WorldWideScience

Sample records for disposal contract research

  1. Development of a model for evaluating mechanical effects of crustal movements on the disposal system in Japan (Contract research)

    International Nuclear Information System (INIS)

    Nagasawa, Hirokazu; Takeda, Seiji; Kimura, Hideo

    2010-08-01

    In the safety assessment of geological disposal for high level radioactive wastes, it is important to develop the modelling for evaluating mechanical effects of crustal movements on the disposal system in Japan. In this study, the model on crustal movements is represented by accumulating two components of velocity magnitude of the crust to horizontal direction, caused by transient movements associated with fault and/or volcanic activities and ordinary movements with the other continuous factors. We have quantified the ordinary movements with the statistical analysis of data included in the GEONET (GPS Earth Observation Network System) of GSI (Geographical Survey Institute). Okada Model is applied for evaluating the transient movements, which can handle three-dimensional movements of earthquake and volcanic activities theologically and comprehensively. In this report, we provide the specification of the model on crustal movement and analyze the horizontal velocity in Tohoku region using the model. The result indicates that the ordinary movements are classified with magnitude of the longitudinal velocities. The cluster of longitudinal velocities has been distributed along the plate boundary. Because the velocities of the ordinary movements are grater than one of transient movements, the spatial distribution of longitudinal velocities in Tohoku region is similar to that of the ordinary movements. (author)

  2. Research on geological disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The aims of this research are to develop criteria for reviewing reliability and suitability of the result from Preliminary Investigations to be submitted by the implementer, and to establish a basic policy for safety review. For development of reliability and suitability criteria for reviewing the result of Preliminary Investigations, we evaluated the uncertainties and their influence from limited amount of investigations, as well as we identified important procedures during investigations and constructions of models, as follows: (1) uncertainties after limited amount of geological exploration and drilling, (2) influence of uncertainties in regional groundwater flow model, (3) uncertainties of DFN (Discrete Fracture Network) models in the fractured rock, (4) analyzed investigation methods described in implementer's report, and (5) identified important aspects in investigation which need to be reviewed and follow QA (Quality Assurance). For development of reliability and suitability criteria for reviewing the result of Detailed Investigations, we analyzed important aspects in investigation which supplies data to design and safety assessment, as well as studied the applicability of pressure interference data during excavation to verify hydrogeological model. Regarding the research for safety review, uncertainties of geologic process in long time-scale was studied. In FY2012, we started to evaluate the structural stabilities of concrete and bentonite in disposal environment. Finally, we continued to accumulate the knowledge on geological disposal into the database system. (author)

  3. 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)

  4. Researching radioactive waste disposal

    International Nuclear Information System (INIS)

    Feates, F.; Keen, N.

    1976-01-01

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

  5. IAEA research contracts. Second annual report

    International Nuclear Information System (INIS)

    1962-01-01

    patients with parasitic infections and in cases losing iron through sweat or desquamation; Research Contract No. 41, Non-destructive analysis of irradiated fuel elements using a flux integrating monitor; Research Contract No. 42, Mechanism of proteolysis of I-131-labelled fibrinogen; Research Contract No.45, An investigation of the radiosensitivity of spermatogonia of Drosophila melanogaster; Research Contract No. 47, Non-destructive analysis of irradiated fuel elements by gamma ray scanning; Research Contract No. 57, An investigation of the factors which influence the movement of radioactive strontium from soils to plants; Research Contract No. 59, Studies on the biological concentration of fission products in molluscs from water, with special reference to an index of radioactivity in water; Research Contract No. 72/US, Investigation of the decay scheme of Tl-210 (RaC); Research Contract No. 78, Calcium balance studies in metabolic bone disease; Research Contract No. 84, The development of radioactive drugs with special reference to tritiated drugs as radiotherapeutic agents; Research Contract No. 97, Physico-chemical requirements for the disposal of low-activity liquid radioactive wastes in soil'

  6. IAEA research contracts. Second annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1962-07-01

    patients with parasitic infections and in cases losing iron through sweat or desquamation; Research Contract No. 41, Non-destructive analysis of irradiated fuel elements using a flux integrating monitor; Research Contract No. 42, Mechanism of proteolysis of I-131-labelled fibrinogen; Research Contract No.45, An investigation of the radiosensitivity of spermatogonia of Drosophila melanogaster; Research Contract No. 47, Non-destructive analysis of irradiated fuel elements by gamma ray scanning; Research Contract No. 57, An investigation of the factors which influence the movement of radioactive strontium from soils to plants; Research Contract No. 59, Studies on the biological concentration of fission products in molluscs from water, with special reference to an index of radioactivity in water; Research Contract No. 72/US, Investigation of the decay scheme of Tl-210 (RaC); Research Contract No. 78, Calcium balance studies in metabolic bone disease; Research Contract No. 84, The development of radioactive drugs with special reference to tritiated drugs as radiotherapeutic agents; Research Contract No. 97, Physico-chemical requirements for the disposal of low-activity liquid radioactive wastes in soil'.

  7. Development of safety assessment method for human intrusion scenario in Japan. Part 1. Drilling scenario database for safety assessment of geological disposal (Contract research)

    International Nuclear Information System (INIS)

    Nagasawa, Hirokazu; Takeda, Seiji; Kimura, Hideo; Sasaki, Toshihisa

    2010-11-01

    In deep geological disposal or intermediate depth disposal, human intrusion, i.e. accidental excavation or drilling into the disposal site, may make a direct or an indirect effect on the disposal system. Safety assessment method for the human intrusion scenario, that is, the evaluation code of radiological effect from the human intrusion and the data to examine the reduction of the probability of the human intrusion occurring, is essential for the future safety regulation. Assuming that drilling action into the disposal site leads to the human proximity to the radioactive waste or the damage to the barrier system (drilling scenario), we have collected both the data on borehole drilling implemented in Japan and information on actual situation of drilling activities. Based on the data and information, we provide concrete exposure scenarios associated with borehole drilling in the vicinity of the repository and model for estimating the frequency on borehole reaching the depth of repository. The frequency is characterized with the relation to objective of excavation, geographical features, and region in Japan etc. We have developed an assembly of the information mentioned above as database, including the model parameters used in the code to assess radiation dose for drilling scenario. (author)

  8. Safety in the Chemical Laboratory: Contracts to Dispose of Laboratory Waste.

    Science.gov (United States)

    Fischer, Kenneth E.

    1985-01-01

    Presents a sample contract for disposing of hazardous wastes in an environmentally sound, timely manner in accordance with all federal, state, and local requirements. Addresses situations where hazardous waste must be disposed of outside the laboratory and where alternate disposal methods are not feasible. (JN)

  9. 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

  10. Legal Considerations for International Collaborative Research Contract

    International Nuclear Information System (INIS)

    Lee, D. S.; Oh, K. B.; Kim, H. J.; Lee, J. H.

    2007-01-01

    Though collaborative research is pure academic activity the research plan and resource allocation for the research are shaped under foam of contract. Thus, legal binding effect and compulsive instrument is adopted at the research contract. This paper aimed at guiding equal collaborative research contract in legal aspect. To reach the goal (1) enforceability and elements of international collaborative contract, (2) damage calculation and related issues with those topics shall be discussed in each section

  11. Contract Research, the University, and the Academic.

    Science.gov (United States)

    Crawshaw, Bruce

    1985-01-01

    Implications of the growth of university-based contract research are examined, including moral and ethical issues, legal aspects, ownership of research results, staff rights, researcher status, publication, authority, responsibility, social justice, and conflicts between teaching and research. Eleven suggestions for successful contract research…

  12. 26 CFR 1.631-2 - Gain or loss upon the disposal of timber under cutting contract.

    Science.gov (United States)

    2010-04-01

    ... cutting contract. 1.631-2 Section 1.631-2 Internal Revenue INTERNAL REVENUE SERVICE, DEPARTMENT OF THE... loss upon the disposal of timber under cutting contract. (a) In general. (1) If an owner disposes of... deemed to be the date such timber is cut. However, if payment is made to the owner under the contract for...

  13. IAEA research contracts. Third annual report

    International Nuclear Information System (INIS)

    1963-01-01

    During the period in which the Agency's research programme has been operative, nearly 150 research contracts have been placed with institutions in 35 Member States. While considerable emphasis was placed initially on research of a more fundamental nature - as reflected by the summaries presented herein of work under contracts awarded in the early stages of the programme - recent policy has shifted the major emphasis toward research of a practical nature, as the results of this type of research are likely to be of more immediate interest to Member States, and particularly to the developing nations. In every case, the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been closely connected with that particular subject of research. Thus, the scientific data reported in the summary remain the responsibility of the contractor, the Agency being responsible for any additional observations. The reports in the field of Radioactive waste management and environmental research included are: Research Contract No.20. Studies in the uptake of radioisotopes by edible marine products; Research Contract No. 33, Behaviour of fission products in soil; Research Contract No.100, Ionic interaction near clay surfaces. Reports dealing with Health physics and radiation protection presented are: Research Contract No.14, The effect of radiation on plant cells and its modification with protective substances; Research Contract No.32, Determination of the enrichment factors of calcium isotopes on ion exchange resins and the investigation of the various systems of electrolytic separation; Research Contract No. 53, Selection of sulphydryl compounds for radiation protection, using a new microbiological method; Research Contract No. 79, A study of the uptake of radioactive calcium in the skeleton. Reports related to Radiobiology are: Research Contract No.11, Genetical investigations on the effect of ionizing radiation on human cells

  14. IAEA research contracts. Third annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-04-01

    During the period in which the Agency's research programme has been operative, nearly 150 research contracts have been placed with institutions in 35 Member States. While considerable emphasis was placed initially on research of a more fundamental nature - as reflected by the summaries presented herein of work under contracts awarded in the early stages of the programme - recent policy has shifted the major emphasis toward research of a practical nature, as the results of this type of research are likely to be of more immediate interest to Member States, and particularly to the developing nations. In every case, the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been closely connected with that particular subject of research. Thus, the scientific data reported in the summary remain the responsibility of the contractor, the Agency being responsible for any additional observations. The reports in the field of Radioactive waste management and environmental research included are: Research Contract No.20. Studies in the uptake of radioisotopes by edible marine products; Research Contract No. 33, Behaviour of fission products in soil; Research Contract No.100, Ionic interaction near clay surfaces. Reports dealing with Health physics and radiation protection presented are: Research Contract No.14, The effect of radiation on plant cells and its modification with protective substances; Research Contract No.32, Determination of the enrichment factors of calcium isotopes on ion exchange resins and the investigation of the various systems of electrolytic separation; Research Contract No. 53, Selection of sulphydryl compounds for radiation protection, using a new microbiological method; Research Contract No. 79, A study of the uptake of radioactive calcium in the skeleton. Reports related to Radiobiology are: Research Contract No.11, Genetical investigations on the effect of ionizing radiation on human cells

  15. Fundamental research on positive systems of waste disposal and environmental protection using redox reaction and enriching ability of iron for pollutant. JAERI's nuclear research promotion program, H11-003. Contract research

    International Nuclear Information System (INIS)

    Ohashi, Hiroshi; Sato, Seichi; Kozaki, Tamotsu

    2002-03-01

    Iron corrosion products have a potential ability to retard the transport of pollutant in soil by sorption, co-precipitation and redox reaction. In this research program, an electrokinetic soil treatment method using iron anode, which can remove the pollutant and form an iron corrosion product layer in soil, was proposed as a new promising environmental remediation technique for contaminated soil with toxic heavy metal, organic materials and/or radioactive nuclides. As a fundamental study of the electrokinetic soil treatment, the formation mechanism of the corrosion product layer was discussed with the experimental data of the ion migration and the time dependence of the electric current during the treatment. In addition, diffusion behavior of Na + ions and He gas in the clay, which are closely related to the treatment, were studied. Furthermore, the potential ability of the iron corrosion layer to retard the transport of pollutant in soil was evaluated in terms of sorption coefficient of Se and Np onto the iron corrosion products and Fe-montmorillonite, which are the major component of the iron corrosion product layer. As results of these studies, it was confirmed that the electrokinetic soil treatment method using iron anode is one of promising environmental remediation techniques for contaminated soil. (author)

  16. Process Improvement for Interinstitutional Research Contracting.

    Science.gov (United States)

    Varner, Michael; Logan, Jennifer; Bjorklund, Todd; Whitfield, Jesse; Reed, Peggy; Lesher, Laurie; Sikalis, Amy; Brown, Brent; Drollinger, Sandy; Larrabee, Kristine; Thompson, Kristie; Clark, Erin; Workman, Michael; Boi, Luca

    2015-08-01

    Sponsored research increasingly requires multiinstitutional collaboration. However, research contracting procedures have become more complicated and time consuming. The perinatal research units of two colocated healthcare systems sought to improve their research contracting processes. The Lean Process, a management practice that iteratively involves team members in root cause analyses and process improvement, was applied to the research contracting process, initially using Process Mapping and then developing Problem Solving Reports. Root cause analyses revealed that the longest delays were the individual contract legal negotiations. In addition, the "business entity" was the research support personnel of both healthcare systems whose "customers" were investigators attempting to conduct interinstitutional research. Development of mutually acceptable research contract templates and language, chain of custody templates, and process development and refinement formats decreased the Notice of Grant Award to Purchase Order time from a mean of 103.5 days in the year prior to Lean Process implementation to 45.8 days in the year after implementation (p = 0.004). The Lean Process can be applied to interinstitutional research contracting with significant improvement in contract implementation. © 2015 Wiley Periodicals, Inc.

  17. Waste and Disposal: Research and Development

    International Nuclear Information System (INIS)

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

    2002-01-01

    This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2001 in three topical areas are reported on: performance assessments (PA), waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. SCK-CEN partcipated in several PA projects supported by the European Commission. In the BENIPA project, the role of bentonite barriers in performance assessments of HLW disposal systems is evaluated. The applicability of various output variables (concentrations, fluxes) as performance and safety indicators is investigated in the SPIN project. The BORIS project investigates the chemical behaviour and the migration of radionuclides at the Borehole injection site at Krasnoyarsk-26 and Tomsk-7. SCK-CEN contributed to an impact assessment of a radium storage facility at Olen (Belgium) and conducted PA for site-specific concepts regarding surface or deep disposal of low-level waste at the nuclear zones in the Mol-Dessel region. As regards R and D on waste forms and packages, SCK continued research on the compatbility of various waste forms (bituminised waste, vitrified waste, spent fuel) with geological disposal in clay. Main emphasis in 2001 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to

  18. Waste and Disposal: Research and Development

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-04-01

    This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2001 in three topical areas are reported on: performance assessments (PA), waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. SCK-CEN partcipated in several PA projects supported by the European Commission. In the BENIPA project, the role of bentonite barriers in performance assessments of HLW disposal systems is evaluated. The applicability of various output variables (concentrations, fluxes) as performance and safety indicators is investigated in the SPIN project. The BORIS project investigates the chemical behaviour and the migration of radionuclides at the Borehole injection site at Krasnoyarsk-26 and Tomsk-7. SCK-CEN contributed to an impact assessment of a radium storage facility at Olen (Belgium) and conducted PA for site-specific concepts regarding surface or deep disposal of low-level waste at the nuclear zones in the Mol-Dessel region. As regards R and D on waste forms and packages, SCK continued research on the compatbility of various waste forms (bituminised waste, vitrified waste, spent fuel) with geological disposal in clay. Main emphasis in 2001 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to

  19. IAEA research contracts. First annual report

    International Nuclear Information System (INIS)

    1961-01-01

    The present volume is the first issue of what will become a regular annual publication by the Agency. It contains summaries of the final reports on all those contracts which have expired before 31 December 1960 with a few exceptions. In every case, the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been closely connected with that particular subject of research. Thus, the scientific data reported in the summary remain the responsibility of the contractor, the Agency being responsible for any additional observations. The reports of the following contracts are included: Research Contract No.2, The investigation of electrophysiological responses of biological systems, in particular of nerve cells, to irradiation with small doses of X-ray and other types of ionizing radiation, Research Contract No.3, Investigation on the mode of the protective action of certain sulfhydryl compounds against radiation effects on the synthesis of deoxyribonucleic acid, using tritium-labelled thymidine, Research Contract No.6, Investigation and development of a new method of monitoring and dosimetry for low fluxes of fast neutrons, involving the use of a bubble chamber, Research Contract No.13, Effects of incorporated radioisotopes upon the stability of genetic materials, Research Contract No.16, Interrelationship of root absorption and leaf absorption of radioisotopes in herbaceous plants, Research Contract No. 23, The uptake of radioactive wastes by lowland rice from contaminated soils due to irrigation water and its decontamination, Research Contract No.28, Comparison between mutation rates induced by acute and chronic gamma irradiation

  20. IAEA research contracts. First annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-07-01

    The present volume is the first issue of what will become a regular annual publication by the Agency. It contains summaries of the final reports on all those contracts which have expired before 31 December 1960 with a few exceptions. In every case, the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been closely connected with that particular subject of research. Thus, the scientific data reported in the summary remain the responsibility of the contractor, the Agency being responsible for any additional observations. The reports of the following contracts are included: Research Contract No.2, The investigation of electrophysiological responses of biological systems, in particular of nerve cells, to irradiation with small doses of X-ray and other types of ionizing radiation, Research Contract No.3, Investigation on the mode of the protective action of certain sulfhydryl compounds against radiation effects on the synthesis of deoxyribonucleic acid, using tritium-labelled thymidine, Research Contract No.6, Investigation and development of a new method of monitoring and dosimetry for low fluxes of fast neutrons, involving the use of a bubble chamber, Research Contract No.13, Effects of incorporated radioisotopes upon the stability of genetic materials, Research Contract No.16, Interrelationship of root absorption and leaf absorption of radioisotopes in herbaceous plants, Research Contract No. 23, The uptake of radioactive wastes by lowland rice from contaminated soils due to irrigation water and its decontamination, Research Contract No.28, Comparison between mutation rates induced by acute and chronic gamma irradiation.

  1. Waste and Disposal: Research and Development

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-04-01

    This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2000 in three topical areas are reported on: performance assessments, waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. An impact assessment was completed for the radium storage facility at Olen (Belgium). Geological data, pumping rates and various hydraulic parameters were collected in support of the development of a new version of the regional hydrogeological model for the Mol site. Research and Development on waste forms and waste packages included both in situ and laboratory tests. Main emphasis in 2000 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to laboratory experiments, several large-scale migration experiments were performed in the HADES Underground Research Laboratory. In 2000, the TRANCOM Project to study the influence of dissolved organic matter on radionuclide migration as well as the RESEAL project to demonstrate shaft sealing were continued.

  2. Waste and Disposal: Research and Development

    International Nuclear Information System (INIS)

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

    2001-01-01

    This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2000 in three topical areas are reported on: performance assessments, waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. An impact assessment was completed for the radium storage facility at Olen (Belgium). Geological data, pumping rates and various hydraulic parameters were collected in support of the development of a new version of the regional hydrogeological model for the Mol site. Research and Development on waste forms and waste packages included both in situ and laboratory tests. Main emphasis in 2000 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to laboratory experiments, several large-scale migration experiments were performed in the HADES Underground Research Laboratory. In 2000, the TRANCOM Project to study the influence of dissolved organic matter on radionuclide migration as well as the RESEAL project to demonstrate shaft sealing were continued

  3. AERE contracts with DoE on the treatment and disposal of intermediate level wastes

    International Nuclear Information System (INIS)

    Partridge, B.A.

    1984-06-01

    This document reports work carried out in 1983/84 under 10 contracts between DoE and AERE on the treatment and disposal of intermediate level wastes. Individual summaries are provided for each contract report within the document, under the headings: comparative evaluation of α and βγ irradiated medium level waste forms; modelling and characterisation of intermediate level waste forms based on polymers; optimisation of processing parameters for polymer and bitumen modified cements; ceramic waste forms; radionuclide release during leaching; ion exchange processes; electrical processes for the treatment of medium active liquid wastes; fast reactor fuel element cladding; dissolver residues; flowsheeting/systems study. (U.K.)

  4. Deep geological disposal research in Argentina

    International Nuclear Information System (INIS)

    Ninci Martinez, Carlos A.; Ferreyra, Raul E.; Vullien, Alicia R.; Elena, Oscar; Lopez, Luis E.; Maloberti, Alejandro; Nievas, Humberto O.; Reyes, Nancy C.; Zarco, Juan J.; Bevilacqua, Arturo M.; Maset, Elvira R.; Jolivet, Luis A.

    2001-01-01

    Argentina shall require a deep geological repository for the final disposal of radioactive wastes, mainly high-level waste (HLW) and spent nuclear fuel produced at two nuclear power plants and two research reactors. In the period 1980-1990 the first part of feasibility studies and a basic engineering project for a radioactive high level waste repository were performed. From the geological point of view it was based on the study of granitic rocks. The area of Sierra del Medio, Province of Chubut, was selected to carry out detailed geological, geophysical and hydrogeological studies. Nevertheless, by the end of the eighties the project was socially rejected and CNEA decided to stop it at the beginning of the nineties. That decision was strongly linked with the little attention paid to social communication issues. Government authorities were under a strong pressure from social groups which demanded the interruption of the project, due to lack of information and the fear it generated. The lesson learned was: social communication activities shall be carried out very carefully in order to advance in the final disposal of HLW at deep geological repositories (author)

  5. IAEA research contracts. Seventh annual report

    International Nuclear Information System (INIS)

    1967-01-01

    This volume is the seventh annual report and presents full summaries of 52 final reports from contracts, sponsored under the Agency's Research Contract Programme, which were completed during 1966. Including these, a total of 188 summaries have been published in the various fields in which support is provided under the IAEA Research contract program. In every case the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been most closely connected with the particular branch of research concerned. The scientific data are the responsibility of the contractor, though the Agency is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; safeguards methods; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture, medicine and hydrology, food preservation by irradiation

  6. IAEA research contracts. Sixth annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1966-04-01

    This volume is the sixth annual report and presents full summaries of 37 final reports from contracts, sponsored under the Agency's Research Contract Programme, which were completed during 1965. Including these, a total of 136 summaries have been published in the various fields in which support is provided under the IAEA Research contract program. In every case the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been most closely connected with the particular branch of research concerned. The scientific data are the responsibility of the contractor, though the Agency is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; safeguards methods; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture, medicine and hydrology.

  7. IAEA research contracts. Seventh annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1967-05-01

    This volume is the seventh annual report and presents full summaries of 52 final reports from contracts, sponsored under the Agency's Research Contract Programme, which were completed during 1966. Including these, a total of 188 summaries have been published in the various fields in which support is provided under the IAEA Research contract program. In every case the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been most closely connected with the particular branch of research concerned. The scientific data are the responsibility of the contractor, though the Agency is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; safeguards methods; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture, medicine and hydrology, food preservation by irradiation.

  8. IAEA research contracts. Sixth annual report

    International Nuclear Information System (INIS)

    1966-01-01

    This volume is the sixth annual report and presents full summaries of 37 final reports from contracts, sponsored under the Agency's Research Contract Programme, which were completed during 1965. Including these, a total of 136 summaries have been published in the various fields in which support is provided under the IAEA Research contract program. In every case the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been most closely connected with the particular branch of research concerned. The scientific data are the responsibility of the contractor, though the Agency is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; safeguards methods; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture, medicine and hydrology

  9. Federal fees and contracts for storage and disposal of spent LWR fuel

    International Nuclear Information System (INIS)

    Clark, H.J.

    1979-01-01

    The methodology for establishing a fee for federal spent fuel storage and disposal services is explained along with a presentation of the cost centers and cost data used to calculate the fee. Results of the initial fee calculation and the attendant sensitivity studies are also reviewed. The current status of the fee update is presented. The content of the proposed contract for federal services is briefly reviewed

  10. 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)

  11. Researching radioactive waste disposal. [Underground repository

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-02-16

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

  12. 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)

  13. IAEA research contracts. Ninth annual report

    International Nuclear Information System (INIS)

    1969-01-01

    This volume is the seventh annual publication of the summaries of final reports received during 1968 in connection with contracts and agreements awarded by the IAEA Research Contract Programme. Ninety nine such summaries are included, thus bringing to 323 the total number published so far. In every case the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been most closely connected with the particular branch of research concerned. The scientific data are the responsibility of the contractor, though the Agency is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; safeguards methods; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture, medicine and hydrology, food preservation by irradiation

  14. IAEA research contracts. Ninth annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-06-01

    This volume is the seventh annual publication of the summaries of final reports received during 1968 in connection with contracts and agreements awarded by the IAEA Research Contract Programme. Ninety nine such summaries are included, thus bringing to 323 the total number published so far. In every case the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been most closely connected with the particular branch of research concerned. The scientific data are the responsibility of the contractor, though the Agency is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; safeguards methods; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture, medicine and hydrology, food preservation by irradiation.

  15. IAEA research contracts. Fourth annual report

    International Nuclear Information System (INIS)

    1964-01-01

    This volume represents the fourth annual report on the results obtained under the Agency's research contract programme. During the short life of this programme, which is not quite six years old, a total investment of more than three million dollars has been made to support research in selected fields at institutes in 50 Member States. Extensive summaries are presented herein for all final reports relating to contracts which were completed during 1963. As it is the policy of the Agency to encourage publication in the open scientific literature of the results of work done under research contracts, a number of papers have also appeared in the appropriate journals - the Agency having been notified of 75 such publications in 1963. A complete list of references to these is given at the end of this report. The scientific data presented in the summaries of course remain the responsibility of the contractor. The Agency, however, is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture and medicine

  16. IAEA research contracts. Fourth annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-04-01

    This volume represents the fourth annual report on the results obtained under the Agency's research contract programme. During the short life of this programme, which is not quite six years old, a total investment of more than three million dollars has been made to support research in selected fields at institutes in 50 Member States. Extensive summaries are presented herein for all final reports relating to contracts which were completed during 1963. As it is the policy of the Agency to encourage publication in the open scientific literature of the results of work done under research contracts, a number of papers have also appeared in the appropriate journals - the Agency having been notified of 75 such publications in 1963. A complete list of references to these is given at the end of this report. The scientific data presented in the summaries of course remain the responsibility of the contractor. The Agency, however, is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture and medicine.

  17. Radioactive waste disposal in deep geologic deposits. Associated research problems

    International Nuclear Information System (INIS)

    Rousset, G.

    1992-01-01

    This paper describes the research associated problems for radioactive waste disposal in deep geologic deposits such granites, clays or salt deposits. After a brief description of the underground disposal, the author studies the rheology of sedimentary media and proposes rheological models applied to radioactive wastes repositories. Waste-rock interactions, particularly thermal effects and temperature distribution versus time. 17 refs., 14 figs

  18. 48 CFR 970.35 - Research and development contracting.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Research and development... SUPPLEMENTARY REGULATIONS DOE MANAGEMENT AND OPERATING CONTRACTS Major System Acquisition 970.35 Research and development contracting. ...

  19. IAEA research contracts. Fifth annual report

    International Nuclear Information System (INIS)

    1965-01-01

    This volume is the fifth annual report and presents full summaries of 26 final reports from contracts, sponsored under the Agency's Research Contract Programme, which were completed during 1964. In addition to the summaries describing more general work in 'Health physics and radiation protection', seven reports are included which describe work done under the Agency's first highly-coordinated programme in which various applications of Ca-47 in the fields of medicine and health physics were explored. In every case the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been most closely connected with the particular branch of research concerned. The scientific data are the responsibility of the contractor, though the Agency is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; safeguards methods; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture and medicine

  20. IAEA research contracts. Fifth annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-04-01

    This volume is the fifth annual report and presents full summaries of 26 final reports from contracts, sponsored under the Agency's Research Contract Programme, which were completed during 1964. In addition to the summaries describing more general work in 'Health physics and radiation protection', seven reports are included which describe work done under the Agency's first highly-coordinated programme in which various applications of Ca-47 in the fields of medicine and health physics were explored. In every case the summary of the contractor's final report has been prepared by that member of the Agency's scientific staff who has been most closely connected with the particular branch of research concerned. The scientific data are the responsibility of the contractor, though the Agency is responsible for any additional observations. The reports presented are related to research in the field of radioactive waste management and environmental sciences; health physics and radiation protection; radiobiology; safeguards methods; nuclear reactors physics and nuclear fuels; radioisotope applications in agriculture and medicine.

  1. Present status of research and development on underground disposal

    International Nuclear Information System (INIS)

    1994-11-01

    Power Reactor and Nuclear Fuel Development Corporation published the technical report 'Research and development of the formation disposal of high level radioactive waste' 1991 in 1992, summarizing the results of the research and development of the formation disposal which have been advanced by dividing into three parts, that is, the investigation and research of geological environment conditions, the research and development of disposal technologies, and the research on the performance evaluation. Based on the subjects pointed out during the process of making the technical report, the results of evaluation by the state, and the opinions of those concerned, the efforts are exerted toward the second summarization expected in about 2000. By informing the present state of the research and development, in order to accept the criticism and advice, this book was published. The way of thinking and the method of advancing of the research and development of formation disposal, the present state of the research on geological environment conditions, disposal technologies and the performance evaluation are described. Also the present state of the research on stratum science in Tono and Kamaishi mines and others is reported. (K.I.)

  2. Basic research needs for management and disposal of DOE wastes

    International Nuclear Information System (INIS)

    Grazis, B.M.; Schulz, W.W.

    1991-04-01

    This document was chartered by the Department of Energy (DOE), Office of Energy Research. It identifies and describes 87 basic research needs in support of advanced technology for management and disposal of Department of Energy radioactive, hazardous chemical, and mixed wastes. A team of scientists and engineers from several DOE laboratories and sites, from academia, and from industry identified and described the basic research needs called out in this report. Special efforts were made to ensure that basic research needs related to management and disposal of any hazardous chemical wastes generated at nonnuclear DOE sites and facilities were properly identified. It is hoped that scientists in both DOE and nongovernment laboratories and institutions will find this document useful when formulating research efforts relevant to waste management and disposal. For management and disposal of DOE radioactive and mixed wastes, basic research needs are identified in nine separate action areas. Basic research needs for management and disposal of DOE hazardous chemical wastes are identified in five action areas. Sufficient description and background information are provided in the report for each particular research need to enable qualified and imaginative scientists to conceive research efforts and programs that will meet the need. 28 refs., 7 tabs

  3. Present status of research and development on underground disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-11-01

    Power Reactor and Nuclear Fuel Development Corporation published the technical report `Research and development of the formation disposal of high level radioactive waste` 1991 in 1992, summarizing the results of the research and development of the formation disposal which have been advanced by dividing into three parts, that is, the investigation and research of geological environment conditions, the research and development of disposal technologies, and the research on the performance evaluation. Based on the subjects pointed out during the process of making the technical report, the results of evaluation by the state, and the opinions of those concerned, the efforts are exerted toward the second summarization expected in about 2000. By informing the present state of the research and development, in order to accept the criticism and advice, this book was published. The way of thinking and the method of advancing of the research and development of formation disposal, the present state of the research on geological environment conditions, disposal technologies and the performance evaluation are described. Also the present state of the research on stratum science in Tono and Kamaishi mines and others is reported. (K.I.).

  4. Argillite And Crystalline Disposal Research: Accomplishments And Path-Forward.

    Energy Technology Data Exchange (ETDEWEB)

    McMahon, Kevin A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jove-Colon, Carlos F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-09-01

    The intention of this document is to provide a path-forward for research and development (R&D) for two host rock media-specific (argillite and crystalline) disposal research work packages within the Used Fuel Disposition Campaign (UFDC). The two work packages, Argillite Disposal R&D and Crystalline Disposal R&D, support the achievement of the overarching mission and objectives of the Department of Energy Office of Nuclear Energy Fuel Cycle Technologies Program. These two work packages cover many of the fundamental technical issues that will have multiple implications to other disposal research work packages by bridging knowledge gaps to support the development of the safety case. The path-forward begins with the assumption of target dates that are set out in the January 2013 DOE Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (http://energy.gov/downloads/strategy-management-and-disposal-used-nuclear-fuel-and-high-levelradioactive- waste). The path-forward will be maintained as a living document and will be updated as needed in response to available funding and the progress of multiple R&D tasks in the Used Fuel Disposition Campaign and the Fuel Cycle Technologies Program. This path forward is developed based on the report of “Used Fuel Disposition Campaign Disposal Research and Development Roadmap (FCR&D-USED- 2011-000065 REV0)” (DOE, 2011). This document delineates the goals and objectives of the UFDC R&D program, needs for generic disposal concept design, and summarizes the prioritization of R&D issues.

  5. Status of UFD Campaign International Activities in Disposal Research

    Energy Technology Data Exchange (ETDEWEB)

    Birkholzer, Jens [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2012-09-01

    While the United States research program for geologic disposal of high-level radioactive waste over the past decades focused solely on an open tunnel emplacement in unsaturated densely fractured tuff, several international organizations have made significant progress in the characterization and performance evaluation of other disposal design options and host rock characteristics, most of which were very different from those studied in the U.S. As a result, areas of direct collaboration between the U.S. Department of Energy’s (DOE) and international geologic disposal programs were quite limited during that time. Recently, the decision by DOE to no longer pursue the geologic disposal of high-level radioactive waste and spent fuel at the Yucca Mountain site has shifted the nation’s focus to disposal design options and geologic environments similar to those being investigated by other nations. DOE started to recognize that close international collaboration is a beneficial and costeffective strategy for advancing disposal science and, in FY12, embarked on a comprehensive effort to identify international collaboration opportunities, to interact with international organizations and advance promising collaborations, and to plan/develop specific R&D activities in cooperation with international partners. This report describes the active collaboration opportunities available to U.S. researchers as a result of this effort, and presents specific cooperative research activities that have been recently initiated within DOE’s disposal research program. The focus in this report is on those opportunities that provide access to field data (and respective interpretation/modeling), and/or may allow participation in ongoing and planned field experiments.

  6. Sustainable Disposal of Edible Food Byproducts at University Research Farms

    Science.gov (United States)

    Baldwin, Sherill; Chung, Kimberly

    2007-01-01

    Purpose: Research at agricultural universities often generates food crops that are edible by-products of the research process. The purpose of this paper is to explore the factors that affect decision-making around the disposal of these crops. Understanding decision-making suggests how universities might include food crop production into campus…

  7. Conceptual design of disposal facility below the generally used depth. Document prepared by other institute, based on the trust contract

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Wataru; Nakagawa, Tatsuo; Mukunoki, Atsushi; Goto, Kikuji [JGC Corp., Tokyo (Japan)

    2002-02-01

    Radioisotope, nuclear fuel materials, and so on have been used in the various fields such as the research activities of universities and research institutes or the treatment and diagnosis of the medical institutes. It is necessary to treat and dispose of radioactive wastes safety and economically. However, as for radioactive wastes disposal below the generally used depth, a concrete disposal concept isn't examined, and the safety of disposal isn't evaluated, either. This report contains building of the database for the radioactive wastes applicable for disposal below the generally used depth, and preliminary safety evaluation was enforced on the setup of condition presumed in the present. Finally subjects for the conceptual design of the disposal facility below the generally used depth were extracted. (author)

  8. Research reactor decommissioning experience - concrete removal and disposal -

    International Nuclear Information System (INIS)

    Manning, Mark R.; Gardner, Frederick W.

    1990-01-01

    Removal and disposal of neutron activated concrete from biological shields is the most significant operational task associated with research reactor decommissioning. During the period of 1985 thru 1989 Chem-Nuclear Systems, Inc. was the prime contractor for complete dismantlement and decommissioning of the Northrop TRIGA Mark F, the Virginia Tech Argonaut, and the Michigan State University TRIGA Mark I Reactor Facilities. This paper discusses operational requirements, methods employed, and results of the concrete removal, packaging, transport and disposal operations for these (3) research reactor decommissioning projects. Methods employed for each are compared. Disposal of concrete above and below regulatory release limits for unrestricted use are discussed. This study concludes that activated reactor biological shield concrete can be safely removed and buried under current regulations

  9. Radiation research contracts: Distribution of fission products in the biosphere

    International Nuclear Information System (INIS)

    Schoenfeld, T.

    1959-01-01

    According to its Statute the IAEA has to fulfil a dual function - to help individual countries in solving their specific problems and to undertake tasks in the common interest of all its Member States. With this latter aim in mind the Agency has placed a number of research contracts with national research institutes. One of them deals with the distribution of fission products in the biosphere. The Agency has contributed to this work by putting at the institutes' disposal scientists from its own staff apparatus and financial aid. Protection against ionizing radiation given off in nuclear transformations is one of the foremost safety problems in all atomic energy operations. While every effort is being made to prevent reactors, processing plants and all other installations from releasing radioactive materials into the biosphere - air, water and earth - under any foreseeable conditions, small amounts of it are actually released into man's living space. Undoubtedly, this will continue to be so, at least for the time being. For example, low activity liquid wastes from some chemical processing plants are decontaminated in special processes, but traces of fission products remain in the liquids finally discharged on the ground or to nearby waterways. In some installations low and medium activity liquid wastes are even released on the ground or into swamps without prior decontamination. It is also to be expected that in accidents larger amounts of fission products may occasionally be released. (author)

  10. Contracting in vivo research: what are the issues?

    Science.gov (United States)

    Underwood, Wendy J

    2007-07-01

    As a result of increasing internal and external pressures, research institutions are using contract research organizations for the conduct of in vivo research. Many issues arise when contracting animal research, including concern regarding animal health and welfare. Each sponsor institution should develop a program for outsourced in vivo research that evaluates and ensures appropriate care and use of research animals. Each sponsoring institution should consider establishing a policy and procedure for how outsourced in vivo studies will be approved, conducted, and monitored. An approved list of contract facilities can be established on the basis of accepted standards for animal care and use. Written contracts should include confidentiality agreements, the delineation of animal ownership, and the expectation to comply with all applicable regulations and guidelines for research animal care and use. Finally, a process for communication of adverse study or animal welfare events should be established. Thorough evaluation of contract organizations will help ensure appropriate research animal care and use.

  11. Engineering and Statistical Research Institute contract reports to May, 1983

    Energy Technology Data Exchange (ETDEWEB)

    Thuns, A; Morrison, B A

    1983-06-01

    The purpose of this publication is to provide information on certain Canadian agricultural research contracts which are completed, published and available for loan. These contracts reports are documentation of research contracted out to non-federal government agencies, universities or individuals. Reports on contracts under the control of the Engineering and Statistical Research Institute are written by the contractor, and are reviewed by the scientific authority. Some reports date back to 1973, when the initial contracting program began. The first program was called DREAM (Development, Research, and Evaluation in Agricultural Mechanization). In 1977-78, projects under the Energy in Agriculture program were added. This was the beginning of the AERD (Agricultural Enginering Research and Development) program. In 1981, energy research had expanded and came under a separate progam called ERDAF (Energy Research and Development in Agriculture and Food). The remaining contract work stayed with the AERD program. This publication lists only contracts completed having final reports, and available contract reports with separate listings sorted by contract file number, title, author or subject.

  12. Argentina: Disposal aspects of RA-1 research reactor decommissioning waste

    Energy Technology Data Exchange (ETDEWEB)

    Harriague, S; Barberis, C; Cinat, E; Grizutti, C; Scolari, H [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

    2007-12-15

    The objective of the project is to analyze disposal aspects of waste from total dismantling of Argentinean research reactors, starting with the oldest one, 48 years old RA-1. In order to estimate decommissioning waste, data was collected from files, area monitoring, measurements, sampling to measure activity and composition, operational history and tracing of operational incidents. Measurements were complemented with neutron activation calculations. Decommissioning waste for RA-1 is estimated to be 71.5 metric tons, most of it concrete (57 tons), the rest being steels, lead and reflector graphite (4.8 tons). Due to their low specific activities, no disposal problems are foreseen in the case of metals and concrete. Disposal of aluminium, steel, lead and concrete is analyzed. On the contrary, as the country has no experience in managing graphite radioactive waste, work was concentrated on that material. Stored (Wigner) energy may exist in RA-1 graphite reflectors irradiated at room temperature. Evaluation of stored energy by calorimetric methods is proposed, and its annealing by inductive heating; HEPA filters should be used to deal with gaseous activity emissions, mainly Cl-36 and C-14. Galvanic corrosion, dust explosion, ignition and oxidation can be addressed and should not become disposal problems. Care must be taken with graphite dust generation and disposal, due to wetting and flotation problems. Lessons learned from the project are presented, and the benefits of sharing international experience are stressed. (author)

  13. Radiation research contracts: Biological effects of small radiation doses

    International Nuclear Information System (INIS)

    Hug, O.

    1959-01-01

    According to its Statute the IAEA has to fulfil a dual function - to help individual countries in solving their specific problems and to undertake tasks in the common interest of all its Member States. With this latter aim in mind the Agency has placed a number of research contracts with national research institutes. The purpose and scope of two of them is described below by the scientists responsible for their execution. The Agency has contributed to this work by putting at the institutes' disposal scientists from its own staff apparatus and financial aid.IAEA placed a research contract concerning the effects of small radiation doses on cells, in particular on nervous cells, with the Pharmacological Institute of the University of Vienna. This Institute appeared well suited to deal with the problem owing to the type of its previous research work. The Director, Prof. Franz Bruecke, and his collaborator Dr. Otto Kraupp, have long been interested in the functioning of the nervous system and in the influence of different drugs upon it. It was particularly fortunate that the electrical properties and functions of cells had been measured by a method specially developed at this Institute. From the above mentioned observations one could expect that instantaneous reactions of cells to radiation would also lead to changes of the electrical status. Consequently, this method is now being applied to the research undertaken for IAEA. Different cells of plants and animals, ranging from algae to muscle fibres of mammals, were chosen as objects. So far changes of potentials-had been observed only during irradiation with very high doses. During these investigations another useful test for small radiation doses was developed, namely the measurement of the through-flow of an artificial blood solution through the blood vessels of an intestinal loop. It was observed that a few seconds after irradiation the flow rate diminishes, and returns to its normal level only when irradiation ends

  14. Radiation research contracts: Biological effects of small radiation doses

    Energy Technology Data Exchange (ETDEWEB)

    Hug, O

    1959-01-15

    According to its Statute the IAEA has to fulfil a dual function - to help individual countries in solving their specific problems and to undertake tasks in the common interest of all its Member States. With this latter aim in mind the Agency has placed a number of research contracts with national research institutes. The purpose and scope of two of them is described below by the scientists responsible for their execution. The Agency has contributed to this work by putting at the institutes' disposal scientists from its own staff apparatus and financial aid.IAEA placed a research contract concerning the effects of small radiation doses on cells, in particular on nervous cells, with the Pharmacological Institute of the University of Vienna. This Institute appeared well suited to deal with the problem owing to the type of its previous research work. The Director, Prof. Franz Bruecke, and his collaborator Dr. Otto Kraupp, have long been interested in the functioning of the nervous system and in the influence of different drugs upon it. It was particularly fortunate that the electrical properties and functions of cells had been measured by a method specially developed at this Institute. From the above mentioned observations one could expect that instantaneous reactions of cells to radiation would also lead to changes of the electrical status. Consequently, this method is now being applied to the research undertaken for IAEA. Different cells of plants and animals, ranging from algae to muscle fibres of mammals, were chosen as objects. So far changes of potentials-had been observed only during irradiation with very high doses. During these investigations another useful test for small radiation doses was developed, namely the measurement of the through-flow of an artificial blood solution through the blood vessels of an intestinal loop. It was observed that a few seconds after irradiation the flow rate diminishes, and returns to its normal level only when irradiation ends

  15. Incomplete contracting theory in empirical accounting research

    NARCIS (Netherlands)

    van Lent, L.A.G.M.

    1999-01-01

    In three essays, the implications of the costly contracting approach in accounting are investigated. First, the consequences of changing the set of acceptable accounting techniques in the banking and insurance industry are examined. The regulations imposed by a government agency alter the

  16. Presentation of the Nirex disposal safety research programme

    International Nuclear Information System (INIS)

    1988-01-01

    Implementation of Nirex plans for the disposal of solid low and intermediate level radioactive waste deep underground requires assurances of safety at every stage. This includes assessment of long-term safety, which must be based on an understanding of how the repository and its contents will behave far into the future. This understanding is being provided by the company's substantial disposal research and development programme, currently running at a level of more than Pound 5 million annually. The principal contractor for the work is the UKAEA's Harwell Laboratory, with contributions from experts in universities and industry. Information from other national and international programmes also contributes. This document supports a presentation held at the CEGB Conference Centre, Didcot Power Station, Oxfordshire on 1st November 1988 to outline the scope of the work and its objectives in the context of the Company's plans and the requirements of safety assessments. It summarises the results and understanding being obtained from the current programme. (author)

  17. DOE's foreign research reactor transportation services contract: Perspective and experience

    International Nuclear Information System (INIS)

    Patterson, John

    1997-01-01

    DOE committed to low- and moderate-income countries participating in the foreign research reactor spent fuel returns program that the United States government would provide for the transportation of the spent fuel. In fulfillment of that commitment, DOE entered into transportation services contracts with qualified, private-sector firms. NAC will discuss its experience as a transportation services provider, including range of services available to the foreign reactors, advantages to DOE and to the foreign research reactors, access to contract services by high income countries and potential advantages, and experience with initial tasks performed under the contract. (author)

  18. Present state on research and development of underground disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    In September, 1996, Power Reactor and Nuclear Fuel Development Corp. (PNC) arranged her old research and development (R and D) results to issue as a shape of `Technical report on R and D of high level radioactive waste underground disposal`. On the other hand, Radioactive waste special party in Committee of Atomic Energy at that time evaluated that technical possibility for safety establishment of underground disposal in Japan was elucidated and showed future problems in the technical development. Therefore, PNC proceeded further R and D for the second arrangement under consideration of such comments. As a result, in investigation of geological environment condition, main points were laid at study on rear-field feature and its long-term stability. In development of disposal technique, main points were laid at elucidation of design requirements confirmable to the near-field evaluation, main points were laid at upgrading validity of evaluation model to analytically evaluate the near-field feature using data with high reliability. (G.K.)

