. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Merrett, G.J.; Gillespie, P.A.

    1983-07-01

    This report discusses events and processes that could adversely affect the long-term stability of a nuclear fuel waste disposal vault or the regions of the geosphere and the biosphere to which radionuclides might migrate from such a vault

  17. Disposal leachates treatment

    Energy Technology Data Exchange (ETDEWEB)

    Coulomb, I.; Renaud, P. (SITA, 75 - Paris (France)); Courant, P. (FD Conseil, 78 - Gargenville (France)); Manem, J.; Mandra, V.; Trouve, E. (Lyonnaise des Eaux-Dumez, 78 - Le Pecq (France))

    1993-12-01

    Disposal leachates are complex and variable effluents. The use of a bioreactor with membranes, coupled with a reverse osmosis unit, gives a new solution to the technical burying centers. Two examples are explained here.

  18. Safe Disposal of Pesticides

    Science.gov (United States)

    ... Toxics Environmental Information by Location Greener Living Health Land, Waste, and Cleanup Lead Mold Pesticides Radon Science ... or www.earth911.com . Think before disposing of extra pesticides and containers: Never reuse empty pesticide containers. ...

  19. Disposal of Iodine-129

    International Nuclear Information System (INIS)

    Morgan, M.T.; Moore, J.G.; Devaney, H.E.; Rogers, G.C.; Williams, C.; Newman, E.

    1978-01-01

    One of the problems to be solved in the nuclear waste management field is the disposal of radioactive iodine-129, which is one of the more volatile and long-lived fission products. Studies have shown that fission products can be fixed in concrete for permanent disposal. Current studies have demonstrated that practical cementitious grouts may contain up to 18% iodine as barium iodate. The waste disposal criterion is based on the fact that harmful effects to present or future generations can be avoided by isolation and/or dilution. Long-term isolation is effective in deep, dry repositories; however, since penetration by water is possible, although unlikely, release was calculated based on leach rates into water. Further considerations have indicated that sea disposal on or in the ocean floor may be a more acceptable alternative

  20. 27 Febuary 2012 - US DoE Associate Director of Science for High Energy Physics J. Siegrist visiting the LHC superconducting magnet test hall with adviser J.-P. Koutchouk and engineer M. Bajko; in CMS experimental cavern with Spokesperson J. Incadela;in ATLAS experimental cavern with Deputy Spokesperson A. Lankford; in ALICE experimental cavern with Spokesperson P. Giubellino; signing the guest book with Director for Accelerators and Technology S. Myers.

    CERN Multimedia

    Laurent Egli

    2012-01-01

    27 Febuary 2012 - US DoE Associate Director of Science for High Energy Physics J. Siegrist visiting the LHC superconducting magnet test hall with adviser J.-P. Koutchouk and engineer M. Bajko; in CMS experimental cavern with Spokesperson J. Incadela;in ATLAS experimental cavern with Deputy Spokesperson A. Lankford; in ALICE experimental cavern with Spokesperson P. Giubellino; signing the guest book with Director for Accelerators and Technology S. Myers.