  19. Present state on research and development of underground disposal

    International Nuclear Information System (INIS)

    1996-12-01

    In September, 1996, Power Reactor and Nuclear Fuel Development Corp. (PNC) arranged her old research and development (R and D) results to issue as a shape of 'Technical report on R and D of high level radioactive waste underground disposal'. On the other hand, Radioactive waste special party in Committee of Atomic Energy at that time evaluated that technical possibility for safety establishment of underground disposal in Japan was elucidated and showed future problems in the technical development. Therefore, PNC proceeded further R and D for the second arrangement under consideration of such comments. As a result, in investigation of geological environment condition, main points were laid at study on rear-field feature and its long-term stability. In development of disposal technique, main points were laid at elucidation of design requirements confirmable to the near-field evaluation, main points were laid at upgrading validity of evaluation model to analytically evaluate the near-field feature using data with high reliability. (G.K.)

  20. Stimulation of Research in Biomedicine. Role of Effective Contract.

    Science.gov (United States)

    Aleksandrova, N V; Shkolnikova, M A; Dlin, V V; Yugay, M T

    Analysis of publication activity in the field of biomedicine shows insignificant input of Russia in the world scientific product. This is largely due to the lack of incentives for researchers. Article describes stimulation of researchers in Russia, compares it with foreign models, formulates main shortcomings of support and stimulation of research in Russia and introduces the concept of effective contract. Development of personnel motivation and stimulation of employees of scientific and research organizations in the field of health. As a successful experience the article describes the implementation of effective contract in Veltishev Research and Clinical Institute for Pediatrics where for years remuneration of researchers depended upon their positions without consideration of research results. Effective contract brought significant changes in the traditional system setting new performance and efficiency criteria. New evaluation system took into account publication activity, presentation activity, implementation of research results, raising scientific personnel, thesis work and income-generating activities. Introduction of effective contract already in the second year led to a rise in the number of foreign publications, publications in journals with impact factor of more than 2, the general increase in the number of articles in peer-reviewed journals with impact factor more than 0.3, the growth of the number of articles by 1 researcher, Hirsch index improving both by individual employees and the entire Institute, increase of grant activity and presentation activity at top-rated professional congresses. The growth of publication and presentation activities has been achieved at the reduction of research staff by 23%. From financial viewpoint effective contract resulted in the redistribution of resources in favour of more efficient researchers. The introduction of effective contract and increase of requirements for scientific output did not cause resistance of staff

  1. Research contracts in the life sciences

    International Nuclear Information System (INIS)

    1975-01-01

    Research studies during 1975 in the fields of health, biology, environment, and related studies that received financial aid from ERDA are listed by institution and location. The title of the study, principal investigator, and annual level of financial aid are included

  2. Disposal of radioactive waste from nuclear research facilities

    CERN Document Server

    Maxeiner, H; Kolbe, E

    2003-01-01

    Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

  3. Research on the disposal of radioactive wastes; Forschung zur Entsorgung radioaktiver Abfaelle

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-02-15

    The report covers the following issues: Challenges of the nuclear disposal; actual state of knowledge: research and development on final disposal in salt rocks, clays, granite, general topics; research and development strategy: goals of the governmental project funding, strategic research objectives, research and development needs; research and development projects.

  4. Into the Looking Glass: Psychological Contracts in Research Administration

    Science.gov (United States)

    Hicks, Melanie; Monroy-Paz, Jorge

    2015-01-01

    In a world of fast moving technology, pressure cooker work climates and stretched resources, productivity, employee engagement, and talent retention are critical to the success of any organization. Research administration offices are no exception. Psychological contract theory provides insightful illumination on reactions to these environments by…

  5. Contracting out maintenance and a plan for future research

    NARCIS (Netherlands)

    Martin, H.H.

    1997-01-01

    Presents a discussion of the research survey carried out at the Faculty of Technology Management at the Eindhoven University of Technology concerning contractors’ maintenance. First, gives a brief introduction to the emerging contracting out phenomenon in The Netherlands. Then, provides an overview

  6. AERE contracts with DoE on the treatment and disposal of intermediate level wastes

    International Nuclear Information System (INIS)

    Partridge, B.A.

    1984-11-01

    Reports are presented on work on the following topics concerned with the treatment and disposal of intermediate-level radioactive wastes: comparative evaluation of α and β γ irradiated medium level waste forms; modelling and characterisation of intermediate level waste forms based on polymers; optimisation of processing parameters for polymer and bitumen modified cements; α damage in non-reference waste form matrix materials; leaching mechanisms and modelling; inorganic ion exchange treatment of medium active effluents; electrical processes for the treatment of medium active liquid waste; fast reactor fuel element cladding; dissolver residues; effects of radiation on the properties of cemented MTR waste forms; equilibrium leach testing of cemented MTR waste forms; radiolytic oxidation of radionuclides; immobilisation of liquid organic waste; quality control, non-conformances and corrective action. (U.K.)

  7. 48 CFR 46.309 - Research and development contracts (short form).

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Research and development... REGULATION CONTRACT MANAGEMENT QUALITY ASSURANCE Contract Clauses 46.309 Research and development contracts... Development (Short Form), in solicitations and contracts for research and development when the clause...

  8. 48 CFR 235.070-1 - Indemnification under research and development contracts.

    Science.gov (United States)

    2010-10-01

    ... research and development contracts. 235.070-1 Section 235.070-1 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT OF DEFENSE SPECIAL CATEGORIES OF CONTRACTING RESEARCH AND DEVELOPMENT CONTRACTING 235.070-1 Indemnification under research and development contracts. (a...

  9. AERE contracts with DOE on the treatment and disposal of Intermediate Level Wastes

    International Nuclear Information System (INIS)

    Partridge, B.A.

    1985-07-01

    Individual summaries are provided for each contract report, under the titles: comparative evaluation of α and βγ irradiated medium level waste forms; modelling and characterisation of intermediate level waste forms based on polymers; optimisation of processing parameters for polymer and bitumen modified cements; α damage in non-reference matrix materials; leaching mechanisms and modelling; inorganic ion exchange treatment of medium active effluents; electrical processes for the treatment of medium active liquid waste; fast reactor fuel element cladding; dissolver residues; effects of radiation on the properties of cemented MTR waste forms; equilibrium leach testing of cemented MTR waste forms; radiolytic oxidation of radionuclides; immobilisation of liquid organic wastes; quality control, non-conformances and corrective action; application of gel processes in the treatment of actinide-containing liquid wastes; the role of colloids in the release of radionuclides from nuclear waste. (author)

  10. Development through science: The IAEA research contract programme

    International Nuclear Information System (INIS)

    Benson Wiltschegg, T.; Gillen, V.

    1991-01-01

    The IAEA strives to stimulate the growth of science in developing countries by assuring that the IAEA and the scientific communities of developed and developing countries share their knowledge and experience. If the assistance provided is well organized and in keeping with the needs of developing countries it can make the crucial difference in sustainable development. This booklet provides a survey of the historical development of the IAEA's Research Contract Programme and outlines the aims and achievements of selected Co-ordinated Research Programmes. A complete listing of Co-ordinated Research Programmes is provided

  11. Co-ordinated research and environmental surveillance programme related to sea disposal of radioactive waste

    International Nuclear Information System (INIS)

    1996-01-01

    The co-ordinated Research and Environmental Surveillance Programme relevant to sea disposal of radioactive waste (CRESP) was created in 1981 in the framework of the 1977 Decision of the OECD Council establishing a Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste. CRESP was essentially a scientific research programme. Its main objective was to increase the knowledge of processes controlling the transfer of radionuclides in the marine environment, so that safety assessments could be based on more accurate and comprehensive scientific data. From 1986, in response to a request from the Paris Commission, CRESP also considered the scientific aspects of coastal releases. CRESP made it possible to co-ordinate national research activities and generated an important international co-operation in its areas of work. The vast amount of scientific information gathered in this framework increased strongly our knowledge of the impact of radionuclides introduced to the deep sea environment. In particular, CRESP provided the basis for a comprehensive safety analysis of sea dumping operations. This study, published by the NEA in 1985, is still e reference on the subject. In November 1993, the Sixteenth Consultative Meeting of Contracting Parties to the London Convention 1972 voted a total ban on the disposal at sea of radioactive wastes and other radioactive matter. Considering this decision, the conclusions of the 1985 safety analysis, and CRESP's view that new scientific findings are unlikely to alter these conclusions, the NEA Steering Committee for nuclear Energy decided in October 1995 to terminate the programme. The present report summarises the knowledge accumulated within CRESP over its fifteen years of existence. (author)

  12. Physical Research Program: research contracts and statistical summary

    International Nuclear Information System (INIS)

    1975-01-01

    The physical research program consists of fundamental theoretical and experimental investigations designed to support the objectives of ERDA. The program is directed toward discovery of natural laws and new knowledge, and to improved understanding of the physical sciences as related to the development, use, and control of energy. The ultimate goal is to develop a scientific underlay for the overall ERDA effort and the fundamental principles of natural phenomena so that these phenomena may be understood and new principles, formulated. The physical research program is organized into four functional subprograms, high-energy physics, nuclear sciences, materials sciences, and molecular sciences. Approximately four-fifths of the total physical research program costs are associated with research conducted in ERDA-owned, contractor-operated federally funded research and development centers. A little less than one-fifth of the costs are associated with the support of research conducted in other laboratories

  13. The complexity of collaboration: Opportunities and challenges in contracted research

    Directory of Open Access Journals (Sweden)

    Marion Bowl

    2010-11-01

    Full Text Available This article explores some of the challenges of utilising collaborative research approaches when undertaking contracted research projects for government and non-government agencies in the adult and community education (ACE sector. To discuss these challenges, the article draws on three recent examples of research projects undertaken for ACE sector organisations in Aotearoa New Zealand. These challenges include managing relationships with the different parties to the research; dealing with conflicting expectations of funding agencies, commissioning organisations and practitioners; and ownership and dissemination of findings. We highlight the complexity of notions of collaboration and the importance of deliberate trust-building in establishing credibility. We also open up for discussion the thorny issues of who owns the right to disseminate research findings and how far should researchers’ and universities’ responsibilities extend to ensure that research findings are put in the public domain?

  14. Waste disposal[1997 Scientific Report of the Belgian Nuclear Research Centre

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-07-01

    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.

  15. Announced document collection of the 3rd information exchange meeting on radioactive waste disposal research network

    International Nuclear Information System (INIS)

    2008-03-01

    The 3rd meeting on 'Radioactive Waste Disposal Research Network' was held at the Ricotti techno community square of JAEA on September 3 and 4, 2007. The 'Radioactive Waste Disposal Research Network' was established in Interorganization Atomic Energy Research Program under academic collaborative agreement between Japan Atomic Energy Agency and the University of Tokyo. The objective is to bring both research infrastructures and human expertise in Japan to an adequate performance level, thereby contributing to the development of the fundamental research area in the field of radioactive waste disposal. This lecture material is a collection of presentations and discussions during the information exchange meeting. (author)

  16. Development of disposal technologies for radioactive waste generated from radioisotope users and research institutes

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro

    2001-01-01

    In order to safely dispose of a radioactive waste, which is generated from radioisotope users and research institutes, investigation of characteristics of the waste and conceptual design of disposal facility were carried out. As a result of investigating JAERI that the waste has mainly been stored, it became clear that radioactivities of 19 nuclides are important from the viewpoint of the safety of the disposal. And the result of the conceptual design of disposal facilities on the assumption of 3 kinds of sites, the differences on the safety could not be recognized in either case, though the installation depth to construct the facilities influenced the economical efficiency. (author)

  17. Research oil guidelines for safety review of category 2 waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Safety confirmation items and monitoring items for engineered barriers were compiled, considering the current technical status and monitoring plan for the simulated subsurface disposal and its test facilities. In order to develop the guidelines of the safety review for the disposal of LLW generated from RI facilities and research facilities, technical issues relating toxic substances were surveyed. (author)

  18. Treatment and disposal of radioactive wastes from nuclear power plants. Research programs

    International Nuclear Information System (INIS)

    1992-09-01

    The report presents programs for research, development and demonstration concerning radioactive waste disposal in underground facilities. The main topics are: Radioactive waste management, radioactive waste storage, capsules, environmental impacts, risk assessment, radionuclide migration, radioactive waste disposal, decommissioning, cost, and international cooperation. (129 refs.)

  19. Smart Contract Templates: foundations, design landscape and research directions

    OpenAIRE

    Clack, Christopher D.; Bakshi, Vikram A.; Braine, Lee

    2016-01-01

    In this position paper, we consider some foundational topics regarding smart contracts (such as terminology, automation, enforceability, and semantics) and define a smart contract as an automatable and enforceable agreement. We explore a simple semantic framework for smart contracts, covering both operational and non-operational aspects, and describe templates and agreements for legally-enforceable smart contracts, based on legal documents. Building upon the Ricardian Contract, we identify op...

  20. The Research Contract Programme annual report and statistics for 2000

    International Nuclear Information System (INIS)

    2001-06-01

    53 Coordinated Research Projects (CRPs) were completed in 2000. 38 of these CRPs concerned topics in Nuclear Sciences and Applications and 15 were related to nuclear energy and safety. These CRPs were funded for $9,275,648; the average annual cost per CRP was $38,892. A list of these CRPs is included. Evaluations of these CRPs will be completed by the end of 2001 and included in the next annual report. The Agency's unique position as a technical international organization has enabled it to act as an international platform to lead groups of nuclear scientists by co-ordinating research and developmental activities addressing important problems in Member States. CRPs have been used to transfer existing technologies to developing countries, as well as for the development of new technologies in those countries. Since CRPs are tailored to finding solutions to specific problems, as compared to general techniques, their potential value in terms of the effect on Member States' level of development is substantial. In an effort to further enhance the effectiveness of CRPs developed and coordinated by the Agency, various initiatives have been suggested and the Research Contract Programme has been the subject of several advisory fora. The PPAS of Major Programme 2, the Senior Evaluation Group (SEG), and an internal audit of the programme have recently made recommendations to this end. Based on these reviews, the Agency has begun to fund fewer, but better focused and more substantially funded CRPs. Whereas in 1999, the Agency was carrying out 159 CRPs, 132 CRPs were carried out in 2000. The average annual amount of funding available per CRP during this period increased by 14%, from US $47,500 in 1999 to US $ 54,000 in 2000. In addition, the introduction of a new type of CRP (called Thematic CRP), meant to complement traditional CRPs, is currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear

  1. The Research Contract Programme annual report and statistics for 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-06-15

    53 Coordinated Research Projects (CRPs) were completed in 2000. 38 of these CRPs concerned topics in Nuclear Sciences and Applications and 15 were related to nuclear energy and safety. These CRPs were funded for $9,275,648; the average annual cost per CRP was $38,892. A list of these CRPs is included. Evaluations of these CRPs will be completed by the end of 2001 and included in the next annual report. The Agency's unique position as a technical international organization has enabled it to act as an international platform to lead groups of nuclear scientists by co-ordinating research and developmental activities addressing important problems in Member States. CRPs have been used to transfer existing technologies to developing countries, as well as for the development of new technologies in those countries. Since CRPs are tailored to finding solutions to specific problems, as compared to general techniques, their potential value in terms of the effect on Member States' level of development is substantial. In an effort to further enhance the effectiveness of CRPs developed and coordinated by the Agency, various initiatives have been suggested and the Research Contract Programme has been the subject of several advisory fora. The PPAS of Major Programme 2, the Senior Evaluation Group (SEG), and an internal audit of the programme have recently made recommendations to this end. Based on these reviews, the Agency has begun to fund fewer, but better focused and more substantially funded CRPs. Whereas in 1999, the Agency was carrying out 159 CRPs, 132 CRPs were carried out in 2000. The average annual amount of funding available per CRP during this period increased by 14%, from US $47,500 in 1999 to US $ 54,000 in 2000. In addition, the introduction of a new type of CRP (called Thematic CRP), meant to complement traditional CRPs, is currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear

  2. 48 CFR 46.307 - Fixed-price research and development contracts.

    Science.gov (United States)

    2010-10-01

    ... REGULATION CONTRACT MANAGEMENT QUALITY ASSURANCE Contract Clauses 46.307 Fixed-price research and development... Development—Fixed-Price, in solicitations and contracts for research and development when (1) the primary... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Fixed-price research and...

  3. Research of the tasks on risk communication enforcement (Contract research)

    International Nuclear Information System (INIS)

    Tanaka, Masaru; Aoyama, Isao; Ishizaka, Kaoru; Ohata, Yuki; Fukuike, Iori; Miyagawa, Hiroshi; Ishimori, Yuu

    2017-01-01

    From 1955 to 2001, Japan Atomic Energy Agency (JAEA) carried out research and development projects related to uranium exploration, mining, refining, conversion and enrichment at/around Ningyo-toge in Japan. Subsequently, JAEA has been carrying out remediation of the uranium mine legacy sites and decommissioning of the nuclear fuel cycle facilities. JAEA has many experiences of communication with local stakeholders from these projects. Among such experiences, management of the waste rock sites became local concern in 1988, 27 years after completion of the exploration. The issue was resolved in 2012 after several efforts. From this experience, it was suggested that the lack of information sharing with local stakeholders and that the inadequate support to stakeholder's requests caused the delay of problem solving. Therefore, sustainable relationship with local stakeholders for over decades is important for JAEA Ningyo-toge Environmental Engineering Center. As reference, similar domestic cases were investigated and strategies for risk communication were planned. As follows; (1) Clarify roles and responsibilities of communication staffs for sustainable communicating with local residents. (2) Identify gaps in risk communication knowledge among center and local residents and work toward filling those gaps. (3) Improve the effectiveness of Ningyo-toge center's website and PR-magazines as primary mechanism for communicating with wide stakeholders. (4) Investigate new communication methods for sustainable communicating, such as combination of environmental restoration studies by experts and environmental learning activities by residents. (author)

  4. U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990

    Science.gov (United States)

    Trask, N.J.; Stevens, P.R.

    1991-01-01

    The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research efforts are categorized according to whether they are related most directly to: (1) high-level wastes, (2) transuranic wastes, (3) low-level and mixed low-level and hazardous wastes, or (4) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, to development of techniques and methods for characterizing disposal sites, and to studies of geologic and hydrologic processes related to the transport and/or retention of waste radionuclides.

  5. Nuclear chemistry research for the safe disposal of nuclear waste

    International Nuclear Information System (INIS)

    Fanghaenel, Thomas

    2011-01-01

    The safe disposal of high-level nuclear waste and spent nuclear fuel is of key importance for the future sustainable development of nuclear energy. Concepts foresee the isolation of the nuclear waste in deep geological formations. The long-term radiotoxicity of nuclear waste is dominated by plutonium and the minor actinides. Hence it is essential for the performance assessment of a nuclear waste disposal to understand the chemical behaviour of actinides in a repository system. The aqueous chemistry and thermodynamics of actinides is rather complex in particular due to their very rich redox chemistry. Recent results of our detailed study of the Plutonium and Neptunium redox - and complexation behaviour are presented and discussed. (author)

  6. Collaborative Research: The Alphabetic Braille and Contracted Braille Study as an Example of Collaborative Research

    Science.gov (United States)

    Wormsley, Diane P.; Emerson, Robert Wall; Erin, Jane

    2011-01-01

    This article examines the Alphabetic Braille Contracted Braille Study in relation to the dimensions of collaborative research: extent, intensity, substance, heterogeneity, velocity, formality, and productivity. It also discusses the dimensions of financing research and researchers' attitudes. The overall consensus is that the study would not have…

  7. Emerging trends in contract research industry in India.

    Science.gov (United States)

    Drabu, Sushma; Gupta, Alka; Bhadauria, Anupama

    2010-09-01

    A Contract Research Organization (CRO) is a service organization that provides support to the pharmaceutical industry and offers a wide range of "outsourced" pharmaceutical research services to aid in R&D process and is thus an essential tool for undertaking clinical trials in the present scenario when high stakes are involved in the drug discovery process. This industry also offers a safe option of investment as the industry is largely recession-proof, with a significant upscale growth. Presently India occupies a very small pie of the global market share in the Clinical Trials Industry but it is estimated to conduct nearly 5% of global clinical trials by 2012. The global CRO industry valued $18 bn in 2008 and the market is expected to grow at an annual rate of 14% between 2009 and 13. Top multinational pharmaceuticals companies are venturing into the Indian business, in collaboration with the Indian Drug Companies. According to a recent study by Mckinsey & Company, the Indian Clinical Research Industry can attract $1.5 bn of revenue from US and EU by 2010. Such an increase in outsourcing from the western countries has led the global pharma companies and Indian entrepreneurs to set up Contract Research Organizations (CROs) in India. To bring this into realization and fulfil the market demand, while simultaneously aiding in improving the country's economical standards and market position, joint and well-coordinated efforts on part of the government, industry, and working professionals are needed in terms of regulatory affairs, audits, transparency in work affairs, garnering patient confidence, and pharmacovigilance. Copyright 2010 Elsevier Inc. All rights reserved.

  8. Current researches on safety assessment of radioactive waste disposal in the United States

    International Nuclear Information System (INIS)

    Tasaka, Hiroshi; Kiyose, Ryohei

    1980-01-01

    Recently, the problem of safe disposal of radioactive waste generated from nuclear fuel cycle becomes more important in Japan. On the other hand, many researches on shallow land burial of low-level wastes and geologic isolation of high-level wastes have been carried out in the United States of America. In this report, the researches on the safety assessment of radioactive waste disposal in the United States of America were briefly introduced with emphasis on the studies on behavior and migration of radionuclide from disposed waste in geosphere. (author)

  9. 48 CFR 46.308 - Cost-reimbursement research and development contracts.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Cost-reimbursement... ACQUISITION REGULATION CONTRACT MANAGEMENT QUALITY ASSURANCE Contract Clauses 46.308 Cost-reimbursement... of Research and Development—Cost-Reimbursement, in solicitations and contracts for research and...

  10. 21 CFR 312.52 - Transfer of obligations to a contract research organization.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 5 2010-04-01 2010-04-01 false Transfer of obligations to a contract research... and Investigators § 312.52 Transfer of obligations to a contract research organization. (a) A sponsor may transfer responsibility for any or all of the obligations set forth in this part to a contract...

  11. Review of national research programmes on the microbiology of radioactive waste disposal

    International Nuclear Information System (INIS)

    Rosevear, A.

    1991-06-01

    Published results on the microbial effects of relevance to radioactive waste disposal are reviewed. The subjects covered by each of the various national programmes are considered in turn and the important themes that emerge from these are summarised. Finally the relevance of this microbiological research to the Nirex Safety case is discussed in brief. All references to research papers that deal with microbial aspects of radioactive waste disposal are listed and the key publications identified. (author)

  12. U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1983, 1984, and 1985

    Science.gov (United States)

    Dinwiddie, G.A.; Trask, N.J.

    1986-01-01

    The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research is described according to whether it is related most directly to: (1) high-level and transuranic wastes, (2) low-level wastes, or (3) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, and to studies of regions or environments where waste-disposal sites might be located. A significant part of the activity is concerned with techniques and methods for characterizing disposal sites and studies of geologic and hydrologic processes related to the transport and (or) retention of waste radionuclides.

  13. Contract employment policy and research productivity of knowledge workers: An analysis of Spanish universities

    OpenAIRE

    Lafuente González, Esteban Miguel; Berbegal-Mirabent, Jasmina

    2017-01-01

    This article investigates how contract employment practices adopted by universities—fixed-term contracts and permanent contracts—impact research productivity measured in terms of publications in scholarly journals. The empirical application considers the Spanish public higher education system for the period 2002-2008. We report an inverse U-shaped relationship between the rate fixed-term contracts and the research productivity of Spanish universities. That is, contract policies based on fixed...

  14. Research on safety evaluation for TRU waste disposal

    International Nuclear Information System (INIS)

    Senoo, M.; Shirahashi, K.; Sakamoto, Y.; Moriyama, N.; Konishi, M.

    1989-01-01

    Studies on adsorption behavior of transuranic (TRU) elements have been performed from the view point of validating the data for safety assessment and investigating adsorption behavior of TRU elements. Distribution coefficient (Kd value) of plutonium between groundwater and soils sampled at the planning site of low level waste disposal facility were measured for safety assessment. Kd values measured were the order of 10 3 ml/g. For investigating adsorption behavior, pH dependency of Kd value of neptunium and Am for soils were studied. It was concluded that pH dependency of Kd value of neptunium was mainly owing to amount of surface charge of soils, on the other hand that of Am was due to chemical form of Am. Influence of carbonation of cement for adsorption behavior of neptunium and plutonium was also investigated and it was concluded that Kd value of carbonated cement was lower than that of fresh cement

  15. 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

  16. Roles of contract research organizations in translational medicine

    Directory of Open Access Journals (Sweden)

    Mei-Shu Shih

    2015-04-01

    Full Text Available Transitional medicine/science is shifting the medical research paradigm from compound-based to evidence-based drug/device discovery. It is increasing interdisciplinary collaborations, enhancing usage of advanced technologies, and facilitating therapeutics reaching patients faster. The fundamental theme of evidence-based discovery is to apply what is revealed in preclinical experimentation and to bring the resulting safety and efficacy to clinics. In the medical fields, a contract research organization (CRO works like a hired agent who has corresponding knowledge and experience to conduct and complete tasks for a sponsor. The relationship is business, and the contract is for deliverables. The increasingly high volume of sponsored outsourcing work has made this for-profit business boom in the past decade. Location boundaries are being blurred under globalization in the sciences and cross-border regulatory reviews. Getting from bench to bedside is a winding road with many obstacles and high hurdles. Efficient teamwork becomes essential to materialize ideas and bring them to the market. The professionals within team communities include drug/device makers and CROs. It has become increasingly obvious that CROs play pivotal roles in the chain of discovery/design, developing product to market through in vitro, in vivo, and ex vivo testing during preclinical experimentations and clinical trials. Project management teams are responsible for nurturing the materialization in a collaborative manner and enhancing the productivity of the pipelines. CROs have many functional aspects and specialties, and no one organization is fully capable of serving, i.e., integrated services, with expertise in each step of the chain to the needs of a variety of sponsors. Instead of competition among the CROs themselves, the continuously expanding market demands can be shared by Expertise-Based Integrated Services among allied CROs, in contrast to the few large CROs

  17. Studies on engineering technologies in the Mizunami Underground Research Laboratory. FY 2007 (Contract research)

    International Nuclear Information System (INIS)

    Noda, Masaru; Suyama, Yasuhiro; Nobuto, Jun; Ijiri, Yuji; Mikake, Shinichiro; Matsui, Hiroya

    2009-07-01

    The Mizunami Underground Research Laboratory (MIU) of the Japan Atomic Energy Agency is a major site for geoscientific research to advance the scientific and technological basis for geological disposal of high-level radioactive waste in crystalline rock. Studies on relevant engineering technologies in the MIU consist of a) research on design and construction technology for very deep underground applications, and b) research on engineering technology as a basis of geological disposal. In the Second Phase of the MIU project (the construction phase), engineering studies have focused on research into design and construction technologies for deep underground. The main subjects in the study of very deep underground structures consist of the following: 'Demonstration of the design methodology', 'Demonstration of existing and supplementary excavation methods', 'Demonstration of countermeasures during excavation' and 'Demonstration of safe construction'. In the FY 2007 studies, identification and evaluation of the subjects for study of engineering technologies in the construction phase were carried out to optimize future research work. Specific studies included: validation of the existing design methodology based on data obtained during construction; validation of existing and supplementary rock excavation methods for very deep shafts; estimation of rock stability under high differential water pressures, methodology on long-term maintenance of underground excavations and risk management systems for construction of underground structures have been performed. Based on these studies, future research focused on the four subject areas, which are 'Demonstration of the design methodology', 'Demonstration of existing and supplementary excavation methods', 'Demonstration of countermeasures during excavation' and 'Demonstration of safe construction', has been identified. The design methodology in the first phase of the MIU Project (surface-based investigation phase) was verified to

  18. Contracts for field projects and supporting research on enhanced oil recovery. Progress review No. 89

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    Summaries are presented for the DOE contracts related to supported research for thermal recovery of petroleum, geoscience technology, and field demonstrations in high-priority reservoir classes. Data included for each project are: title, contract number, principal investigator, research organization, beginning date, expected completion date, amount of award, objectives of the research, and summary of technical progress.

  19. Development and enhancement of grouting technologies in the Mizunami Underground Research Laboratory (Contract research)

    International Nuclear Information System (INIS)

    Nobuto, Jun; Mikake, Shinichiro

    2008-03-01

    In the Tono Geoscience Center of Japan Atomic Energy Agency (hereafter, JAEA), Mizunami Underground Research Laboratory project is being advanced to develop a scientific and technological basis for geological disposal. The concept of geological disposal is based on a multi-barrier system which combines a stable geological environment with an engineered barrier system (EBS). In order to develop a engineering basis for the construction of disposal system, the enhancement of grouting technologies among engineering technologies is needed. In this study, the comprehensive performance of suspension type grouting materials to seal rock fractures encountered in excavation works at deep underground has been checked, and the clogging phenomenon at the entrance of rock fractures has been investigated following the previous year. Research issues are as follows; Study on grouting concept to secure high-level water sealing, study on the test method to check grout clogging under high injection pressure, study on grouting material which can penetrate into finer fractures. Among these, in the study on penetrability test method, prototype test instruments were made and a series of preliminary tests were conducted. (author)

  20. Aspects of research and development contract terms in the bio/pharmaceutical sector.

    Science.gov (United States)

    Banerjee, Tannista

    2012-01-01

    The cost of new drug development is increasing every year. Pharmaceutical companies use R&D joint ventures, mergers, and outsource different stages of pharmaceutical R&D activities for a faster and cost minimizing method of innovation. Pharmaceutical companies outsource R&D activities to independent small biotech or pharmaceutical companies that specialize in different stages of pharmaceutical R&D. This chapter examines the determinants of the payment structure of research contracts between large bio/pharmaceutical companies and specialized research firms. Determinants of R&D contracts are analyzed using detailed R&D contract data between bio/pharmaceutical companies and independent research firms for 10 years. A multinomial logit model is used in order to understand the determinants of three different types of contracts; royalty contracts, fixed payment contracts, and the mixed contracts. Under uncertainty, the likelihood of a royalty contract rises for the early stages of the research and with the patent stock of the research firm. It is more likely to observe both royalty and fixed payment if the pharmaceutical client has past contracts with the same research firm. The results also suggest that if Food and Drug Administration (FDA) is more stringent in any disease area in reviewing the new drug application, then the likelihood of signing pure royalty contract decreases. Understanding the nature of R&D contracts and the effects of FDA's behavior on the pharmaceutical R&D contract is important because these contracts not only affect the cost of new drug invention but also the quality and the rate of invention. VALUE: Results are useful for both the pharmaceutical companies and the economic/business researchers.

  1. Clemson Apparel Research Demonstration Contract. Years 6 and 7

    National Research Council Canada - National Science Library

    Kernodle, Joseph

    2003-01-01

    The purpose of this contract is to develop and demonstrate modern technologies and management practices that optimize the performance of the Department of Defense's Clothing and Textiles (C&T) supply chain...

  2. Clemson Apparel Research. Years 4 and 5 Demonstration Contract

    National Research Council Canada - National Science Library

    Kernodle, Joseph

    2001-01-01

    The purpose of this contract is to develop and demonstrate modern technologies and management practices that optimize the performance of the Department of Defense's Clothing and Textile's supply chain...

  3. Use of Federal Acquisition Regulation. Part 12. Contracts for Applied Research

    National Research Council Canada - National Science Library

    2001-01-01

    ...) Part 12, "Acquisition of Commercial Items,"contracts for acquiring applied research. Applied research involves the scientific efforts to translate basic research into solutions for broadly defined military needs...

  4. 48 CFR 227.7204 - Contracts under the Small Business Innovative Research Program.

    Science.gov (United States)

    2010-10-01

    ... Business Innovative Research Program. 227.7204 Section 227.7204 Federal Acquisition Regulations System... under the Small Business Innovative Research Program. When contracting under the Small Business Innovative Research Program, follow the procedures at 227-7104. ...

  5. A study for the safety evaluation of geological disposal of TRU waste and influence on disposal site design by change of amount of TRU waste (Joint research)

    International Nuclear Information System (INIS)

    Hasegawa, Makoto; Kondo, Hitoshi; Takahashi, Kuniaki; Funabashi, Hideaki; Kawatsuma, Shinji; Kamei, Gento; Hirano, Fumio; Mihara, Morihiro; Ueda, Hiroyoshi; Ohi, Takao; Hyodo, Hideaki

    2011-02-01

    In the safety evaluation of the geological disposal of the TRU waste, it is extremely important to share the information with the Research and development organization (JAEA: that is also the waste generator) by the waste disposal entrepreneur (NUMO). In 2009, NUMO and JAEA set up a technical commission to investigate the reasonable TRU waste disposal following a cooperation agreement between these two organizations. In this report, the calculation result of radionuclide transport for a TRU waste geological disposal system was described, by using the Tiger code and the GoldSim code at identical terms. Tiger code is developed to calculate a more realistic performance assessment by JAEA. On the other hand, GoldSim code is the general simulation software that is used for the computation modeling of NUMO TRU disposal site. Comparing the calculation result, a big difference was not seen. Therefore, the reliability of both codes was able to be confirmed. Moreover, the influence on the disposal site design (Capacity: 19,000m 3 ) was examined when 10% of the amount of TRU waste increased. As a result, it was confirmed that the influence of the site design was very little based on the concept of the Second Progress Report on Research and Development for TRU Waste Disposal in Japan. (author)

  6. Regulatory research for waste disposal - Objectives and international approaches

    International Nuclear Information System (INIS)

    Wanner, Hans; Fischer-Appelt, Klaus; Pescatore, Claudio

    2011-01-01

    The question of active involvement of nuclear regulatory and supervisory bodies in research and development (R and D) projects has become a topic of increasing interest in recent years. The way in which research is included in regulatory activities varies from country to country, ranging from countries with no regulatory R and D activities to countries with extensive activities which are often carried out by independent research organisations acting on behalf of the regulatory body. The present report outlines (part 1) the potential merits of R and D work carried out by the regulator, and summarizes (part 2) the results of a questionnaire that was circulated among the members of the Regulators' Forum of NEA's Radioactive Waste Management Committee in 2009. Part 3 presents the conclusions of discussions within the RWMC-RF. The detailed answers to the questionnaire are also provided

  7. Proposal for a research programme on geological disposal of radioactive waste in the Netherlands

    International Nuclear Information System (INIS)

    1984-06-01

    The present report sets out a tentative research program related to radiologic safety of geological disposal of radioactive waste, set against the background of present knowledge in this field. The final stage of this program has to lead to a definitive appraisal of the suitability of the site explored in that stage for disposal of high-level radioactive waste. Subsequent stages of the research effort is outlined in a critical path diagram. Radiological safety figures as the central factor in making choices. The report indicates the state of the art in different specialisms involved in the study of both natural barriers (rheology, hydrology, radionuclide transport, radiation damage) and artificial barriers (mining engineering) for geological disposal. (G.J.P.)

  8. University Research and Development Activities: The Federal Income Tax Consequences of Research Contracts, Research Subsidiaries and Joint Ventures.

    Science.gov (United States)

    Kertz, Consuelo Lauda; Hasson, James K., Jr.

    1986-01-01

    Features of the federal income tax law applying to income received from commercially funded university-based scientific research and development activities are discussed, including: industry-sponsored research contracts, separately incorporated entities, partnerships and joint ventures, subsidiaries and unrelated income consequences of…

  9. Achievements of research and development of Kajima on radioactive waste disposal

    International Nuclear Information System (INIS)

    Hironaka, Yoshikazu; Morikawa, Seiji; Okutsu, Kazuo; Furuichi, Mitsuaki; Toida, Masaru; Yamamoto, Takuji

    2004-01-01

    Kajima Corporation has been committed to the construction of nuclear power plant for a long time as a construction company. In 1957 Kajima made its first construction of the main building for the JRR-1 (Japan Research Reactor No.1) of JAERI, which was the first and historical one in Japan. Since then the company has been involved in many projects related to nuclear power generation. In addition to the construction, Kajima has been playing an important role in the technology development of decommissioning system as well as radioactive waste waste disposal facilities, both of which are now having an increasing importance. In a sense of technology development, the technology of civil engineering is commonly applicable to the construction of radioactive waste disposal facilities, however, some other technology developments have to be made due to the unique characteristics of radioactive waste disposal. Kajima has promoted many research and development projects related to radioactive waste disposal in order to improve the reliability and the feasibility of the nuclear recycling process. This report introduces some of the achievements as follows made by Kajima: Construction of radioactive waste disposal facilities, Natural barrier, Engineering barrier, Monitoring. (author)

  10. Guidelines for cost control and analysis of cost-type research and development contracts

    Science.gov (United States)

    Sibbers, C. W.

    1981-01-01

    The cost information which should be obtained from a contractor(s) on a major, cost type research and development contract(s), and the analyses and effective use of these data are discussed. Specific type(s) of information which should be required, methods for analyzing such information, and methods for effectively using the results of such analyses to enhance NASA contract and project management are included. The material presented is based primarily on the principal methods which have been effectively used in the management of major cost type research and development contracts.

  11. Opportunities for Research in the UK for decommissioning and disposal

    International Nuclear Information System (INIS)

    Smart, N.

    2008-01-01

    The NDA remit as set out within the Energy Act includes - 'promote, and where necessary fund, research relevant to nuclear clean up'. The NDA need to underpin delivery and / or accelerate programmes to fulfil the overall mission and technical underpinning of these activities is critical. In this paper we will present consideration of the investment required in nuclear waste Research and Development. Firstly, NDA set the requirement for nuclear sites to write down within the Life Time Plans (LTP), at a high level, the proposed technical baseline underpinning the LTP activities; furthermore we required technology gaps / opportunities in the technical baselines to be outlined in a R and D requirements section to the LTP. Criteria were established to categorise the R and D in three areas: - 'needs' - those development activities needed to underpin the proposed technical solutions - 'risks' - those activities required to reduce / eliminate key risks to the proposed technical solutions - 'opportunities' - innovations / changes to the technical baselines The purpose of production of the technical baselines and underpinning R and D requirements is to establish an auditable trail through the LTP from programme components into how the programme will be delivered. NDA believes the production of the technical baselines and R and D requirements will be of benefit to the Site License Companies (SLC) in terms of ensuring a focus on overall programme delivery and not just short term activities. Furthermore, we can ensure that investment in technology is targeted at priority areas, with common issues and requirements identified and solutions on a broader scale will be achievable. (authors)

  12. Review on Overseas Contracts of a Nuclear Research Institute in Korea

    International Nuclear Information System (INIS)

    Lee, Myung Ho; Lee, Eui Jin

    2010-01-01

    Since its establishment, Korea Atomic Energy Research Institute (KAERI) has made various contracts in research, design, engineering and consultation with a lot of foreign counterparts all over the world, including international organizations. As one of the global nuclear energy research leaders, KAERI can make a large scale contract because it has already procured a turnkey EPC (Engineering, Procurement, Construction) contract for a research and training reactor in the spring of 2010 by forming a consortium with a construction and engineering company. A contract in nuclear business industries is to be made under the limited control of regulatory authorities because the contractors must ensure nuclear safety and follow the international nuclear non-proliferation guidelines to secure the peaceful use of nuclear energy at an international level. The export and import of strategic technologies, products or materials (including nuclear materials) must be directly controlled by the authorities in accordance with the applicable law. In 2009, KAERI organized a new team to manage the overseas contracts and to make the limited control reflected in the contract documentation. In large scale project contracts, more attention shall be given to the contracts to prevent claims and also to the consideration of the regulatory requirements. In this context, the nature of the past KAERI contracts was reviewed. The conditions of several recent KAERI contracts were also individually reviewed based on the FIDIC (Federation Internationale des Ingenieurs-Conseils) model service agreement, which is generally accepted by service contractors. Ways to increase the quality of future contracts and to improve the standard model agreement which is used to prepare the draft contract were also considered

  13. Review on Overseas Contracts of a Nuclear Research Institute in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Myung Ho; Lee, Eui Jin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    Since its establishment, Korea Atomic Energy Research Institute (KAERI) has made various contracts in research, design, engineering and consultation with a lot of foreign counterparts all over the world, including international organizations. As one of the global nuclear energy research leaders, KAERI can make a large scale contract because it has already procured a turnkey EPC (Engineering, Procurement, Construction) contract for a research and training reactor in the spring of 2010 by forming a consortium with a construction and engineering company. A contract in nuclear business industries is to be made under the limited control of regulatory authorities because the contractors must ensure nuclear safety and follow the international nuclear non-proliferation guidelines to secure the peaceful use of nuclear energy at an international level. The export and import of strategic technologies, products or materials (including nuclear materials) must be directly controlled by the authorities in accordance with the applicable law. In 2009, KAERI organized a new team to manage the overseas contracts and to make the limited control reflected in the contract documentation. In large scale project contracts, more attention shall be given to the contracts to prevent claims and also to the consideration of the regulatory requirements. In this context, the nature of the past KAERI contracts was reviewed. The conditions of several recent KAERI contracts were also individually reviewed based on the FIDIC (Federation Internationale des Ingenieurs-Conseils) model service agreement, which is generally accepted by service contractors. Ways to increase the quality of future contracts and to improve the standard model agreement which is used to prepare the draft contract were also considered

  14. Study on advanced systematic function of the JNC geological disposal technical information integration system. Research document

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Fukui, Hiroshi; Sagawa, Hiroshi; Matsunaga, Kenichi; Ito Takaya

    2004-02-01

    In this study, while attaining systematization about the technical know-how mutually utilized between geology environmental field, disposal technology (design) field and safety assessment field, the share function of general information in which the formation of an information share and the use promotion between the technical information management databases built for every field were aimed at as an advancement of the function of JNC Geological Disposal Technical Information Integration System considered, and the system function for realizing considered in integration of technical information. (1) Since the concrete information about geology environment which is gradually updated with progress of stratum disposal research, or increases in reflected suitable for research of design and safety assessment. After arranging the form suitable for systematizing technical information, while arranging the technical information in both the fields of design and safety assessment with the form of two classes based on tasks/works, it systematized planning adjustment about delivery of technical information with geology environmental field. (2) In order to aim at integration of 3-fields technical information of geological disposal, based on the examination result of systematization of technical information, the function of mutual use of the information managed in two or more databases was considered. Moreover, while considering system functions, such as management of the use history of technical information, connection of information use, and a notice of common information, the system operation windows in consideration of the ease of operation was examined. (author)

  15. 48 CFR 227.7107-2 - Contracts for construction supplies and research and development work.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Contracts for construction supplies and research and development work. 227.7107-2 Section 227.7107-2 Federal Acquisition Regulations... PATENTS, DATA, AND COPYRIGHTS Rights in Technical Data 227.7107-2 Contracts for construction supplies and...

  16. Listing of engineering research contract reports under the DREAM, AERD and ERDAF programs of the Research Branch, 1973-1988

    Energy Technology Data Exchange (ETDEWEB)

    Morrison, B A; Thuns, A; Feldman, M

    1988-01-01

    To supplement in-house investigations, Agriculture Canada contracted out research in a number of programs including three which supported engineering work. This document lists the contracts awarded under the programs and provides reference citations of the contract reports. Reports are grouped by file number, scientific authority, author or contractor, and subject, and a subject index is also included. The three programs are: Development, Research and Evaluation in Agricultural Mechanization (DREAM), Agricultural Engineering Research and Development Program (AERD), and Energy Research and Development in Agriculture and Food (ERDAF). AERD, which replaced DREAM, has been terminated, but the ERDAF program is still continuing as of the date of this document.

  17. Collaboration of the Dutch research program for radioactive waste disposal (OPERA) and TU Delft

    Energy Technology Data Exchange (ETDEWEB)

    Bykov, D.M.; Kloosterman, J.L. [TU Delft (Netherlands). Reactor Inst. Delft; Neeft, E.A.C.; Verhoef, E.V. [COVRA N.V., Nieuwdorp (Netherlands)

    2015-07-01

    Radioactive waste in the Netherlands is collected, treated and stored by COVRA (Centrale Organisatie Voor Radioactief Afval) in the interim storage facility for at least 100 a. After this period of long-term storage, geological disposal is foreseen. The policy is based on a step-wise decision process in which all decisions are taken to ensure safe disposal in a repository, but without excluding unforeseen alternative solutions that might develop in the future. OPERA is the Dutch acronym for research program into geological disposal of radioactive waste. It started in 2011 and is running for five years. The OPERA Research plan is developed by NRG in close collaboration with COVRA. Radioactive waste disposal in the Netherlands is at an early, conceptual phase. The aim of Opera is to develop a first preliminary safety case to structure the research necessary for the eventual deployment of a repository in the Netherlands. The OPERA research program aims at a close cooperation with the Belgian research program on radioactive waste disposal. The result of OPERA will be to detail a first roadmap for the long-term research on geological disposal of radioactive waste in the Netherlands, based initially on a re-evaluation of existing safety and feasibility studies conducted more than ten years ago, making use of present international and, wherever possible, national knowledge. This will be done by developing initial and conditional safety cases for generic GDFs in Zechstein rock salt and Boom Clay formations in the Netherlands. The goal in OPERA is to develop initial safety cases that are intended to mark the start of the research development process and to iterate these as knowledge grows to new developed insights. The safety case is conditional since plausible assumptions must later be confirmed in a safety case e.g. for site selection. Dutch, Belgian, German, English and French organizations participate in OPERA. These organizations can be found in the two documents with

  18. Collaboration of the Dutch research program for radioactive waste disposal (OPERA) and TU Delft

    International Nuclear Information System (INIS)

    Bykov, D.M.; Kloosterman, J.L.

    2015-01-01

    Radioactive waste in the Netherlands is collected, treated and stored by COVRA (Centrale Organisatie Voor Radioactief Afval) in the interim storage facility for at least 100 a. After this period of long-term storage, geological disposal is foreseen. The policy is based on a step-wise decision process in which all decisions are taken to ensure safe disposal in a repository, but without excluding unforeseen alternative solutions that might develop in the future. OPERA is the Dutch acronym for research program into geological disposal of radioactive waste. It started in 2011 and is running for five years. The OPERA Research plan is developed by NRG in close collaboration with COVRA. Radioactive waste disposal in the Netherlands is at an early, conceptual phase. The aim of Opera is to develop a first preliminary safety case to structure the research necessary for the eventual deployment of a repository in the Netherlands. The OPERA research program aims at a close cooperation with the Belgian research program on radioactive waste disposal. The result of OPERA will be to detail a first roadmap for the long-term research on geological disposal of radioactive waste in the Netherlands, based initially on a re-evaluation of existing safety and feasibility studies conducted more than ten years ago, making use of present international and, wherever possible, national knowledge. This will be done by developing initial and conditional safety cases for generic GDFs in Zechstein rock salt and Boom Clay formations in the Netherlands. The goal in OPERA is to develop initial safety cases that are intended to mark the start of the research development process and to iterate these as knowledge grows to new developed insights. The safety case is conditional since plausible assumptions must later be confirmed in a safety case e.g. for site selection. Dutch, Belgian, German, English and French organizations participate in OPERA. These organizations can be found in the two documents with

  19. Development of the disposal technology research component of the national uranium tailings program

    International Nuclear Information System (INIS)

    Melis, L.A.

    1983-03-01

    The National Technical Planning Group on Uranium Tailings Research, organized by CANMET in 1980, recommended the establishment of a National Uranium Tailings Program to develop research on the long-term abandonment of uranium mine tailings. This report deals with the disposal technology component of this program and attempts to provide recommendations with respect to potential research avenues in this area. A description of uranium tailings in Canada is provided in order to identify the current situation with uranium tailings management. Uranium mining sites described include the Elliot Lake and Bancroft area of Ontario, the northern Saskatchewan properties and the two abandoned sites in the North West Territories. The description of the sites was facilitated by subdividing the tailings into inactive sites, active sites, new tailings sites and areas of tailings in a close-out situation. Methods identified as promising include subsurface disposal, in-situ leaching, prevention of pyrite oxidation and reclamation studies at abandoned sites

  20. 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

  1. Horonobe Underground Research Laboratory project. Synthesis of phase 1 investigation 2001-2005, Volume 'geological disposal research'

    International Nuclear Information System (INIS)

    Fujita, Tomoo; Taniguchi, Naoki; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; Sasamoto, Hiroshi; Yoshikawa, Hideki; Shibata, Masahiro; Ota, Kunio; Miyahara, Kaname; Naito, Morimasa; Yui, Mikazu; Matsui, Hiroya; Hama, Katsuhiro; Kunimaru, Takanori; Takeuchi, Ryuji; Tanai, Kenji; Kurikami, Hiroshi; Wakasugi, Keiichiro; Ishii, Eiichi

    2011-03-01

    This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project, of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological conditions obtained from the project as an example of actual geological environment. For the first aim, the design methods for the geological disposal facility proposed in 'H12 report (the second progress report)' was reviewed and then improved based on the recent knowledge. The applicability of design for engineered barrier system, backfill of disposal tunnel, underground facility was illustrated. For the second aim, the conceptual structure from site investigation and evaluation to mass transport analysis was developed as a work flow at first. Then following this work flow a series of procedures for mass transport analysis was applied to the actual geological conditions to illustrate the practical workability of the work flow and the applicability of this methodology. Consequently, based on the results, future subjects were derived. (author)

  2. Horonobe Underground Research Laboratory project synthesis of phase I investigation 2001-2005. Volume 'Geological disposal research'

    International Nuclear Information System (INIS)

    Fujita, Tomoo; Taniguchi, Naoki; Tanai, Kenji; Nishimura, Mayuka; Kobayashi, Yasushi; Hiramoto, Masayuki; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; Sasamoto, Hiroshi; Yoshikawa, Hideki; Shibata, Masahiro; Wakasugi, Keiichiro; Nakano, Katsushi; Seo, Toshihiro; Miyahara, Kaname; Naito, Morimasa; Yui, Mikazu; Matsui, Hiroya; Kurikami, Hiroshi; Kunimaru, Takanori; Ishii, Eiichi; Ota, Kunio; Hama, Katsuhiro; Takeuchi, Ryuji

    2007-03-01

    This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project (HOR), of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological conditions obtained from the surface-based investigations in HOR as an example of actual geological environment. For the first aim, the design methods for the geological disposal facility proposed in 'H12 report (the second progress report)' was reviewed and then improved based on the recent knowledge. The applicability of design for engineered barrier system, backfill of disposal tunnel, underground facility was illustrated. For the second aim, the conceptual structure from site investigation and evaluation to mass transport analysis was developed as a work flow at first. Then following this work flow a series of procedures for mass transport analysis was applied to the actual geological conditions to illustrate the practical workability of the work flow and the applicability of this methodology. Consequently, based on the results, future subjects were derived. (author)

  3. KAERI Underground Research Facility (KURF) for the Demonstration of HLW Disposal Technology

    International Nuclear Information System (INIS)

    Hahn, P. S.; Cho, W. J.; Kwon, S.

    2006-01-01

    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 paper, the current status of the conceptual design and the construction of a small scale URL, which is named as KURF, were described. To confirm the validity of the conceptual design of the underground facility, a geological survey including a seismic refraction survey, an electronic resistivity survey, a borehole drilling, and in situ and laboratory tests had been carried out. Based on the site characterization results, it was possible to effectively design the KURF. The construction of the KURF was started in May 2005 and the access tunnel was successfully completed in March 2006. Now the construction of the research modules is under way

  4. Research requirements for a unified approach to modelling chemical effects associated with radioactive waste disposal

    International Nuclear Information System (INIS)

    Krol, A.A.; Read, D.

    1986-09-01

    This report contains the results of a review of the current modelling, laboratory experiments and field experiments being conducted in the United Kingdom to aid understanding and improve prediction of the effects of chemistry on the disposal of radioactive wastes. The aim has been to summarise present work and derive a structure for future research effort that would support the use of probabilistic risk assessment (pra) methods for the disposal of radioactive wastes. The review was conducted by a combination of letter and personal visits, and preliminary results were reported to a plenary meeting of participants held in April, 1986. Following this meeting, copies of the report were circulated to participants at draft stage, so that the finalised report should be taken to provide as far as possible a consensus of opinion of research requirements. (author)

  5. IRSN safety research carried out for reviewing geological disposal safety case

    International Nuclear Information System (INIS)

    Serres, Christophe; Besnus, Francois; Gay, Didier

    2010-01-01

    The Radiation Protection and Nuclear Safety Institute develops a research programme on scientific issues related to geological disposal safety in order to supporting the technical assessment carried out in the framework of the regulatory review process. This research programme is organised along key safety questions that deal with various scientific disciplines as geology, hydrogeology, mechanics, geochemistry or physics and is implemented in national and international partnerships. It aims at providing IRSN with sufficient independent knowledge and scientific skills in order to be able to assess whether the scientific results gained by the waste management organisation and their integration for demonstrating the safety of the geological disposal are acceptable with regard to the safety issues to be dealt with in the Safety Case. (author)

  6. Report on the Status of the SFWST Campaign International Activities in Disposal Research at SNL

    Energy Technology Data Exchange (ETDEWEB)

    McMahon, Kevin A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Waste Disposal Research and Analysis. New Mexico Energy and Geoscience Center

    2017-08-22

    The following summaries are provided as fulfillment of milestone M4SF-17SN080305022 and represent international coordination activities in disposal research funded by the US DOE Spent Fuel and Waste Storage and Technologies (SFWST) Campaign during Fiscal Year 2017: SFWST funded bi-lateral interactions with Taiwan, OECD-NEA Repository Metadata (RepMet) project, SFWST funded bi-lateral interactions with the Republic of Korea.

  7. Process and research method of radionuclide migration in high level radioactive waste geological disposal system

    International Nuclear Information System (INIS)

    Chen Rui; Zhang Zhanshi

    2014-01-01

    Radionuclides released from waste can migrate from the repository to the rock and soil outside. On the other hand, nuclides also are retarded by the backfill material. Radionuclide migration is the main geochemical process of the waste disposal. This paper introduces various methods for radionuclide migration research, and give a brief analysis of the geochemical process of radionuclide migration. Finally, two of the most important processes of the radionuclide migration have been instanced. (authors)

  8. Radionuclide migration study in the case of a geological disposal site. Bibliographic research report

    International Nuclear Information System (INIS)

    Rio, Sophie

    1997-01-01

    The present bibliographic research deals with the study of radionuclide migration in the case of a geological disposal of spent fuel from PWR nuclear reactors. Bibliography was made with the DIALOG server on the following databases: INSPEC, NTIS, Ei Compendex Plus, SPIN, SciSearch, Pascal et Current Contents Search, and with the INIS and DocTheses CD-Roms. A synthesis based on a few documents is made in the second part of the report. (author) [fr

  9. Researches on tectonic uplift and denudation with relation to geological disposal of HLW in Japan

    International Nuclear Information System (INIS)

    Fujiwara, Osamu; Sanga, Tomoji; Moriya, Toshifumi

    2005-01-01

    This paper reviews the present state of researches on tectonic uplift and denudation, and shows perspective goals and direction of future researches from the viewpoint of geological disposal of HLW in Japan. Detailed history of tectonics and denudation in geologic time scale, including the rates, temporal and spatial distributions and processes, reconstructed from geologic and geomorphologic evidences will enable us to make the geological predictions. Improvements of the analytic methods for the geological histories, e.g. identification of the tectonic and denudational imprints and age determinations, are indispensable for the accurate prediction. Developments of the tools and methodologies for assessments of the degree and extension of influences by the tectonic uplift, subsidence and denudation on the geological environments such as ground water flows are also fundamental problem in the study field of the geological disposal of HLW. Collaboration of scientific researches using the geological and geomorphological methods and applied technology, such as numerical simulations of ground water flows, is important in improving the safety and accuracy of the geological disposal of HLW. (author)

  10. Nordic nuclear safety research 1994-1997. Project on disposal of radioactive waste

    International Nuclear Information System (INIS)

    Broden, Karin

    1999-01-01

    This presentation describes the Nordic Nuclear Safety Research (NKS) programme, which is a scientific co-operation programme in nuclear safety, radiation protection and emergence preparedness. The purpose of the programme is to carry out cost-effective Nordic projects, thus producing research results, exercises, information, manuals, recommendations, and other types of background material. This material is to serve decision-makers and other concerned staff members at authorities, research establishments and enterprises in the nuclear field. Three waste disposal projects under NKS are briefly described: (1) Waste characterisation, (2) Performance analysis of the engineered barrier system of the repositories for low- and intermediate-level waste, (3) Environmental impact assessment

  11. 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)

  12. Comments on report ''The impact of nuclear waste disposals to the marine environment'' by Political Ecology Research Group (RR-8)

    International Nuclear Information System (INIS)

    1982-06-01

    A series of statements made by the Political Ecology Research Group in a report ''The Impact of Nuclear Waste Disposals to the Marine Environment'' are commented on by British Nuclear Fuels Ltd. Areas covered include radioactive discharges, health effects, recommendations for reducing discharge arising from the Windscale Inquiry and solid waste disposal to the deep ocean. (author)

  13. Comparative research on decommissioning disposal effect of two uranium mines at home and abroad

    International Nuclear Information System (INIS)

    Shi Yuke; Peng Daofeng; Liu Qingcheng

    2014-01-01

    Taking two typical decommissioned uranium mines at home and abroad for an example, disposal means and effects of two uranium mines were compared and analyzed in three aspects of waste dump disposal, mine sealing treatment, and wastewater disposal. The results showed that two uranium mines were basically identical in the disposal standards and disposal means, but the works in the source survey, wastewater disposal and long-term supervision done by oversea uranium mine were more detailed than domestic uranium mine. (authors)

  14. 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

  15. The international STRIPA project. Experimental research on the underground disposal of radioactive waste

    International Nuclear Information System (INIS)

    1983-03-01

    The International Stripa Project is a joint undertaking by a number of countries, carried out under the sponsorship of the OECD Nuclear Energy Agency. It concerns research into the feasibility and safety of disposal of highly radioactive wastes from nuclear power generation, deep underground in crystalline rock. The Project is managed by the Division KBS of the Swedish Nuclear Fuel Supply Company (SKBF), under the direction of representatives from each participating country. This report summarizes the objectives and preliminary results of experimental work performed within the framework of the Stripa Project and that undertaken prior to the establishment of the Project at the Stripa Mine in Sweden. It also describes the part played by the Project in the development of national policies for the safe disposal of radioactive wastes

  16. Directions in locational conflict research: Voting on the location of nuclear waste disposal facilities

    International Nuclear Information System (INIS)

    Shelley, F.M.; Murauskas, G.T.

    1985-01-01

    It is clear from empirical evidence that currently significant locational conflicts concerning the siting of nuclear waste disposal facilities cannot be modeled under the standard noxious facility location paradigm that views locational conflict as conflict between regions. Rather, local populations are characterized by sharp disagreements as to whether the proposed facility is in fact salutary or noxious. Thus, conflict concerning nuclear waste disposal must be understood as a conflict among preferences and values, rather than among competing, areally defined interest groups. This has significant implications for the outcomes of political processes leading to siting decisions, as indicated in this paper. Whether intransivity occurs depends on the location and proportion of persons with different preference orderings concerning possible outcomes. Further research on this issue can and should be directed to further mathematical specification of these conditions along with empirical analysis where appropriate

  17. 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

  18. 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.

  19. 77 FR 47797 - Federal Acquisition Regulation; Small Business Set Asides for Research and Development Contracts

    Science.gov (United States)

    2012-08-10

    ... Acquisition Regulation; Small Business Set Asides for Research and Development Contracts AGENCY: Department of... when the market research conducted in accordance with FAR part 10 indicates there are small businesses... officer can proceed with a small business set-aside for research and development. FAR 19.502-2(b...

  20. Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal. Results of a Coordinated Research Project

    International Nuclear Information System (INIS)

    2016-05-01

    Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal. It presents the findings of the CRP, the general conclusions and recommendations. The topics covered include, graphite management issues, characterization of irradiated graphite, processing and treatment, immobilization and disposal. Included on the attached CD-ROM are formal reports from the participants

  1. The U.S. Public's Investment in Medical Research: An Evolving Social Contract.

    Science.gov (United States)

    Heinig, Stephen J; Dev, Anurupa; Bonham, Ann C

    2016-01-01

    Medical researchers and their institutions are operating under extraordinary financial stress. More than a decade after completion of the 5-year doubling of the National Institutes of Health budget, the medical research community must confront a significant loss in National Institutes of Health purchasing power and downward pressures in federal discretionary spending. In part, this trend results from a federal budget stalemate over the growth in entitlement programs, particularly spending on medical care. This article considers the changing nature of the federal investment in medical research and the potential for medical researchers and institutions conducting the full spectrum of research to improve health system performance and health equity. In our view, continued federal investments reflect an evolving social contract for research serving the public good; the term contract is used metaphorically to represent a figurative, implicit agreement between the scientific community and the public's representatives in government. Under this conceptual contract, the American people--who are ultimately the funders of research, research training and infrastructure--expect outcomes that lead to better health, security or other benefits. The evolving contract includes expectations for more accountability, transparency, sharing of results and resources, and better integration of research systems and cultures that used to take pride in boundaries and distinctions. We outline here some of the major movements of organizations realigning to social support, which are increasingly essential to sustain public investment in medical research. Copyright © 2016 Southern Society for Clinical Investigation. Published by Elsevier Inc. All rights reserved.

  2. United States private-sector physicians and pharmaceutical contract research: a qualitative study.

    Science.gov (United States)

    Fisher, Jill A; Kalbaugh, Corey A

    2012-01-01

    There have been dramatic increases over the past 20 years in the number of nonacademic, private-sector physicians who serve as principal investigators on US clinical trials sponsored by the pharmaceutical industry. However, there has been little research on the implications of these investigators' role in clinical investigation. Our objective was to study private-sector clinics involved in US pharmaceutical clinical trials to understand the contract research arrangements supporting drug development, and specifically how private-sector physicians engaged in contract research describe their professional identities. We conducted a qualitative study in 2003-2004 combining observation at 25 private-sector research organizations in the southwestern United States and 63 semi-structured interviews with physicians, research staff, and research participants at those clinics. We used grounded theory to analyze and interpret our data. The 11 private-sector physicians who participated in our study reported becoming principal investigators on industry clinical trials primarily because contract research provides an additional revenue stream. The physicians reported that they saw themselves as trial practitioners and as businesspeople rather than as scientists or researchers. Our findings suggest that in addition to having financial motivation to participate in contract research, these US private-sector physicians have a professional identity aligned with an industry-based approach to research ethics. The generalizability of these findings and whether they have changed in the intervening years should be addressed in future studies. Please see later in the article for the Editors' Summary.

  3. United States private-sector physicians and pharmaceutical contract research: a qualitative study.

    Directory of Open Access Journals (Sweden)

    Jill A Fisher

    Full Text Available There have been dramatic increases over the past 20 years in the number of nonacademic, private-sector physicians who serve as principal investigators on US clinical trials sponsored by the pharmaceutical industry. However, there has been little research on the implications of these investigators' role in clinical investigation. Our objective was to study private-sector clinics involved in US pharmaceutical clinical trials to understand the contract research arrangements supporting drug development, and specifically how private-sector physicians engaged in contract research describe their professional identities.We conducted a qualitative study in 2003-2004 combining observation at 25 private-sector research organizations in the southwestern United States and 63 semi-structured interviews with physicians, research staff, and research participants at those clinics. We used grounded theory to analyze and interpret our data. The 11 private-sector physicians who participated in our study reported becoming principal investigators on industry clinical trials primarily because contract research provides an additional revenue stream. The physicians reported that they saw themselves as trial practitioners and as businesspeople rather than as scientists or researchers.Our findings suggest that in addition to having financial motivation to participate in contract research, these US private-sector physicians have a professional identity aligned with an industry-based approach to research ethics. The generalizability of these findings and whether they have changed in the intervening years should be addressed in future studies. Please see later in the article for the Editors' Summary.

  4. User study: information needs of contracting companies of market research

    Directory of Open Access Journals (Sweden)

    Frederico Cesar Mafra Pereira

    2018-01-01

    Full Text Available This paper has as main objective to understand why companies use market research as a source of information for their business, with a comparison between what they want to apply for a research and the effective use of the information received. The main methodological approach was based on the 'Model for identifying needs, seeking and use of information' (MAFRA PEREIRA, 2010, and from this approach has drawn up a script for conducting interviews with clients of research institute located in Belo Horizonte (MG. The results showed the applicability of the model, identifying information needs, gaps of information and the effective use of information in their respective organizational contexts; besides the methodological procedures for conducting and analyzing the results.

  5. Handling and final disposal of nuclear waste. Programme for research development and other measures

    International Nuclear Information System (INIS)

    1989-09-01

    The report is divided into two parts. Part 1 presents the premises for waste management in Sweden and the waste types that are produced in Sweden. A brief description is then provided of the measures required for the handling and disposal of the various waste forms. An account of measures for decommissioning of nuclear power plants is also included. Part 2 describes the research program for 1990-1995, which includes plans for siting, repository design; studies of rock properties and chemistry, biosphere, technological barriers. Activities within two large projects, the Stripa laboratory and Natural analogues are also described. 240 refs. 40 figs

  6. Life-cycle cost analysis for Foreign Research Reactor, Spent Nuclear Fuel disposal

    International Nuclear Information System (INIS)

    Parks, P.B.; Geddes, R.L.; Jackson, W.N.; McDonell, W.R.; Dupont, M.E.; McWhorter, D.L.; Liutkus, A.S.

    1994-01-01

    DOE-EM-37 requested a life-cycle cost analysis for disposal of the Foreign Research Reactor-Spent Nuclear Fuel (FRR-SNF). The analysis was to address life-cycle and unit costs for a range of FRR-SNF elements from those currently available (6,000 elements) to the (then) bounding case (15,000 elements). Five alternative disposition strategies were devised for the FRR-SNF elements. Life-cycle costs were computed for each strategy. In addition, the five strategies were evaluated in terms of six societal and technical goals. This report summarizes the study that was originally documented to DOE-EM

  7. 48 CFR 53.235 - Research and Development Contracting (SF 298).

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Research and Development Contracting (SF 298). 53.235 Section 53.235 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION (CONTINUED) CLAUSES AND FORMS FORMS Prescription of Forms 53.235 Research and Development...

  8. 48 CFR 227.7104 - Contracts under the Small Business Innovation Research (SBIR) Program.

    Science.gov (United States)

    2010-10-01

    ... Business Innovation Research (SBIR) Program. 227.7104 Section 227.7104 Federal Acquisition Regulations... Data and Computer Software—Small Business Innovation Research (SBIR) Program, when technical data or... PATENTS, DATA, AND COPYRIGHTS Rights in Technical Data 227.7104 Contracts under the Small Business...

  9. Contracts for field projects and supporting research on enhanced oil recovery. Progress review number 87

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    Approximately 30 research projects are summarized in this report. Title of the project, contract number, company or university, award amount, principal investigators, objectives, and summary of technical progress are given for each project. Enhanced oil recovery projects include chemical flooding, gas displacement, and thermal recovery. Most of the research projects though are related to geoscience technology and reservoir characterization.

  10. Perspectives for deep geological formation disposal research in France beyond 2006

    International Nuclear Information System (INIS)

    Landais, P.

    2006-01-01

    One finalised aim underlies research conducted on the feasibility of geological disposal: the possibility of having a reversible disposal system available. A model has been drawn up to provide a framework for the analysis and propose possible research content between 2006 and 2015. This period will correspond to the move from the feasibility to a development, optimisation and detailed study phase. It aims at answering any questions raised by reviewers and develops forward the study of a repository. It will also correspond to the consolidation of scientific data, greater understanding of certain mechanisms and an approach of scientific and technical integration. Another goal of the period 2006-2015 would be to collect elements for a decision on the sitting issue through an extended survey. This phase of development includes confirmation of the data acquired during the previous phase and over relatively long periods, optimisation of repository concepts and detailed study of their main components, the production of full-scale mock-ups or simulations to validate the main technological design points and refining of data extrapolation methods. (author)

  11. Catalytic activity of catalysts for steam reforming reaction. Contract research

    Energy Technology Data Exchange (ETDEWEB)

    Ohashi, Hirofumi; Inagaki, Yoshiyuki [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    2003-05-01

    Japan Atomic Energy Research Institute has been developing a hydrogen production system by means of steam reforming of methane (chemical reation: CH{sub 4} + H{sub 2}O = CO + 3H{sub 2}) coupling with High Temperature Engineering Test Reactor (HTTR) to demonstrate effectiveness of high-temperature nuclear heat utilization. Prior to construction of HTTR hydrogen production system, a mock-up test facility with a full-scale reaction tube was constructed to investigate transient behavior of the hydrogen production system an establish system controllability. In order to predict transient behavior and hydrogen productivity of the hydrogen production system, it is important to estimate the reaction characteristics under the same temperature and pressure conditions as those of HTTR hydrogen production system. For the purpose of investigate an apparent activation energy of catalysts, catalytic activity test using small apparatus was carried out under the condition of methane flow rate from 1.18 x 10{sup -3} to 3.19 x 10{sup -3} mol/s, temperature from 500 to 900degC, pressure from 1.1 to 4.1MPa, and mol ratio of steam to methane from 2.5 to 3.5. It was confirmed that apparent activation energies of two kinds of Ni catalysts which are to be used in the mock-up test were 51.7 and 57.4kJ/mol, respectively, and reaction rate constants were propositional to the value from P{sup -0.15} to P{sup -0.33}. (author)

  12. Feasible research on VLLW disposal in control area of nuclear installation

    International Nuclear Information System (INIS)

    Kong Jinsong; Guo Weiqun

    2013-01-01

    Based on the basic requirements on the VLLW landfill disposal specified by the national codes and standards, a on-site disposal of VLLW in the control area of nuclear installation was proposed. A detail analysis of the advantages and disadvantages about the disposal method and the problem to be solved were described. Results showed that the on-site disposal of VLLW in the control area of nuclear installation was feasible in practice. (authors)

  13. Research and development programme on radioactive waste disposal in deep geological formation (study of a clay formation)

    International Nuclear Information System (INIS)

    Heremans, R.; Manfroy, P.; Bonne, A.

    1980-01-01

    The experiments carried out at the Mol nuclear research center from 1 January 1976 to 30 June 1978 on the management and storage of radioactive wastes are described. The possibility of underground disposal and storage at Mol has been studied. Mol clay samples and ground water were analysed. Hydrogeological measurement were made together with experiments or heat transfer in clayes. The technical realization and environmental riscks of radioactive underground disposal at Mol are discussed

  14. Study of waste acceptance criteria for low-level radioactive waste from medical, industrial, and research facilities (Contract research)

    International Nuclear Information System (INIS)

    Koibuchi, Hiroto; Dohi, Terumi; Ishiguro, Hideharu; Hayashi, Masaru; Senda, Masaki

    2008-12-01

    Japan Atomic Energy Agency (JAEA) is supposed to draw up the plan for the disposal program of the very low-level radioactive waste and low-level radioactive waste generated from medical, industrial and research facilities. For instance, there are these facilities in JAEA, universities, private companies, and so on. JAEA has to get to know about the waste and its acceptance of other institutions described above because it is important for us to hold the licenses for the disposal program regarding safety assessment. This report presents the basic data concerning radioactive waste of research institutes etc. except RI waste, domestic and foreign information related to acceptance criteria for disposal of the low-level radioactive waste, the current status of foreign medical waste management, waste acceptance, and such. In this report, Japan's acceptance criteria were summarized on the basis of present regulation. And, the criteria of foreign countries, United States, France, United Kingdom and Spain, were investigated by survey of each reference. In addition, it was reported that the amount of waste from laboratories etc. for near-surface disposal and their characterization in our country. The Subjects of future work: the treatment of hazardous waste, the problem of the double-regulation (the Nuclear Reactor Regulation Law and the Law Concerning Prevention from Radiation Hazards due to Radioisotopes and Others) and the possession of waste were discussed here. (author)

  15. Program criteria for subseabed disposal of radioactive waste: research strategies and review processes

    International Nuclear Information System (INIS)

    1981-09-01

    The Subseabed Disposal Program follows the policies and criteria of the National Waste Terminal Storage program for the development of land-based repositories, except where the technical differences between land and ocean geologic disposal make different approaches or criteria necessary. This is the first of a series of documents describing the procedures and criteria for the Subseabed Disposal Program

  16. NEA Research and Environmental Surveillance Programme related to sea disposal of low-level radioactive waste

    International Nuclear Information System (INIS)

    Ruegger, B.; Templeton, W.L.; Gurbutt, P.

    1983-05-01

    Sea dumping operations of certain types of packaged low and medium-level radioactive wastes have been carried out since 1967 in the North-East Atlantic under the auspices of the OECD Nuclear Energy Agency. On the occasion of the 1980 review of the continued suitability of the North-East Atlantic site used for the disposal of radioactive waste, it was recommended that an effort should be made to increase the scientific data base relating to the oceanographic and biological characteristics of the dumping area. In particular, it was suggested that a site specific model of the transfer of radionuclides in the marine environment be developed, which would permit a better assessment of the potential radiation doses to man from the dumping of radioactive waste. To fulfill these objectives a research and environmental surveillance programme related to sea disposal of radioactive waste was set up in 1981 with the participation of thirteen Member countries and the International Laboratory for Marine Radioactivity of the IAEA in Monaco. The research program is focused on five research areas which are directly relevant to the preparation of more site-specific assessments in the future. They are: model development; physical oceanography; geochemistry; biology; and radiological surveillance. Promising results have already been obtained and more are anticipated in the not too distant future. An interim description of the NEA dumping site has been prepared which provides an excellent data base for this area (NEA 1983).It includes data in bathymetry, isopycnal topography, local and larger scale currents, sediment distribution and sedimentary processes, hydrochemistry, deep ocean biology and results of radiochemical analyses of sea water, sediments and biological materials. The modelling work is also well advanced allowing comparison of results obtained from different codes. After integration of the models, sensitivity analyses will provide indications for future research needs

  17. 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...

  18. 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...

  19. The WIPP research and development program: providing the technical basis for defense waste disposal

    International Nuclear Information System (INIS)

    Hunter, Th.O.

    1983-01-01

    The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, is being developed by the US Department of Energy as a research and development facility to demonstrate the safe disposal of radioactive wastes from the defense programs of the United States. Underground workings are at a depth of 660 in a bedded-salt formation. Site investigations began in the early 1970s and are culminating with the completion of the Site and Preliminary Design Validation (SPDV) program in 1983 in which two shafts and several thousand feet of underground drifts are being constructed. The underground facility will be used for in situ tests and demonstrations that address technical issues associated with the disposal of transuranic and defense high-level wastes (DHLW) in bedded salt. These tests are based on several years of laboratory tests, field tests in mines, and analytical modeling studies. They primarily address repository development in bedded salt, including thermal-structural interactions plugging and sealing, and facility operations; and waste package interactions, including the effects of the waste on local rock salt and the evaluation of waste package materials. In situ testing began in the WIPP with the initiation of the SPDV program in 1981. In 1983, a major series of tests will begin to investigate the response of the rock salt without the use of any radioactivity

  20. Co-ordinated research and environmental surveillance programme related to sea disposal of radioactive waste

    International Nuclear Information System (INIS)

    1984-01-01

    Sea disposal operations of packaged low-level radioactive waste are carried out under the provisions of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, also referred to as the London Dumping Convention. The environmental impact of this disposal method is continuously kept under review, in particular within the IAEA which has provided the ''Definition of High-Level Radioactive Waste or Other High-Level Radioactive Matter Unsuitable for Dumping at Sea'' for the purpose of the Convention and within the OECD-NEA in the framework of its Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste. The NEA Co-Ordinated Research and Environmental Surveillance Programme (CRESP) is focussed on the actual North-East Atlantic dump site. Its objective is to increase the available scientific data base related to the oceanographic and biological characteristics of the dump site and elaborate a site specific model of the transfers of radionuclides to human populations. Future site suitability reviews, as periodically requested under the terms of the Multilateral Consultation and Surveillance Mechanism, will therefore be based on a more accurate and comprehensive scientific basis

  1. The IAEA research project on improvement of safety assessment methodologies for near surface disposal facilities

    International Nuclear Information System (INIS)

    Torres-Vidal, C.; Graham, D.; Batandjieva, B.

    2002-01-01

    The International Atomic Energy Agency (IAEA) Research Coordinated Project on Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities (ISAM) was launched in November 1997 and it has been underway for three years. The ISAM project was developed to provide a critical evaluation of the approaches and tools used in long-term safety assessment of near surface repositories. It resulted in the development of a harmonised approach and illustrated its application by way of three test cases - vault, borehole and Radon (a particular range of repository designs developed within the former Soviet Union) type repositories. As a consequence, the ISAM project had over 70 active participants and attracted considerable interest involving around 700 experts from 72 Member States. The methodology developed, the test cases, the main lessons learnt and the conclusions have been documented and will be published in the form of an IAEA TECDOC. This paper presents the work of the IAEA on improvement of safety assessment methodologies for near surface waste disposal facilities and the application of these methodologies for different purposes in the individual stages of the repository development. The paper introduces the main objectives, activities and outcome of the ISAM project and summarizes the work performed by the six working groups within the ISAM programme, i.e. Scenario Generation and Justification, Modelling, Confidence Building, Vault, Radon Type Facility and Borehole test cases. (author)

  2. Underground disposal of vitrified high level radioactive waste: a review of research and development

    International Nuclear Information System (INIS)

    1982-11-01

    A review has been undertaken of the worldwide status of research and development related to the geological disposal of vitrified high level radioactive waste. The nature and quantities of vitrified high level waste that will arise from nuclear power generation in the UK have been estimated and considered. The safety case for establishing a geological repository would have to be based on predictive models, which could adequately represent the interactions and effects of a wide range of gradual processes and possible sudden events. No detailed repository design has yet been published, but the configuration currently favoured, in the UK and in most other countries, comprises a small number of vertical shafts, from which a network of horizontal tunnels would be excavated. Waste packages would be placed in holes drilled in the floors of the tunnels. The excavation of such a repository in hard crystalline rock, in a thick homogeneous formation of rock salt, or in the less plastic argillaceous formations, appears to be within the scope of present technology. Rock types available in the UK, which are likely to prove suitable for the accommodation of a repository, have been identified. The strategies and programmes for high level waste disposal in other countries have been reviewed. (U.K.)

  3. The Construction of Academic Time: Sub/Contracting Academic Labour in Research.

    Science.gov (United States)

    Hey, Valerie

    2001-01-01

    Offers a poststructuralist analysis of the UK higher education sector's academic division of labor, exploring some new contradictions from a contract researcher's standpoint. Raises political, social, and methodological questions about these divisions by exploring their class and gender dimensions. Too many academics remain silent about adverse…

  4. Survey of the geological characteristics on the Japanese Islands for disposal of RI and research institute waste

    Energy Technology Data Exchange (ETDEWEB)

    Hagiwara, Shigeru [Chuo Kaihatsu Co., Ltd., Tokyo (Japan); Sakamoto, Yoshiaki; Takebe, Shinichi; Ogawa, Hiromichi; Nakayama, Shinichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-12-01

    In the disposal of radioactive wastes arising from radioisotope utilization facilities and nuclear research facilities, it is necessary to establish the disposal system in proportion to half-lives of radionuclides and radioactivity concentrations in the wastes. According to this disposal system, the radioactive waste should be buried in the underground near the surface, shallow position and deep position. Therefore, it is important to grasp the features of the earth scientific phenomena and geological structure for the disposal system of radioactive waste. Then, for the purpose of the survey of the geological characteristics around the Japanese Islands whole neighborhood, the earth scientific phenomena at present, the geological structure and geotectonic history were summarized on the basis of the existing literatures. (author)

  5. EnergySolution's Clive Disposal Facility Operational Research Model - 13475

    Energy Technology Data Exchange (ETDEWEB)

    Nissley, Paul; Berry, Joanne [EnergySolutions, 2345 Stevens Dr. Richland, WA 99354 (United States)

    2013-07-01

    EnergySolutions owns and operates a licensed, commercial low-level radioactive waste disposal facility located in Clive, Utah. The Clive site receives low-level radioactive waste from various locations within the United States via bulk truck, containerised truck, enclosed truck, bulk rail-cars, rail boxcars, and rail inter-modals. Waste packages are unloaded, characterized, processed, and disposed of at the Clive site. Examples of low-level radioactive waste arriving at Clive include, but are not limited to, contaminated soil/debris, spent nuclear power plant components, and medical waste. Generators of low-level radioactive waste typically include nuclear power plants, hospitals, national laboratories, and various United States government operated waste sites. Over the past few years, poor economic conditions have significantly reduced the number of shipments to Clive. With less revenue coming in from processing shipments, Clive needed to keep its expenses down if it was going to maintain past levels of profitability. The Operational Research group of EnergySolutions were asked to develop a simulation model to help identify any improvement opportunities that would increase overall operating efficiency and reduce costs at the Clive Facility. The Clive operations research model simulates the receipt, movement, and processing requirements of shipments arriving at the facility. The model includes shipment schedules, processing times of various waste types, labor requirements, shift schedules, and site equipment availability. The Clive operations research model has been developed using the WITNESS{sup TM} process simulation software, which is developed by the Lanner Group. The major goals of this project were to: - identify processing bottlenecks that could reduce the turnaround time from shipment arrival to disposal; - evaluate the use (or idle time) of labor and equipment; - project future operational requirements under different forecasted scenarios. By identifying

  6. Grimsel test site. Research on safe geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    2010-07-01

    The Grimsel Test Site is located at an altitude of 1730 meters in the granitic formations of the Aare Massif. Some 300 million years ago, magmas solidified to form granitic rocks in the Grimsel area. New molten masses flowed into fissures of the cooling rock and formed dyke rocks. During the alpine orogeny around 40 million years ago, the rocks of the Aare Massif were passed over by the northwards-moving alpine layers and subsided by around 12 kilometres. The rocks were then overprinted under high temperature and pressure conditions and shear zones and fracture systems were formed. Uplift (0.5 to 0.8 mm/a) and erosion processes, which are still continuing today, brought the rocks of the Aare Massif to the surface once more. The mineral fractures for which the Grimsel area is famous, formed around 14 million years ago. Deep in the rock, the range of geological conditions found in the laboratory present ideal boundary conditions for investigating the functioning of both the geological and engineered barriers of deep repositories. Projects that look at the disposal concepts on a large scale are also an important aspect of the work at the Test Site. A radiation controlled zone allows radionuclides to be used under monitored conditions, giving a direct insight into the transport of radioactive substances in the rock. Around 25 partner organisations from various countries are involved in the projects at the Test Site. The European Union and the Swiss State Secretariat for Education and Research provide financial support to several experiments. In Switzerland, deep geological disposal is required by law for all types of radioactive waste. Field investigations for determining the suitability of potential disposal sites are an important component of a waste management programme. The field work is complemented by laboratory studies, investigations of relevant natural processes and research projects in underground rock laboratories; these provide a better understanding of the

  7. Grimsel test site. Research on safe geological disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-15

    The Grimsel Test Site is located at an altitude of 1730 meters in the granitic formations of the Aare Massif. Some 300 million years ago, magmas solidified to form granitic rocks in the Grimsel area. New molten masses flowed into fissures of the cooling rock and formed dyke rocks. During the alpine orogeny around 40 million years ago, the rocks of the Aare Massif were passed over by the northwards-moving alpine layers and subsided by around 12 kilometres. The rocks were then overprinted under high temperature and pressure conditions and shear zones and fracture systems were formed. Uplift (0.5 to 0.8 mm/a) and erosion processes, which are still continuing today, brought the rocks of the Aare Massif to the surface once more. The mineral fractures for which the Grimsel area is famous, formed around 14 million years ago. Deep in the rock, the range of geological conditions found in the laboratory present ideal boundary conditions for investigating the functioning of both the geological and engineered barriers of deep repositories. Projects that look at the disposal concepts on a large scale are also an important aspect of the work at the Test Site. A radiation controlled zone allows radionuclides to be used under monitored conditions, giving a direct insight into the transport of radioactive substances in the rock. Around 25 partner organisations from various countries are involved in the projects at the Test Site. The European Union and the Swiss State Secretariat for Education and Research provide financial support to several experiments. In Switzerland, deep geological disposal is required by law for all types of radioactive waste. Field investigations for determining the suitability of potential disposal sites are an important component of a waste management programme. The field work is complemented by laboratory studies, investigations of relevant natural processes and research projects in underground rock laboratories; these provide a better understanding of the

  8. REMEDIAL ACTION, TREATMENT AND DISPOSAL OF HAZARDOUS WASTE: PROCEEDINGS OF THE SIXTEENTH ANNUAL HAZARDOUS WASTE RESEARCH SYMPOSIUM

    Science.gov (United States)

    The Sixteenth Annual Research Symposium on Remedial Action, Treatment and Disposal of Hazardous Waste was held in Cincinnati, Ohio, April 3-5, 1990. he purpose of this Symposium was to present the latest significant research findings from ongoing and recently completed projects f...

  9. Study on disposal method of graphite blocks and storage of spent fuel for modular gas-cooled reactor. Joint research

    Energy Technology Data Exchange (ETDEWEB)

    Sumita, Junya; Sawa, Kazuhiro; Kunitomi, Kazuhiko [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Tsuchie, Yasuo; Urakami, Masao [Japan Atomic Power Co., Tokyo (Japan)

    2003-02-01

    This report describes the result of study on disposal method of graphite blocks in future block-type reactor. Present study was carried out within a framework of joint research, ''Research of Modular High Temperature Gas-cooled Reactors (No. 3)'', between Japan Atomic Energy Research Institute (JAERI) and the Japan Atomic Power Company (JAPCO), in 2000. In this study, activities in fuel and reflector graphite blocks were evaluated and were compared with the disposal limits defined as low-level of radioactive waste. As a result, it was found that the activity for only C-14 was higher than disposal limits for the low-level of radioactive waste and that the amount of air in the graphite is important to evaluate precisely of C-14 activity. In addition, spent fuels can be stored in air-cooled condition at least after two years cooling in the storage pool. (author)

  10. 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)

  11. A top priority problem of national radiation protection - proper disposal of research reactor spent fuel

    International Nuclear Information System (INIS)

    Marinkovic, N.; Matausek, M.V.; Jovic, V.

    1997-01-01

    The paper presents basic facts about RA research reactor at the Vinca Institute. The present state of the RA reactor spent fuel storage pool appears to be a serious safety and radiological problem, which must be solved urgently, independent of the decision about the future status of the reactor itself. The following paragraphs describe current activities on improving storage conditions of the research reactor RA spent fuel. Activities performed so far, concerning identification and improvement of the spent fuel storage conditions are presented. These are verification of radiation protection measures, radiological and chemical analyses, visual inspection and photographing, safety analyses and nuclear criticality studies.A project for long-term solution of the research reactor spent fuel storage is proposed. In order to minimise further corrosion and establish strict control of all the relevant technological parameters of the utility, improvement of conditions for disposal of the fuel in the existing storage, is foreseen in the first phase. New dry storage for long-term storing of the spent fuel should be built during the second phase of the project. Particular attention is paid to the activities related to radiation protection and waste treatment, starting from standard monitoring and control, radiological analyses, regulations and legislation, to complicated handling of high level radioactive waste. (authors)

  12. Treatment and final disposal of nuclear waste. Programme for research, development, demonstration and other measures

    International Nuclear Information System (INIS)

    1992-09-01

    The swedish program for R,D and D on disposal of radioactive waste in an underground repository is presented. Main topics are: Radioactive waste management, storage and disposal; encapsulation; environmental impacts; risk assessment; radionuclide migration; decommissioning; cost and international cooperation. 129 refs, 43 figs, 10 tabs

  13. 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.)

  14. A review of DOE chemical and geochemical research programmes (for disposal of low and intermediate level waste)

    International Nuclear Information System (INIS)

    May, R.

    1987-01-01

    A study of 26 DOE sponsored research programmes has been carried out with respect to their coverage of various chemical and geochemical issues posed by the proposed disposal of low and intermediate level wastes in a land repository. The study also took into account various experimental programmes sponsored by NIREX and abroad. The findings of the study are reported here. (author)

  15. Feasibility of disposal of high-level radioactive waste into the seabed. Volume 1: Overview of research and conclusions

    International Nuclear Information System (INIS)

    1988-01-01

    One of the options suggested for disposal of high-level radioactive waste resulting from the generation of nuclear power is burial beneath the deep ocean floor in geologically stable sediment formations which have no economic value. The 8-volume series provides an assessment of the technical feasibility and radiological safety of this disposal concept on the results obtained by ten years of co-operation and information exchange among the Member countries participating in the NEA Seabed Working Group. This volume provides an overview of the research and a summary of the results

  16. Research on near-surface disposal of very low level radioactive waste

    International Nuclear Information System (INIS)

    Wang Shaowei; Yue Huiguo; Hou Jie; Chen Haiying; Zuo Rui; Wang Jinsheng

    2012-01-01

    Radioactive waste disposal is one of the most sensitive environmental problems to control and solve. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low level radioactive waste and its disposal were introduced, and then siting principles of near-surface disposal of very low level radioactive waste were discussed. The near- surface disposal siting methods of very low level radioactive waste were analyzed from natural and geographical conditions assessment, geological conditions analysis, hydrogeological conditions analysis, geological hazard assessment and radioactive background investigation; the near-surface disposal sites'natural barriers of very low level radioactive waste were analyzed from the crustal structure and physico-chemical characteristics, the dynamics characteristics of groundwater, the radionuclide adsorption characteristics of natural barriers and so on; the near-surface disposal sites' engineered barriers of very low level radioactive waste were analyzed from the repository design, the repository barrier materials selection and so on. Finally, the improving direction of very low level radioactive waste disposal was proposed. (authors)

  17. Research on advanced technology of performance assessment for geological disposal of high-level radioactive waste (Joint research)

    International Nuclear Information System (INIS)

    2006-12-01

    JAEA and RWMC have carried out a joint research program on advanced technologies that could be used to support performance assessments of geological disposal concepts for high-level radioactive waste. The following 5 items were considered in the program: 1) planning of a basic strategy for the development of analysis technologies on nuclide migration over various spatial and temporal scales; 2) development of analysis technologies for vitrified waste scale; 3) development of analysis technologies for repository scale; 4) development of integration technologies for geochemical information; and 5) development of technologies to promote the logical understanding of repository performance and safety. The above items were discussed in the context of technological experiences gained by JAEA and RWMC in previous repository-related studies. According to the results of these discussions, development strategies for each of the technology areas identified above were efficiently formulated by appropriate task allocations. Specific technical subjects requiring further investigation were also identified using this approach, and potential feed-backs from the results of these investigations into the overall research plan and strategy were considered. These specific research and development subjects in the overall strategy defined by this project should be implemented in the future. (author)

  18. Review of the research contract programs in the field of nuclear science and technology (1959-1979)

    Energy Technology Data Exchange (ETDEWEB)

    Bonoan, L S; Marasigan, C J; Relunia, E D [Philippine Atomic Energy Commission, Diliman, Quezon City

    1982-01-01

    This paper presents the 20 year span of cooperative services in the form of research contracts availed of by the country with the International Atomic Energy Agency (IAEA). All research contract grants are placed under the direct supervision of educational institutions, industrial laboratories, research centers and other institutions on areas of direct interest of the Agency's work. These areas are generally in the field of: life sciences with emphasis on medical and agricultural applications, radiation biology; nuclear safety; environmental protection; physical sciences such as physics and chemistry; engineering and technology, with special emphasis on nuclear power. Tables and figures graphically present research contracts grants and field classification.

  19. Cooperative management of nuclear waste disposal in Switzerland

    International Nuclear Information System (INIS)

    Rometsch, R.

    1984-01-01

    Together with the Federal Government, which is responsible for wastes from reactor research and isotope applications, the electricity companies founded in 1972 a national cooperative, NAGRA, with the objective of providing common repositories for radioactive waste products. The author discusses the developments leading to the expansion of NAGRA to allow the letting of research and development contracts in high level radioactive waste disposal. (Auth.)

  20. 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

  1. Evaluating the potential for large-scale fracturing at a disposal vault: an example using the underground research laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Martin, C D; Chandler, N A; Brown, Anton

    1994-09-01

    The potential for large-scale fracturing (> 10 m{sup 2}) around a nuclear fuel waste disposal vault is investigated in this report. The disposal vault is assumed to be located at a depth of 500 m in the plutonic rocks of the Canadian Shield. The rock mass surrounding the disposal vault is considered to have similar mechanical properties and in situ stress conditions to that found at a depth of 420 m at the Underground Research Laboratory. Theoretical, experimental and field evidence shows that Mode I fractures propagate in a plane perpendicular to {sigma}{sub 3} and only if the tensile stress at the tip of the advancing crack is sufficient to overcome the tensile strength of the rock. Because the stress state at a depth of 500 m or more is compressive, and will very probably stay so during the 10,000 year life of the disposal vault, there does not appear to be any mechanism which could propagate large-scale Mode I fracturing in the rock mass surrounding the vault. In addition because {sigma}{sub 3} is near vertical any Mode I fracture propagation that might occur would be in a horizontal plane. The development of either Mode I or large-scale shear fractures would require a drastic change in the compressive in situ stress state at the depth of the disposal vault. The stresses developed as a result of both thermal and glacial loading do not appear sufficient to cause new fracturing. Glacial loading would reduce the shear stresses in the rock mass and hence improve the stability of the rock mass surrounding the vault. Thus, it is not feasible that large-scale fracturing would occur over the 10,000 year life of a disposal vault in the Canadian Shield, at depths of 500 m or greater, where the compressive stress state is similar to that found at the Underground Research Laboratory. 107 refs., 44 figs.

  2. Evaluating the potential for large-scale fracturing at a disposal vault: an example using the underground research laboratory

    International Nuclear Information System (INIS)

    Martin, C.D.; Chandler, N.A.; Brown, Anton.

    1994-09-01

    The potential for large-scale fracturing (> 10 m 2 ) around a nuclear fuel waste disposal vault is investigated in this report. The disposal vault is assumed to be located at a depth of 500 m in the plutonic rocks of the Canadian Shield. The rock mass surrounding the disposal vault is considered to have similar mechanical properties and in situ stress conditions to that found at a depth of 420 m at the Underground Research Laboratory. Theoretical, experimental and field evidence shows that Mode I fractures propagate in a plane perpendicular to σ 3 and only if the tensile stress at the tip of the advancing crack is sufficient to overcome the tensile strength of the rock. Because the stress state at a depth of 500 m or more is compressive, and will very probably stay so during the 10,000 year life of the disposal vault, there does not appear to be any mechanism which could propagate large-scale Mode I fracturing in the rock mass surrounding the vault. In addition because σ 3 is near vertical any Mode I fracture propagation that might occur would be in a horizontal plane. The development of either Mode I or large-scale shear fractures would require a drastic change in the compressive in situ stress state at the depth of the disposal vault. The stresses developed as a result of both thermal and glacial loading do not appear sufficient to cause new fracturing. Glacial loading would reduce the shear stresses in the rock mass and hence improve the stability of the rock mass surrounding the vault. Thus, it is not feasible that large-scale fracturing would occur over the 10,000 year life of a disposal vault in the Canadian Shield, at depths of 500 m or greater, where the compressive stress state is similar to that found at the Underground Research Laboratory. 107 refs., 44 figs

  3. 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

  4. Nuclear waste disposal and terrestrial and radiological research: needs and perspectives

    International Nuclear Information System (INIS)

    Myttenaere, C.; Girardi, F.

    1982-01-01

    The safety assessment of the disposal of nuclear waste is complex. A multi-barrier approach may be adopted. In studying the various options, possible contamination of the environment resulting from a waste repository will have characteristics that are not usually considered in radiological and radioprotection studies. The transport of radioactivity through the geosphere is governed by mechanisms controlling the migration of nuclides leached from the waste by groundwater. Experimental results demonstrate that these mechanisms are complex and consist of several processes not always related to reversible equilibrium reactions (e.g. colloidal filtration). On the other hand, the terrestrial cycle may be capable of altering in the long-term the bio-available fraction of certain radioelements by repeated biological processes. Data on natural long-lived radionuclides in the biosphere have given useful information on trends in long-term behaviour. Moreover, information now becoming available on the impact on mankind contests the validity of the linear no-threshold model for predicting dose/response relationships at low levels of radiation. Risk assessment appears to be an extremely difficult problem; however, by the use of uncertainty and sensitivity analysis of assessment models, the most important processes can probably be identified and research effort promoted. International co-ordination would also be required to obtain, in a reasonable time, the information required. (author)

  5. The French underground research laboratory program, contribution to the feasibility and safety studies of geological disposal

    International Nuclear Information System (INIS)

    Hoorelbeke, J.M.; Niezborala, J.M.; Ben Slimane, K.

    2001-01-01

    The paper presents the content of the research program to be performed during the construction and the operation of the National Agency for Radioactive Waste Management's (ANDRA) underground laboratory, located in the east of France. The general architecture of the program is presented. Emphasis is put on an iterative process, the purpose of which is mainly to: Prepare site behavior models before starting each phase of the field work (bore hole drilling, shaft sinking, construction of underground galleries, specific experiments); Test and check each model through actual observations and measurements; Adjust the models to take into account the results of the former phase and predict the results expected during the following one. All these models, after validation, will be exploited during the assessment of the safety related performance of the components of the potential repository as well as the whole facility; Obtain necessary data related to the feasibility study of the disposal facility (mechanical design, thermal design, etc.,) and its safety assessment. The relationship between the experimental program, the conceptual design program and the safety evaluation program is explained in order to reach the project objectives which is the final document set to be provided to French authorities in 2006 according to the French law of December 1991. (author)

  6. Research and development for treatment and disposal technologies of TRU waste

    International Nuclear Information System (INIS)

    Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Nakanishi, Hiroshi; Sasaki, Ryoichi; Ichige, Satoru; Takahashi, Kuniaki; Meguro, Yoshihiro; Yamaguchi, Hiromi; Aoyama, Yoshio

    2007-09-01

    After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology. (author)

  7. Research on Application of Internet of Things in the Disposal of Environmental Emergency

    Directory of Open Access Journals (Sweden)

    Zhu Yanju

    2015-01-01

    Full Text Available Internet of things is an important part of a new generation of information technology and also an important stage of Information Age. Application of Internet of things in the disposal of environmental emergency is an inevitable trend of application of Internet of things in the field of environmental protection. This paper summarizes the principle, process and application field of Internet of things, and focuses on the general frame-work of environmental emergency disposal system based on Internet of things and further analyses the factors of restricting application of Internet of things in the disposal of environmental emergency. At last, the suggestions and countermeasures to optimize environmental emergency disposal system are proposed.

  8. Big-pharmaceuticalisation: clinical trials and Contract Research Organisations in India.

    Science.gov (United States)

    Sariola, Salla; Ravindran, Deapica; Kumar, Anand; Jeffery, Roger

    2015-04-01

    The World Trade Organisation's Trade Related Intellectual Property Rights [TRIPS] agreement aimed to harmonise intellectual property rights and patent protection globally. In India, the signing of this agreement resulted in a sharp increase in clinical trials since 2005. The Indian government, along with larger Indian pharmaceutical companies, believed that they could change existing commercial research cultures through the promotion of basic research as well as attracting international clinical trials, and thus create an international level, innovation-based drug industry. The effects of the growth of these outsourced and off-shored clinical trials on local commercial knowledge production in India are still unclear. What has been the impact of the increasing scale and commercialisation of clinical research on corporate science in India? In this paper we describe Big-pharmaceuticalisation in India, whereby the local pharmaceutical industry is moving from generic manufacturing to innovative research. Using conceptual frameworks of pharmaceuticalisation and innovation, this paper analyses data from research conducted in 2010-2012 and describes how Contract Research Organisations (CROs) enable outsourcing of randomised control trials to India. Focussing on twenty-five semi-structured interviews CRO staff, we chart the changes in Indian pharmaceutical industry, and implications for local research cultures. We use Big-pharmaceuticalisation to extend the notion of pharmaceuticalisation to describe the spread of pharmaceutical research globally and illustrate how TRIPS has encouraged a concentration of capital in India, with large companies gaining increasing market share and using their market power to rewrite regulations and introduce new regulatory practices in their own interest. Contract Research Organisations, with relevant, new, epistemic skills and capacities, are both manifestations of the changes in commercial research cultures, as well as the vehicles to

  9. Research on Layout Optimization of Urban Circle Solid Waste Transfer and Disposal Stations

    OpenAIRE

    Xuhui Li; Gangyan Li; Guowen Sun; Huiping Shi; Bao’an Yang

    2013-01-01

    Based on the Systematic Layout Planning theory and the analysis of transfer stations’ technological processes, a layout optimization model for solid waste transfer and disposal stations was made. The operating units’ layout of the solid waste transfer and disposal stations was simulated and optimized using the genetic algorithm, which could achieve reasonable technological processes, the smallest floor space and the lowest construction cost. The simulation result can also direct t...

  10. Waste from medicine, industry and research must also be disposed of

    International Nuclear Information System (INIS)

    Issler, H.

    1990-01-01

    Disposal of waste in a manner which is environmentally acceptable is an important political concern of our society today. Nagra has been charged with the resposibility of solving this problem with respect to disposal of radioactive waste in particular. In this context, the fact that radioactive waste also arises from activities other than the operation of nuclear power plants is often overlooked. (author) 7 figs., 3 tabs

  11. Water Resources Research Program. Abatement of malodors at diked, dredged-material disposal sites. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Harrison, W.; Dravnieks, A.; Zussman, R.; Goltz, R.

    1976-06-01

    Samples of malodorous air and dredged material were collected at diked disposal sites at the following locations: Buffalo, NY; Milwaukee, WI; Mobile, AL; York Harbor, ME; Houston, TX; Detroit, MI; and Anacortes, WA; during the period July--October, 1975. Odorous compounds in the air samples were identified by gas chromatography/mass spectrometry, while the detection threshold, intensity, and character of the various odors were determined by experienced panelists using a dynamic, forced-choice-triangle olfactometer. Although significant problems with malodors were not observed beyond the disposal-area dikes during site visits, noteworthy odor episodes had occurred at some sites. An odor-abatement strategy is presented for handling the expected range of odor conditions at dredged-material disposal sites. Its aim is to reduce to an acceptable level the intensity of malodors in an affected community. The main steps in the strategy cover selection of the disposal site, site preparation, odor characterization of sediments to be dredged, malodor abatement during dredging and disposal operations, malodor abatement after filling of the disposal site, and the handling of malodor complaints.

  12. Research and development plans for disposal of high-level and transuranic wastes

    International Nuclear Information System (INIS)

    Bartlett, J.W.; Platt, A.M.

    1978-09-01

    This plan recommends a 20-year, 206 million (1975 $'s) R and D program on geologic structures in the contiguous U.S. and on the midplate Pacific seabed with the objective of developing an acceptable method for disposal of commercial high-level and transuranic wastes by 1997. No differentiation between high-level and transuranic waste disposal is made in the first 5 years of the program. A unique application of probability theory to R and D planning establishes, at a 95% confidence level, that the program objective will be met if at least fifteen generic options and five specific disposal sites are explored in detail and at least two pilot plants are constructed and operated. A parallel effort on analysis and evaluation maximizes information available for decisions on the acceptability of the disposal techniques. Based on considerations of technical feasibility, timing and technical risk, the other disposal concepts, e.g., ice sheets, partitioning, transmutation and space disposal cited in BNWL-1900 are not recommended for near future R and D

  13. Preliminary consideration for research on geological disposal of high-level radioactive waste in China in the period of 2000-2040

    International Nuclear Information System (INIS)

    Xu Guoqing

    2004-01-01

    Based on the overseas practical experiences with combination of domestic realistic conditions a preliminary consideration of a long-range plan is proposed for research on geological disposal of high-level radioactive waste in China in the period of 2000-2040. An overview of research on geological disposal of high-level radioactive waste in the overseas and mainland is presented shortly first in this paper. Then the discussion is centered on the preliminary consideration of a long-range plan for research on geological disposal of high-level radioactive waste in China. The partition of stages of research on geological disposal of high-level radioactive waste, the goal, task, research contents and time table for each research stage is stated in this preliminary consideration. The data mentioned above will probably be useful for making plan for geological disposal of high-level radioactive waste in the future in China. (author)

  14. Rock fracture dynamics research at AECL's Underground Research Laboratory: applications to geological disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Young, R.P. [Univ. of Toronto, Toronto, ON (Canada); Haycox, J.R. [Applied Seismology Consultants Limited, Shrewsbury, Shropshire (United Kingdom); Martino, J. [Atomic Energy of Canada Limited, Pinawa, MB (Canada)

    2011-07-01

    Studies of rock fracture dynamics at AECL's Underground Research Laboratory (URL) have helped to provide a fundamental understanding of how crystalline rock responds to stresses induced from excavation, pressurization and temperature changes. The data acquired continue to provide insights into how a facility for the future geological disposal of radioactive waste could be engineered. Research into microseismic (MS), acoustic emission (AE), and ultrasonic velocity measurements has been performed on the full-scale sealed, pressurized, and heated horizontal elliptical tunnel at the Tunnel Sealing Experiment (TSX). The continuous monitoring of the experiment for 8 years provides a unique dataset for the understanding of the medium-term performance of an engineered disposal facility. This paper summarizes the results, interpretations and key findings of the experiment paying particular focus to the heating and cooling/depressurization of the chamber. Initial drilling of the tunnel and bulkheads causes microfracturing around the tunnel, mapped by MS and AEs, and is used as a benchmark for fracturing representing the excavated damaged zone (EDZ). There is no further extension to the volume during pressurization or heating of the tunnel suggesting an increase in crack density and coalescence of cracks rather than extension into unfractured rock. The dominant structure within the seismic cloud has been investigated using a statistical approach applying the three-point method. MS events in the roof exhibit a dominant pattern of sub-horizontal and shallow-dipping well defined planar features, but during cooling and depressurization a 45 degree dip normal to the tunnel axis is observed, which may be caused by movement in the rock-concrete interface due to differential cooling of the bulkhead and host rock. Cooling and depressurization of the TSX have not led to a significant increase in the number of MS or AE events. Ultrasonic results suggest the rock gets even stiffer

  15. Pilot research projects for underground disposal of radioactive wastes in the United States of America

    International Nuclear Information System (INIS)

    Stein, R.; Collyer, P.L.

    1984-01-01

    Disposal of commercial radioactive waste in the United States of America in a deep underground formation will ensure permanent isolation from the biosphere with minimal post-closure surveillance and maintenance. The siting, design and development, performance assessment, operation, licensing, certification and decommissioning of an underground repository have stimulated the development of several pilot research projects throughout the country. These pilot tests and projects, along with their resulting data base, are viewed as important steps in the overall location and construction of a repository. Beginning in the 1960s, research at pilot facilities has progressed from underground spent fuel tests in an abandoned salt mine to the production of vitrified nuclear waste in complex borosilicate glass logs. Simulated underground repository experiments have been performed in the dense basalts of Washington State, the volcanic tuffaceous rock of Nevada and both domal and bedded salts of Louisiana and Kansas. In addition to underground pilot in situ tests, other facilities have been constructed or modified to monitor the performance of spent fuel in dry storage wells and self-shielded concrete casks. As the National Waste Terminal Storage (NWTS) programme advances to the next stage of underground site characterization for each of three different geological sites, additional pilot facilities are under consideration. These include a Test and Evaluation Facility (TEF) for site verification and equipment performance and testing, as well as a salt testing facility for verification of in situ simulation equipment. Although not associated with the NWTS programme, the construction of the Waste Isolation Pilot Plant (WIPP) in the bedded salts of New Mexico is well under way for deep testing and experimentation with the defence programme's transuranic nuclear waste. (author)

  16. Investigation on proper materials of a liner system for trench type disposal facilities of radioactive wastes from research, industrial and medical facilities

    International Nuclear Information System (INIS)

    Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Arikawa, Masanobu; Sakamoto, Yoshiaki

    2011-08-01

    The Low-level Radioactive Waste Disposal Project Center of Japan Atomic Energy Agency will settle on near surface disposal facilities with and without engineered barriers for radioactive wastes from research, industrial and medical facilities. Both of them are so called 'concrete pit type' and 'trench type', respectively. The technical standard of constructing and operating a disposal facility based on 'Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors' have been regulated partly by referring to that of 'Waste Management and Public Cleansing Law'. This means that the concrete pit type and the trench type disposal facility resemble an isolated type for specified industrial wastes and a non leachate controlled type final disposal site for stable industrial wastes, respectively. On the other, We plan to design a disposal facility with a liner system corresponding to a leachate controlled type final disposal site on a crucial assumption that radioactive wastes other than stable industrial wastes to be disposed into the trench type disposal facility is generated. By current nuclear related regulations in Japan, There are no technical standard of constructing the disposal facility with the liner system referring to that of 'Waste Management and Public Cleansing Law'. We investigate the function of the liner system in order to design a proper liner system for the trench type disposal facility. In this report, We investigated liner materials currently in use by actual leachate controlled type final disposal sites in Japan. Thereby important items such as tensile strength, durability from a view point of selecting proper liner materials were studied. The items were classified into three categories according to importance. We ranked proper liner materials for the trench type disposal facility by evaluating the important items per material. As a result, high density polyethylene(HDPE) of high elasticity type polymetric sheet was selected

  17. Perspectives on past and Present Waste Disposal Practices: A community-Based Participatory Research Project in Three Saskatchewan First Nations Communities

    OpenAIRE

    Rebecca Zagozewski; Ian Judd-Henrey; Suzie Nilson; Lalita Bharadwaj

    2011-01-01

    The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR) was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatche...

  18. Perspectives on Past and Present Waste Disposal Practices: A Community-Based Participatory Research Project in Three Saskatchewan First Nations Communities

    OpenAIRE

    Rebecca Zagozewski; Ian Judd-Henrey; Suzie Nilson; Lalita Bharadwaj

    2011-01-01

    The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR) was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatche...

  19. Contracts for field projects and supporting research on enhanced oil recovery. Progress review No. 78, quarter ending March 31, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    This report presents descriptions of various research projects and field projects concerned with the enhanced recovery of petroleum. Contract numbers, principal investigators, company names, and project management information is included.

  20. Federal Research and Development Contract Trends and the Supporting Industrial Base, 2000-2014

    Science.gov (United States)

    2016-04-30

    Homeland Security, and government-wide services contracting trends; sourcing policy and cost estimation methodologies; and recent U.S. Army modernization ...been fears that the sharp downturn in federal contract obligations would disproportionately impact the R&D contracting portfolios within individual...329 - contracting portfolios , and the industrial base that supports those efforts, within each R&D contracting agency. The main finding of this

  1. INDEFINITE CONTRACT REVIEW 1999 Procedure for Research Physicists (Professional Category 1)

    CERN Multimedia

    1999-01-01

    In view of the long-standing deliberate turnover policy of professional category 1 research physicists on fixed-term contracts, a special procedure is defined, distinct from the other professional categories. This procedure takes into account that research physicists stay at CERN for only up to 6 years and that periods of service as Fellow may be counted within these six years.The following procedure has been agreed:1.\tThe review covers research physicists holding fixed-term contracts and having completed at least 4 years of service on 30 June 1999. Prior years as Fellow may be taken into consideration in the specific context.\tAll candidates are informed individually.2.\tThe files of all candidates are considered by search committees. The members of the committees are nominated by the Director-General and comprise members of the senior CERN staff as well as at least one senior external physicist. The committees are free to take up references and to interview the candidates.3.\tIn ord...

  2. Microbial effects on high-level waste disposal. Research review and perspective

    Energy Technology Data Exchange (ETDEWEB)

    Ohnuki, Toshihiko [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-09-01

    Various microorganisms have been observed in deep geologic formation. The effects of such microorganisms on the performance of HLW disposal are still unknown. This paper reviews the studies of microbial effects on the long-term containment of HLW disposal, and discusses the future work to be carried out. Microbial reduction and oxidation and byproducts derived from microbial activities affect performance of HLW repository and have a potential to enhance actinides migration in geologic formation (degradation of the materials of repository, complex-formation, dissolution of actinides precipitates and occurrence of nm scale colloid formation). Potential microbial perturbation of performance of the barriers may enhance confinement of actinides by biomineralization, bioadsorption, bioaccumulation and precipitation. These studies indicate that further experiments are required to elucidate microbial effects on the performance of HLW disposal. (author)

  3. Research on the assessment technology of the radionuclide inventory for the radioactive waste disposal(I)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. J.; Hong, D. S.; Hwang, G. H.; Shin, J. J.; Yuk, D. S. [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2002-03-15

    Characteristics and states of management of low and intermediate level radioactive waste in site : state of management for each type of wastes, characteristics of low and intermediate level solid radioactive waste, stage of management of low and intermediate level solid radioactive waste. Survey of state of management and characteristics of low and intermediate level radioactive waste disposal facility in foreign countries : state of management of disposal facilities, classification criteria and target radionuclides for assessment in foreign disposal facilities. Survey of the assessment methods of the radionuclides inventory and establishing the direction of requirement : assessment methods of the radionuclides inventory, analysis of radionuclides assay system in KORI site, establishment the direction of requirement in the assessment methods.

  4. The role of research in the development of radioactive waste disposal strategies and routes for the future

    International Nuclear Information System (INIS)

    Orlowski, S.

    1993-01-01

    Hazardous radioactive waste containing natural radionuclides have been generated for nearly a century. The volume cumulated of radioactive wastes over the years has been evaluated at some 2.5 million cubic meters for the USA alone. The electro-nuclear industry, adds to this picture significant amounts of industrial radioactive waste from the early seventies onwards. The volume of these industrial radioactive wastes cumulated since 1960 in the 24 countries concerned worldwide is today reaching the same order of magnitude as the Defence and R and D waste volume. The difference of objectives and a 20 to 30 years delay between the first occurrence of waste produced by the defence and electricity sectors, the emergence of the environmental concern in the early 70's, and last but not least the continuous wastes piling up are among the main circumstances which explain and lead to the following needs: a need for the environmental restoration of old disposal sites, a need for waste minimization to limit the disposal burden under the aspects of safety, and environmental protection, and economies; and finally, a need for an ability - technical and non technical - to dispose of all types of waste. R and D programmes on radioactive waste management and disposal have been heavily financed in most nuclear countries for at least two decades. The role of research for the future shall therefore be carefully considered. Safety and environmental concerns are widespread in the public and should be mitigated by providing additional confidence in existing strategies. 13 refs

  5. Contracts for field projects and supporting research on enhanced oil recovery. Progress review number 83, quarter ending June 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    Summaries of 41 research projects on enhanced recovery are presented under the following sections: (1) chemical flooding; (2) gas displacement; (3) thermal recovery; (4) geoscience technology; (5) resource assessment technology; and (6) reservoir classes. Each presentation gives the title of the project, contract number, research facility, contract date, expected completion data, amount of the award, principal investigator, and DOE program manager, and describes the objectives of the project and a summary of the technical progress.

  6. Research in connexion with the possible disposal of high level radioactive waste on or beneath the ocean floor

    International Nuclear Information System (INIS)

    1983-01-01

    Progress on five research contracts, selection and evaluation of areas and sites, the properties of ocean sediments, biological transfer of materials between seabed and surface, studies of the benthic boundary layer and dispersion in the Northwest Atlantic, is reported. (U.K.)

  7. Disposal project for LLW and VLLW generated from research facilities in Japan: A feasibility study for the near surface disposal of VLLW that includes uranium

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Hasegawa, M.; Sakamoto, Y.; Nakatani, T.

    2016-01-01

    Conclusion and future work: • JAEA plans trench disposal of U-bearing waste with less than 100 Bq/g. • Two safety measures of trench disposal of U-bearing waste have been discussed taking into account increasing radioactivity over a long period of time. 1. First is to carry out dose assessment of site use scenario by using a conservatively stylized condition. 2. Second is to control the average concentration of U in the trench facilities based on the concept of the existing exposure situation. • We are continuously developing the method for safety measures of near surface disposal of VLLW including U-bearing waste.

  8. Research ethics in the era of personalized medicine: updating science's contract with society.

    Science.gov (United States)

    Meslin, Eric M; Cho, Mildred K

    2010-01-01

    With the completed sequence of the human genome has come the prospect of substantially improving the quality of life for millions through personalized medicine approaches. Still, any advances in this direction require research involving human subjects. For decades science and ethics have enjoyed an allegiance reflected in a common set of ethical principles and procedures guiding the conduct of research with human subjects. Some of these principles emphasize avoiding harm over maximizing benefit. In this paper we revisit the priority given to these ethical principles - particularly the principles that support a cautious approach to science - and propose a reframing of the 'social contract' between science and society that emphasizes reciprocity and meeting public needs.

  9. Proceedings of the FNCA 2004 workshop on the utilization of research reactors (Contract research)

    International Nuclear Information System (INIS)

    2006-07-01

    The FNCA 2004 Workshop on the Utilization of Research Reactors, which is the twelfth workshop on the theme of research reactor utilization, was held in Bangkok, Thailand from January 13 to 21, 2005. This workshop was executed based on the agreement in the fifth Coordinator's Meeting of Forum for Nuclear Cooperation in Asia (FNCA) held in Tokyo, March 2004. The workshop consisted of three groups under the themes of the following fields; 1) Neutron Activation Analysis, 2) Research Reactor Technology and 3) Tc-99m Generator Technology. The total number of participants for the workshop was 59 people from 8 countries; China, Indonesia, Korea, Malaysia, the Philippines, Thailand, Vietnam and Japan. This report consists of 6 papers for Neutron Activation Analysis, 5 papers for Research Reactor Technology, 5 Papers for Tc-99m Generator Technology and a summary report. The 15 of the presented papers are indexed individually. (J.P.N.)

  10. Researching the potentials and limitations of contract farming in sub-Saharan Africa

    DEFF Research Database (Denmark)

    Kuzilwa, Joseph A.; Fold, Niels; Henningsen, Arne

    2017-01-01

    Contract farming has received renewed attention recently as developing economies try to grapple with how to transform the agricultural sector and its associated value chains. This book examines different contract arrangements for selected crops, applying both qualitative and quantitative approach...

  11. Radioactive waste processing and disposal

    International Nuclear Information System (INIS)

    1980-01-01

    This compilation contains 4144 citations of foreign and domestic reports, journal articles, patents, conference proceedings, and books pertaining to radioactive waste processing and disposal. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

  12. Proceedings of the FNCA 2006 workshop on the utilization of research reactors (Contract research)

    International Nuclear Information System (INIS)

    2007-09-01

    The FNCA 2006 Workshop on the Utilization of Research Reactors was held in Manila, Philippines from August 28 to September 1, 2006. This workshop was executed based on the agreement in the seventh Coordinator's Meeting of Forum for Nuclear Cooperation in Asia (FNCA) held in Tokyo, Mach 2006. The workshop consisted of three groups under the themes of the following fields; 1) Neutron Activation Analysis, 2) Research Reactor Technology and 3) Tc-99m Generator Technology. The total number of participants for the workshop was 45 people from 9 countries; China, Indonesia, Korea, Malaysia, the Philippines, Thailand, Vietnam, Bangladesh and Japan. This report consists of 10 papers for Neutron Activation Analysis, 7 papers for Tc-99m Generator Technology, 9 papers for Research Reactor Technology and a summary report. (author)

  13. Proceedings of the FNCA 2003 workshop on the utilization of research reactors (Contract research)

    International Nuclear Information System (INIS)

    2006-03-01

    The FNCA 2003 Workshop on the Utilization of Research Reactors, which is the twelfth workshop on the theme of research reactor utilization, was held in Dalat, Vietnam and Jakarta and Serpong, Indonesia from January 12 to 16, 2004. This workshop was executed based on the agreement in the fourth Coordinator's Meeting of Forum for Nuclear Cooperation in Asia (FNCA) held in Tokyo, March 2003. The workshop consisted of four groups under the theme of the following fields; 1) Neutron Activation Analysis, 2) Research Reactors, 3) Tc-99m Generator Technology and 4) Neutron Scattering. The total number of participants for the workshop was 93 people from 8 countries; China, Indonesia, Korea, Malaysia, the Philippines, Thailand, Vietnam and Japan. The 30 of the presented papers are indexed individually. (J.P.N.)

  14. Proceedings of the FNCA 2005 workshop on the utilization of research reactors (Contract research)

    International Nuclear Information System (INIS)

    2007-02-01

    The FNCA 2005 Workshop on the Utilization of Research Reactors, which is the twelfth workshop on the theme of research reactor utilization, was held in Kuala Lumpur, Malaysia from August 8 to 12, 2005. This workshop was executed based on the agreement in the sixth Coordinator's Meeting of Forum for Nuclear Cooperation in Asia (FNCA) held in Tokyo, March 2005. The workshop consisted of three groups under the themes of the following fields; 1) Neutron Activation Analysis, 2) Research Reactor Technology and 3) Tc-99m Generator Technology. The total number of participants for the workshop was 49 people from 8 countries; China, Indonesia, Korea, Malaysia, the Philippines, Thailand, Vietnam and Japan. 17 reports by NAA, 11 reports by RRT, and 15 reports by TCG were presented. This report consists of 5 Papers of those reports from Tc-99m Generator Technology and a summary report. All of these 5 papers are indexed individually. (J.P.N.)

  15. Contracts for field projects and supporting research on enhanced oil recovery. Progress review number 86, quarter ending March 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    Summaries are presented for 37 enhanced oil recovery contracts being supported by the Department of Energy. The projects are grouped into gas displacement methods, thermal recovery methods, geoscience technology, reservoir characterization, and field demonstrations in high-priority reservoir classes. Each summary includes the objectives of the project and a summary of the technical progress, as well as information on contract dates, size of award, principal investigator, and company or facility doing the research.

  16. Rock mechanics issues and research needs in the disposal of wastes in hydraulic fractures

    International Nuclear Information System (INIS)

    Doe, T.W.; McClain, W.C.

    1984-07-01

    The proposed rock mechanics studies outlined in this document are designed to answer the basic questions concerning hydraulic fracturing for waste disposal. These questions are: (1) how can containment be assured for Oak Ridge or other sites; and (2) what is the capacity of a site. The suggested rock mechanics program consists of four major tasks: (1) numerical modeling, (2) laboratory testing, (3) field testing, and (4) monitoring. These tasks are described

  17. Research in the selection of very low level radioactive waste disposal site in southwest China

    International Nuclear Information System (INIS)

    Tuo, Xianguo; Long, Qiong; Zhong, Hongmei; Xu, Zhengqi; Mu, Keliang; Gao, Lan

    2008-01-01

    The ultimate goal of Chinese Radioactive Nuclear Waste Management and Disposal Security is that must use proper and optimized ways to manage radioactive waste and make sure human beings and the environment either at the present or in the future can be free from any unacceptable risks. According to the goal, this paper presents an overview of comprehensive site characterization work that comprises investigations of physical geography, climatology, geology and hydrogeology, as well as geological hazard on two candidate Very Low Level Radioactive Waste (VLLW) disposal sites (Site 1 and Site 2) which are both located in the south west of China. The results showed that there are many similarities in the regional extent of the two sites, but many distinct differences are found in terrain and topographic features, granule stratum, hydraulic gradient, and so on. On the whole, the two alternative sites are in line with the requirements for very low level radioactive waste disposal, and Site 1 is superior to Site 2. (author)

  18. Proceedings of the FNCA 2002 workshop on the utilization of research reactors (Contract research)

    International Nuclear Information System (INIS)

    2004-06-01

    The FNCA 2002 Workshop on the Utilization of Research Reactors, which is the eleventh workshop on the theme of research reactor utilization, was held in Jakarta and Serpong, Indonesia from January 13 to 17. This workshop was executed based on the agreement in the third Coordinator's Meeting of Forum for Nuclear Cooperation in Asia (FNCA) held in Tokyo, March 2002. The workshop consists of two groups under the theme of the following fields; 1) Tc-99m Generator Technology, 2) Neutron Activation Analysis. The total number of participants for the workshop was 88 people from 8 countries; China, Indonesia, Korea, Malaysia, the Philippines, Thailand, Vietnam and Japan. This report consists of 8 papers from the plenary session, 10 papers for Tc-99m Generator, 10 Papers for Neutron Activation Analysis and a summary report. The 28 of the presented papers are indexed individually. (J.P.N.)

  19. Proceedings of the 2001 workshop on the utilization of research reactors (Contract research)

    International Nuclear Information System (INIS)

    2003-03-01

    The 2001 Workshop on the Utilization of Research Reactors, which is the tenth Workshop on the theme of research reactor utilization, was held in Beijing, China from November 5 to 9. This Workshop was executed based on the agreement in the Second Coordinator's Meeting of Forum for Nuclear Cooperation in Asia (FNCA) held in Tokyo, March 2001. The Workshop consists of three groups under the themes of the following fields; 1) Neutron Scattering, 2) Tc Generator, and 3) Neutron Activation Analysis. The total number of participants for the Workshop was about 70 people from 8 countries; China, Indonesia, Korea, Malaysia, the Philippines, Thailand, Vietnam, and Japan. This report consists of 12 papers from the plenary session, 12 papers for Neutron Scattering, 13 papers for Tc Generator, 11 papers for Neutron Activation Analysis and a summary report. The 48 of the presented papers are indexed individually. (J.P.N.)

  20. Perspectives on past and Present Waste Disposal Practices: A community-Based Participatory Research Project in Three Saskatchewan First Nations Communities

    Directory of Open Access Journals (Sweden)

    Rebecca Zagozewski

    2011-01-01

    Full Text Available The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatchewan First Nations Communities. Utilizing a qualitative approach, we aimed to gain an understanding of past and present waste disposal practices and to identify any human and environmental health concerns related to these practices. One to one interviews and sharing circles were conducted with Elders. Elders were asked to share their perspectives on past and present waste disposal practices and to comment on the possible impacts these practices may have on the environment and community health. Historically waste disposal practices were similar among communities. The homeowner generated small volumes of waste, was exclusively responsible for disposal and utilized a backyard pit. Overtime waste disposal evolved to weekly pick-up of un-segregated garbage with waste disposal and open trash burning in a community dump site. Dump site locations and open trash burning were identified as significant health issues related to waste disposal practices in these communities. This research raises issues of inequity in the management of waste in First Nations Communities. It highlights the need for long-term sustainable funding to support community-based waste disposal and management strategies and the development of First Nations centered and delivered educational programs to encourage the adoption and implementation of waste reduction, reutilization and recycling activities in these communities.

  1. Perspectives on past and present waste disposal practices: a community-based participatory research project in three Saskatchewan first nations communities.

    Science.gov (United States)

    Zagozewski, Rebecca; Judd-Henrey, Ian; Nilson, Suzie; Bharadwaj, Lalita

    2011-04-28

    The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR) was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatchewan First Nations Communities. Utilizing a qualitative approach, we aimed to gain an understanding of past and present waste disposal practices and to identify any human and environmental health concerns related to these practices. One to one interviews and sharing circles were conducted with Elders. Elders were asked to share their perspectives on past and present waste disposal practices and to comment on the possible impacts these practices may have on the environment and community health. Historically waste disposal practices were similar among communities. The homeowner generated small volumes of waste, was exclusively responsible for disposal and utilized a backyard pit. Overtime waste disposal evolved to weekly pick-up of un-segregated garbage with waste disposal and open trash burning in a community dump site. Dump site locations and open trash burning were identified as significant health issues related to waste disposal practices in these communities. This research raises issues of inequity in the management of waste in First Nations Communities. It highlights the need for long-term sustainable funding to support community-based waste disposal and management strategies and the development of First Nations centered and delivered educational programs to encourage the adoption and implementation of waste reduction, reutilization and recycling activities in these communities.

  2. Progress of the research and development on the geological disposal technology of HLW with aid of the industry/university collaboration system and fixed term researcher system

    International Nuclear Information System (INIS)

    Yamada, Fumitaka; Sonobe, Hitoshi; Igarashi, Hiroshi

    2008-02-01

    In Japan Atomic Energy Agency (JAEA), various systems associated with the collaboration with industries and universities on the Nuclear Fuel Cycle and the Postdoctoral Fellow system, etc. are enacted. These systems have been operated considering the needs of JAEA's program, industry and academia, resultantly contributed, for example, to basic research and the project development. The activities under these collaboration systems contain personal exchanges, the publication of the accomplishments and utilization of those, in research and development concerning geological disposal technology of high-level radioactive waste (HLW). These activities have progressed in Power Reactor and Nuclear Fuel Development Corporation (PNC) and Japan Nuclear Cycle Development Institute (JNC), which are the successive predecessors of JAEA, through JAEA. The accomplishments from these systems have been not only published as papers in journals and individual technical reports but also integrated into the project reports, accordingly contributed to the advancement of the national program on the geological disposal of HLW. In this report, the progress of the research and development under these systems was investigated from the beginning of the operation of the systems. The contribution to the research and development on geological disposal technology of HLW was also studied. On the basis of these studies, the future utilization of the systems of the collaboration was also discussed from the view point of the management of research and development program. A CD-ROM is attached as an appendix. (J.P.N.)

  3. A comparative analysis of quality management standards for contract research organisations in clinical trials.

    Science.gov (United States)

    Murray, Elizabeth; McAdam, Rodney

    2007-01-01

    This article compares and contrasts the main quality standards in the highly regulated pharmaceutical industry with specific focus on Good Clinical Practice (GCP), the standard for designing, conducting, recording and reporting clinical trials involving human participants. Comparison is made to ISO quality standards, which can be applied to all industries and types of organisation. The study is then narrowed to that of contract research organisations (CROs) involved in the conduct of clinical trials. The paper concludes that the ISO 9000 series of quality standards can act as a company-wide framework for quality management within such organisations by helping to direct quality efforts on a long-term basis without any loss of compliance. This study is valuable because comparative analysis in this domain is uncommon.

  4. Study on applicability of low alkaline cement in Horonobe Underground Research Laboratory project (2) (Contract research)

    International Nuclear Information System (INIS)

    Nakayama, Masashi; Kobayashi, Yasushi; Matsuda, Takeshi; Noda, Masaru; Iriya, Keishiro; Takeda, Nobufumi

    2009-11-01

    In Horonobe Underground Research Center construction of underground facility began in 2005 and a construction practicality test with HFSC (Highly Fly-ash contained Silica-fume Cement) is planned in a part of the gallery. Before the HFSC is used as a tunnel support in the gallery, it is necessary to validate that the HFSC is valid under the actual construction condition. The research results in the FY 2007 are as follows. For evaluating corrosion behavior in the HFSC and the durability of the HFSC, reinforced concrete specimen with HFSC 226 have been exposed to off-shore condition in saline water and splashed zone for 6 years and analyzed the corrosion rate and the amount of chloride intrusion. The durability of the HFSC reinforced concrete was assessed to be more than 50 years until cracking due to corrosion is generated. The pH measurements and the analysis of the chemical composition of solid and liquid phase in the HFSC cocrete-water immersion experiments, which were started in the FY 2002, were carried out. Also for the experiments of cement paste for shotcreting, which were started in the FY 2005, were analyzed. Furthermore, results and findings obtained in earlier studies including this study were summarized, and based on those, method of quality control including test method, frequency, standards etc. was suggested. (author)

  5. Research on changes of nitrate by interactions with metals under the wastes disposal environment containing TRU nuclide. 2

    International Nuclear Information System (INIS)

    Wada, Ryutaro; Nishimura, Tsutomu; Masuda, Kaoru; Fujiwara, Kazuo; Imakita, Tsuyoshi; Tateishi, Tsuyoshi

    2004-02-01

    In TRU wastes, wastes containing nitrate ion as salt exist. In the disposal site environment, this nitrate ion changes into nitrite ion, ammonia, etc., and possibly affects disposal site environmental changes or nuclide migration parameters. In the present research, evaluation was carried out on the chemical interaction between nitrate ion and carbon steel, which is primary reducing agent, under the low-oxygen conditions simulating a disposal site. (1) In the electrochemical test, test data were generated in order to supplement influence parameters required for improvement of the accuracy of the nitrate reaction model (NEON). As the results, it was found that the influence of potential and pH is remarkable, also that of initial nitrate concentration is significant, while the temperature is not remarkable to the nitrate and nitrite reaction themselves. Besides, it was found that the difference in the surface condition of the electrodes is not remarkable. (2) Several long-term reaction tests were carried out to assume the effects of important parameters on the nitrate behavior with carbon steel under low-oxygen high-alkaline type simulated groundwater conditions using glass sealed apparatus (ampoule tests). As the results, it was found that initial nitrate ion concentration and temperature causes the increase of hydrogen generation as well as ammonia generation, while it was found that the difference of carbon steel composition doesn't affect significantly. (3) The parameter fitting NEON was reexamined to improve accuracy, gathering data of electrochemical tests and ampoule tests conducted in 2003 and 2000 through 2002. In addition by comparing the calculation results with experimental results, applicability of NEON was investigated. (4) Implementation of NEON to the mass transfer calculation code was carried out in order to enable the calculation of the nitrate ion behavior including incomings and outgoings of substance to and from the system, resulting in the

  6. Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal. Results of a Coordinated Research Project. Companion CD-ROM

    International Nuclear Information System (INIS)

    2016-05-01

    Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal. It presents the findings of the CRP, the general conclusions and recommendations. The topics covered include, graphite management issues, characterization of irradiated graphite, processing and treatment, immobilization and disposal. Included on the attached CD-ROM are formal reports from the participants

  7. Compilation of contract research for the Materials Engineering Branch, Division of Engineering Technology. Annual report for FY 1982

    International Nuclear Information System (INIS)

    1983-03-01

    This report presents summaries of the research work performed during Fiscal Year 1982 by laboratories and organizations under contracts administered by the NRC's Materials Engineering Branch, Office of Nuclear Regulatory Research. The contractor reports are organized into the major areas of concern to Primary System Integrity: Vessel and Piping Fracture Mechanics; Pressure Vessel Surveillance Dosimetry; Steam Generators and Environmental Cracking; and Nondestructive Examination

  8. Nuclear waste disposal research and studies on natural groundwater colloids in Finland

    International Nuclear Information System (INIS)

    Vuorinen, U.

    1995-01-01

    In Finland there are two programmes carrying out studies on the safe disposal of nuclear fuel. One programme is funded by the nuclear power producing companies and the other one is publicly financed. Different natural sites are being investigated within the two programme of the nuclear power producing companies, while the publicly financed programme is concentrating its investigations on the Finnish natural analogue site at Palmottu. Both programmes are briefly discussed. Within both programmes some studies on natural groundwater colloids have been performed. However, a characterization of organic colloids has been performed on only one occasion so far. The colloid studies and results are discussed. (authors). 8 refs

  9. The Behaviours of Cementitious Materials in Long Term Storage and Disposal of Radioactive Waste. Results of a Coordinated Research Project

    International Nuclear Information System (INIS)

    2013-09-01

    Radioactive waste with widely varying characteristics is generated from the operation and maintenance of nuclear power plants, nuclear fuel cycle facilities, research laboratories and medical facilities. This waste must be treated and conditioned, as necessary, to provide waste forms acceptable for safe storage and disposal. Many countries use cementitious materials (concrete, mortar, etc.) as a containment matrix for immobilization, as well as for engineered structures of disposal facilities. Radionuclide release is dependent on the physicochemical properties of the waste forms and packages, and on environmental conditions. In the use of cement, the diffusion process and metallic corrosion can induce radionuclide release. The advantage of cementitious materials is the added stability and mechanical support during storage and disposal of waste. Long interim storage is becoming an important issue in countries where it is difficult to implement low level waste and intermediate level waste disposal facilities, and in countries where cement is used in the packaging of waste that is not suitable for shallow land disposal. This coordinated research project (CRP), involving 24 research organizations from 21 Member States, investigated the behaviour and performance of cementitious materials used in an overall waste conditioning system based on the use of cement - including waste packaging (containers), waste immobilization (waste form) and waste backfilling - during long term storage and disposal. It also considered the interactions and interdependencies of these individual elements (containers, waste, form, backfill) to understand the processes that may result in degradation of their physical and chemical properties. The main research outcomes of the CRP are summarized in this report under four topical sections: (i) conventional cementitious systems; (ii) novel cementitious materials and technologies; (iii) testing and waste acceptance criteria; and (iv) modelling long

  10. The Behaviours of Cementitious Materials in Long Term Storage and Disposal of Radioactive Waste. Results of a Coordinated Research Project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-09-15

    Radioactive waste with widely varying characteristics is generated from the operation and maintenance of nuclear power plants, nuclear fuel cycle facilities, research laboratories and medical facilities. This waste must be treated and conditioned, as necessary, to provide waste forms acceptable for safe storage and disposal. Many countries use cementitious materials (concrete, mortar, etc.) as a containment matrix for immobilization, as well as for engineered structures of disposal facilities. Radionuclide release is dependent on the physicochemical properties of the waste forms and packages, and on environmental conditions. In the use of cement, the diffusion process and metallic corrosion can induce radionuclide release. The advantage of cementitious materials is the added stability and mechanical support during storage and disposal of waste. Long interim storage is becoming an important issue in countries where it is difficult to implement low level waste and intermediate level waste disposal facilities, and in countries where cement is used in the packaging of waste that is not suitable for shallow land disposal. This coordinated research project (CRP), involving 24 research organizations from 21 Member States, investigated the behaviour and performance of cementitious materials used in an overall waste conditioning system based on the use of cement - including waste packaging (containers), waste immobilization (waste form) and waste backfilling - during long term storage and disposal. It also considered the interactions and interdependencies of these individual elements (containers, waste, form, backfill) to understand the processes that may result in degradation of their physical and chemical properties. The main research outcomes of the CRP are summarized in this report under four topical sections: (i) conventional cementitious systems; (ii) novel cementitious materials and technologies; (iii) testing and waste acceptance criteria; and (iv) modelling long

  11. Research and development on reduced-moderation light water reactor with passive safety features (Contract research)

    International Nuclear Information System (INIS)

    Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; Okumura, Keisuke; Suzuki, Motoe; Mineo, Hideaki; Nakatsuka, Toru

    2004-06-01

    The present report contains the achievement of 'Research and Development on Reduced-moderation Light Water Reactor with Passive Safety Features', which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies. Our development target is 'Reduced-moderation Light Water Reactor with Passive Safety Features' with innovative technologies to achieve above mentioned requirement. Electric power is selected as 300 MWe considering anticipated size required for future deployment. The reactor core consists of MOX fuel assemblies with tight lattice arrangement to increase the conversion ratio. Design targets of the core specification are conversion ratio more than unity, negative void reactivity feedback coefficient to assure safety, discharged burnup more than 60 GWd/t and operation cycle more than 2 years. As for the reactor system, a small size natural circulation BWR with passive safety systems is adopted to increase safety and reduce construction cost. The results obtained are as follows: As regards core design study, core design was performed to meet the goal. Sequence of startup operation was constructed for the RMWR. As the plant design, plant system was designed to achieve enhanced economy using passive safety system effectively. In

  12. Multi-scale analysis of deformation behavior at SCC crack tip (2). (Contract research)

    International Nuclear Information System (INIS)

    Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Hayakawa, Masao; Nagashima, Nobuo

    2007-03-01

    This report describes a result of the research conducted by the Japan Atomic Energy Agency and the National Institute for Materials Science under contract with Japan Nuclear Energy Safety Organization (JNES) that was concerned with a multi-scale analysis of plastic deformation behavior at the crack tip of stress corrosion cracking (SCC). The research was carried out to evaluate the validity of the SCC growth data acquired in the intergranular SCC (IGSCC) project based on a mechanistic understanding of SCC. For the purpose, in this research, analyses of the plastic deformation behavior and microstructure around the crack tip were performed in a nano-order scale. The hardness measured in nano, meso and macro scales was employed as a common index of the strength, and the essential data necessary to understand the SCC propagation behavior were acquired and analyzed that are mainly a size of plastic deformation region and a microstructural information in the region, e.g. data of crystallografy, microscopic deformation and dislocations at the inside of grains and grain boundaries. In this year, we analyzed the state of plastic deformation region at the crack tip of IGSCC under various conditions and investigated relationship between crack growth behavior and stress intensity factor. Especially, we investigated in detail about two different hardened specimens used in the SCC growth tests in the IGSCC project. (J.P.N.)

  13. A study on source term assessment and waste disposal requirement of decontamination and decommissioning for the TRIGA research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Whang, Joo Ho; Lee, Kyung JIn; Lee, Jae Min; Choi, Gyu Seup; Shin, Byoung Sun [Kyunghee Univ., Seoul (Korea, Republic of)

    1999-08-15

    The objective and necessity of the project : TRIGA is the first nuclear facility that decide to decommission and decontamination in our nation. As we estimate the expected life of nuclear power generation at 30 or 40 years, the decommissioning business should be conducted around 2010, and the development of regulatory technique supporting it should be developed previously. From a view of decommissioning and decontamination, the research reactor is just small in scale but it include all decommissioning and decontamination conditions. So, the rules by regulatory authority with decommissioning will be a guide for nuclear power plant in the future. The basis of regulatory technique required when decommissioning the research reactor are the radiological safety security and the data for it. The source term is very important condition not only for security of worker but for evaluating how we dispose the waste is appropriate for conducting the middle store and the procedure after it when the final disposal is considered. The content and the scope in this report contain the procedure of conducting the assessment of the source term which is most important in understanding the general concept of the decommissioning procedure of the decommissioning and decontamination of TRIGA research reactor. That is, the sampling and measuring method is presented as how to measure the volume of the radioactivity of the nuclear facilities. And also, the criterion of classifying the waste occurred in other countries and the site release criteria which is the final step of decommissioning and decontamination presented through MARSSIM. Finally, the program to be applicable through comparing the methods of our nation and other countries ones is presented as plan for disposal of the waste in the decommissioning.

  14. Effect of Contract Research Organization Bureaucracy in Clinical Trial Management: A Model From Lung Cancer.

    Science.gov (United States)

    Gobbini, Elisa; Pilotto, Sara; Pasello, Giulia; Polo, Valentina; Di Maio, Massimo; Arizio, Francesca; Galetta, Domenico; Petrillo, Patrizia; Chiari, Rita; Matocci, Roberta; Di Costanzo, Alessandro; Di Stefano, Teresa Severina; Aglietta, Massimo; Cagnazzo, Celeste; Sperduti, Isabella; Bria, Emilio; Novello, Silvia

    2018-03-01

    Contract research organization (CRO) support is largely included in clinical trial management, although its effect in terms of time savings and benefit has not yet been quantified. We performed a retrospective multicenter analysis of lung cancer trials to explore differences in term of trial activation timelines and accrual for studies with and without CRO involvement. Results regarding study timelines from feasibility data to first patient enrollment were collected from 7 Italian thoracic oncology departments. The final accruals (screened/enrolled patients) are reported. We considered CRO/sponsor-administered and CRO-free trials according to who was responsible for the management of the crucial setup phases. Of 113 trials, 62 (54.9%) were CRO-administered, 34 (30.1%) were sponsor-administered, and 17 (15.0%) were CRO-free. The median time from feasibility invitation to documentation obtainment was 151 days in the CRO-administered trials versus 128 in the sponsor-administered and 120 in the CRO-free trials. The time from document submission to contract signature was 142 days in the CRO-administered versus 128 in the sponsor-administered and 132 in the CRO-free trials. The time from global accrual opening to first patient enrollment was 247 days for the CRO-administered versus 194 in the sponsor-administered and 151 in the CRO-free trials. No significant differences were observed in terms of the median overall timeline: 21 months in the CRO-administered, 15 in the sponsor-administered, and 18 months in the CRO-free studies (P = .29). Although no statistically significant differences were identified, the results of our analysis support the idea that bureaucratic procedures might require more time in CRO-administered trials than in sponsor-administered and CRO-free studies. This bureaucratic delay could negatively affect Italian patients' screening and enrollment compared with other countries. Copyright © 2017 Elsevier Inc. All rights reserved.

  15. Recent Research Status on the Microbes in the Radioactive Waste Disposal and Identification of Aerobic Microbes in a Groundwater Sampled from the KAERI Underground Research Tunnel(KURT)

    International Nuclear Information System (INIS)

    Baik, Min Hoon; Lee, Seung Yeop; Cho, Won Jin

    2006-11-01

    In this report, a comprehensive review on the research results and status for the various effects of microbes in the radioactive waste disposal including definition and classification of microbes, and researches related with the waste containers, engineered barriers, natural barriers, natural analogue studies, and radionuclide migration and retardation. Cultivation, isolation, and classification of aerobic microbes found in a groundwater sampled from the KAERI Underground Research Tunnel (KURT) located in the KAERI site have carried out and over 20 microbes were found to be present in the groundwater. Microbial identification by a 16S rDNA genetic analysis of the selected major 10 aerobic microbes was performed and the identified microbes were characterized

  16. RD and D Programme 98. Treatment and final disposal of nuclear waste. Programme for research, development and demonstration of encapsulation and geological disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    RD and D-Programme 98 is intended to provide an overview of SKBs activities and plans. The detailed research programme is presented in a separate background report. In parallel with RDD-Programme 98, SKB is publishing a number of reports that provide a more thorough background and a more detailed account, particularly on those issues that the Government mentioned in its decision regarding RD and D-Programme 95. The programme is divided into two parts: Background and Execution. The background part begins with a chapter on the basic premises. It deals with general principles, laws and the properties of the waste. The facilities that exist today for dealing with the nuclear waste are also described in the introductory chapter. The two following chapters have to do with the choice between different methods for disposing of nuclear waste and with the KBS-3 method, which SKB has chosen as its main alternative. These two chapters provide a broader account of both the KBS-3 method and different alternative methods than previous RD and D-programmes. The background part concludes with a chapter about the long-term safety of the deep repository. The second part, Execution, begins with an overview of SKBs strategy and the main features of the programme, both for the next few years and further in the future. The plans for siting, technology and safety assessment are then presented in greater detail. This is followed by an overview of our plans for supportive research and development, including continued R and D on other methods than the KBS-3 method. The programme concludes with a chapter on decommissioning of nuclear facilities. An important part of the ongoing and planned work is consultation on environmental impact assessments. A first draft of the contents of future environmental impact statements is therefore provided. By attaching it to RD and D-Programme 98, SKB wishes to give all reviewing bodies an opportunity to offer their viewpoints at an early stage on what future

  17. RD and D Programme 98. Treatment and final disposal of nuclear waste. Programme for research, development and demonstration of encapsulation and geological disposal

    International Nuclear Information System (INIS)

    1998-09-01

    RD and D-Programme 98 is intended to provide an overview of SKBs activities and plans. The detailed research programme is presented in a separate background report. In parallel with RDD-Programme 98, SKB is publishing a number of reports that provide a more thorough background and a more detailed account, particularly on those issues that the Government mentioned in its decision regarding RD and D-Programme 95. The programme is divided into two parts: Background and Execution. The background part begins with a chapter on the basic premises. It deals with general principles, laws and the properties of the waste. The facilities that exist today for dealing with the nuclear waste are also described in the introductory chapter. The two following chapters have to do with the choice between different methods for disposing of nuclear waste and with the KBS-3 method, which SKB has chosen as its main alternative. These two chapters provide a broader account of both the KBS-3 method and different alternative methods than previous RD and D-programmes. The background part concludes with a chapter about the long-term safety of the deep repository. The second part, Execution, begins with an overview of SKBs strategy and the main features of the programme, both for the next few years and further in the future. The plans for siting, technology and safety assessment are then presented in greater detail. This is followed by an overview of our plans for supportive research and development, including continued R and D on other methods than the KBS-3 method. The programme concludes with a chapter on decommissioning of nuclear facilities. An important part of the ongoing and planned work is consultation on environmental impact assessments. A first draft of the contents of future environmental impact statements is therefore provided. By attaching it to RD and D-Programme 98, SKB wishes to give all reviewing bodies an opportunity to offer their viewpoints at an early stage on what future

  18. Study on crystalline rock for evaluating method of long-term behavior. FY2012 (Contract research)

    International Nuclear Information System (INIS)

    Fukui, Katsunori; Hashiba, Kimihiro; Tanno, Takeo; Hikima, Ryoichi; Sanada, Hiroyuki; Sato, Toshinori

    2013-12-01

    Rock shows time-dependent behavior such as creep/relaxation. With respect to high-level radioactive waste disposal, knowledge of the long-term mechanical stability of shafts and galleries excavated in rock are required, over a period of thousands of years after closure as well as during construction and operation. Therefore, it is very important to understand the time-dependent behavior of rock for evaluating long-term mechanical stability. The purpose of this study is to determine the mechanisms of time-dependent behavior of rock by the precise test (e.g. laboratory creep test), observation and measurement and to develop methods for evaluating long-term mechanical stability. In previous works, testing techniques were established and basic evaluation methods were developed. Recently, some parameters, which required for simulation of time-dependent behavior, were determined for the modeling of biotite granite (Toki granite) distributed around the Mizunami underground research laboratory. However, we were not able to obtain enough data to assess the reliability of the method to evaluate these parameters. This report describes the results of the research activities carried out in fiscal year 2012. In Chapter 1, we provide background and an overview of this study. In Chapter 2, the results of a long-term creep test on Tage tuff, started in fiscal year 1997, are described. In Chapter 3, the experimental results concerning the loading-rate dependency of rock strength were examined to understand the time-dependent behavior of rock. In Chapter 4, the stability of tunnels, under conditions which rock stress is larger than that around a circular tunnel, were examined to obtain useful information on the future plan for in-situ tests in the underground research laboratory. (author)

  19. The NEA research and environmental surveillance programme related to sea disposal of low-level radioactive waste

    Science.gov (United States)

    Rugger, B.; Templeton, W. L.; Gurbutt, P.

    1983-05-01

    Sea dumping operations of certain types of packaged low and medium level radioactive wastes have been carried out since 1967 in the North-East Atlantic under the auspices of the OECD Nuclear Energy Agency. On the occasion of the 1980 review of the continued suitability of the North-East Atlantic site used for the disposal of radioactive waste, it was recommended that an effort should be made to increase the scientific data base relating to the oceanographic and biological characteristics of the dumping area. In particular, it was suggested that a site specific model of the transfer of radionuclides in the marine environment be developed, which would permit a better assessment of the potential radiation doses to man from the dumping of radioactive waste. To fulfill these objectives a research and environmental surveillance program related to sea disposal of radioactive waste was set up in 1981 with the participation of thirteen Member countries and the International Laboratory for Marine Radioactivity of the IAEA in Monaco. The research program is focused on five research areas which are directly relevant to the preparation of more site specific assessments in the future. They are: model development; physical oceanography; geochemistry; biology; and radiological surveillance. Promising results have already been obtained and more are anticipated in the not too distant future. An interim description of the NEA dumping site has been prepared which provides an excellent data base for this area.

  20. Low level tank waste disposal study

    Energy Technology Data Exchange (ETDEWEB)

    Mullally, J.A.

    1994-09-29

    Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

  1. Low level tank waste disposal study

    International Nuclear Information System (INIS)

    Mullally, J.A.

    1994-01-01

    Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site

  2. 48 CFR 2845.603 - Disposal methods.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Disposal methods. 2845.603 Section 2845.603 Federal Acquisition Regulations System DEPARTMENT OF JUSTICE Contract Management GOVERNMENT PROPERTY Reporting, Redistribution, and Disposal of Contractor Inventory 2845.603 Disposal methods...

  3. 48 CFR 945.603 - Disposal methods.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Disposal methods. 945.603 Section 945.603 Federal Acquisition Regulations System DEPARTMENT OF ENERGY CONTRACT MANAGEMENT GOVERNMENT PROPERTY Reporting, Redistribution, and Disposal of Contractor Inventory 945.603 Disposal methods. ...

  4. Safe disposal of research reactor RA spent fuel-activities, problems and prospects

    International Nuclear Information System (INIS)

    Matausek, M.V.; Vukadin, Z.; Plecas, I.; Pavlovic, R.; Sotic, O.; Bulkin, S.; Sokolov, A.; Morduhai, A.

    2001-01-01

    In order to improve conditions in the existing temporary spent fuel storage pool, technology was elaborated and equipment was produced and applied for removal of sludge and other debris from the bottom of the pool, filtration of the pool water, sludge conditioning in cement matrix and disposal at the low and medium waste repository at Vinca site. Safety measures and precautions were determined. Subcriticality was proved under normal and/or possible abnormal conditions. In the frame of the joint Yugoslav-Russian project, the technology has been developed and the equipment has been manufactured, tested and applied for underwater inspection the state of spent fuel inside the aluminum barrels. Based on the results of this inspection, a procedure will be proposed for transferring spent fuel to a more reliable storage facility. (author)

  5. Current status and future plan of research and development program related to geological disposal at CEN-SCK

    Energy Technology Data Exchange (ETDEWEB)

    Neerdael, Bernard; Put, Martin [Centre d`Etude de l`Energie Nucleaire, Mol (BBE)

    1994-12-31

    The studies at CEN-SCK related to the R and D of geological disposal are performed within the research unit `waste and disposal` which also deals with the characterization of waste packages and their compatibility with host clay. The in situ test program developed by the underground research facility is shown. The in situ corrosion and leaching test, the combined radiation/heating test CERBERUS, the in situ migration experiment and the geotechnical survey on the gallery structures and their surrounding clay have been continued, and the main achievements until mid 1993 are reported. New actions have been started since 1991 related to hydrogeological modeling, the migration of gas in clay and the `PARCLAY` demonstration test. Besides the periodic measurement of water level in hydrological observation well network, the critical review of the previous regional hydrological modeling has been carried out. Migration studies were extended to the permeation of hydrogen, and the MEGAS project of the modeling and experiment of gas migration was started. Four main experiments, ARCHIMEDES, PHEBUS, BACCHUS 2 and ATLAS, as the international efforts are explained. (K.I.).

  6. Annual report of contract research for the Metallurgy and Materials Research Branch, Division of Reactor Safety Research, Fiscal Year 1977

    International Nuclear Information System (INIS)

    1978-05-01

    Research is reported in the areas of: fracture and structural mechanics; non-destructive testing; steam generator integrity and corrosion; pressure vessel surveillance dosimetry and piping system analysis

  7. Compliance revisited: pharmaceutical drug trials in the era of the contract research organization.

    Science.gov (United States)

    Jonvallen, Petra

    2009-12-01

    Over the past decade, the management of clinical trials of pharmaceuticals has become a veritable industry, as evidenced by the emergence and proliferation of contract research organizations (CROs) that co-ordinate and monitor trials. This article focuses on work performed by one CRO involved in the introduction of new software, modelled on industrial production processes, into clinical trial practices. It investigates how this new management technique relates to the work performed in the clinic to ensure that trial participants comply with the protocol. Using an analytical distinction between 'classical' management work and invisible work, the article contextualizes the meaning of compliance in the clinic and suggests that the work involved in producing compliance should be taken into consideration by those concerned with validity of trials, as clinical trials are put under private industrial management. The article builds on participant observation at a Swedish university hospital and interviews the nurses, dieticians, doctors and a software engineer, all part of a team involved in pharmaceutical drug trials on a potential obesity drug.

  8. Durability test of geomembrane liners presumed to avail near surface disposal facilities for low-level waste generated from research, industrial and medical facilities

    International Nuclear Information System (INIS)

    Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Kurosawa, Ryohei; Sakamoto, Yoshiaki; Kanno, Naohiro; Kashima, Takahiro

    2014-02-01

    The Low-level Radioactive Waste Disposal Project Center will construct near surface disposal facilities for radioactive wastes from research, industrial and medical facilities. The disposal facilities consist of “concrete pit type” for low-level radioactive wastes and “trench type” for very low level radioactive wastes. As for the trench type disposal facility, two kinds of facility designs are on projects – one for a normal trench type disposal facility without any of engineered barriers and the other for a trench type disposal facility with geomembrane liners that could prevent from causing environmental effects of non radioactive toxic materials contained in the waste packages. The disposal facility should be designed taking basic properties of durability on geomembrane liners into account, for it is exposed to natural environment on a long-term basis. This study examined mechanical strength and permeability properties to assess the durability on the basis of an indoor accelerated exposure experiment targeting the liner materials presumed to avail the conceptual design so far. Its results will be used for the basic and detailed design henceforth by confirming the empirical degradation characteristic with the progress of the exposure time. (author)

  9. Preliminary research on groundwater flow characteristics of the low- and Intermediate-level radioactive waste disposal site

    International Nuclear Information System (INIS)

    Koh, Young Kwon; Bae, Dae Seok; Kim, Geon Young; Ryu, Ji Hoon; Park, Kyung Woo; Ji, Sung Hoon; Kim, Kyung Su

    2009-08-01

    Preliminary site survey and candidate survey complements the purpose of the current site selection and disposal place selected for the study because of hydraulic to the geological survey done for the general idea was brought in the field of geochemistry survey was made. Therefore, this report hydraulic - the underlying structure of the model deterministic deformation zone model to focus on the configuration kept, according to data survey by hydraulic and hydraulic rock star pitcher trying to figure out the scope of the structure factors were hydraulic. Groundwater and related land place shares characteristics of the existing data and complementary research and laboratory research performed on the basis of geochemical data, based on the following major finding were present

  10. The AMES Laboratory chemical disposal site removal action: Source removal, processing, and disposal

    International Nuclear Information System (INIS)

    Shirley, R.S.

    1996-01-01

    The Ames Laboratory has historically supported the U.S. Department of Energy (USDOE) and its predecessor agencies by providing research into the purification and manufacturing of high purity uranium, thorium, and yttrium metals. Much of this work was accomplished in the late 1950s and early 1960s prior to the legislation of strict rules and regulations covering the disposal of radioactive and chemical wastes. As a result, approximately 800 cubic meters of low-level radioactive wastes, chemical wastes, and contaminated debris were disposed in nine near surface cells located in a 0.75 hectare plot of land owned by Iowa State University in Ames, Iowa. Under a national contract with the U.S. Army Corps of Engineers (USACE), OHM Remediation Services Corp (OHM) was tasked with providing turnkey environmental services to remove, process, package, transport, and coordinate the disposal of the waste materials and contaminated environmental media

  11. The Ames Laboratory Chemical Disposal Site removal action: Source removal, processing, and disposal

    International Nuclear Information System (INIS)

    Shirley, R.S.

    1995-01-01

    The Ames Laboratory has historically supported the US Department of Energy (USDOE) and its predecessor agencies by providing research into the purification and manufacturing of high purity uranium, thorium, and yttrium metals. Much of this work was accomplished in the late 1950s and early 1960s prior to the legislation of strict rules and regulations covering the disposal of radioactive and chemical wastes. As a result, approximately 800 cubic meters of low-level radioactive wastes, mixed wastes, and contaminated debris were disposed in nine near surface cells located in a 0.75 hectare plot of land owned by Iowa State University in Ames, Iowa. Under a national contract with the US Army Corps of Engineers (USACE), OHM Remediation Services Corp. (OHM) was tasked with providing turnkey environmental services to remove, process, package, transport, and coordinate the disposal of the waste materials and contaminated environmental media

  12. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  13. Research results of sewage sludge and waste oil disposal by entrained bed gasification

    Energy Technology Data Exchange (ETDEWEB)

    Schingnitz, M.; Goehler, P.; Wenzel, W.; Seidel, W. (Noell-DBI Energie- und Entsorgungstechnik GmbH, Freiberg (Germany))

    1992-01-01

    Presents results of gasifying sewage sludge and waste oil with the GSP technology, developed by the Freiberg Fuel Institute (FRG). The GSP reactor was developed in 1976 for gasification of pulverized brown coal. An industrial reactor of this design operated for over 5 years with a total coal throughput of more than 300,000 t. The design of the gasification generator and the flowsheet of a 3 MW experimental pilot plant for waste gasification are presented. The PCB content in the gasification sludge is 6.14 mg/kg, in waste oil - 160 mg/kg. Gasification takes place at high temperatures of more than 1,400 C for complete destruction of toxic pollutants. Gasification results compare composition of raw gas produced by gasification of brown coal, sewage sludge and waste oil. A detailed list of content of pollutants (PCDD, PCDF, PAH, dioxin and furan) in the gasification gas, in process waters and in solid residue of the process water is provided. It is concluded that the GSP gasification process is suitable for safe disposal of waste with toxic content. 3 refs.

  14. Bentonite analogue research related to geological disposal of radioactive waste: current status and future outlook

    Energy Technology Data Exchange (ETDEWEB)

    Reijonen, H.M. [Saanio and Rickkola Oy, Helsinki (Finland); Russel, A.W. [Bedrock Geosciences, Auenstein (Switzerland)

    2015-06-15

    The practice of utilising natural analogues in assessing the long-term behaviour of various components of geological repositories for radioactive waste is already well established in most disposal programmes. Numerous studies on bentonites, focussing on bentonite interaction with other components of the engineered barrier system and a range of host rock environments, are present in the literature. In this article, recent bentonite natural analogue studies are briefly reviewed, and gaps in the current literature identified, with the aim of (1) suggesting where relevant new information could be obtained by data mining published bentonite natural analogue studies with a new focus on current safety case requirements, (2) collecting relevant information by revisiting known bentonite analogue sites and conducting investigations with more appropriate analytical techniques, and (3) identifying novel study sites where, for example, bentonite longevity in very dilute to highly saline groundwater conditions can be studied. It must be noted that the use of natural analogues in safety case development is likely to be site and repository design-specific in nature and thus emphasis is placed on the appropriate use of relevant natural analogue data on bentonite longevity. (authors)

  15. Bentonite analogue research related to geological disposal of radioactive waste: current status and future outlook

    International Nuclear Information System (INIS)

    Reijonen, H.M.; Russel, A.W.

    2015-01-01

    The practice of utilising natural analogues in assessing the long-term behaviour of various components of geological repositories for radioactive waste is already well established in most disposal programmes. Numerous studies on bentonites, focussing on bentonite interaction with other components of the engineered barrier system and a range of host rock environments, are present in the literature. In this article, recent bentonite natural analogue studies are briefly reviewed, and gaps in the current literature identified, with the aim of (1) suggesting where relevant new information could be obtained by data mining published bentonite natural analogue studies with a new focus on current safety case requirements, (2) collecting relevant information by revisiting known bentonite analogue sites and conducting investigations with more appropriate analytical techniques, and (3) identifying novel study sites where, for example, bentonite longevity in very dilute to highly saline groundwater conditions can be studied. It must be noted that the use of natural analogues in safety case development is likely to be site and repository design-specific in nature and thus emphasis is placed on the appropriate use of relevant natural analogue data on bentonite longevity. (authors)

  16. US Geological Survey research in radioactive waste disposal: Fiscal Years, 1983, 1984, and 1985

    International Nuclear Information System (INIS)

    Dinwiddie, G.A.; Trask, N.J.

    1986-01-01

    The USGS has been assisting the DOE in evaluating the suitability of the Yucca Mountain area, located on and adjacent to the Nevada Test Site (NTS) and about 160 km northwest of Las Vegas, as a possible repository site for the disposal of commercially generated high-level radioactive wastes and wastes from DOE facilities. An essential part of this work is defining the geology and hydrology of the area in order to assess the potential for the transport of radionuclides from a repository to the human environment. In addition, the potential for disruption of a repository as a result of volcanic or tectonic activity or accelerated erosion is being evaluated. As part of the Nevada Nuclear Waste Storage Investigations (NNWSI) project, the USGS is performing multi-disciplinary studies involving detailed surface mapping, surface geophysics, exploratory drilling, borehole geophysics, and topical studies of hydrology, climate, and tectonics. Studies are being performed to assess the potential for faulting, damaging earthquakes, recurrence of volcanism, and local acceleration of erosion in parts of the southern Great Basin. Hydrologic investigations are directed to determination of present and past hydrologic regimes of the NTS and vicinity in order to predict the potential for ground-water transport of radioactive waste from a repository in Yucca Mountain to the accessible environment. Paleoclimatic studies are also being performed to aid in predicting future climate in the NTS vicinity

  17. Compilation of contract research for the Chemical Engineering Branch, Division of Engineering Technology. Annual report for FY 1985

    International Nuclear Information System (INIS)

    1986-07-01

    This compilation of annual research reports by the contractors to the Chemical Engineering Branch, DET, is published to disseminate information from ongoing programs and covers research conducted during fiscal year 1985. The programs covered in this document include research on: (1) engineered safety feature (ESF) system effectiveness in terms of fission product retention under severe accident conditions; (2) effectiveness and safety aspects of selected decontamination methods; (3) decontamination impacts on solidification and waste disposal; (4) evaluation of nuclear facility decommissioning projects and concepts, and (5) operational schemes to prevent or mitigate the effects of hydrogen combustion during LWR accidents

  18. Assessment report of research and development on 'geological disposal of high-level radioactive waste' (Interim report)

    International Nuclear Information System (INIS)

    Notoya, Shin; Shimizu, Kazuhiko; Ota, Kunio; Sasao, Eiji

    2010-08-01

    Japan Atomic Energy Agency (JAEA) consulted an assessment committee, 'Evaluation Committee of Research and Development (R and D) Activities for Geological Disposal of High-Level Radioactive Waste', for interim assessment of R and D on high-level radioactive waste disposal in accordance with 'General Guideline for Evaluation of Government R and D Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by Japan. In response to JAEA's request, the Committee assessed mainly the progress of the R and D project according to guidelines, which addressed the rationale behind the R and D project, the relevance of the project outcome and the efficiency of the project implementation during the period of the first midterm plan. As a result, the Committee concluded that the progress of the R and D project is satisfactory. In addition, the Committee provided a couple of issues and suggestions to be addressed in the implementation of the project during the period of the second midterm. A CD-ROM is attached as an appendix. (J.P.N.)

  19. Studies on the reconstruction of the concept of rock mass around the tunnel. Japanese fiscal year, 2013 (Contract research)

    Energy Technology Data Exchange (ETDEWEB)

    Kojima, Keiji [Geospace Laboratory, Tokyo (Japan); Ohnishi, Yuzo [Kansai Univ., Suita, Osaka (Japan); Aoki, Kenji [Geosystem Research Inst., Kyoto (Japan); Tochiyama, Osamu [Nuclear Safety Research Association, Radioactive Waste Disposal Safety Center, Tokyo (Japan); Nishigaki, Makoto [Okayama Univ., Okayama (Japan); Tosaka, Hiroyuki [Tokyo Univ., Tokyo (Japan); Yoshida, Hidekazu [Nagoya Univ., Nagoya, Aichi (Japan); Ogata, Nobuhisa [Japan Atomic Energy Agency, Sector of Decommissioning and Radioactive Waste Management, Tono Geoscience Center, Mizunami, Gifu (Japan)

    2014-09-15

    This report is concerned with research to reconstruct more realistic near-field (NF) concept for the geological disposal. In previous year, we examined the realistic concept for near-field, including rock mass around the tunnel, particularly based on the nuclide migration scenario. The time-series change of the field was divided into five stages of 0 to IV through the process of geological disposal (Excavation, Operation and Post-closure). Then, at each respective stage, post-closure stage in particular; we examined interaction between environmental factors and exhaustive extraction of those factors affecting the near-field, focusing on each scale-time cross-section. Subsequently, we committee, presented tasks for the next fiscal year. This year, to reflect/develop the results obtained from above study, we tried to establish a realistic conceptual model of near-field focusing on, which is among the factors that have been extracted. In addition, Japan Atomic Energy Agency is planning to re-flood studies at the -500m Research Gallery, which leads to the verification of the matters as part of reconstructing practical near-field concept. The committee has conducted this plan and exchanging of views was held among the committee members. Comments on the chapter I from respective members are compiled in Appendix. In chapter II, we discussed and then summarized the 'Realistic conceptual model description of near field focusing on fault and fractures in crystalline rock' described in chapter I. In addition, since the 'Great East Japan Earthquake 2011', a paradigm shift for safety has dramatically changed. In the reconstruction of realistic near-field concept, it is necessary to analyze security matters are unacceptable by society, regarding geological disposal. In the committee, we also exchanged views on those matters and presented the future direction of research and development for geological disposal. (author)

  20. Multi-scale analysis of deformation behavior at SCC crack tip (3) (Contract research)

    International Nuclear Information System (INIS)

    Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Hayakawa, Masao; Nagashima, Nobuo

    2008-08-01

    In recent years, incidents of the stress corrosion cracking (SCC) were frequently reported that occurred to the various components of domestic boiling water reactors (BWR), and the cause investigation and measure become the present important issue. By the Japan nuclear energy safety organization (JNES), a research project on the intergranular SCC (IGSCC) in nuclear grade stainless steels (henceforth, IGSCC project) is under enforcement from a point of view to secure safety and reliability of BWR, and SCC growth data of low carbon stainless steels are being accumulated for the weld part or the work-hardened region adjacent to the weld metal. In the project, it has been an important subject to guarantee the validity of accumulated SCC data. At a crack tip of SCC in compact tension (CT) type specimen used for the SCC propagation test, a macroscopic plastic region is formed where heterogeneity of microstructure developed by microscopic sliding and dislocations is observed. However, there is little quantitative information on the plastic region, and therefore, to assess the data of macroscopic SCC growth rate and the validity of propagation test method, it is essentially required to investigate the plastic region at the crack tip in detail from a microscopic viewpoint. This report describes a result of the research conducted by the Japan Atomic Energy Agency and the National Institute for Materials Science under contract with JNES that was concerned with a multi-scale analysis of plastic deformation behavior at the crack tip of SCC. The research was carried out to evaluate the validity of the SCC growth data acquired in the IGSCC project based on a mechanistic understanding of SCC. For the purpose, in this research, analyses of the plastic deformation behavior and microstructure around the crack tip were performed in a nano-order scale. The hardness measured in nano, meso and macro scales was employed as a common index of the strength, and the essential data necessary

  1. Phenomenological study on crystalline rock for evaluating of long-term behavior (Contract research)

    International Nuclear Information System (INIS)

    Okubo, Seisuke; Seno, Yasuhiro; Hirano, Toru; Matsui, Hiroya; Nakama, Shigeo

    2008-08-01

    The Japan Atomic Energy Agency (JAEA) is conducting the Mizunami Underground Research Laboratory (MIU) Project in order to develop comprehensive geological investigation and engineering techniques for deep underground applications (e.g. repository of HLW). The purpose of this study is to contribute to the evaluation of the mechanical stability of a research drift and to plan the future studies. Rock shows time-dependent behavior such as creep/relaxation. For the shaft and gallery of the geological disposal for the radioactive waste, the mechanical stability over a period of thousands of years is demanded not only during construction and operation but also after back-filling. So, to understand the time-dependent behavior of rock is very important for evaluating the long-term mechanical stability. This study is aiming to find out the mechanism of time-dependent behavior of rock such as creep by the precision test, observation and measurement, to develop the evaluating method of long-term behavior of rock mass, and to get the information for planning the study of the Phase III (Operation Phase) at the Mizunami URL. In the previous work conducted before this fiscal year 2007, we improved the testing technique and started test of Toki granite sampled from target site. Furthermore we studied the in-situ measurement method for evaluating the scatter of rock properties. This report describes the results of the works in the fiscal year 2007. In Chapter 1, we described the overview and background of this study. In Chapter 2, the result of continuing creep test of Tage tuff which was started from the fiscal year 1997 was described. Although there was some annual variability, the precious data were obtained. In Chapter 3, the control program for the generalized relaxation test was developed. The generalized relaxation test of Toki granite was conducted in order to get basically data. In Chapter 4, the extended constitutive equation of variable compliance was analytically

  2. ORNL results for Test Case 1 of the International Atomic Energy Agency's research program on the safety assessment of Near-Surface Radioactive Waste Disposal Facilities

    International Nuclear Information System (INIS)

    Thorne, D.J.; McDowell-Boyer, L.M.; Kocher, D.C.; Little, C.A.; Roemer, E.K.

    1993-01-01

    The International Atomic Energy Agency (IAEA) started the Coordinated Research Program entitled '''The Safety Assessment of Near-Surface Radioactive Waste Disposal Facilities.'' The program is aimed at improving the confidence in the modeling results for safety assessments of waste disposal facilities. The program has been given the acronym NSARS (Near-Surface Radioactive Waste Disposal Safety Assessment Reliability Study) for ease of reference. The purpose of this report is to present the ORNL modeling results for the first test case (i.e., Test Case 1) of the IAEA NSARS program. Test Case 1 is based on near-surface disposal of radionuclides that are subsequently leached to a saturated-sand aquifer. Exposure to radionuclides results from use of a well screened in the aquifer and from intrusion into the repository. Two repository concepts were defined in Test Case 1: a simple earth trench and an engineered vault

  3. Compilation of contract research for the Materials Branch, Division of Engineering Safety: Annual report for FY 1986

    International Nuclear Information System (INIS)

    1987-03-01

    This report presents summaries of the research work performed during Fiscal Year 1986 by laboratories and organizations under contracts administered by the NRC's Materials Branch, Office of Nuclear Regulatory Research. Each contractor has written a more complete and detailed annual report of their work which can be obtained by writing to NRC; however, we believe it is useful to have a summary of each contractor's efforts for the year combined into one volume

  4. 2005 dossier. ANDRA's researches on the geological disposal of high-level and long-lived radioactive wastes. Results and perspectives

    International Nuclear Information System (INIS)

    2005-06-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the geologic disposal of high-level and long-lived radioactive wastes in deep geologic formations (argilites and granites). Content: 1 - Research on deep disposal of radioactive waste: general interest task: Legislative framework, ANDRA scientific objectives, Inspections and assessments; 2 - Designing a safe and reversible disposal system: Repository safety, Reversibility: an essential requirement; 3 - Clay Research on a repository in a clay formation, A long research programme, Dossier 2005 Argile; 4 - Meuse/Haute-Marne site clay: Expected properties of the rock formation, Choice of argillite, Meuse/Haute-Marne site, Conclusions from 10 years of research at the Meuse/Haute-Marne site; 5 - Repository installations: Safe and reversible architecture, Disposal of B waste, Disposal of C waste, Possible disposal of spent fuel (CU); 6 - The disposal facility in operation: From waste packages reception to their disposal in cells, Stages of the progressive closure of engineered structures; 7 - Reversible management: Freedom of choice for future generations, Various closure stages; 8 - Long-term evolution of the repository: Apprehending the repository complexity Main evolutions expected, Slow and limited release of radioactive substances; 9 - Repository safety and impact on man: Several evolution scenarios, Normal evolution, Altered evolution; 10 - Granite Research on a repository in a granite formation: A global approach, Scientific co-operations, Dossier 2005 Granite; 11 - Characteristics of French granite formations: What properties are required for a repository?, Different types of granite formations; 12 - Repository installations: Repository design adapted to granite fractures, Clay seals to prevent water flows, Waste disposal packages ensuring long-term leak-tightness, Physical and chemical environment favourable for waste packages, Architecture

  5. Thermal-hydraulic-geochemical coupled processes around disposed high level nuclear waste in deep granite hosted geological repositories: frontier areas of advanced groundwater research in India

    International Nuclear Information System (INIS)

    Bajpai, R.K.

    2012-01-01

    Indian policy for permanent disposal of high level nuclear wastes with radionuclide having very long half lives include their immobilization in a stable matrix i.e. glasses of suitable composition, its storage in high integrity steel canisters and subsequent disposal in suitable host rock like granites at a depth of 400-500m in stable geological set up. The site for such disposal facilities are selected after vigorous assessment of their stability implying an exhaustive site selection methodology based on a large number of criteria and attributes. In India, an area of about 70000 square kilometers occupied by granites has been subjected to such evaluation for generating comprehensive database on host rock parameters. The sites selected after such intensive analysis are expected to remain immune to processes like seismicity, volcanism, faulting, uplift, erosion, flooding etc. even in distant future spanning over tens of thousands of years. Nevertheless, groundwater has emerged as the only credible pathway through which disposed waste can eventually find its way to accessible biosphere. Hence groundwater research constitutes one of the most important aspects in demonstration of safety of such disposal. The disposed waste due to continuous emission of decay heat creates high temperature field around them with resultant increase in groundwater temperature in the vicinity. Hot groundwater on reacting with steel canisters, backfill clays and cement used around the disposed canister, produces geochemical environment characterized by altered Ph, Eh and groundwater compositions. Acceleration in geochemical interaction among waste-groundwater-clay-cement-granite often results in dissolution or precipitation reactions along the groundwater flow paths i.e. fractures with resultant increase or decrease in their permeability. Thus thermal, hydraulic and geochemical processes work interdependently around the disposed waste. These coupled processes also control the release and

  6. The International Stripa Project: Technology transfer from cooperation in scientific and technological research on nuclear waste disposal

    International Nuclear Information System (INIS)

    Levich, R.A.; Ferrigan, P.M.; Wilkey, P.L.

    1990-01-01

    The Nuclear Energy Agency of the organization for Economic Cooperation and Development (OECD/NEA) sponsors the International Stripa Project. The objectives of the Stripa Project are to develop techniques for characterizing sites located deep in rock formations that are potentially suitable for the geologic disposal of high-level radioactive wastes and to evaluate particular engineering design considerations that could enhance the long-term safety of a high-level radioactive waste repository in a geologic medium. The purpose of this paper is to briefly summarize the research conducted at Stripa and discuss the ways in which the technology developed for the Stripa Project has been and will be transfered to the United States Civilian Radioactive Waste Management Program's Yucca Mountain Project. 3 refs., 2 figs

  7. The use of scientific and technical results from underground research laboratory investigations for the geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    2001-09-01

    The objective of the report is to provide information on the use of results obtained from underground research laboratory investigations for the development of a deep geological repository system for long lived and/or high level radioactive waste including spent fuel. Specifically, it should provide Member States that intend to start development of a geological disposal system with an overview of existing facilities and of the sorts and quality of results that have already been acquired. The report is structured into six main themes: rock characterization methodologies and testing; assessment of the geological barrier; assessment of the engineered barrier system; respository construction techniques; demonstration of repository operations; confidence building and international co-operation

  8. Final report on the IAEA research contracts No. 1194/RB, 1194/R1/RB and 1194/R2/RB

    International Nuclear Information System (INIS)

    Zobor, E.; Janosy, J.S.; Szentgali, A.

    1980-09-01

    The final report summarizes the research activities made in the framework of the IAEA Research Contracts No. 1194/RB, 1194/R1/RB and 1194/R2/RB. A multilevel hierarchical control system is treated which uses weakly-coupled low dimensional subsystems under the supervision of a dynamic coordinator program. This self-organizing adaptive control system was checked by a 5 MW research reactor. As an example the paper describes the experimental computer control system of the 5 MW WWR-SM research reactor, where the reactor power and outlet temperature have been controlled on the basis of the treated control concept since 1978. (author)

  9. Disposal of spent fuel in Olkiluoto bedrock. Programme for research, development and technical design for the pre-construction phase

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    The spent fuel from the nuclear power plants at Olkiluoto and Loviisa will be disposed of in Finnish bedrock. Posiva aims at starting the construction of the disposal facility in the 2010's and the actual disposal operations in 2020. In May 1999 Posiva submitted an application for the so-called Decision-in-Principle (DiP) on the facility to the Finnish Government. According to the application the repository would be based on a KBS-3 type concept and sited at Olkiluoto. The application was approved by the Government in December 2000 and will go next to the Parliament for final approval. However, Posiva has already started the planning for the next programme phase on the assumption that a positive decision will be made. The purpose of the present document is to describe the objectives and major items of research, development, technical planning and design work for the period preceding the construction license. According to the current official guidelines Posiva should prepare for submitting the application for the license in 2010. For the technical development and design work the main target for the starting programme phase is to reach the maturity of design and technical plans that allows the specification of work packages for bid calls and gives sufficient confidence in the technical feasibility of planned operations at the encapsulation facility and in the repository. The main objectives for the complementary characterisation work at Olkiluoto consist of the verification of the present conclusions on site suitability, the definition and identification of suitable rock volumes for repository space and the characterisation of the target host rock for repository design, safety assessment and planning of construction work. The technical design and demonstration work together with the results of complementary site characterisation will provide the basis of the safety case prepared as the support for the construction license application. An integrated safety

  10. Disposal of spent fuel in Olkiluoto bedrock. Programme for research, development and technical design for the pre-construction phase

    International Nuclear Information System (INIS)

    2000-12-01

    The spent fuel from the nuclear power plants at Olkiluoto and Loviisa will be disposed of in Finnish bedrock. Posiva aims at starting the construction of the disposal facility in the 2010's and the actual disposal operations in 2020. In May 1999 Posiva submitted an application for the so-called Decision-in-Principle (DiP) on the facility to the Finnish Government. According to the application the repository would be based on a KBS-3 type concept and sited at Olkiluoto. The application was approved by the Government in December 2000 and will go next to the Parliament for final approval. However, Posiva has already started the planning for the next programme phase on the assumption that a positive decision will be made. The purpose of the present document is to describe the objectives and major items of research, development, technical planning and design work for the period preceding the construction license. According to the current official guidelines Posiva should prepare for submitting the application for the license in 2010. For the technical development and design work the main target for the starting programme phase is to reach the maturity of design and technical plans that allows the specification of work packages for bid calls and gives sufficient confidence in the technical feasibility of planned operations at the encapsulation facility and in the repository. The main objectives for the complementary characterisation work at Olkiluoto consist of the verification of the present conclusions on site suitability, the definition and identification of suitable rock volumes for repository space and the characterisation of the target host rock for repository design, safety assessment and planning of construction work. The technical design and demonstration work together with the results of complementary site characterisation will provide the basis of the safety case prepared as the support for the construction license application. An integrated safety assessment

  11. Phenomenological study on crystalline rock for evaluating of long-term behavior (Contract research)

    International Nuclear Information System (INIS)

    Okubo, Seisuke; Fukui, Katsunori; Hashiba, Kimihiro; Hikima, Ryoichi; Tanno, Takeo; Sanada, Hiroyuki; Matsui, Hiroya; Sato, Toshinori

    2012-02-01

    Rock, under in situ conditions, shows time-dependent behavior such as creep/relaxation. With respect to high-level radioactive waste disposal, knowledge of the long-term mechanical stability of shafts and galleries excavated in rock is required, not only during construction and operation but also over a period of thousands of years after closure. Therefore, it is very important to understand the time-dependent behavior of rock for evaluating long-term mechanical stability. The purpose of this study is determining the mechanisms of time-dependent behavior of rock by precise testing, observation and measurement in order to develop methods for evaluating long-term mechanical stability of a rock mass. In the previous work, testing techniques have been established and basic evaluation methods were developed. Recently, some parameters needed for simulation of time-dependent behavior were determined at the Mizunami underground research facilities. However, sufficient data to check the reliability of the evaluation method for these parameters were not available. This report describes the results of the activities in fiscal year 2010. In Chapter 1, we provide an overview and the background to this study. In Chapter 2, the results of a long-term creep test on Tage tuff, started in fiscal year 1997 are described. In Chapter 3, the relation of loading-rate dependency of strength and stress dependency of creep life, the relation of time dependency, probability distribution and size effects are discussed to indicate more clearly the meaning of the value of 'n' to express the degree of time dependency of the rock. Furthermore, past studies concerning the value of 'n' are reviewed and the tests that could be carried out in future studies of mechanical properties and time dependency of Toki granite are considered in this Chapter. In Chapter 4, failure criterions of a rock mass considering time dependency are discussed. In Chapter 5, the FEM analysis implemented with a generalized

  12. Theoretical study on crystalline rock for evaluating of long-term behavior (Contract research)

    International Nuclear Information System (INIS)

    Ichikawa, Yasuaki; Seno, Yasuhiro; Sato, Toshinori; Nakama, Shigeo

    2008-03-01

    The Japan Atomic Energy Agency (JAEA) is working on the Project of Mizunami Underground Research Laboratory (MIU). The project aims at developing comprehensive techniques of geological investigation and of construction of deep underground space for a repository of HLW and/or TRU. This study contributes to an estimation of long-term stability of underground spaces. Rock materials commonly show time-dependent behavior such as creep and relaxation. The underground structures for geological disposal of radioactive wastes must keep stable not only during construction and operation but also after closing, and then the long-term stability of rock structures (over thousands of years) is essentially important for designing the structures. The true mechanism of time-dependent behavior of rock materials is not yet clearly understood, though the phenomena are widely known. This study aims at elucidating the scientific truth involved in the time-dependent behavior of rock showing creep and relaxation. We used samples of Toki granite and performed precise tests under laser microscope observation, and then developed theories representing the experimental results. These experimental and theoretical results will be served for the design and construction of the Phase III (Operation Phase) of the MIU Project. This is the report worked out in the fiscal year 2006. In this work we performed the following subjects: 1) Uniaxial and stress relaxation tests under observation of a confocal laser scanning microscope (CLSM) by using granite specimens of MIU. 2) Pressure dissolution experiment by using specimens of single crystal quartz and glass beads. 3) Development of the rate of pressure dissolution of quartz and a homogenization analysis for quartz dissolution. In Chapter 2 CLSM was used to acquire clear three-dimensional images of Mizunami granite specimens for uniaxial and stress relaxation tests, and observed the change of microscale structure including the mineral configuration under

  13. Performance of engineered barrier materials in near surface disposal facilities for radioactive waste. Results of a co-ordinated research project

    International Nuclear Information System (INIS)

    2001-11-01

    The primary objectives of the CRP were to: promote the sharing of experiences of the Member States in their application of engineered barrier materials for near surface disposal facilities; help enhance their use of engineered barriers by improving techniques and methods for selecting, planning and testing performance of various types of barrier materials for near surface disposal facilities. The objective of this publication is to provide and overview of technical issues related to the engineered barrier systems and a summary of the major findings of each individual research project that was carried out within the framework of the CRP. This publication deals with a general overview of engineered barriers in near surface disposal facilities, key technical information obtained within the CRP and overall conclusions and recommendations for future research and development activities. Appendices presenting individual research accomplishments are also provided. Each of the 13 appendices was indexed separately

  14. Research on air and missile defense task allocation based on extended contract net protocol

    Science.gov (United States)

    Zhang, Yunzhi; Wang, Gang

    2017-10-01

    Based on the background of air and missile defense distributed element corporative engagement, the interception task allocation problem of multiple weapon units with multiple targets under network condition is analyzed. Firstly, a mathematical model of task allocation is established by combat task decomposition. Secondly, the initialization assignment based on auction contract and the adjustment allocation scheme based on swap contract were introduced to the task allocation. Finally, through the simulation calculation of typical situation, the model can be used to solve the task allocation problem in complex combat environment.

  15. Practical guide on contract of technology

    International Nuclear Information System (INIS)

    Choi, Chiho

    1991-12-01

    This book gives descriptions of practical guide on contract of technology, which deals with basic of contract like meaning, function term, singing and sealing, contract and stamp tax, common things on contract of research like keeping secret and prevention and treat of dispute, compensation for damages, notice, expiration date of contract and measurement at end of contract, contract of joint research such as meaning and necessity, note at contract, check list at contract, and return of the research product.

  16. Suitable Penalty for Breach of Contract: AFROTC Cadets. A Research Report Submitted to the Faculty.

    Science.gov (United States)

    Reese, Robert D.

    A legislative history of financial incentives in the Reserve Officer Training Corps gives perspective to an analysis of present law and policy concerning breach of contract for Air Force ROTC cadets. The changed environment, criticisms of the present law and policy, and the example of three other Western nations with all volunteer militaries are…

  17. Contract Research, Curricular Reform, and Situated Selves: Between Social Justice and Commercialized Knowledge

    Science.gov (United States)

    Sturges, Keith M.

    2014-01-01

    Using a critical ethnographic perspective, I describe how social scientists actively transition into the evaluation industry in a reform environment that is marked by increased privatization of all aspects of public education. I do this by exploring adaptations that contract evaluators use to enhance a sense of personal connection to their work…

  18. 75 FR 18034 - Defense Federal Acquisition Regulation Supplement; Research and Development Contract Type...

    Science.gov (United States)

    2010-04-08

    ... Budget under 44 U.S.C. 3501, et seq. List of Subjects in 48 CFR Parts 234 and 235 Government procurement...). ACTION: Final rule. SUMMARY: DoD is adopting as final, without change, an interim rule that requires the Milestone Decision Authority (MDA) for a major defense acquisition program (MDAP) to select the contract...

  19. Geotechnical aspects of the UK DOE-sponsored radioactive waste disposal research programme

    International Nuclear Information System (INIS)

    Cooling, C.M.; Hudson, J.A.

    1987-01-01

    One of the crucial factors for underground repository design is understanding the engineering properties and behaviour of the host rock. To develop this understanding, the Department of the Environment has sponsored a continuing programme of geotechnical research from 1979 to the present day. The authors describe the structure of the research programme, highlight some of the individual projects, indicate the most important conclusions and provide an overview of both the current state of knowledge and 'the way ahead'. 9 refs.; 9 figs.; 1 table

  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. The Nagra Research, Development and Demonstration (RD and D) plan for the disposal of radioactive waste in Switzerland

    International Nuclear Information System (INIS)

    2009-11-01

    NAGRA's mission is to develop safe geological repositories for all radioactive wastes arising in Switzerland. Two types of repositories are foreseen, one for low and intermediate level waste (L/ILW) and one for spent fuel, vitrified high level waste and long-lived ILW (SF/HLW/ILW). Repository implementation involves a stepwise process that takes several decades, which is presented in the RD and D (research, development and demonstration) plan). The main objective of the RD and D Plan is to establish the purpose, scope, nature and timing of future RD and D activities. Chapter 1 presents the overall objectives of the report and a brief history of the steps leading to the present situation. NAGRA had shown in the project 'Entsorgungsnachweis' (disposal feasibility) that safe disposal of SF/HLW/ILW in Switzerland is technically feasible. Based on this result, the Federal Government initiated the Sectoral Plan for Geological Repositories. This Plan provides a framework within which specific objectives must be met for selecting suitable sites for disposal of both L/ILW and SF/HLW/ILW for which general licence applications are to be made. Stage 1 of the Sectoral Plan results in the selection of geologically suitable siting regions. Chapter 2 presents the overall planning premises for implementation of repositories for L/ ILW and SF/HLW/ILW including the assumed schedule, the waste types and quantities and the safety strategy for the repositories. The time plan includes the general licence procedure, construction and operation of Underground Research Laboratories at the sites, construction licence procedure and the operating licence procedure. It is expected that emplacement of L/ILW could begin in about 2035, whereas SF/HLW emplacement would begin about 2050. Waste emplacement is followed by a monitoring period (planning assumption of 50 years), at the end of which an application would be made for closure. The various waste types and quantities produced by nuclear power

  2. Disposal of Information Seeking and Retrieval Research: Replacement with a Radical Proposition

    Science.gov (United States)

    Budd, John M.; Anstaett, Ashley

    2013-01-01

    Introduction: Research and theory on the topics of information seeking and retrieval have been plagued by some fundamental problems for several decades. Many of the difficulties spring from mechanistic and instrumental thinking and modelling. Method: Existing models of information retrieval and information seeking are examined for efficacy in a…

  3. Neutron-Induced Fission Cross Section of Uranium, Americium and Curium Isotopes. Progress report - Research Contract 14485, Coordinated Research Project on Minor Actinide Neutron Reaction Data (MANREAD)

    International Nuclear Information System (INIS)

    Alekseev, A.A.; Bergman, A.A.; Berlev, A.I.; Koptelov, E.A.; Samylin, B.F.; Trufanov, A.M.; Fursov, B.I.; Shorin, V.S.

    2009-12-01

    This report contains brief description of the Lead Slowing Down Spectrometer and results of measurements of neutron-induced fission cross sections for 236 U, 242m Am, 243 Cm, 244 Cm, 245 Cm and 246 Cm done at this spectrometer. The work was partially supported through the IAEA research contract RC-14485-RD in the framework of the IAEA Coordinated Research Project 'Minor Actinide Neutron Reaction Data (MANREAD)'. The detailed description of the experimental set up, measurements procedure and data treatment can be found in the JIA-1182 (2007) and JIA-1212 (2009) reports from the Institute of Nuclear Research of the Russian Academy of Science published in Russian. Part 1 contains the first year report of the research contract and part 2 the second year report. (author)

  4. Research study for extremely unlikely scenario of high level waste disposal: Part 3

    International Nuclear Information System (INIS)

    Ohkubo, Hiroo

    1999-02-01

    In this research, first, event and process relevant to the key words (or scenario initiator) such as volcanism have been identified and, especially a middle-scale eruption scenario including pyroclastic flows has been analyzed as the catastrophic scenario, which inspires ordinary people to have tremendous concern. Secondly, based upon the characteristic events and processes of each scenario considered in the above and through the research of existing model of such risk, quantitative concept (release amount magnitude, release mode, release form, frequency of release, probability etc.) and impact on repository system, facility and environment have been analyzed, defended and defined. Model which can assess and analyze such impact has been built. Using these models, risks directly or indirectly caused by HLW repository have been calculated. Finally, the process for assessing the consequence of volcanism scenario and its risk calculated by the model developed in the above have been visualized, and presented by comparing with other risks. (author)

  5. Radioactive Waste Management - Community Policy and Research Initiatives. The sixth international conference on the management and disposal of radioactive waste - Euradwaste '04

    Energy Technology Data Exchange (ETDEWEB)

    Forsstroem, Hans [Research Directorate Energy, Nuclear Fission and Radiation Protection, European Commission, MO-75 5/37, 200 avenue de la Loi, B-1049 Brussels (Belgium); Ruiz, P Fernandez [DG Research, Energy, Consejo de Seguridad Nuclear, CSN, C/ Justo Dorado, 11, E-28040 Madrid (Spain)

    2004-07-01

    The sixth international conference on the management and disposal of radioactive waste organized be European Commission, held on 29-31 March 2004 in Luxembourg aimed to cover the following objectives: - To present EC policy in waste management, in particular the proposed 'Directive on the Management of Spent Nuclear Fuel and Radioactive Waste' and to discuss relating issues such as the effect on national programmes, site selection, EU added value, the case for EU safety standards, and various socio-political aspects; - To highlight the main results of the Fifth Framework Programme (FP5) of EURATOM for 'Nuclear Energy, Fission Research and Training Activities' in the field of waste in spent fuel management and disposal, and partitioning and transmutation; - To present examples of activities under FP5 and to discuss further research European integration through FP6. The program was divided into two main groups: 1. 'Community Policy and Socio-Political Aspects' which included sessions on community policy initiatives, disposal option, common safety standards and public involvement and acceptance; 2. 'Community Research Activities - FP5' which included sessions on partitioning and transmutation, geological disposal and research networking. There were 29 oral presentations and 36 poster presentations which, for the latter, allowed detailed presentations of the results of the EU-funded research projects. The conference was attended by some 240 participants from 27 countries.

  6. Radioactive Waste Management - Community Policy and Research Initiatives. The sixth international conference on the management and disposal of radioactive waste - Euradwaste '04

    Energy Technology Data Exchange (ETDEWEB)

    Forsstroem, Hans [Research Directorate Energy, Nuclear Fission and Radiation Protection, European Commission, MO-75 5/37, 200 avenue de la Loi, B-1049 Brussels (Belgium); Ruiz, P. Fernandez (ed.) [DG Research, Energy, Consejo de Seguridad Nuclear, CSN, C/ Justo Dorado, 11, E-28040 Madrid (Spain)

    2004-07-01

    The sixth international conference on the management and disposal of radioactive waste organized be European Commission, held on 29-31 March 2004 in Luxembourg aimed to cover the following objectives: - To present EC policy in waste management, in particular the proposed 'Directive on the Management of Spent Nuclear Fuel and Radioactive Waste' and to discuss relating issues such as the effect on national programmes, site selection, EU added value, the case for EU safety standards, and various socio-political aspects; - To highlight the main results of the Fifth Framework Programme (FP5) of EURATOM for 'Nuclear Energy, Fission Research and Training Activities' in the field of waste in spent fuel management and disposal, and partitioning and transmutation; - To present examples of activities under FP5 and to discuss further research European integration through FP6. The program was divided into two main groups: 1. 'Community Policy and Socio-Political Aspects' which included sessions on community policy initiatives, disposal option, common safety standards and public involvement and acceptance; 2. 'Community Research Activities - FP5' which included sessions on partitioning and transmutation, geological disposal and research networking. There were 29 oral presentations and 36 poster presentations which, for the latter, allowed detailed presentations of the results of the EU-funded research projects. The conference was attended by some 240 participants from 27 countries.

  7. Radioactive waste handling and disposal at King Faisal Specialist Hospital and Research Centre.

    Science.gov (United States)

    Al-Haj, Abdalla N; Lobriguito, Aida M; Al Anazi, Ibrahim

    2012-08-01

    King Faisal Specialist Hospital & Research Centre (KFSHRC) is the largest specialized medical center in Saudi Arabia. It performs highly specialized diagnostic imaging procedures with the use of various radionuclides required by sophisticated dual imaging systems. As a leading institution in cancer research, KFSHRC uses both long-lived and short-lived radionuclides. KFSHRC established the first cyclotron facility in the Middle East, which solved the in-house high demand for radionuclides and the difficulty in importing them. As both user and producer of high standard radiopharmaceuticals, KFSHRC generates large volumes of low and high level radioactive wastes. An old and small radioactive facility that was used for storage of radioactive waste was replaced with a bigger warehouse provided with facilities that will reduce radiation exposure of the staff, members of the public, and of the environment in the framework of "as low as reasonably achievable." The experiences and the effectiveness of the radiation protection program on handling and storage of radioactive wastes are presented.

  8. Experience and related research and development in applying corrective measures at the major low-level radioactive waste disposal sites

    International Nuclear Information System (INIS)

    Rose, R.R.; Mahathy, J.M.; Epler, J.S.; Boing, L.E.; Jacobs, D.G.

    1983-07-01

    A review was conducted of experience in responding to problems encountered in shallow land burial of low-level radioactive waste and in research and development related to these problems. The operating histories of eleven major disposal facilities were examined. Based on the review, it was apparent that the most effective corrective measures administered were those developed from an understanding of the site conditions which caused the problems. Accordingly, the information in this document has been organized around the major conditions which have caused problems at existing sites. These include: (1) unstable trench cover, (2) permeable trench cover, (3) subsidence, (4) ground water entering trenches, (5) intrusion by deep-rooted plants, (6) intrusion by burrowing animals, and (7) chemical and physical conditions in trench. Because the burial sites are located in regions that differ in climatologic, geologic, hydrologic, and biologic characteristics, there is variation in the severity of problems among the sites and in the nature of information concerning corrective efforts. Conditions associated with water-related problems have received a great deal of attention. For these, corrective measures have ranged from the creation of diversion systems for reducing the contact of surface water with the trench cover to the installation of seals designed to prevent infiltration from reaching the buried waste. On the other hand, corrective measures for conditions of subsidence or of intrusion by burrowing animals have had limited application and are currently under evaluation or are subjects of research and development activities. 50 references, 20 figures, 10 tables

  9. Laboratory directed research and development on disposal of plutonium recovered from weapons. FY1994 final report

    International Nuclear Information System (INIS)

    Pitts, J.H.; Choi, J.S.

    1994-01-01

    This research project was conceived as a multi-year plan to study the use of mixed plutonium oxide-uranium oxide (MOX) fuel in existing nuclear reactors. Four areas of investigation were originally proposed: (1) study reactor physics including evaluation of control rod worth and power distribution during normal operation and transients; (2) evaluate accidents focusing upon the reduced control rod worth and reduced physical properties of PuO 2 ; (3) assess the safeguards required during fabrication and use of plutonium bearing fuel assemblies; and (4) study public acceptance issues associated with using material recovered from weapons to fuel a nuclear reactor. First year accomplishments are described. Appendices contain 2 reports entitled: development and validation of advanced computational capability for MOX fueled ALWR assembly designs; and long-term criticality safety concerns associated with weapons plutonium disposition

  10. The role of research programs and commercial contracts for increase of economic competitiveness and development at INR Pitesti

    International Nuclear Information System (INIS)

    Petra, Nicoleta Mihaela; Ionila, Maria; Datcu, Mirela; Balan, Iosif Bogdan; Cretu, Ileana

    2008-01-01

    In the period in which globalization is increasing, one of the strategic objectives of the institute is to focus on those activities which help developing of services, products and technologies, applicable in nuclear industry, environment protection and medicine. One way to sustain INR activity is the technological transfer which ensures availability of research results by carrying out of R and D contracts in priority areas and of contracts with economical agents for the supply of services, products, technologies, such as: - Materials irradiation for medicine, industry and research; - Neutron Activation Analysis (NAA) and prompt gamma spectrometry for Cernavoda NPP - Unit 1; - Control and testing: non-destructive examination, functional tests of samples and equipment from Cernavoda NPP - Unit 1; - Characterization, conditioning and treatment of radioactive wastes for NPP- Cernavoda, Unit 1, Nuclear Fuel Plant (FCN) - Pitesti; - Measurement of isotopes concentration in environmental samples; -Corrosion experiments in static autoclaves and experiments regarding microbial corrosion for NPP Cernavoda Unit 1 and FCN Pitesti; - Nuclear consultancy for Cernavoda NPP - Unit 1 and Unit 2; - Stainless steel casks for radwaste; - Containers for heavy water; - Training and practice for students at the Universities of Pitesti, Bucuresti, Brasov. The paper presents the main areas where the results obtained in R and D programs can be applied, their implementation can be done, and the status of contracts and their importance for INR Pitesti and Romanian society development, as well. (authors)

  11. Safety cases for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

    International Nuclear Information System (INIS)

    Kozak, M.W.; Torres-Vidal, C.; Kelly, E.; Guskov, A.; Blerk, J. van

    2002-01-01

    A Co-ordinated Research Project (CRP) has recently been completed on the Improvement of Safety Assessment Methodologies for Near-Surface Radioactive Waste Disposal Facilities (ISAM). A major aspect of the project was the use of safety cases for the practical application of safety assessment. An overview of the ISAM safety cases is given in this paper. (author)

  12. Status report on research at the Institute of Oceanographic Sciences related to the possible disposal of radioactive waste on or beneath the seafloor April 1979 - March 1984

    International Nuclear Information System (INIS)

    Booty, B.

    1985-01-01

    This report summarises all of the research carried out by the Institute of Oceanographic Sciences in connection with the possible disposal of radioactive waste at sea. It covers the period April 1 1979 to March 31 1984. All the work mentioned here is reported upon, usually in much greater detail, in a series of individual reports. (author)

  13. The search for a final disposal site as field of conflict. A proposition for a profile of a problem-oriented sociological repository research

    International Nuclear Information System (INIS)

    Hocke, P.

    2005-01-01

    The search for a final disposal site for high-level nuclear waste in Germany is to characterize as an enduring and politicised conflict causing a blocked process of decision making. A social science based research on final disposals, reflecting this stalemate situation in Germany, did not take place since the middle of the 1980s. This ITAS paper presents a proposal, how - by the means of social science - the chances and risks for further decision making about nuclear waste could be articulated more precise. (orig.)

  14. The application of isotopic technique to the hydrogeological condition research in a nuclear waste disposal site

    International Nuclear Information System (INIS)

    Xiao Feng; Wang Zhiming; Li Sen

    1995-01-01

    Through the research on chemical compositions of various kinds of ground water, hydrogen and oxygen stable isotopes and radioactive isotopes in ground water in the study area, the shallow underground water (pore water) and the weathering fissure water in bedrock are distinguished. It is determined that the recharge area of ground water is the Paiyashan area. The main direction for the surface water and ground water runoff is SE-striking, in the meantime the lateral migration of ground water exists and recharges the shallow water and surface water in the form of springs. Based on the decay calculation of tritium and compared with the data from Hongkong observation station, the relative ages of water in the area have been established and they are divided into 3 age groups: (1) ground water with the shortest runoff time, having tritium concentration identical to that of recent meteoric water; (2) shallow ground water with the relative age of about 20 years; (3) low tritium water with the relative age of more than 30 years

  15. Corrosion research of alloys for use in nuclear waste disposal canisters

    International Nuclear Information System (INIS)

    Sorensen, N.R.; Diegle, R.B.

    1984-01-01

    All tests involving the corrosion behavior of TiCode-12 (Ti-0.3Mo-0.8Ni) indicate that this alloy is a suitable choice for the containment of nuclear wastes. Although cracking was observed under conditions of hydrogen embrittlement, and pitting occurred in aggressive media, the conditions which produce these two failure modes represented severe overtests and are not expected in a repository. Both Mo and Ni increase the degree of corrosion resistance of Ti alloys. Mo changes the nature of the oxide, while Ni forms intermetallic precipitates which, through galvanic coupling, polarize the Ti into the passive region. All alternate alloys tested (including cast iron) exhibit acceptable corrosion behavior relative to their role as backup canister materials. In the case of cast iron, the material provides for a corrosion allowance design in contrast to the corrosion resistant design offered by Ti alloys. The effects of gamma irradiation still need to be adequately characterized. Research on such effects is underway at Sandia and the University of Minnesota. 11 references, 5 figures, 1 table

  16. Final disposal of high-level radioactive waste in deep boreholes. An evaluation based on recent research on the bedrock at great depths

    International Nuclear Information System (INIS)

    Aahaell, Karl-Inge

    2006-05-01

    New knowledge in hydrogeology and boring technology have opened the possibility to use deep boreholes as a repository for the Swedish high-level radioactive wastes. The determining property is that the repository can be housed in the stable bedrock at levels where the ground water has no contact with the biosphere and disposal and sealing can take place without disturbing the ground water stratification outside the disposal area. An advantage compared to a shallow repository of KBS-3 type, that is now being planned in Sweden, is that a borehole repository is likely to be technologically more robust, since the concept 'deep boreholes' seems to admit such a deep disposal that the entire disposal area would be surrounded by stable density-layered ground water, while a KBS-3 repository would be surrounded by moving ground water in contact with level close to the surface. This hydrological difference is of great importance for the safety in scenarios with leaching of radioactive substances. A deep repository is also less vulnerable for effects from natural events such as glaciation and earthquakes as well as from technological mishaps and terrorist actions. A crucial factor is, however, that the radioactive waste can be disposed of, in a secure way, at the intended depth, which will require new research and technology development

  17. Study on systemizing technology on investigation and analysis of deep underground geological environment. Japanese fiscal year, 2007 (Contract research)

    International Nuclear Information System (INIS)

    Kojima, Keiji; Ohnishi, Yuzo; Aoki, Kenji; Watanabe, Kunio; Nishigaki, Makoto; Tosaka, Hiroyuki; Shimada, Jun; Tochiyama, Osamu; Yoshida, Hidekazu; Ogata, Nobuhisa; Nishio, Kazuhisa

    2009-03-01

    In this year, the following studies were carried out with the aim of systemizing the technology on the investigation and analysis to understand the deep underground geological environment in relation to the radioactive waste disposal. (1) The study on the research and development (R and D) subjects which turned to the practical investigation and analysis of deep underground geological environment. (2) The study on the advanced technical basis for the investigation and analysis of deep underground geological environment. The results obtained from the studies are as follows: Regarding (1), the specific investigations, measurements and numerical and chemical analyses were performed particularly for research subjects: 1) engineering technology and 2) geological environment. Based on the results on (1), 3) tasks of collaboration research on intermediate area between the research fields, including the safety assessment field, were selected. Also redefinition of the NFC (Near Field Concept) were discussed. Regarding (2), based on the extracted tasks of JAEA (Japan Atomic Energy Agency) research project, the study was implemented considering previous R and D results and detailed research at the research field was carried out. This study contributed to the R and D development for its practical application. Concurrently, information exchange and discussion on the 2nd phase (the Construction Phase) of the MIU (Mizunami Underground Research Laboratory) research program were often held. (author)

  18. Results of hydrologic research at a low-level radioactive-waste disposal site near Sheffield, Illinois

    Science.gov (United States)

    Ryan, Barbara J.

    1989-01-01

    Ten years of hydrologic research have been conducted by the U.S. Geological Survey at a commercial low-level radioactive-waste disposal site near Sheffield, Illinois. Research included studies of microclimate, evapotranspiration, and tritium release by plants; runoff and land modification; water movement through a trench cover; water and tritium movement in the unsaturated zone; gases in the unsaturated zone; water and tritium movement in the saturated zone; and water chemistry. Implications specific to each research topic and those based on overlapping research topics are summarized as to their potential effect on the selection, characterization, design, operation, and decommissioning processes of future low-level radioactive-waste disposal sites. Unconsolidated deposits at the site are diverse in lithologic character and are spatially and stratigraphically complex. Thickness of these Quaternary deposits ranges from 3 to 27 meters and averages 17 meters. The unconsolidated deposits overlay 140 meters of Pennsylvanian shale, mudstone, siltstone, and coal. Approximately 90,500 cubic meters of waste were buried from August 1967 through August 1978, in 21 trenches that were constructed in glacial materials by using a cut-and-fill process. Trenches generally were constructed below grade and ranged from 11 to 180 meters long, 2.4 to 21 meters wide, and 2.4 to about 7.9 meters deep. Research on microclimate and evapotranspiration at the site was conducted from July 1982 through June 1984. Continuous measurements were made of precipitation, incoming and reflected solar (shortwave) radiation, incoming and emitted terrestrial (longwave) radiation, horizontal windspeed and direction, wet- and dry-bulb air temperature, barometric pressure, soil-heat fluxes, and soil temperature. Soil-moisture content, for this research phase, was measured approximately biweekly. Evapotranspiration rates were estimated by using three techniques--energy budget, aerodynamic profile, and water

  19. On area-specific underground research laboratory for geological disposal of high-level radioactive waste in China

    Directory of Open Access Journals (Sweden)

    Ju Wang

    2014-04-01

    Full Text Available Underground research laboratories (URLs, including “generic URLs” and “site-specific URLs”, are underground facilities in which characterisation, testing, technology development, and/or demonstration activities are carried out in support of the development of geological repositories for high-level radioactive waste (HLW disposal. In addition to the generic URL and site-specific URL, a concept of “area-specific URL”, or the third type of URL, is proposed in this paper. It is referred to as the facility that is built at a site within an area that is considered as a potential area for HLW repository or built at a place near the future repository site, and may be regarded as a precursor to the development of a repository at the site. It acts as a “generic URL”, but also acts as a “site-specific URL” to some extent. Considering the current situation in China, the most suitable option is to build an “area-specific URL” in Beishan area, the first priority region for China's high-level waste repository. With this strategy, the goal to build China's URL by 2020 may be achieved, but the time left is limited.

  20. RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-09-01

    SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another new

  1. RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-09-01

    SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another

  2. RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

    International Nuclear Information System (INIS)

    2004-09-01

    SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another new

  3. Study on the fuel cycle cost of gas turbine high temperature reactor (GTHTR300). Contract research

    Energy Technology Data Exchange (ETDEWEB)

    Takei, Masanobu; Katanishi, Shoji; Nakata, Tetsuo; Kunitomi, Kazuhiko [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Oda, Takefumi; Izumiya, Toru [Nuclear Fuel Industries, Ltd., Tokyo (Japan)

    2002-11-01

    In the basic design of gas turbine high temperature reactor (GTHTR300), reduction of the fuel cycle cost has a large benefit of improving overall plant economy. Then, fuel cycle cost was evaluated for GTHTR300. First, of fuel fabrication for high-temperature gas cooled reactor, since there was no actual experience with a commercial scale, a preliminary design for a fuel fabrication plant with annual processing of 7.7 ton-U sufficient four GTHTR300 was performed, and fuel fabrication cost was evaluated. Second, fuel cycle cost was evaluated based on the equilibrium cycle of GTHTR300. The factors which were considered in this cost evaluation include uranium price, conversion, enrichment, fabrication, storage of spent fuel, reprocessing, and waste disposal. The fuel cycle cost of GTHTR300 was estimated at about 1.07 yen/kWh. If the back-end cost of reprocessing and waste disposal is included and assumed to be nearly equivalent to LWR, the fuel cycle cost of GTHTR300 was estimated to be about 1.31 yen/kWh. Furthermore, the effects on fuel fabrication cost by such of fuel specification parameters as enrichment, the number of fuel types, and the layer thickness were considered. Even if the enrichment varies from 10 to 20%, the number of fuel types change from 1 to 4, the 1st layer thickness of fuel changes by 30 {mu}m, or the 2nd layer to the 4th layer thickness of fuel changes by 10 {mu}m, the impact on fuel fabrication cost was evaluated to be negligible. (author)

  4. Study on systematic integration technology of design and safety assessment for HLW geological disposal. 2. Research document

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Fukui, Hiroshi; Sagawa, Hiroshi; Matsunaga, Kenichi; Ito, Takaya; Kohanawa, Osamu; Kuwayama, Yuki

    2003-02-01

    The present study was carried out relating to basic design of the Geological Disposal Technology Integration System' that will be systematized as knowledge base for design analysis and safety assessment of HLW geological disposal system by integrating organically and hierarchically various technical information in three study field. The key conclusions are summarized as follows: (1) As referring to the current performance assessment report, the technical information for R and D program of HLW geological disposal system was systematized hierarchically based on summarized information in a suitable form between the work flow (work item) and processes/characteristic flow (process item). (2) As the result of the systematized technical information, database structure and system functions necessary for development and construction to the computer system were clarified in order to secure the relation between technical information and data set for assessment of HLW geological disposal system. (3) The control procedure for execution of various analysis code used by design and safety assessment in HLW geological disposal study was arranged possibility in construction of 'Geological Disposal Technology Integration System' after investigating the distributed computing technology. (author)

  5. Compilation of contract research for the Materials Engineering Branch, Division of Engineering Technology. Annual report for FY 1983. Vol.2

    International Nuclear Information System (INIS)

    1984-03-01

    This report presents summaries of the research work performed during Fiscal Year 1983 by laboratories and organizations under contracts administered by the NRC's Materials Engineering Branch, Office of Nuclear Regulatory Research. Each contractor has written a more complete and detailed annual report of their work which can be obtained by writing to NRC. The contractor reports are organized into the major areas of concern to Primary System Integrity, which is the main focus for the branch's research. These areas are: Vessel and Piping Fracture Mechanics; Pressure Vesel Surveillance Dosimetry; Steam Generators, Aging, and Environmental Cracking; and Non-Destructive Examination. The research programs reported provide information on the overall program objectives, a more limited scope of work for FY 1983, a technical description of the year's work, and a brief forecast of the plans for continuing work

  6. The social impacts of the final disposal of spent nuclear fuel from the point of view of the inhabitants. Interview research

    International Nuclear Information System (INIS)

    Viinikainen, T.

    1998-12-01

    The research studied the social impacts of the final disposal of spent nuclear fuel by the means of qualitative methods. The principal research material consisted of 49 theme interviews carried out in four municipalities, Eurajoki, Kuhmo, Loviisa and Aeaenekoski, all of which have a candidate site for spent fuel disposal. The interviews covered residents living near the possible disposal site, local authorities from different sectors of the municipality, social workers, youth workers and teachers, local businesses, trade and other organisations as well as environmental and citizen movements. When considering the risk conceptions and worries over safety, a fairly consistent view on the safety of the different phases of the project can be identified in all the municipalities. The transportation of nuclear waste aroused definitely the most worries over safety, especially because of the danger of sabotage and traffic accidents. When considering the encapsulation stage' the interviews revealed that risks are associated with this stage because it entails a 'human factor': the treatment of a dangerous substance in a disposal site above ground is considered hazardous. When considering the time after the closing of the disposal system, an opinion could be formed on the basis of the interviews that a final disposal system in hard bedrock would probably perform adequately in the short term but there can be no certain knowledge of risks in the long term. Confidence or lack of confidence in the safety of the project appeared as the most important factor causing social impacts. As a summary of the results, it can be concluded that especially (1) familiarity of the risk and (2) the possibility that taking risks are advantageous to oneself increase the acceptability of the risk. These are also the factors which distinguish the municipalities with nuclear power plants (Loviisa and Eurajoki) from the other two municipalities. The fair allocation of risks as well as the division of

  7. Banking contracts

    OpenAIRE

    Durčáková, Klára

    2010-01-01

    Resumé - Bank Contracts Bank Contracts are an integral part of our everyday lives. Citizen and bussines entities used bank contracts very often. Despite this fact we can't find legal definition in the Czech law. Banking contracts understand contracts that are signed by banks in their business activities and obligations under these contracts arise. While the banking contracts have been widely used, in Czech law there is not too much literature and judgements abou this issue. Lack of legislatio...

  8. 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

  9. Review to give the public clear information on near surface disposal project of low-level radioactive wastes generated from research, industrial and medical facilities

    International Nuclear Information System (INIS)

    Shobu, Nobuhiro; Amazawa, Hiroya; Koibuchi, Hiroto; Nakata, Hisakazu; Kato, Masatoshi; Takao, Tomoe; Terashima, Daisuke; Tanaka, Yoshie; Shirasu, Hisanori

    2013-12-01

    Japan Atomic Energy Agency (hereafter abbreviated as “JAEA”) has promoted near surface disposal project for low-level radioactive wastes generated from research, industrial and medical facilities after receiving project approval from the government in November 2009. JAEA has carried out public information about low-level radioactive wastes disposal project on the web site. When some town meetings are held toward mutual understanding with the public, more detailed and clear explanations for safety management of near surface disposal are needed especially. Therefore, the information provision method to make the public understand should be reviewed. Moreover, a web-based survey should be carried out in order to get a sense of what the public knows, what it values and where it stands on nuclear energy and radiation issues, because the social environment surrounding nuclear energy and radiation issues has drastically changed as a result of the accident at the Fukushima Daiichi Nuclear Power Station on March 11, 2011. This review clarified the points to keep in mind about public information on near surface disposal project for low-level radioactive wastes generated from research, industrial and medical facilities, and that public awareness and understanding toward nuclear energy and radiation was changed before and after the accident at Fukushima Daiichi Nuclear Power Plant. (author)

  10. Addendum to Final Audit Report on Contracting Practices for the Use and Operations of DoD-Sponsored Federally Funded Research and Development Centers

    National Research Council Canada - National Science Library

    1995-01-01

    Inspector General, DoD, Report No. 95-048, "Contracting Practices for the Use and Operations of DoD-Sponsored Federally Funded Research and Development Centers," December 2, 1994, was published without management comments...

  11. A research needs assessment for the capture, utilization and disposal of carbon dioxide from fossil fuel-fired power plants. Volume 2, Topical reports: Final report

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    This study, identifies and assesses system approaches in order to prioritize research needs for the capture and non-atmospheric sequestering of a significant portion of the carbon dioxide (CO{sub 2}) emitted from fossil fuel-fired electric power plants (US power plants presently produce about 7% of the world`s CO{sub 2} emissions). The study considers capture technologies applicable either to existing plants or to those that optimistically might be demonstrated on a commercial scale over the next twenty years. The research needs that have high priority in establishing the technical, environmental, and economic feasibility of large-scale capture and disposal of CO{sub 2} from electric power plants are:(1) survey and assess the capacity, cost, and location of potential depleted gas and oil wells that are suitable CO{sub 2} repositories (with the cooperation of the oil and gas industry); (2) conduct research on the feasibility of ocean disposal, with objectives of determining the cost, residence time, and environmental effects for different methods of CO{sub 2} injection; (3) perform an in-depth survey of knowledge concerning the feasibility of using deep, confined aquifers for disposal and, if feasible, identify potential disposal locations (with the cooperation of the oil and gas industry); (4) evaluate, on a common basis, system and design alternatives for integration of CO{sub 2} capture systems with emerging and advanced technologies for power generation; and prepare a conceptual design, an analysis of barrier issues, and a preliminary cost estimate for pipeline networks necessary to transport a significant portion of the CO{sub 2} to potentially feasible disposal locations.

  12. Information on Coordinated Research Project: Behaviours of Cementitious Materials in Multipurpose Packaging for Transportation, Long Term Storage and Disposal

    International Nuclear Information System (INIS)

    Meyer, W.

    2013-01-01

    The durability of concrete is an important issue and the imaging thereof plays a major part in the understanding of the characteristics of concrete. The ability of concrete to withstand the penetration of liquid and oxygen contribute to the durability of concrete. The durability of concrete, can in turn, be quantified by certain characteristics such as the porosity, sorptivity and permeability. For non-destructive analytical quantification of these parameters, neutron radiography was developed and validated against conventional measurements. Results indicated that because the neutron attenuation of the concrete and water differs to a significant degree, the movement of water in concrete (sorptivity) could be visualized. The neutron radiography results were validated against conventional measurements and excellent correlation was found. To improve the characteristics of current grout/cement matrixes used for the encapsulation of radioactive waste, different cement mixtures Cem 1 (96% OPC) and Cem 5 (mixture of 20% fly ash, 20% blast furnace slag and 60% cement powder) with the addition of different admixtures, inert fibre material and plasticizers were investigated. With no formal guidance from the WAC of the disposal site, it was decided that the following matrix requirements have to be met in order to qualify a possible matrix for radioactive waste immobilisation research: -Total porosity less than 10% (Implies a compression strength higher than 50 MPa) and -Sorptivity rate lower than 2.5 g/h (Implies pore structure not interlinked). Results with radioactive waste (excluding organic waste) indicated an admixture of bitumen or asphalt in CEM 1 (96% OPC cement) has the best characteristics and comply with the specified requirement. Treatment of contaminated organic waste which is a non standard waste stream proved to be difficult and direct disposal is also not an option because many organic liquids are immiscible. Cementation is generally not an option as the

  13. 48 CFR 935.071 - Contract clause.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Contract clause. 935.071... CONTRACTING RESEARCH AND DEVELOPMENT CONTRACTING 935.071 Contract clause. The contracting officer must insert the clause at 952.235-71, Research Misconduct, in contracts, including management and operating...

  14. The role of the public sector's research programme in support of the authorities and in building confidence on the safety of spent fuel disposal

    International Nuclear Information System (INIS)

    Vuori, S.; Rasilainen, K.

    2002-01-01

    A multiphase research programme was launched in 1989 to support the Finnish authorities in their activities concerning spent fuel management. The Finnish programme for spent fuel management has so far managed to keep its original time schedule at least partly due to clearly defined responsibilities between the nuclear energy producing industry and the authorities. It appears that the public sector's research programme has been successful in its supporting role by providing research results both on technical/ natural science and social science issues. In addition, the research programme has contributed directly and indirectly in building confidence on the post-closure and operational safety of a spent fuel disposal facility. (authors)

  15. Contracts, grants and funding summary of supersonic cruise research and variable-cycle engine technology programs, 1972 - 1982

    Science.gov (United States)

    Hoffman, S.; Varholic, M. C.

    1983-01-01

    NASA-SCAR (AST) program was initiated in 1972 at the direct request of the Executive Office of the White House and Congress following termination of the U.S. SST program. The purpose of SCR was to conduct a focused research and technology program on those technology programs which contributed to the SST termination and, also, to provide an expanded data base for future civil and military supersonic transport aircraft. Funding for the Supersonic Cruise Research (SCR) Program was initiated in fiscal year 1973 and terminated in fiscal year 1981. The program was implemented through contracts and grants with industry, universities, and by in-house investigations at the NASA/OAST centers. The studies included system studies and five disciplines: propulsion, stratospheric emissions impact, materials and structures, aerodynamic performance, and stability and control. The NASA/Lewis Variable-Cycle Engine (VCE) Component Program was initiated in 1976 to augment the SCR program in the area of propulsion. After about 2 years, the title was changed to VCE Technology program. The total number of contractors and grantees on record at the AST office in 1982 was 101 for SCR and 4 for VCE. This paper presents a compilation of all the contracts and grants as well as the funding summaries for both programs.

  16. Regulatory review and confidence building in post-closure safety assessments and safety cases for near surface disposal facilities-IAEA ASAM coordinated research programme

    International Nuclear Information System (INIS)

    Gonzales, A.; Simeonov, G.; Bennett, D.G.; Nys, V.; Ben Belfadhel, M.

    2005-01-01

    Some years ago, the IAEA successfully concluded a Coordinated Research Program (CRP) called Islam, which focussed on the development of an Improved Safety Assessment Methodology for near-surface radioactive waste disposal facilities. In November 2002, and as an extension of ISAM, the IAEA launched a new CRP called ASAM, designed to test the Application of the Safety Assessment Methodology by considering a range of near-surface disposal facilities. The ASAM work programme is being implemented by three application working groups and two cross-cutting working groups. The application working groups are testing the applicability of the ISAM methodology by assessing an existing disposal facility in Hungary, a copper mine in South Africa, and a hypothetical facility containing heterogenous wastes, such as disused sealed sources. The first cross-cutting working group is addressing a number of technical issues that are common to all near-surface disposal facilities, while the second group, the Regulatory Review Working Group (RRWG) is developing guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides a brief overview of the work being conducted by the Regulatory Review Working Group. (author)

  17. Research on the energy-saving and revenue sharing strategy of ESCOs under the uncertainty of the value of Energy Performance Contracting Projects

    International Nuclear Information System (INIS)

    Qian, Dong; Guo, Ju’e

    2014-01-01

    Under the uncertainty of the value of Energy Performance Contracting Projects (EPCPs), this paper develops a revenue-sharing bargaining model between an Energy Service Company (ESCO) and an Energy-Using Organization (EU). Based on the model the paper analyzes the impacts of energy prices, risk-adjusted discount rates and accidents on the ESCO’s bargaining strategies. The research shows that the greater the probability of adverse circumstances is, the higher is the revenue share (of the EU), and the more disadvantageous is the ESCO’s position in the game. Furthermore, we design a forecast–commitment contract between an ESCO and an EU and analyze the optimal product’s energy savings commitment strategy of the ESCO to cope with uncertain energy savings and contract risk. The research illustrates that by introducing penalties and commitments, the contract can eliminate the impact of the uncertain energy savings on the contract execution to a certain extent; when the EU takes a greater commitment risk, the ESCO is willing to provide a higher commitment, thus enhancing the strategy value of the bilateral relationship and reducing the contract risk. Finally, the policy recommendations about improving shared savings contract standard, third-party energy savings measurement and verification mechanism and arbitration mechanism of EPCs are provided. - Highlights: • We provide a method for determining the revenue-sharing bargaining strategy space in a finite bargaining game of the ESCO. • The increase of the probability of adverse circumstances will increase the revenue share (of the EU). • We design a forecast–commitment contract between an ESCO and an EU. • The forecast–commitment contract can eliminate the impact of the uncertain energy savings on the contract execution to a certain extent. • When the EU takes a greater commitment risk, the ESCO is willing to provide a higher commitment

  18. Boundary delineation for regional groundwater flow through geographic information system (Contract research)

    International Nuclear Information System (INIS)

    Yamakawa, Tadashi; Munakata, Masahiro; Kimura, Hideo; Hyodo, Hiroshi

    2007-03-01

    Radionuclide migration toward the human environment is to be assessed as the part of long-term safety assessments of geologic disposal of radioactive waste. Geologic processes, which include volcanic activity, hydrothermal activity, seismicity and deformation, bring about hydrogeologic changes in the regional groundwater flow system around a repository site. Groundwater flow systems in Japan have been studied in several sites such as Tono mine, Kamaishi mine and Horonobe area, but methodology of studies in these sites does not have fully developed. This study was conducted to develop methodologies of boundary delineation for regional groundwater flow systems. Geographic Information System, GIS, was applied using available topographic, hydrologic and geologic data for an area of interest. Miyakoji in the Abukuma Mountains was selected as the area, for the reason of its simple geologic setting formed by granitic rocks and topographically gentle hills of drainage basin. Data used in this study cover topographic sheets, digital elevation model, satellite imagery, geologic maps, topographic classification maps, soil distribution maps and landuse maps. Through the GIS techniques using these data, thematic maps on topographic features, surface conditions, land coverage, geology and geologic structure and weathered crust were developed, and these thematic maps were further applied to extract four factors affecting the regional groundwater flows: topographic condition, precipitation recharge, fracture characteristics and potential flows. The present study revealed that, taking the potential groundwater flows and characteristics of fractured zones in the area into consideration, the groundwater flow system in Miyakoji drainage basin should be bounded by the Otakine Mountain and the northern part of Tokoha Drainage Basin. The delineated area is larger than understood before. (author)

  19. Project quality assurance plan for research and development services provided by Oak Ridge National Laboratory in support of the Hanford Grout Disposal Program

    International Nuclear Information System (INIS)

    Spence, R.D.; Gilliam, T.M.

    1991-11-01

    This Project Quality Assurance Plan (PQAP) is being published to provide the sponsor with referenceable documentation for work conducted in support of the Hanford WHC Grout Disposal Program. This plan, which meets NQA-1 requirements, is being applied to work performed at Oak Ridge National Laboratory (ORNL) during FY 1991 in support of this program. It should also be noted that with minor revisions, this plan should be applicable to other projects involving research and development that must comply with NQA-1 requirements

  20. Project quality assurance plan for research and development services provided by Oak Ridge National Laboratory in support of the Hanford Grout Disposal Program

    Energy Technology Data Exchange (ETDEWEB)

    Spence, R.D.; Gilliam, T.M.

    1991-11-01

    This Project Quality Assurance Plan (PQAP) is being published to provide the sponsor with referenceable documentation for work conducted in support of the Hanford WHC Grout Disposal Program. This plan, which meets NQA-1 requirements, is being applied to work performed at Oak Ridge National Laboratory (ORNL) during FY 1991 in support of this program. It should also be noted that with minor revisions, this plan should be applicable to other projects involving research and development that must comply with NQA-1 requirements.

  1. Status report on research programmes of the Commission of European Communities related to risk evaluation of geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Girardi, F.

    1977-01-01

    The programmes of the Commission of European Communities related to risk evaluation of geological disposal of radioactive waste are presented. The Joint Research Centre carries out theoretical modelling activities and a few selected experimental activities which are related to model development and verification. A set of contractual research activities, coordinated by the General Directorate of Research, Scientific Affairs and Education and set up primarily to encourage development of optimised waste management strategies will provide the many additional experimental data which are necessary for a realistic evaluation of long term hazard to man and the environment

  2. 41 CFR 301-54.2 - What is disposable pay?

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 4 2010-07-01 2010-07-01 false What is disposable pay... BILLED TRAVEL CHARGE CARD General Rules § 301-54.2 What is disposable pay? Disposable pay is your..., etc. Deductions may be made from any type of pay you receive from your agency, e.g., basic pay...

  3. 41 CFR 301-76.2 - What is disposable pay?

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 4 2010-07-01 2010-07-01 false What is disposable pay... What is disposable pay? Disposable pay is the part of the employee's compensation remaining after the... deductions such as savings bonds, charitable contributions, etc. Deductions may be made from any type of pay...

  4. 48 CFR 45.604-1 - Disposal methods.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Disposal methods. 45.604-1 Section 45.604-1 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION CONTRACT MANAGEMENT GOVERNMENT PROPERTY Reporting, Reutilization, and Disposal 45.604-1 Disposal methods. (a) Except as provided...

  5. Advice for a career in academic gastroenterology: from fellowship application through job selection and contract negotiations to research and promotion.

    Science.gov (United States)

    Cappell, M S

    2009-03-01

    This study aims to describe a comprehensive strategy for success in academic gastroenterology by reporting common sense, but mostly previously unpublished, recommendations. The recommendation are based on expert opinion from personal experience mentoring 125 gastroenterology fellows and residents as a program director for nine years and from mentoring research while publishing more than 160 articles in peer-reviewed journals and editing 11 books during a 23-year academic career. Primary criteria for fellowship applicant selection include board scores, clinical performance, interview performance, clinical training, and research productivity. For optimal chances, select the subspecialty of gastroenterology early during residency, consult a mentor, and develop a well-planned strategy. Faculty advancement depends upon publications, grants, national recognition, interpersonal skills, and recommendations. Article categories from highest-to-lowest in prestige are original investigations, review articles, book chapters, case reports, and letters/abstracts. Articles are judged by the prestige of the journal of publication. Resubmit rejected articles to successively less prestigious journals until accepted for publication. Articles in journals without peer-review have negligible career impact. Grant support creates protected time. Institutional reputation is important in academics. Do not accept a job without a written contract. Have a lawyer review your contract. An outside offer strengthens a negotiating position. Be sociable and nonconfrontational at work. Network with colleagues. Seek a mentor. Meet your supervisor regularly for feedback. Never express anger at your boss or patients. Avoid litigation with employers. Sub-subspecialize to develop expertise in one area. Focus on this area in your research and clinical practice. In conclusion, a well-planned strategy can help you achieve a senior academic position early and efficiently.

  6. 41 CFR 102-75.280 - What information concerning a proposed disposal must a disposal agency provide to the Attorney...

    Science.gov (United States)

    2010-07-01

    ... applicability of antitrust laws? 102-75.280 Section 102-75.280 Public Contracts and Property Management Federal... PROPERTY DISPOSAL Surplus Real Property Disposal Applicability of Antitrust Laws § 102-75.280 What... the applicability of antitrust laws? The disposal agency must promptly provide the Attorney General...

  7. Research of the cost-benefit evaluation for reprocessing research and development and high-level radioactive waste disposal research and development. Establishing R and D scenarios and extracting their effects

    International Nuclear Information System (INIS)

    Sugihara, K; Miura, N; Arii, Y

    2004-02-01

    This report is intended to explain the outline of research in the FY 2003 on cost-benefit evaluation for Reprocessing R and D and High-Level Radioactive Waste Disposal R and D. We decided to apply the Method of Cost-Benefit Analysis, based on cost-benefit analysis for Fast Reactor cycle system R and D, to Reprocessing R and D and High-Level Radioactive Waste Disposal R and D, and to compare with the results of cost-benefit analysis for both the JNC R and D scenario and the other optional scenarios. In this year, we first thought out all R and D scenarios in the future for Reprocessing R and D and High-Level Radioactive Waste Disposal R and D, and rejected difficult scenarios technically and impossible scenarios socially. Finally, the reasonable R and D scenarios were established. Besides, we thought out the effects (merits) by carrying out the R and D, and separated out them from economical view, environmental view, view of nuclear non-proliferation and so on. (author)

  8. 75 FR 990 - HHS Intent To Publish Grant and Contract Solicitations for Comparative Effectiveness Research...

    Science.gov (United States)

    2010-01-07

    ... Prescription Drug, Improvement, and Modernization Act of 2003, (2) 100 Institute of Medicine topic... Coordinating Council for Comparative Effectiveness Research (FCC), and the Institute of Medicine Report on CER...

  9. Project Summaries: Office of Basic Research Contract Program, 1989-1991

    Science.gov (United States)

    1990-08-01

    United States Army Research Institute for the BAhavioral and Social Sciences Approved !or public release; distribution is unlimited U.S. ARMY RESEARCH...Soldiers’ evaluation of their leaders in World WarII and the All- Volunteer Force. 27 (N): Group Functioning and Communicative Processes (0...Fischer, G. & Stevens, C. (1987) Volunteering Information: Enhancing the Communication Capabilities of Knowledge-Based Systems, Proceedings of INTERACT

  10. Korean Reference HLW Disposal System

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heui Joo; Lee, J. Y.; Kim, S. S. (and others)

    2008-03-15

    This report outlines the results related to the development of Korean Reference Disposal System for High-level radioactive wastes. The research has been supported around for 10 years through a long-term research plan by MOST. The reference disposal method was selected via the first stage of the research during which the technical guidelines for the geological disposal of HLW were determined too. At the second stage of the research, the conceptual design of the reference disposal system was made. For this purpose the characteristics of the reference spent fuels from PWR and CANDU reactors were specified, and the material and specifications of the canisters were determined in term of structural analysis and manufacturing capability in Korea. Also, the mechanical and chemical characteristics of the domestic Ca-bentonite were analyzed in order to supply the basic design parameters of the buffer. Based on these parameters the thermal and mechanical analysis of the near-field was carried out. Thermal-Hydraulic-Mechanical behavior of the disposal system was analyzed. The reference disposal system was proposed through the second year research. At the final third stage of the research, the Korean Reference disposal System including the engineered barrier, surface facilities, and underground facilities was proposed through the performance analysis of the disposal system.

  11. Formation of secondary phases during deep geological final disposal of research reactor fuel elements. Structure and phase analysis

    International Nuclear Information System (INIS)

    Neumann, Andreas

    2012-01-01

    For the assessment of a confident und sustainable final disposal of high level radioactive waste - fuel elements of german research reactors also account for such waste - in suitable, deep geological facilities, processes of the alteration of the disposed of waste and therefore the formation of the corrosion products, i. e. secondary phases must be well understood considering an accident scenario of a potential water inflow. In order to obtain secondary phases non-irradiated research reactor fuel elements (FR-BE) consisting of UAl x -Al were subjected to magnesium chloride rich brine (brine 2, salt repository) and to clay pore solution, respectively and furthermore of the type U 3 Si 2 -Al were solely subjected to magnesium chloride rich brine. Considering environmental aspects of final repositories the test conditions of the corrosion experiments were adjusted in a way that the temperature was kept constant at 90 C and a reducing anaerobic environment was ensured. As major objective of this research secondary phases, obtained from the autoclave experiments after appropriate processing and grain size separation have been identified and quantified. Powder X-ray diffraction (PXRD) and the application of Rietveld refinement methods allowed the identification of the corrosion products and a quantitative assessment of crystalline and amorphous contents. Scanning and transmission electron microscopy were additionally applied as a complementary method for the characterisation of the secondary phases. The qualitative phase analysis of the preprocessed secondary phases of the systems UAl x -Al and U 3 Si 2 -Al in brine 2 shows many similarities. Lesukite - an aluminium chloro hydrate - was observed for the first time considering the given experimental conditions. Further on different layered structures of the LDH type, iron oxyhydroxide and possibly iron chlorides, uncorroded residues of nuclear fuel and elementary iron were identified as well. Depending on preceding

  12. The experimental testing of the long-term behaviour of cemented radioactive waste from nuclear research reactors in the geological disposal conditions of the boom clay

    International Nuclear Information System (INIS)

    Sneyers, A.; Marivoet, J.; Iseghem, P. van

    1998-01-01

    Liquid wastes, resulting from the reprocessing of spent nuclear fuel from the BR-2 Materials Testing Reactor, will be conditioned in a cement matrix at the dedicated cementation facility of UKAEA at Dounreay. In Belgium, the Boom clay formation is studied as a potential host rock for the final geological disposal of cemented research reactor waste. In view of evaluating the safety of disposal, laboratory leach experiments and in situ tests have been performed. Leach experiments in synthetic clay water indicate that the leach rates of calcium and silicium are relatively low compared to those of sodium and potassium. In situ experiments on inactive samples are performed in order to obtain information on the microchemical and mineralogical changes of the cemented waste in contact with the Boom clay. Finally, results from a preliminary performance assessment calculation suggest a non-negligible maximum dose rate of 5 10 -9 Sv/a for 129 I. (author)

  13. The experimental testing of the long-term behaviour of cemented radioactive waste from nuclear research reactors in the geological disposal conditions of the boom clay

    Energy Technology Data Exchange (ETDEWEB)

    Sneyers, A.; Marivoet, J.; Iseghem, P. van [SCK-CEN, B-2400 Mol (Belgium)

    1998-07-01

    Liquid wastes, resulting from the reprocessing of spent nuclear fuel from the BR-2 Materials Testing Reactor, will be conditioned in a cement matrix at the dedicated cementation facility of UKAEA at Dounreay. In Belgium, the Boom clay formation is studied as a potential host rock for the final geological disposal of cemented research reactor waste. In view of evaluating the safety of disposal, laboratory leach experiments and in situ tests have been performed. Leach experiments in synthetic clay water indicate that the leach rates of calcium and silicium are relatively low compared to those of sodium and potassium. In situ experiments on inactive samples are performed in order to obtain information on the microchemical and mineralogical changes of the cemented waste in contact with the Boom clay. Finally, results from a preliminary performance assessment calculation suggest a non-negligible maximum dose rate of 5 10{sup -9} Sv/a for {sup 129}I. (author)

  14. The International Atomic Energy Agency (IAEA) research program to improve safety assessment methodologies for near-surface radioactive waste disposal facilities (ISAM)

    International Nuclear Information System (INIS)

    Torres-Vidal, C.; Kozak, M.W.

    2000-01-01

    The International Atomic Energy Agency (IAEA) launched a Coordinated Research Program in November 1997 on Improvement of Safety Assessment Methodologies for Near Surface Radioactive Waste Disposal Facilities (ISAM). The purpose of this paper is to describe the program and its goals, and to describe achievements of the program to date. The main objectives of the ISAM program are outlined. The primary focus of ISAM is on the practical application of safety assessment methodologies. Three kinds of practical situations are being addressed in the program: safety assessments for large vaults typical of those in Western Europe and North America, smaller vaults for medium and industrial wastes typical in eastern Europe and the former Soviet Union, and a proposed borehole technology for disposal of spent sources in low-technology conditions. (author)

  15. Small and large animal models in cardiac contraction research: advantages and disadvantages.

    Science.gov (United States)

    Milani-Nejad, Nima; Janssen, Paul M L

    2014-03-01

    The mammalian heart is responsible for not only pumping blood throughout the body but also adjusting this pumping activity quickly depending upon sudden changes in the metabolic demands of the body. For the most part, the human heart is capable of performing its duties without complications; however, throughout many decades of use, at some point this system encounters problems. Research into the heart's activities during healthy states and during adverse impacts that occur in disease states is necessary in order to strategize novel treatment options to ultimately prolong and improve patients' lives. Animal models are an important aspect of cardiac research where a variety of cardiac processes and therapeutic targets can be studied. However, there are differences between the heart of a human being and an animal and depending on the specific animal, these differences can become more pronounced and in certain cases limiting. There is no ideal animal model available for cardiac research, the use of each animal model is accompanied with its own set of advantages and disadvantages. In this review, we will discuss these advantages and disadvantages of commonly used laboratory animals including mouse, rat, rabbit, canine, swine, and sheep. Since the goal of cardiac research is to enhance our understanding of human health and disease and help improve clinical outcomes, we will also discuss the role of human cardiac tissue in cardiac research. This review will focus on the cardiac ventricular contractile and relaxation kinetics of humans and animal models in order to illustrate these differences. © 2013.

  16. Compilation of contract research for the Materials Engineering Branch, Division of Engineering

    International Nuclear Information System (INIS)

    1991-03-01

    This compilation of annual reports for FY 1990 by contractors to the Materials Engineering Branch of the Nuclear Regulatory Commission Office of Research concentrates on achievements in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators, and nondestructive examination of primary system components. Separate abstracts have been prepared for each of the reports which are divided into the following categories: (1) vessel and piping fracture mechanics (including irradiation embrittlement); (2) pressure vessel surveillance dosimetry; (3) steam generators, aging, and environmental cracking; and (4) nondestructive examination techniques

  17. The Beishan underground research laboratory for geological disposal of high-level radioactive waste in China: Planning, site selection, site characterization and in situ tests

    Directory of Open Access Journals (Sweden)

    Ju Wang

    2018-06-01

    Full Text Available With the rapid development of nuclear power in China, the disposal of high-level radioactive waste (HLW has become an important issue for nuclear safety and environmental protection. Deep geological disposal is internationally accepted as a feasible and safe way to dispose of HLW, and underground research laboratories (URLs play an important and multi-faceted role in the development of HLW repositories. This paper introduces the overall planning and the latest progress for China's URL. On the basis of the proposed strategy to build an area-specific URL in combination with a comprehensive evaluation of the site selection results obtained during the last 33 years, the Xinchang site in the Beishan area, located in Gansu Province of northwestern China, has been selected as the final site for China's first URL built in granite. In the process of characterizing the Xinchang URL site, a series of investigations, including borehole drilling, geological mapping, geophysical surveying, hydraulic testing and in situ stress measurements, has been conducted. The investigation results indicate that the geological, hydrogeological, engineering geological and geochemical conditions of the Xinchang site are very suitable for URL construction. Meanwhile, to validate and develop construction technologies for the Beishan URL, the Beishan exploration tunnel (BET, which is a 50-m-deep facility in the Jiujing sub-area, has been constructed and several in situ tests, such as drill-and-blast tests, characterization of the excavation damaged zone (EDZ, and long-term deformation monitoring of surrounding rocks, have been performed in the BET. The methodologies and technologies established in the BET will serve for URL construction. According to the achievements of the characterization of the URL site, a preliminary design of the URL with a maximum depth of 560 m is proposed and necessary in situ tests in the URL are planned. Keywords: Beishan, Xinchang site, Granite

  18. Climate change research methods and its significance in the study of choosing candidate site in nuclear waste disposal sites

    International Nuclear Information System (INIS)

    Zhao Yong; Zhang Zhanshi

    2008-01-01

    A high-level nuclear waste is the inevitable product accompanies the development of the nuclear power station. How to dispose it properly has become focused by all over the world. Some of the important progresses have been achieved in the fields of site setting, performance assessment and underground laboratory recently. Palaeoclimate patter and the tendency of climate change are very important aspects for the site setting This paper discussed some of the important progresses on the disposal of unclear wastes, the influence of the climate change on the site setting and main methods such as lake sediments, marine sediment, loess, ancient soil and ice core deal with palaeoclimate and palaeo environment study. (authors)

  19. Government/Andra 2001/2004 quadrennial contract

    International Nuclear Information System (INIS)

    2002-01-01

    The French national agency for the management of radioactive wastes (ANDRA) was created on December 31, 1991 with the objective of carrying out research works in the domain of the long term management of radioactive wastes: research programs, management of waste disposal facilities, realisation and exploitation of underground laboratories for the design and setting up of new disposal facilities, definition of safety rules, conditioning and disposal specifications, inventory and localization of all radioactive wastes inside the French territory. This documents aims at defining the missions of the Andra for the 2001-2004 era, ten years after its creation: classification of radioactive wastes; positioning and missions of the Agency; objectives for the industrial mission (safety, storage and disposal solutions, management solutions, continuation of the inventory work, optimization of disposal costs, memory and surveillance); objectives of the research mission (high scientific level projects, structuration of researches, reinforcement of the coordination between the 3 axes of the 1991 law, exploitation and management of underground laboratories, spreading out of scientific results); objectives of the information mission (inventory and localization of wastes, realization of a reference inventory, contribution to the local information, proposal for a clear and verifiable information); international policy objectives (promotion of contacts and cooperations with foreign partners, representation of the Agency among the big international organizations, punctual missions for the valorization of the Agency competencies); evaluation and quality assurance inside the Agency (safety evaluation, scientific and technical evaluation, quality policy and environment, ethics, contract follow up). (J.S.)

  20. Understanding the Psychological Contract in Apprenticeships and Traineeships to Improve Retention. Research Report

    Science.gov (United States)

    Smith, Erica; Walker, Arlene; Kemmis, Ros Brennan

    2011-01-01

    Attrition in apprenticeships and traineeships is an ongoing concern for employers and government alike, with completion standing at around 50% on average. One possible explanation for this high attrition rate is that there is a mismatch between the respective expectations of apprentices/trainees and employers. This research uses the concept of the…

  1. COLLABORATIVE RESEARCH AND DEVELOPMENT CONTRACT. Delivery Order 0038: Microbial Biotechnology and Biocatalysis

    Science.gov (United States)

    2010-04-01

    Insights into Bacillus Spore Coat Assembly. Eby, D.M., and Johnson, G.R. Air Force Research Laboratory Materials Directorate, Biotechnology Group...integration with the HVAC intake to building. The sensitivity and detection limits demonstrate the potential f the system as a proof of concept, but

  2. Study on engineering technologies in the Mizunami Underground Research Laboratory (FY 2015). Development of design and construction planning and countermeasure technologies (Contract research)

    International Nuclear Information System (INIS)

    Toguri, Satohito; Kobayashi, Shinji; Tsuji, Masakuni; Yahagi, Ryoji; Yamada, Toshiko; Matsui, Hiroya; Mikake, Shinichiro; Aoyagi, Yoshiaki; Sato, Toshinori

    2017-03-01

    The study on engineering technology in the Mizunami Underground Research Laboratory (MIU) project roughly consists of (1)development of design and construction planning technologies, (2)development of construction technology, (3)development of countermeasure technology, (4)development of technology for security, and (5) development of technologies regarding restoration and mitigating of the excavation effect. So far, the verification of the initial design based on the data obtained during excavation was mainly conducted as a research in the Construction Phase, also the countermeasure technologies to control groundwater inflow were examined as a research in the Operation Phase. In FY2015, as a part of the important issues on the research program, “Development of countermeasure technologies for reducing groundwater inflow” in the Japan Atomic Energy Agency 3rd Midterm Plan, water-tight grouting method has been developed. Grouting methods utilized in the MIU were evaluated and the post-excavation grouting at the -500m Access/Research Gallery-South was planned based on these evaluation results. Also, technology development from the viewpoint of geological disposal was summarized, and information on the alternative method to the grouting method was collected and organized. (author)

  3. Final report on: Grain size determination in zirconium alloys (IAEA Research Contract No. 6025/Rb.)

    International Nuclear Information System (INIS)

    Martinez M, E.

    1991-12-01

    In spite of the amount of research developed the knowledge still is far from complete and in this basis the International Atomic Energy Agency, (IAEA), by means of the Working Group on Water Reactor Fuel Performance and Technology, initiated, in 1990 the Coordinated Research Programme named Grain Size Determination In Zirconium Alloys. Several countries were invited to participate and to contribute to the main objective of the programme, which can be state as: To develop a unified metallographic technique capable to show the microstructure of zircaloy in a reproducible and uniform manner. To fulfill the objective the following goals were established: A. To measure the grain size and perform an statistical treatment, in samples prepared specifically to show different amounts of cold work, recrystallization and grain growth. B. To compare the results obtained by the different laboratories involved in the programme. C. Finally, after the Ugine meeting, also the determination of the recrystallization and grain growth kinetics. (Author)

  4. Report of The Special Study Group on Federal Contract Research Centers (FCRCs)

    Science.gov (United States)

    1971-08-30

    reimbursements and to increase capital. The largest portion of fee received is retained as capital to finance fixed assets, to provide a reserve... reimbursement . The remainder—about one-third of ANSER’s total earnings—Is used for working capital. 9, Celling. Its almost exclusive dependence...profit. All research is performed on a strictly cost- reimburable basis, subject to the Armed Service procurement Regulation applicable

  5. Production of high-quality marketing applications: strategies for biotechnology companies working with contract research organizations.

    Science.gov (United States)

    Hecker, Sandra J; Preston, Christopher; Foote, MaryAnn

    2003-01-01

    Many biotechnology and pharmaceutical companies use clinical research organizations (CROs) to assist in the writing and preparation of clinical documents intended for submission to health authorities. Start-up companies often require the expertise of a CRO to prepare their first regulatory documents. Larger or more experienced companies often require CRO staff to assist at times of multiple simultaneous submissions. The timely production of high-quality new drug marketing applications requires close collaborations between the drug company and the CRO. The views of both CRO and industry in ensuring best practices are discussed.

  6. The last stand of the psychocultural cold warriors: military contract research in Vietnam.

    Science.gov (United States)

    Rohde, Joy

    2011-01-01

    In 1966, the social scientists of the Simulmatics Corporation arrived in Saigon. Tasked by the Pentagon with helping to pacify South Vietnam, they conducted political and social psychological research on Viet Cong defectors, government soldiers, and Vietnamese villagers. This essay argues that Simulmatics's work captures some of the ironies of Cold War social science: its tendency to mask militarization behind the rhetoric of peaceful nation-building, its blurring of data collection and intelligence gathering, and its ambitious dedication to revealing the unseen contents of hearts and minds while remaining ignorant of the historical, cultural, and linguistic contexts in which its subjects lived. © 2011 Wiley Periodicals, Inc.

  7. Radiation protection research and training programme 1990-91 Catalogue of contracts

    International Nuclear Information System (INIS)

    1991-01-01

    This catalogue contains summaries of contacts included in the 1990-91 radiation protection research and training programme, which is divided into three sectors: (a) human exposure to radiation and radioactivity: (i) measurement of radiation dose and its interpretation, (ii) transfer and behaviour of radionuclides in the environment; (b) consequences of radiation exposure to man; their assessment, prevention and treatment: (i) stochastic effects of radiation, (ii) non-stochastic effects of radiation, (iii) radiation effects on the developing organism; (c) risks and management of radiation exposure: (i) assessment of human exposure and risks, (ii) optimization and management of radiation protection

  8. Assessment of heterogeneous geological environment at Tono. Japanese fiscal year 2004 (Contract research)

    International Nuclear Information System (INIS)

    Toida, Masaru; Suyama, Yasuhiro; Mori, Takayuki; Inaba, Takeshi; Sasakura, Takeshi; Atsumi, Hiroyuki; Masumoto, Kazuhiko; Kobayashi, Ichizo; Iwano, Keita; Furuichi, Mitsuaki; Ogata, Nobuhisa

    2007-09-01

    'Geoscientific research' at the Tono Area is developing site investigation, characterization and assessment techniques for understanding of geological environment. Their important goals are to establish a methodology for analyzing uncertainties in heterogeneous geological environment and to develop investigation technique for efficiently reducing the uncertainties. The current study proposes a new approach where all the possible options in the models and data-sets, which cannot be excluded in the light of the evidences available, are identified. This approach enables uncertainties associated with the understanding at a given stage of the site characterization to be made explicitly using an uncertainty analysis technique based on Fuzzy geostatics. This approach supports the design of the following investigation stage and reduces the uncertainties efficiently. In FY H16 the technique has been tested through geological modelling and groundwater analyses with Tono Area case based on current knowledge, to demonstrate its applicability and to compile the knowledge/information required to describe the H17 report. This report can be summarized as follows: 1) The knowledge/information required to describe the heterogeneous characteristics was compiled and connected to uncertainties associated with the characterization of a geological environment using a synthesis diagram. 2) Methodologies for assignment and screening of parameters were developed by using Evidential Support Logic (ESL). 3) Applicability of the technique could be confirmed with Tono Area case. 4) This report proposed a new methodology that integrates the technique into JAEA ordinary technique to good advantage in the geoscientific research project. (author)

  9. The 2004 activities and the workshop of the human resources development project in FNCA. Contract research

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-08-01

    In 1999, the Project for Human Resources Development (HRD Project) was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asian countries. In the Project there are two kinds of activity; in-workshop activity and Outside-of-workshop activity. The FNCA 2004 Workshop on HRD Project was held on October 4-7, 2004, in Kuala Lumpur, Malaysia. The Workshop was sponsored by the Ministry of Science and Technology Innovation (MOSTI) of Malaysia and the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan. The Malaysian Institute for Nuclear Technology Research (MINT) and the Japan Atomic Energy Research Institute (JAERI) acted as the hosts. Participating countries were China, Indonesia, Republic of Korea, Japan, Malaysia, the Philippines, Thailand, and Vietnam. The activities of HRD Project was presented in the Sixth Coordinators Meeting of FNCA was held on March 30 - April 1, 2005, in Tokyo, Japan. This report consists of presentation papers and materials at the FNCA 2004 Workshop, a review document of HRD Project for the Coordinators Meeting of FNCA, a letter of request from the Project Leader of Japan to the Project Leaders of the participating countries and theme of the country report as Outside-Workshop Activity. (author)

  10. Survey and analytical studies on a 'TAKANUKE' collapse mechanism for greatly deeper shafts (Contract research)

    International Nuclear Information System (INIS)

    Kurosaki, Yukio; Yamachi, Hiroshi; Matsui, Hiroya

    2008-09-01

    Mizunami underground research laboratory (MIU) is planned to be excavated to the depth of 1000m below the ground surface and is now under construction. One of the most serious problems in a greatly deeper shaft is 'TAKANUKE' collapse caused by slip movement of large discontinuities, as we have reported in the report of 'Study on Collapse Mechanism of Junction between Greatly Deeper Shaft and Horizontal Drifts [JAEA-Research 2008-248 (2008)]'. TAKANUKE collapse has been well known among mining engineers in JAPAN. However, an occurring mechanism of the collapse has not yet been revealed and a design code for it also has not been established. In this report, we have conducted numerical studies using finite difference method in order to throw an objective light on a mechanism of TAKANUKE collapse. These studies show two different stress states in upper and lower side of a large discontinuities. In lower side, a minimum principal stress at shaft wall region drastically reduces due to shaft sinking. This might make shaft wall stability difficult in poor geological condition. Such a TAKANUKE collapse can be found in ventilation shaft projects of the ENASAN tunnel. In the another side of discontinuity, a slip movement along discontinuities takes place due to shaft sinking. This slip movement induces a typical TAKANUKE collapse, as we have reported in 2007. In order to evaluate a possibility of TAKANUKE collapse during MIU main shaft sinking, we have conducted a particle body analysis, which can estimate a brittle failure of hard rock, such as MIU construction site. A fault with a steeply dipping over 79 degree to the main shaft, discovered in a survey boring at MIU site, has a low potential of TAKANUKE collapse during shaft sinking. Beside, a fault with dip of 60 degree may easily slip in a form of TAKANUKE collapse. One CD-ROM is attached as an appendix. (J.P.N.)

  11. Geotechnical site assessment for underground radioactive waste disposal in rock

    International Nuclear Information System (INIS)

    Hudson, J.A.

    1986-05-01

    This report contains a state-of-the-art review of the geotechnical assessment of Land 3 and Land 4 repository sites (at 100 - 300 m depth in rock) for intermediate level radioactive waste disposal. The principles established are also valid for the disposal of low and high level waste in rock. The text summarizes the results of 21 DoE research contract reports, firstly 'in series' by providing a technical review of each report and then 'in parallel' by considering the current state of knowledge in the context of the subjects in an interaction matrix framework. 1214 references are cited. It is concluded that four further research projects are required for site assessment procedures to be developed or confirmed. These are coupled modelling, mechanical properties, water flow and establishment of 2 phase site assessment procedures. (author)

  12. The long-term behaviour of cemented research reactor waste under the geological disposal conditions of the Boom Clay Formation: results from leach experiments

    International Nuclear Information System (INIS)

    Sneyers, A.; Fays, J.; Iseghem, P. van

    2001-01-01

    The Belgian Nuclear Research Centre SCK-CEN has carried out a number of studies to evaluate the long-term behaviour of cemented research reactor waste under the geological disposal conditions of the Boom Clay Formation. Static leach experiments in synthetic clay water were performed on active samples of cemented research reactor waste. The leach experiments were carried out under anaerobic conditions at two testing temperatures (23 and 85 o C). Leach rates of seven radionuclides ( 60 Co, 90 Sr, 134 Cs, 137 Cs, 144 Ce, 154 Eu and 241 Am) were measured. Most investigated radionuclides are well retained within the cement matrix over a 280 days testing period. Results on the source term of radionuclides were complemented with data on the leaching behaviour of cement matrix constituents as Ca, Si, Al, Na, K, Mg and SO 4 as well as with data from performance assessment calculations and in situ tests. Despite limitations inherent to short-term experiments, combined results from these investigations indicate only limited interactions of disposed research reactor waste with the near field of a geological repository in clay. (author)

  13. Experimental study on accelerator driven subcritical reactor. JAERI's nuclear research promotion program, H12-031 (Contract research)

    International Nuclear Information System (INIS)

    Shiroya, Seiji; Misawa, Tsuyoshi; Unesaki, Hironobu

    2004-03-01

    In view of the future plan of Research Reactor Institute, Kyoto University (KURRI), the present study consisted of 1) the transmission experiments of high energy neutrons through materials, 2) experimental simulation of ADSR using the Kyoto University Critical Assembly (KUCA), and 3) conceptual neutronics design study on Kyoto University Reactor (KUR) type ADSR using the MCNPX code. The purpose of the present study was not only to obtain the knowledge usable for the realization of ADSR as a new neutron source for research but also to select technical issues in the field of reactor physics for the development of ADSR in general. Through the present study, valuable knowledge on the basic nuclear characteristics of ADSR was obtained both theoretically and experimentally. This kind of knowledge is indispensable to promote the study on ADSR further. If one dare say the main part of knowledge in short words, the basic nuclear characteristics of ADSR is overwhelmed by the characteristics of the subcritical reactor as expected. For the realization of ADSR in the future, it is considered to be necessary to accumulate results of research steadily. For this purpose, it is inevitable 1) to compile the more precise nuclear data for the wide energy range, 2) to establish experimental techniques for reactor physics study on ADSR including subcriticality measurement and absolute neutron flux measurement from the low energy region to the high energy region, and 3) to develop neutronics calculation tools which facilitate to take into account the neutron generation process by the spallation reaction and the delayed neutron behavior. (author)

  14. Development of simulation code for MOX dissolution using silver-mediated electrochemical method (Contract research)

    Energy Technology Data Exchange (ETDEWEB)

    Kida, Takashi; Umeda, Miki; Sugikawa, Susumu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    MOX dissolution using silver-mediated electrochemical method will be employed for the preparation of plutonium nitrate solution in the criticality safety experiments in the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF). A simulation code for the MOX dissolution has been developed for the operating support. The present report describes the outline of the simulation code, a comparison with the experimental data and a parameter study on the MOX dissolution. The principle of this code is based on the Zundelevich's model for PuO{sub 2} dissolution using Ag(II). The influence of nitrous acid on the material balance of Ag(II) is taken into consideration and the surface area of MOX powder is evaluated by particle size distribution in this model. The comparison with experimental data was carried out to confirm the validity of this model. It was confirmed that the behavior of MOX dissolution could adequately be simulated using an appropriate MOX dissolution rate constant. It was found from the result of parameter studies that MOX particle size was major governing factor on the dissolution rate. (author)

  15. Report on results of contract research. 'Research on MHD generation system'; MHD hatsuden system no kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-03-01

    'Research on MHD generation system' was implemented by its expert committee in the electric joint study group, with the results of fiscal 1982 reported. This year is the final year of this research; therefore, reexamination was made from the practical standpoint on the R and D of coal fired MHD generation, evaluating the present technological level as well as clarifying the development procedures, with proposals made as to the R and D from now on. The present technological level in the practicability is still in the basic stage, where the essential problem is the development of combustors, air heaters and generation channels in particular. An examination was conducted for the problems, procedures and period of the development for each component equipment, with the results provided as materials for studying the path to the experimental plant of 100 MW heat input. In the method of proceeding with the R and D in the future, it was decided as essential, in order to enter the stage of the experimental plant from the element technology development, that R and D is carried out on the unestablished component technology, making sure that no excessive risk is taken in scaling up to the next stage. (NEDO)

  16. Study on collapse mechanism of junction between greatly deeper shaft and horizontal drifts (Contract research)

    International Nuclear Information System (INIS)

    Kurosaki, Yukio; Yamachi, Hiroshi; Katsunuma, Yoshio; Nakata, Masao; Kuwahara, Hideki; Yamada, Fumitaka; Matsushita, Kiyoshi; Sato, Toshinori

    2008-03-01

    The Mizunami underground research laboratory is planned to consist of greatly deeper shaft and horizontal drifts. A junction space between a greatly deeper shaft and horizontal drifts forms which would take a complicated mechanical behavior during a junction excavation. However, a quantitative design method of supporting measures for a deep junction has not yet been established. This is because a conventional shaft design has been conducted based on past experience. Detail records have not been left either in what kind of collapses and deformed phenomena occurring in shaft constructions in a past. In order to examine a collapse mechanism of greatly deeper shaft junction, we have conducted literature surveys and interview studies concerned with deep shaft construction works in a past, and investigated what collapses or difficulties had been occurred in deep shaft junctions. Considering the results of investigations with reviews of intellectuals, a collapse mechanism of a super deep shaft junction depends on both a construction procedure of shaft junction and a geological condition at great depth. During a construction of a shaft junction, stress state of rock masses near junction wall would take a complicated stress path. Especially, it should be necessary to take a most careful consideration on that tangential stress acted around a shaft wall may reduce during horizontal drift excavation. On the other hand, where greatly deeper junction intersects faults and/or fractures with a large angle, a collapse called 'Take-nuke' may occur or extraordinary earth pressure acts on a concrete wall. This is the most typical difficulties during shaft construction. In order to recognize a mechanism of these phenomena and to find out a cause of collapse generation, numerical studies that can simulate a practical rock mass behavior around a shaft junction should be carry out. We demonstrate the finite difference method is most adequate for these simulations with intellectual review

  17. Preparation of computer codes for analyzing sensitivity coefficients of burnup characteristics (2) (Contract research, translated document)

    International Nuclear Information System (INIS)

    Hanaki, Hiroshi; Sanda, Toshio; Ohashi, Masahisa

    2008-10-01

    To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-sections library has been made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible. And the distinct improvement of the accuracy in nuclear design of large LMFBR cores has been achieved. In the design of large LMFBR cores, however, it is important to accurately estimate not only nuclear characteristics, for example, reaction rate distribution and control rod worth but also burnup characteristics, for example, burnup reactivity loss, breeding ratio and so on. Therefore, it is thought to improve the prediction accuracy for burnup characteristics using many burnup data of 'Joyo' effectively. It is thought the best way to adjust cross sections using sensitivity coefficients of burnup characteristics to utilize burnup data of 'Joyo'. It is able to know the accuracy quantitatively for burnup characteristics of large LMFBR by analyzing the sensitivity coefficients. Therefore in this work computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared since 1992. In 1992 cross-section adjustment was done by using the data of 'Joyo' and the effect was studied. In this year the adequacy of the codes was studied with a view of applying of design of large LMFBR cores. The results are as follows: (1) The computer codes which could analyze sensitivity coefficients of burnup characteristics taking into consideration plural cycles and refueling were prepared, therefore it came of be able to adjust cross sections using burnup data and to estimate the accuracy for design of large LMFBR cores. The characteristics are not only burnup reactivity loss, breeding ratio but also number density, criticality, reactivity worth, reaction rate ratio, and reaction rate

  18. Analysis of FP aerosol behavior in piping in WIND project. Contract research

    Energy Technology Data Exchange (ETDEWEB)

    Hidaka, Akihide; Maruyama, Yu; Shibazaki, Hiroaki; Maeda, Akio; Harada, Yuhei [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nagashima, Toshio; Yoshino, Takehito; Sugimoto, Jun

    1998-07-01

    In the analyses of aerosol behavior test in piping in WIND (Wide Range Piping Integrity Demonstration) project at Japan Atomic Energy Research Institute (JAERI), ART code developed by JAERI and VICTORIA code developed by Sandia National Laboratories are used to perform WIND test analysis and to validate the models in the both codes. It is noted that VICTORIA code is supposed to be used as reference code of ART at JAERI. As a part of these activities, WIND Aerosol Deposition tests (WAD4 and 5) and FP aerosol behaviors in safety relief valve (SRV) line during BWR high pressure sequence which will be performed in future WIND experiment were analyzed with ART and VICTORIA codes. The present analyses showed that the portion and mass with relatively large amount of cesium iodide (CsI) deposition observed in WAD4 and 5 tests were reasonably reproduced by ART and VICTORIA codes. A difference was found in condensation and revaporization behaviors of gaseous CsI between the two codes. VICTORIA overestimated the condensed mass of CsI vapor while ART reproduced better the experimental data than the VICTORIA calculation. Further investigation is needed for this issue. Although the deposition mass at the pipe connection part in WAD4 and 5 experiments was not measured, the mass at that portion will be measured from next experiment because relatively large amount of CsI could be deposited there and the measurement is considered to be useful for code verification. The predicted principal aerosol deposition mechanism in SRV line is turbulence. Temperature of SRV line could increase by about 300 K by decay heat from deposited FPs. However, the SRV line made of carbon steel would not be failed because the predicted temperature is still far lower than the melting temperature of carbon steel. (author)

  19. Ground penetrating radar for fracture mapping in underground hazardous waste disposal sites: A case study from an underground research tunnel, South Korea

    Science.gov (United States)

    Baek, Seung-Ho; Kim, Seung-Sep; Kwon, Jang-Soon; Um, Evan Schankee

    2017-06-01

    Secure disposal or storage of nuclear waste within stable geologic environments hinges on the effectiveness of artificial and natural radiation barriers. Fractures in the bedrock are viewed as the most likely passage for the transport of radioactive waste away from a disposal site. We utilize ground penetrating radar (GPR) to map fractures in the tunnel walls of an underground research tunnel at the Korea Atomic Energy Research Institute (KAERI). GPR experiments within the KAERI Underground Research Tunnel (KURT) were carried out by using 200 MHz, 500 MHz, and 1000 MHz antennas. By using the high-frequency antennas, we were able to identify small-scale fractures, which were previously unidentified during the tunnel excavation process. Then, through 3-D visualization of the grid survey data, we reconstructed the spatial distribution and interconnectivity of the multi-scale fractures within the wall. We found that a multi-frequency GPR approach provided more details of the complex fracture network, including deep structures. Furthermore, temporal changes in reflection polarity between the GPR surveys enabled us to infer the hydraulic characteristics of the discrete fracture network developed behind the surveyed wall. We hypothesized that the fractures exhibiting polarity change may be due to a combination of air-filled and mineralogical boundaries. Simulated GPR scans for the considered case were consistent with the observed GPR data. If our assumption is correct, the groundwater flow into these near-surface fractures may form the water-filled fractures along the existing air-filled ones and hence cause the changes in reflection polarity over the given time interval (i.e., 7 days). Our results show that the GPR survey is an efficient tool to determine fractures at various scales. Time-lapse GPR data may be essential to characterize the hydraulic behavior of discrete fracture networks in underground disposal facilities.

  20. Research on changes of nitrate by interactions with metals under the wastes disposal environment containing TRU nuclide

    International Nuclear Information System (INIS)

    Wada, Ryutaro; Nishimura, Tsutomu; Masuda, Kaoru; Fujiwara, Kazuo; Imakita, Tsuyoshi; Tateishi, Tsuyoshi

    2003-02-01

    There exists the waste including a nitrate ion as a salt in the TRU waste materials. This nitrate ion can transferred to the nitrite ion and/or ammonia by reducing materials such as metals in the waste disposal environment, and has the possibility to affect on the disposal environment and nuclide transfer parameters. Therefore, electrochemical tests were conducted to evaluate the reaction rate parameters of the nitrate ion and metals under the low oxygen environment. The long-term reaction test using the glass-seal vessel was also conducted to grasp precisely the nitrate ion transition reaction rate and the gas generation rate caused by the reaction of metal and the nitrate ion coexist solution. (1) Reaction rate constants under various environments were obtained performing the potentiostatic holding tests with the parameters of the solution pH, temperature, and the nitrate and nitrite ion concentrations. The formula of the nitrate ion transition reaction rate was also examined based on these obtained data. (2) Conducting the immersion tests under the environment of the low oxygen and high-pH rainfall underground water site, the long-term reaction rate data were obtained on the reaction products (ammonia, hydrogen gas etc.) of metals (carbon steel, stainless steel and zircaloy etc.) with nitrate ion. The tests under the same conditions as in the past were also conducted to evaluate the test accuracy and error range of the long-term reaction test with the glass-seal vessels. (author)

  1. Safety cases for radioactive waste disposal facilities: guidance on confidence building and regulatory review IAEA-ASAM co-ordinated research project

    International Nuclear Information System (INIS)

    Ben Belfadhel, M.; Bennett, D.G.; Metcalf, P.; Nys, V.; Goldammer, W.

    2008-01-01

    The IAEA has been conducting two co-ordinated research programmes (CRPs) projects to develop and apply improved safety assessment methodologies for near-surface radioactive waste disposal facilities. The more recent of these projects, ASAM (application of safety assessment methodologies), included a Regulatory Review Working Group (RRWG) which has been working to develop guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides an overview of the ASAM project, focusing on the safety case and regulatory review. (authors)

  2. Reconciling Contracts and Relational Governance through Strategic Contracting

    DEFF Research Database (Denmark)

    Petersen, Bent; Østergaard, Kim

    2018-01-01

    on contract types, such as strategic versus conventional, may reconcile the enduring research controversy between the substitution and complements perspectives. Practical implications: Today, formal contracts with foreign distributors tend to resemble “prenuptial agreements”. The opportunity for relational...

  3. Establishment of research and development priorities regarding the geologic disposal of nuclear waste in the United States and strategies for international collaboration

    International Nuclear Information System (INIS)

    McMahon, Kevin; Swift, Peter; Nutt, Mark; Peters, Mark; Williams, Jeff; Voegele, Michael; Birkholzer, Jens

    2011-01-01

    The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technologies (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct research and development (R and D) activities related to storage, transportation and disposal of low level waste (LLW), used nuclear fuel (UNF) and high level radioactive waste (HLW). The U.S. has, for the past twenty-plus years, focused efforts on disposing spent nuclear fuel (SNF) and HLW in a geologic repository at Yucca Mountain Nevada. The recent decision by the U.S. DOE to no longer pursue the development of that repository has necessitated investigating alternative concepts for the disposal of SNF and HLW that exists today and that could be generated under future fuel cycles. The disposal of SNF and HLW in a range of geologic media has been investigated internationally. Considerable progress has been made by in the U.S and other nations, but gaps in knowledge still exist. The U.S. national laboratories have participated in these programs and have conducted R and D related to these issues to a limited extent. However, a comprehensive R and D program investigating a variety of storage, geologic media and disposal concepts has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R and D program has been developed in the UFDC using a systematic approach to identify potential R and D opportunities. This paper will describe the process used by the UFDC and summarize the R and D being pursued. The U.S. DOE has cooperated and collaborated with other countries in many different 'arenas' including the Nuclear Energy Agency (NEA) within the Organisation for Economic Co-operation and Development (OECD), the International Atomic Energy Agency (IAEA), and through bilateral agreements with other countries. These international activities benefited the DOE through the acquisition and exchange of information, database development, and peer reviews by experts from

  4. Report on results of contract research. 'Research on MHD generation system'; MHD hatsuden system no kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-03-01

    'Research on MHD generation system' was implemented by its expert committee in the electric joint study group, with the results of fiscal 1980 reported. This year, a detailed conceptual design was carried out on a coal fired MHD generation system, with points for the technological development concretely examined. In addition, investigation was conducted on the progress of MHD generation technology, development situation of other generation systems, state of energy resources, etc., in various foreign countries. In the conceptual design of the coal fired MHD generation plant, the system structure of a 2,000 MWt class commercial MHD generation plant was explained, as were the conceptual design of the structural elements and proposals for a 500 MWt class demonstration plant and an 100 MWt class experimental plant, for example. In the overseas trend of R and D on MHD generation, investigations were made concerning the U.S., Soviet Union, and China, with details compiled for such items as generation plants, combustors, generation channels, heat resisting materials, superconducting magnets, heat exchangers, seed slags, inverters, boilers and environments, and commercial plants. (NEDO)

  5. Report on results of contract research. 'Research on MHD generation system'; MHD hatsuden system no kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-03-01

    'Research on MHD generation system' was implemented by its expert committee in the electric joint study group, with the results of fiscal 1981 reported. This year, technological reexamination was conducted for a 2,000 MWt commercial MHD generation plant, with evaluation carried out on the cost performance including the construction and operation cost. In addition, for the purpose of intermediate R and D towards the practicability, examination was also conducted on a system structure, concrete specifications of component element, cost of R and D including operation expenses for example, concerning an 100 MWt class experimental plant and a 500 MWt class plant. In the investigation of the overseas trend, information was summarized in detail on the experimental devices, combustors, generation channels, electrode materials, electrode phenomena, theoretical analyses, seeds, slag, component equipment, instrumental technologies, conceptual designs of generation plant, commercial plant, etc., in Soviet Union, China, Holland, India and EPRI, on the basis of the materials from the 19th MHD symposium held in UTSI and from the coal MHD specialist conference held in Sydney. (NEDO)

  6. Study on development of evaluation technique of in-situ tracer test in Horonobe Underground Research Laboratory project (Contract research)

    International Nuclear Information System (INIS)

    Yokota, Hideharu; Amano, Kenji; Maekawa, Keisuke; Kunimaru, Takanori; Naemura, Yumi; Ijiri, Yuji; Motoshima, Takayuki; Suzuki, Shunichi; Teshima, Kazufumi

    2013-06-01

    In the Horonobe Underground Research Laboratory Project, in-situ tracer tests are valuable and important as the investigations to obtain the mass transportation data of fractures in hostrock. However, it is difficult that the in-situ tests are executed under various conditions due to long test period and the tests results are evaluated about permeable heterogeneity in a fracture and/or scale effects. In this study, a number of tracer tests are simulated in a fictitious single plate fracture generated on computer. And the transport parameters are identified by fitting one- and two-dimensional models to the breakthrough curves obtained from the simulations in order to investigate the applicability of these models to the evaluation of in-situ tracer test. As a result, one-dimensional model yields larger longitudinal dispersion length than two-dimensional model in the both cases of homogeneous and heterogeneous hydraulic conductivity fields of the fictitious fracture. This is because that the effect of transverse dispersion has to be included in the longitudinal dispersion length parameter in the one-dimensional model. It is also found that the larger dipole ratio and the larger natural groundwater flow crossing the flow generated between two boreholes make the identified longitudinal dispersion length larger. And, the longitudinal dispersion length identified from a tracer test is smaller and/or larger than the macroscopic longitudinal dispersion length identified from whole fracture. It is clarified that these are occurred by shorter or longer distance between boreholes compare to the correlation length of geostatistical heterogeneity of fictitious fracture. (author)

  7. Temperature simulation of thermal plasma melting furnace for disposal of radioactive waste and preliminary research of vitrification formula

    International Nuclear Information System (INIS)

    Lin Peng; Lu Yonghong; Xiang Wenyuan; Chen Mingzhou; Liu Xiajie; Qin Yuxin

    2013-01-01

    Radioactive waste treatment techniques currently used in nuclear power plant increase the volume greatly and bring much pressure on final disposal; Thermal plasma treatment as a crucial technique to reduce the waste volume is introduced. How to improve the efficiency of the plasma energy is the limiting factor of concern. In this paper, the temperature field of thermal plasma melting furnace is simulated, the maximal temperature of fixed bed melting furnace is calculated (about 1445 ℃). According to the optional fire-resistant materials, the feasibility of furnace fabrication is discussed. Vitrification formulas for three typical radioactive wastes are tested with their feasibilities being analyzed then. Finally, the prospect of thermal plasma techniques of radioactive waste is discussed, and issues for future study are raised. (authors)

  8. User's manual and analysis methodology of probabilistic fracture mechanics analysis code PASCAL Ver.2 for reactor pressure vessel (Contract research)

    International Nuclear Information System (INIS)

    Osakabe, Kazuya; Onizawa, Kunio; Shibata, Katsuyuki; Kato, Daisuke

    2006-09-01

    As a part of the aging structural integrity research for LWR components, the probabilistic fracture mechanics (PFM) analysis code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed in JAEA. This code evaluates the conditional probabilities of crack initiation and fracture of a reactor pressure vessel (RPV) under transient conditions such as pressurized thermal shock (PTS). The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the recent development in the fracture mechanics and computer performance. PASCAL Ver.1 has functions of optimized sampling in the stratified Monte Carlo simulation, elastic-plastic fracture criterion of the R6 method, crack growth analysis models for a semi-elliptical crack, recovery of fracture toughness due to thermal annealing and so on. Since then, under the contract between the Ministry of Economy, Trading and Industry of Japan and JAEA, we have continued to develop and introduce new functions into PASCAL Ver.2 such as the evaluation method for an embedded crack, K I database for a semi-elliptical crack considering stress discontinuity at the base/cladding interface, PTS transient database, and others. A generalized analysis method is proposed on the basis of the development of PASCAL Ver.2 and results of sensitivity analyses. Graphical user interface (GUI) including a generalized method as default values has been also developed for PASCAL Ver.2. This report provides the user's manual and theoretical background of PASCAL Ver.2. (author)

  9. Analysis of the 314th Contracting Squadrons Contract Management Capability Using the Contract Management Maturity Model (CMMM)

    National Research Council Canada - National Science Library

    Jackson, Jr, Carl J

    2007-01-01

    .... The purpose of this research project is to analyze the 314th Contracting Squadron contracting processes and requirement target areas for improvement efforts by the application of the Contract Management Maturity Model (CMMM...

  10. Establishment of research and development priorities regarding the geologic disposal of nuclear waste in the United States and strategies for international collaboration - 59168

    International Nuclear Information System (INIS)

    Nutt, Mark; Peters, Mark; Voegele, Michael; Birkholzer, Jens; Swift, Peter; McMahon, Kevin; Williams, Jeff

    2012-01-01

    The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technologies (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct research and development (R and D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level radioactive waste (HLW). The U.S. has, in accordance with the U.S. Nuclear Waste Policy Act (as amended), focused efforts for the past twenty plus years on disposing of UNF and HLW in a geologic repository at Yucca Mountain, Nevada. The recent decision by the U.S. DOE to no longer pursue the development of that repository has necessitated investigating alternative concepts for the disposal of UNF and HLW that exists today and that could be generated under future fuel cycles. The disposal of UNF and HLW in a range of geologic media has been investigated internationally. Considerable progress has been made by in the U.S and other nations, but gaps in knowledge still exist. The U.S. national laboratories have participated in these programs and have conducted R and D related to these issues to a limited extent. However, a comprehensive R and D program investigating a variety of storage, geologic media, and disposal concepts has not been a part of the U.S. waste management program since the mid 1980's because of its focus on the Yucca Mountain site. Such a comprehensive R and D program is being developed and executed in the UFDC using a systematic approach to identify potential R and D opportunities. This paper describes the process used by the UFDC to identify and prioritize R and D opportunities. The U.S. DOE has cooperated and collaborated with other countries in many different 'arenas' including the Nuclear Energy Agency (NEA) within the Organisation for Economic Co-operation and Development (OECD), the International Atomic Energy Agency (IAEA), and through bilateral agreements with other countries. These international activities benefited the DOE through the

  11. THE PSYCHOLOGICAL CONTRACT

    Directory of Open Access Journals (Sweden)

    Blanca Giorgiana GRAMA

    2015-04-01

    Full Text Available The psychological contract became known as a research paradigm within corporate research, providing a broad framework which explains the employee-company relations. Despite all this, there are still many debates on the concept and a series of criticism were expressed that led to the necessity of some more rigorous theoretical and empirical analysis. The psychological contract refers to the unwritten, implicit expectations that employees have from the company and vice versa; it is that which defines the things the employee expects from the employer. Consequently, each of the parties involved in the contract may have different perceptions on these commitments and obligations. Thus the psychological contract may be regarded as an exchange relation between the employer and the employee. Breaking the psychological contract affects the performance, the morale, and the motivation of the staff in a negative manner. The information presented in this paper is intended to contribute to the theoretical and methodological development of the concept.

  12. 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

  13. Polymorphic Contracts

    Science.gov (United States)

    Belo, João Filipe; Greenberg, Michael; Igarashi, Atsushi; Pierce, Benjamin C.

    Manifest contracts track precise properties by refining types with predicates - e.g., {x : Int |x > 0 } denotes the positive integers. Contracts and polymorphism make a natural combination: programmers can give strong contracts to abstract types, precisely stating pre- and post-conditions while hiding implementation details - for example, an abstract type of stacks might specify that the pop operation has input type {x :α Stack |not ( empty x )} . We formalize this combination by defining FH, a polymorphic calculus with manifest contracts, and establishing fundamental properties including type soundness and relational parametricity. Our development relies on a significant technical improvement over earlier presentations of contracts: instead of introducing a denotational model to break a problematic circularity between typing, subtyping, and evaluation, we develop the metatheory of contracts in a completely syntactic fashion, omitting subtyping from the core system and recovering it post facto as a derived property.

  14. Administrative contracts

    Directory of Open Access Journals (Sweden)

    Vukićević-Petković Milica

    2015-01-01

    Full Text Available Administrative contracts are a special type of contract where usually one of the contracting parties is a public law body and which is concluded for the performance of public service and the realization of a public interest. They go a long way since its inception to its eventual final acceptance of all the legal systems. One of the enduring characteristics of this type of contract is their disquised or unnoticed existence. This is why only monitoring their development may lead to a complete understanding of the importance and essence of this institution as well as the need for its complete legal regulation.

  15. Electrical contracting

    CERN Document Server

    Neidle, Michael

    2013-01-01

    Electrical Contracting, Second Edition is a nine-chapter text guide for the greater efficiency in planning and completing installations for the design, installation and control of electrical contracts. This book starts with a general overview of the efficient cabling and techniques that must be employed for safe wiring design, as well as the cost estimation of the complete electrical contract. The subsequent chapters are devoted to other electrical contracting requirements, including electronic motor control, lighting, and electricity tariffs. A chapter focuses on the IEE Wiring Regulations an

  16. Administrative contracts

    OpenAIRE

    Vukićević-Petković Milica

    2015-01-01

    Administrative contracts are a special type of contract where usually one of the contracting parties is a public law body and which is concluded for the performance of public service and the realization of a public interest. They go a long way since its inception to its eventual final acceptance of all the legal systems. One of the enduring characteristics of this type of contract is their disquised or unnoticed existence. This is why only monitoring their development may lead to a complete u...

  17. Review of current research into soil decontamination and volume reduction techniques for purposes of transportation and disposal

    International Nuclear Information System (INIS)

    Haywood, F.F.

    1986-01-01

    In recent years, a number of soil decontamination studies have been carried out by investigators in the US and Canada. These investigations have included the segregation of potentially hazardous chemicals from uranium mill tailings, the use of various leaching agents for the selective removal of radium, thorium, and uranium from mine and mill tailings, the study of neutralization, fixation, and conditioning processes for tailings, the separation and removal of transuranium elements from contaminated soil and sediment, and finally studies of the cost effectiveness of various decontamination approaches. Remedial action programs for which soil decontamination may be an attractive alternative are those which include the cleanup of large open land areas since thousands of cubic years of material are generally involved. The practice of decontaminating or otherwise segregating contaminated and uncontaminated soil fractions before shipment to a final disposal site can only be done if it is economical to do so. This paper considers several techniques which have been reported in unclassified literature and includes a comparison of the authors' conclusions regarding the effectiveness of their investigations. The manuscript will include a comprehensive bibliography of references to techniques which appear to be feasible alternatives in remedial action programs

  18. Research on dispose of wastewater from printing and dyeing by CWF combined with Iron-carbon Microelectrolysis

    Science.gov (United States)

    Chen, Xin; Ye, Tingjin; Xu, Zizhen; Chen, Xiaogang; Shi, Liang; He, Lingfeng; Zhang, Yongli

    2018-03-01

    The carboxymethylchitosan cladding coal ash (CWF) was oxidized by the high temperature using coal ash and sodium carboxymethyl chitosan as raw and processed material for treatment of simulated and actual printing and dyeing wastewater over iron-carbon micro-electrolysis. The results on pH and CWF dosage for effluent dispose were evaluated by the decolorization rate, COD removal efficiency and turbidity removal rate. The experimental results indicated that the decolorization rate was first augmented and then declined with the increase of pH, and attained a peak value when pH was at 5-6. The COD removal efficiency augmented with the augmented of pH, and attained a peak value when pH was 6-7. The turbidity removal rate was first increases and afterwards decreases with the augment of pH, and attained a peak value when pH was at 5-6. Furthermore, the optimum pH for the treatment of simulated dyeing wastewater was 6 over iron-carbon micro-electrolysis, which indicated that the appropriate pH can promote the degradation of wastewater.

  19. Research on securing no bacteria and nonfeverish property for disposable medical appliances. Inactivation of endotoxin by Co-60 γ ray

    International Nuclear Information System (INIS)

    Hosobuchi, Kazunari; Tanamoto, Kenichi; Haijima, Yuji.

    1996-01-01

    The contamination by fever-causing endotoxin has become a large problem in medical treatment field. In the industry manufacturing disposable medical appliances, the method of manufacturing endotoxin-free products is an important subject, and the development of the methods of inactivating and eliminating efficiently endotoxin is desired. As a part of this development, the possibility of inactivating endotoxin with Co-60 γ ray was examined. The sample was the endotoxin originated from E.Coli R3 F653 strain. For the irradiation, the Co-60 γ ray irradiation apparatus of 185 T-Bq in National Institute of Hygienic Sciences was used. The measurement of the activity of endotoxin was carried out by limulus test synthetic substrate method. The activity value of the endotoxin in aqueous solution decreased logarithmically with the increasing irradiation dose, and this decreasing tendency was not affected by the initial concentration of the endotoxin. The experiment of recovering freezing-dried endotoxin from a vial is described. The results of inactivating the endotoxin in dry system by γ ray are reported. (K.I.)

  20. Research and development of technologies for safe and environmentally optimal recovery and disposal of explosive wastes. Task 2, Preliminary impact assessment for environment, health and safety (EIA)

    Energy Technology Data Exchange (ETDEWEB)

    Duijm, N.J.; Markert, F. [Risoe (Denmark); Larsen, S.G. [DEMEX A/S (Denmark)

    1998-09-01

    As described in the project proposal `Research and Development of Technologies for Safe and Environmentally optimal recovery and Disposal of Explosive Wastes`, dated 31. May 1996, the objective of Task 2, Preliminary Impact Assessment for Environment, Health and Safety, is to: Analyse the environmental impact of noise and emissions to air, water and soil; Assess the risk of hazards to workers` health and safety and to the public. Task 2, Preliminary Impact Assessment for Environment, Health and Safety (EIA), has been performed from August 1997 to September 1998. First, a methodology has been established, based on Multi-Criteria Decision Analysis (MCDA), to select the `best` technology on the basis of clearly defined objectives, including minimal impacts on environment, health and safety. This included a review of different types of explosive waste with a focus on the environment implications, identifying the issues relevant to defining the criteria or objectives with respect to environment and safety in the framework of explosive waste, as well as the preliminary definition of objectives for the final impact assessment. Second, the previously identified recovery and disposal technologies (Task 1) have been qualitatively assessed on the basis of the relevant objectives. This qualitative assessment includes also economic considerations and an attempt to rank the technologies in an MCDA framework. (au)

  1. The Dynamic Character of a Psychological Contract between the Superior and the Employee (According to Empirical Research

    Directory of Open Access Journals (Sweden)

    Anna ROGOZIŃSKA-PAWEŁCZYK

    2015-12-01

    Full Text Available This article analyses the dynamic character of relationships between superiors and employees in the context of a psychological contract. One of the assumptions is that superiors and employees’ shared understanding of their mutual obligations and expectations underpins the performance of the psychological contract. The article explains the concept of a psychological contract and addresses possible breaches thereto as well as their impact on the shape of relationships between superiors and employees. Information necessary to carry out the analysis was obtained from surveys conducted with 178 representatives of large and medium-sized firms based in Poland and with 800 of their employees. In addition to determining the state and contents of a psychological contract as felt by superiors and employees, the article provides also a description and the rankings of their mutual expectations and obligations related to a psychological contract. The degree of similarity between the opinions of the surveyed superiors and employees on each other’s obligations and expectations was assessed with a specially constructed index (an opinion coincidence index, OCI. the results of the surveys and the direction and amount of OCI’s deviation from show that while employees and superiors frequently differ in the perceptions of their expectations and obligations, there are also areas where their opinions are identical. It has also been found that employees’ perception of the contents of a psychological contract depends on their age and the number of years they have worked in the organisation. This fact points to the dynamic character of a psychological contract.

  2. 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.

  3. 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

  4. Static Verification for Code Contracts

    Science.gov (United States)

    Fähndrich, Manuel

    The Code Contracts project [3] at Microsoft Research enables programmers on the .NET platform to author specifications in existing languages such as C# and VisualBasic. To take advantage of these specifications, we provide tools for documentation generation, runtime contract checking, and static contract verification.

  5. Biosphere modelling for safety assessment of geological disposal taking account of denudation of contaminated soils. Research document

    International Nuclear Information System (INIS)

    Kato, Tomoko

    2003-03-01

    Biosphere models for safety assessment of geological disposal have been developed on the assumption that the repository-derived radionuclides reach surface environment by groundwater. In the modelling, river, deep well and marine have been considered as geosphere-biosphere (GBIs) and some Japanese-specific ''reference biospheres'' have been developed using an approach consistent with the BIOMOVS II/BIOMASS Reference Biosphere Methodology. In this study, it is assumed that the repository-derived radionuclide would reach surface environment in the form of solid phase by uplift and erosion of contaminated soil and sediment. The radionuclides entered into the surface environment by these processes could be distributed between solid and liquid phases and could spread within the biosphere via solid phase and also liquid phase. Based on these concepts, biosphere model that considers variably saturated zone under surface soil (VSZ) as a GBI was developed for calculating the flux-to-dose conversion factors of three exposure groups (farming, freshwater fishing, marine fishing) based on the Reference Biosphere Methodology. The flux-to-dose conversion factors for faming exposure group were the highest, and ''inhalation of dust'', external irradiation from soil'' and ''ingestion of soil'' were the dominant exposure pathways for most of radionuclides considered in this model. It is impossible to compare the flux-to-dose conversion factors calculated by the biosphere model in this study with those calculated by the biosphere models developed in the previous studies because the migration processes considered when the radionuclides entered the surface environment through the aquifer are different among the models; i.e. it has been assumed that the repository-derived radionuclides entered the GBIs such as river, deep well and marine via groundwater without dilution and retardation at the aquifer in the previous biosphere models. Consequently, it must be modelled the migration of

  6. Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

    International Nuclear Information System (INIS)

    1995-11-01

    In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ''Migration and Biological Transfer of Radionuclides from Shallow Land Burial'' during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs

  7. Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ``Migration and Biological Transfer of Radionuclides from Shallow Land Burial`` during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs.

  8. The research on economical ethic issues of medical contract research organization%医药合同研究组织经济伦理问题研究

    Institute of Scientific and Technical Information of China (English)

    廖成娟

    2015-01-01

    This paper based on the delegation agency theory, analyzes the economic ethic problems of CRO (Contract Research Organization) and the current situation of CRO business in international medical service trade. Found three economic ethic problems which including delegation and agency moral hazard caused by information asymmetry, intellectual property and information attributable risks, and share of ethic responsibly arose from clinical trials. Finally, it suggested that to establish an international industry association and improve relevant laws and organizations in developing countries.%结合当前国际医疗服务贸易中合同研究组织(CRO)发展现状,以委托代理理论为基础,分析其中存在的经济伦理问题,包括信息不对称造成委托代理双方的道德风险、知识产权与信息归属风险、临床试验产生的伦理责任分担三个方面。提出建立国际性的行业协会,同时完善发展中国家相关法律和机构的建议。

  9. Social dimensions of nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Grunwald, Armin [Karlsruhe Institute of Technology, Karlsruhe (Germany). Inst. for Technology Assessment and Systems Analysis

    2015-07-01

    Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

  10. Social dimensions of nuclear waste disposal

    International Nuclear Information System (INIS)

    Grunwald, Armin

    2015-01-01

    Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

  11. Disposal configuration options for future uses of greater confinement disposal at the Nevada Test Site

    International Nuclear Information System (INIS)

    Price, L.

    1994-09-01

    The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE's Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada Test Site (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS

  12. 41 CFR 102-75.420 - What happens if the FAA informs the disposal agency that it does not recommend disposal of the...

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false What happens if the FAA... Real Property Disposal Property for Public Airports § 102-75.420 What happens if the FAA informs the... property that the FAA does not recommend for disposal as a public airport must be disposed of in accordance...

  13. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    1982-01-01

    This film for a general audience deals with nuclear fuel waste management in Canada, where research is concentrating on land based geologic disposal of wastes rather than on reprocessing of fuel. The waste management programme is based on cooperation of the AECL, various universities and Ontario Hydro. Findings of research institutes in other countries are taken into account as well. The long-term effects of buried radioactive wastes on humans (ground water, food chain etc.) are carefully studied with the help of computer models. Animated sequences illustrate the behaviour of radionuclides and explain the idea of a multiple barrier system to minimize the danger of radiation hazards

  14. Bibliography on ocean waste disposal. second edition. Final report 1976

    International Nuclear Information System (INIS)

    Stanley, H.G.; Kaplanek, D.W.

    1976-09-01

    This research bibliography is restricted to documents relevant to the field of ocean waste disposal. It is primarily limited to recent publications in the categories of: ocean waste disposal; criteria; coastal zone management; monitoring; pollution control; dredge spoil; dredge spoin disposal; industrial waste disposal; radioactive waste; oil spills; bioassay; fisheries resources; ocean incineration; water chemistry; and, Water pollution

  15. 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

  16. RDandD Programme 2007. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

    International Nuclear Information System (INIS)

    2007-09-01

    The programme describes in general terms the planned measures and the facilities that are needed for the task, with a focus on the plans for the period 2008-2013. The period of immediate concern is 2008-2010. The level of detail for the three subsequent years is naturally lower. The programme provides a basis for designing systems to manage and dispose of the radioactive waste from the nuclear power plants. SKB intends to dispose of the spent nuclear fuel in accordance with the KBS-3 method. In the RDandD Programme we describe our activities and the planning for it. We also deal with societal research and other methods for disposal of spent nuclear fuel. The planning for low- and intermediate-level waste, as well as for the societal research, is presented in separate parts. The upcoming review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they view different parts of the activity. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government. The most important milestone during the coming three-year period is to submit applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. RDandD programme 2007 therefore focuses on the technology development that is needed to realize the final repository for spent nuclear fuel. The site investigations in Forsmark and Laxemar will be concluded in 2007. The work of compiling the applications for the final repository is under way. In contrast to the immediately preceding programmes, RDandD Programme 2007 therefore also contains a summary of the site investigation phase and a look ahead at the steps that remain before the final repository can be put into operation. RDandD Programme 2007 consists of six parts: Part I SKB's plan of action; Part II Final repository for spent

  17. RDandD Programme 2007. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    2007-09-15

    The programme describes in general terms the planned measures and the facilities that are needed for the task, with a focus on the plans for the period 2008-2013. The period of immediate concern is 2008-2010. The level of detail for the three subsequent years is naturally lower. The programme provides a basis for designing systems to manage and dispose of the radioactive waste from the nuclear power plants. SKB intends to dispose of the spent nuclear fuel in accordance with the KBS-3 method. In the RDandD Programme we describe our activities and the planning for it. We also deal with societal research and other methods for disposal of spent nuclear fuel. The planning for low- and intermediate-level waste, as well as for the societal research, is presented in separate parts. The upcoming review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they view different parts of the activity. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government. The most important milestone during the coming three-year period is to submit applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. RDandD programme 2007 therefore focuses on the technology development that is needed to realize the final repository for spent nuclear fuel. The site investigations in Forsmark and Laxemar will be concluded in 2007. The work of compiling the applications for the final repository is under way. In contrast to the immediately preceding programmes, RDandD Programme 2007 therefore also contains a summary of the site investigation phase and a look ahead at the steps that remain before the final repository can be put into operation. RDandD Programme 2007 consists of six parts: Part I SKB's plan of action; Part II Final repository for spent

  18. RDandD Programme 2007. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    2007-09-15

    The programme describes in general terms the planned measures and the facilities that are needed for the task, with a focus on the plans for the period 2008-2013. The period of immediate concern is 2008-2010. The level of detail for the three subsequent years is naturally lower. The programme provides a basis for designing systems to manage and dispose of the radioactive waste from the nuclear power plants. SKB intends to dispose of the spent nuclear fuel in accordance with the KBS-3 method. In the RDandD Programme we describe our activities and the planning for it. We also deal with societal research and other methods for disposal of spent nuclear fuel. The planning for low- and intermediate-level waste, as well as for the societal research, is presented in separate parts. The upcoming review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they view different parts of the activity. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government. The most important milestone during the coming three-year period is to submit applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. RDandD programme 2007 therefore focuses on the technology development that is needed to realize the final repository for spent nuclear fuel. The site investigations in Forsmark and Laxemar will be concluded in 2007. The work of compiling the applications for the final repository is under way. In contrast to the immediately preceding programmes, RDandD Programme 2007 therefore also contains a summary of the site investigation phase and a look ahead at the steps that remain before the final repository can be put into operation. RDandD Programme 2007 consists of six parts: Part I SKB's plan of action; Part II Final repository for

  19. Radioactive waste management and disposal

    International Nuclear Information System (INIS)

    Simon, R.; Orlowski, S.

    1980-01-01

    The first European Community conference on Radioactive Waste Management and Disposal was held in Luxembourg, where twenty-five papers were presented by scientists involved in European Community contract studies and by members of the Commission's scientific staff. The following topics were covered: treatment and conditioning technology of solid intermediate level wastes, alpha-contaminated combustible wastes, gaseous wastes, hulls and dissolver residues and plutonium recovery; waste product evaluation which involves testing of solidified high level wastes and other waste products; engineering storage of vitrified high level wastes and gas storage; and geological disposal in salt, granite and clay formations which includes site characterization, conceptual repository design, waste/formation interactions, migration of radionuclides, safety analysis, mathematical modelling and risk assessment

  20. 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

  1. Scientific investigation in deep wells for nuclear waste disposal studies at the Meuse/Haute Marne underground research laboratory, Northeastern France

    Science.gov (United States)

    Delay, Jacques; Rebours, Hervé; Vinsot, Agnès; Robin, Pierre

    Andra, the French National Radioactive Waste Management Agency, is constructing an underground test facility to study the feasibility of a radioactive waste disposal in the Jurassic-age Callovo-Oxfordian argillites. This paper describes the processes, the methods and results of a scientific characterization program carried out from the surface via deep boreholes with the aim to build a research facility for radioactive waste disposal. In particular this paper shows the evolution of the drilling programs and the borehole set up due to the refinement of the scientific objectives from 1994 to 2004. The pre-investigation phase on the Meuse/Haute-Marne site started in 1994. It consisted in drilling seven scientific boreholes. This phase, completed in 1996, led to the first regional geological cross-section showing the main geometrical characteristics of the host rock. Investigations on the laboratory site prior to the sinking of two shafts started in November 1999. The sinking of the shafts started in September 2000 with the auxiliary shaft completed in October 2004. The experimental gallery, at a depth of 445 m in the main shaft, was in operation by end 2004. During the construction of the laboratory, two major scientific programs were initiated to improve the existing knowledge of the regional hydrogeological characteristics and to accelerate the process of data acquisition on the shales. The aim of the 2003 hydrogeological drilling program was to determine, at regional scale, the properties of groundwater transport and to sample the water in the Oxfordian and Dogger limestones. The 2003-2004 programs consisted in drilling nine deep boreholes, four of which were slanted, to achieve an accurate definition of the structural features.

  2. 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

  3. 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.

  4. Pathways for Disposal of Commercially-Generated Tritiated Waste

    Energy Technology Data Exchange (ETDEWEB)

    Halverson, Nancy V. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Environmental Sciences and Biotechnology

    2016-09-26

    From a waste disposal standpoint, tritium is a major challenge. Because it behaves like hydrogen, tritium exchanges readily with hydrogen in the ground water and moves easily through the ground. Land disposal sites must control the tritium activity and mobility of incoming wastes to protect human health and the environment. Consequently, disposal of tritiated low-level wastes is highly regulated and disposal options are limited. The United States has had eight operating commercial facilities licensed for low-level radioactive waste disposal, only four of which are currently receiving waste. Each of these is licensed and regulated by its state. Only two of these sites accept waste from states outside of their specified regional compact. For waste streams that cannot be disposed directly at one of the four active commercial low-level waste disposal facilities, processing facilities offer various forms of tritiated low-level waste processing and treatment, and then transport and dispose of the residuals at a disposal facility. These processing facilities may remove and recycle tritium, reduce waste volume, solidify liquid waste, remove hazardous constituents, or perform a number of additional treatments. Waste brokers also offer many low-level and mixed waste management and transportation services. These services can be especially helpful for small-quantity tritiated-waste generators, such as universities, research institutions, medical facilities, and some industries. The information contained in this report covers general capabilities and requirements for the various disposal/processing facilities and brokerage companies, but is not considered exhaustive. Typically, each facility has extensive waste acceptance criteria and will require a generator to thoroughly characterize their wastes. Then a contractual agreement between the waste generator and the disposal/processing/broker entity must be in place before waste is accepted. Costs for tritiated waste

  5. Pathways for Disposal of Commercially-Generated Tritiated Waste

    International Nuclear Information System (INIS)

    Halverson, Nancy V.

    2016-01-01

    From a waste disposal standpoint, tritium is a major challenge. Because it behaves like hydrogen, tritium exchanges readily with hydrogen in the ground water and moves easily through the ground. Land disposal sites must control the tritium activity and mobility of incoming wastes to protect human health and the environment. Consequently, disposal of tritiated low-level wastes is highly regulated and disposal options are limited. The United States has had eight operating commercial facilities licensed for low-level radioactive waste disposal, only four of which are currently receiving waste. Each of these is licensed and regulated by its state. Only two of these sites accept waste from states outside of their specified regional compact. For waste streams that cannot be disposed directly at one of the four active commercial low-level waste disposal facilities, processing facilities offer various forms of tritiated low-level waste processing and treatment, and then transport and dispose of the residuals at a disposal facility. These processing facilities may remove and recycle tritium, reduce waste volume, solidify liquid waste, remove hazardous constituents, or perform a number of additional treatments. Waste brokers also offer many low-level and mixed waste management and transportation services. These services can be especially helpful for small-quantity tritiated-waste generators, such as universities, research institutions, medical facilities, and some industries. The information contained in this report covers general capabilities and requirements for the various disposal/processing facilities and brokerage companies, but is not considered exhaustive. Typically, each facility has extensive waste acceptance criteria and will require a generator to thoroughly characterize their wastes. Then a contractual agreement between the waste generator and the disposal/processing/broker entity must be in place before waste is accepted. Costs for tritiated waste

  6. 41 CFR 102-42.25 - Who retains custody of gifts and decorations pending disposal?

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Who retains custody of gifts and decorations pending disposal? 102-42.25 Section 102-42.25 Public Contracts and Property..., Handling and Disposition § 102-42.25 Who retains custody of gifts and decorations pending disposal? (a) The...

  7. Intermediate Level Waste Research Programme: Progress report for 1986/87 from the Waste Treatment and Disposal Working Party covering Joint Funded Work

    International Nuclear Information System (INIS)

    Claxton, D.G.S.A.

    1988-06-01

    The Waste Treatment and Disposal Working Party (WTDWP) covered the areas of: ILW Product Evaluation; ILW and HLW Disposal Studies, and ILW and HLW Quality Checking. The objectives of the programme were to evaluate potential waste products arising from the treatment of ILW/HLW, and to develop appropriate techniques which could be used to check the quality of the finished waste product. (author)

  8. Contract Renewal Information - all Contracts

    Data.gov (United States)

    Department of Housing and Urban Development — Multifamily Portfolio datasets (section 8 contracts) - The information has been compiled from multiple data sources within FHA or its contractors. HUD oversees more...

  9. Development of FEP database for geological and climatic disruptive events. Uplift, subsidence, earthquake activity, and climate change (Contract research)

    International Nuclear Information System (INIS)

    Sakai, Ryutaro; Takeda, Seiji; Kimura, Hideo; Matsuba, Hisashi

    2011-06-01

    In the safety assessment for a geological disposal of radioactive waste such as high-level radioactive waste, it is necessary to estimate the hydrological environmental changes affected by external factors such as long-termed earthquake activity and volcanic activity. Therefore it is important to perform the informations including a wide range of future processes and conditions of engineered barriers and geosphere in a systematic manner and to construct scenarios considering external factors. Generation of geological and climatic disruptive events such as earthquake activity, volcanic activity, uplift, subsidence, climatic change and sea-level change and propagation process of their impacts and their types are needed to be clarified in order to understand the phenomena of their influence on a disposal system in case of our country. Japan Atomic Energy Agency started to develop FEP database including the correlation of FEPs and FEP data sheet. This paper presents the FEP data base of upheaval, submergence, earthquake activity and climate change in this study and also presents the results of the questionnaire survey to external experts to update the technical reliability and to keep the objective view in selecting the critical safety correlations. (author)

  10. The use of the psychological contract to explain turnover intentions in the hospitality industry : A research study on the impact of age categories and gender on turnover intentions of highly educated employees

    NARCIS (Netherlands)

    Blomme, R.J.; Tromp, D.M.; Rheede, van A.

    2010-01-01

    The subject of this study is the psychological contract approach to the employment relationship within the hospitality industry with special reference to highly educated employees. The purpose was to research the differences in the psychological contract and its relation to the intention to leave

  11. Clay 2001 dossier: progress report on feasibility studies and research into deep geological disposal of high-level, long-lived waste

    International Nuclear Information System (INIS)

    2001-12-01

    A French Act of Parliament passed on 30 December 1991 set out the main areas of research required to prepare solutions for the long-term management of high-level, long-lived radioactive waste. The three avenues of research listed in the Act included a feasibility study of the deep geological disposal of these waste, with responsibility for steering the study given to ANDRA, France National Agency for Radioactive Waste Management. Following government decisions taken in 1998, the study focused on two types of geological medium, clay and granite. The clay formations study is essentially based on results from an underground laboratory sited at the border between the Meuse and Haute-Marne departments, where the Callovo-Oxfordian argillite beds are being investigated. No site has yet been chosen for an underground laboratory for the granite study, so for the time being this will draw on generic work and on research carried out in laboratories outside France. ANDRA has decided to present an initial report on the results of its research programme, publishing a dossier on the work on clay formations in 2001 with a second dossier covering the work on granite due for release in 2002. This dossier is thus a review of the work carried out by ANDRA on the feasibility study into a radioactive waste repository in a clay formation. It represents one step in a process of studies and research work leading up to the submission of a report due in 2005 containing ANDRA conclusions on the feasibility of a repository in the clay formation. (author)

  12. Contract theory and EU Contract Law

    OpenAIRE

    Hesselink, M.W.; Twigg-Flesner, C.

    2016-01-01

    This paper explores the relationship between contract theory and European contract law. In particular, it confronts the leading contract law theories with the main characteristics of EU contract law. The conclusion is that the two do not match well. In particular, monist normative contract theories are largely irreconcilable with the contract law of the EU. The paper further addresses the main implications of this mismatch, both for contract theory and for EU contract law. It suggests that in...

  13. 41 CFR 102-75.255 - What are disposal agencies' specific responsibilities concerning the disposal of surplus property?

    Science.gov (United States)

    2010-07-01

    ... estimated fair market value. Where hazardous substance activity is identified, see §§ 102-75.340 and 102-75... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false What are disposal....255 Public Contracts and Property Management Federal Property Management Regulations System (Continued...

  14. A new research reactor? Report by the Select Committee for an inquiry into the contract for a new reactor at Lucas Heights

    International Nuclear Information System (INIS)

    2001-05-01

    On 15 August 2000, the Senate resolved to establish the Select Committee for an Inquiry into the Contract for a New Reactor at Lucas Heights and report to the Parliament. The Select committee majority report is divided into three parts: the need for a new reactor; the tendering process and the nature of the contract; and Australia's nuclear waste management strategy and public health and safety. There is a final chapter which brings together the major issues examined in the report. Based on the evidence presented to it, the Committee notes that some Australian scientists and engineers present a strong case for the new reactor. While the Committee is of the view that nuclear science and technology is not backward looking and does offer opportunities for researchers to keep at the forefront of important areas in scientific research and development it does not automatically follow that the best way to promote scientific and medical research in this country is by spending substantial amounts of public funds for the next forty years on a single research reactor. Nevertheless, the Committee recommends that before the Government proceeds any further with the proposed reactor, it undertake a thorough and comprehensive public review of funding for medical and scientific research in Australia with a view to assessing priorities including the role, if any, a research reactor would have in contributing to Australia's scientific, medical and industrial interests. The Committee also requested that the Australian National Audit Office consider examining the tender and contract documents for the new reactor at Lucas Heights with a view to determining: whether further investigation of the tendering process and the contract is warranted; whether, during the tendering process, ANSTO ensured that there was adequate and appropriate independent verification and validation of the tenderers claims. Two supplementary report are included: one from the Liberal and National members (minority

  15. Co-ordinated research and environmental surveillance programme related to sea disposal of radioactive waste CRESP activity report 1986-1990

    International Nuclear Information System (INIS)

    1990-01-01

    The Co-ordinated Research and Environmental Surveillance Programme relevant to sea disposal of radioactive waste (CRESP) was created in 1981 in the framework of the 1977 Decision of the OECD Council establishing a Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste. The main task of CRESP was to set up a site-specific scientific research programme to increase current knowledge of the processes controlling the transfer of radionuclides in the marine environment, so that impact of past dumping could be monitored and future assessments could be based on more accurate and comprehensive scientific data. The CRESP mandate was extended in 1987 to respond to a request from the Paris Commission to include consideration of radioactive discharges in the maritime area covered by the Convention on the Prevention of Marine Pollution from Land-Based Sources. This report summarizes the CRESP activities carried out during the 1986-1990 five year phase. Concerning the review of deep sea results, the report relates progress achieved above the level of knowledge which was available when the present phase of the CRESP programme was decided and which has been taken into account in the 1985 Site Suitability Review. With respect to coastal discharges, it presents a summary of R and D work undertaken by member countries, including those carried out in other programmes such as MARINA. Finally, it makes proposals for future work within CRESP

  16. Organisation of biological research carried out in the United States by the A.E.C. or under her contract (1960)

    International Nuclear Information System (INIS)

    Pellerin, J.

    1960-01-01

    This report is based on information gathered in the course of a trip to the United States, in November and December 1958 which consisted chiefly of visits to the main biological and medical research laboratories and discussions with the heads of these establishments. A description is given of the general organisation of the Atomic Energy Commission's Division of Biology and Medicine, and of the distribution of responsibility for radiation protection work and for biological, medical and agricultural research amongst the various Services attached to it; this is followed by a more detailed account of the activities carried on in this field at the great national laboratories. Finally, the systems of collaboration set up with external research organisations in the form of research contracts are examined, together with the substantial help provided by the A.E.C. for biological, medical and agricultural research in general, owing to a systematic policy of subsidising the distribution of radioisotopes for this purpose. (author) [fr

  17. 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

  18. 41 CFR 102-75.270 - Must antitrust laws be considered when disposing of property?

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Must antitrust laws be...-REAL PROPERTY DISPOSAL Surplus Real Property Disposal Applicability of Antitrust Laws § 102-75.270 Must antitrust laws be considered when disposing of property? Yes, antitrust laws must be considered in any case...

  19. 48 CFR 16.103 - Negotiating contract type.

    Science.gov (United States)

    2010-10-01

    ... CONTRACTING METHODS AND CONTRACT TYPES TYPES OF CONTRACTS Selecting Contract Types 16.103 Negotiating contract... basic profit motive of business enterprise, shall be used when the risk involved is minimal or can be...) Contracts on a firm fixed-price basis other than those for major systems or research and development, and (3...

  20. Research on the behavior of polonium produced in lead-bismuth eutectic irradiated with neutrons. JAERI's nuclear research promotion program, H10-026. Contract research

    International Nuclear Information System (INIS)

    Sekimoto, Hiroshi; Igashira, Masayuki; Yano, Toyohiko; Obara, Toru; Ohsaki, Toshiro

    2002-03-01

    Lead-Bismuth Eutectic (LBE) is proposed by several research institutes as a coolant of liquid metal cooled fast reactors, instead of sodium, and a target of accelerator driven subcritical nuclear reactor systems (ADS). LBE has some advantages that it is chemically inert compared to sodium and that its melting point is low like sodium. A problem might be that bismuth produces polonium, which is an alpha emitter, by irradiation of neutrons. The purpose of the study is to get information for quantitative estimations of the release of polonium on LBE cooled fast reactors and on ADSs by making it clear about production rate of polonium (information about cross section) by neutron irradiation of LBE, release rate of the produced polonium from LBE, and adsorption rate of the polonium on various materials. To get the information about production rate of polonium, neutron cross sections of bismuth were measured in keV energy region, which was important in fast reactors, by using the Pelletron accelerator in Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology. The obtained neutron capture cross sections were from 1/2 to 1/3 of the evaluated values in JENDL and the obtained polonium production cross sections were almost 1/3 of it. At the same time, an experimental device was designed for heating and adsorption experiments and the performance was tested. The performance of alpha spectrometer was tested also. By those the method was established for the measurement of polonium released from melted LBE after neutron irradiation. (author)

  1. Joint US Geological Survey, US Nuclear Regulatory Commission workshop on research related to low-level radioactive waste disposal, May 4-6, 1993, National Center, Reston, Virginia; Proceedings

    Science.gov (United States)

    Stevens, Peter R.; Nicholson, Thomas J.

    1996-01-01

    This report contains papers presented at the "Joint U.S. Geological Survey (USGS) and U.S. Nuclear Regulatory Commission (NRC) Technical Workshop on Research Related to Low-Level Radioactive Waste (LLW) Disposal" that was held at the USGS National Center Auditorium, Reston, Virginia, May 4-6, 1993. The objective of the workshop was to provide a forum for exchange of information, ideas, and technology in the geosciences dealing with LLW disposal. This workshop was the first joint activity under the Memorandum of Understanding between the USGS and NRC's Office of Nuclear Regulatory Research signed in April 1992.Participants included invited speakers from the USGS, NRC technical contractors (U.S. Department of Energy (DOE) National Laboratories and universities) and NRC staff for presentation of research study results related to LLW disposal. Also in attendance were scientists from the DOE, DOE National Laboratories, the U.S. Environmental Protection Agency, State developmental and regulatory agencies involved in LLW disposal facility siting and licensing, Atomic Energy Canada Limited (AECL), private industry, Agricultural Research Service, universities, USGS and NRC.

  2. Agile Contracts

    DEFF Research Database (Denmark)

    Pries-Heje, Jan; Pries-Heje, Lene

    2014-01-01

    with “endless” re-negotiation of the requirements; you need a more flexible way to develop IS. A new way of coping with many changes is to use an agile development approach and a fixed budget and resources contract. This paper presents an example case. We analyse the case and design a guideline for how......When you have stable and non-ambiguous requirements then a classic contract for IS between a supplier and a public sector institution based on a requirements specification may be well suited. However, if you have to accept many changes or have ambiguous requirements then you may end up...... to implement a fixed budget and resources contract in the public sector. The guideline includes elements to cope with challenges in a tender process such as transparency, criteria for supplier selection, and live assessment of resource skills and capabilities, as well as achieving the flexibility for change...

  3. Turnkey contracts

    International Nuclear Information System (INIS)

    Langetepe, G.

    1977-01-01

    To make energy available economically and in sufficient quantity is a main point for the future of an industrial and more for a developing country. The investment costs and the availability of a power plant and in particular for a nuclear power plant are the most significant factors in the economic operation of the plant. In the phase before signing the contract the essential decisions are made with high influence in the economic operation and the availability of the plant. A turn-key contract offers good possibilities to minimize the risks referring a) the plant quality and functionality, b) the plant investment cost, c) the plant completion date, d) the handling of the licensing procedures, e) the availability of the operation. The lecture mentions the points which are of high influence for a successful erection and operation period and which must be clarified before signing the contract between the buyer and supplier of the plant. (orig./HP) [de

  4. 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)

  5. Government/Andra 2001/2004 quadrennial contract; Contrat quadriennal 2001/2004 Etat/Andra

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The French national agency for the management of radioactive wastes (ANDRA) was created on December 31, 1991 with the objective of carrying out research works in the domain of the long term management of radioactive wastes: research programs, management of waste disposal facilities, realisation and exploitation of underground laboratories for the design and setting up of new disposal facilities, definition of safety rules, conditioning and disposal specifications, inventory and localization of all radioactive wastes inside the French territory. This documents aims at defining the missions of the Andra for the 2001-2004 era, ten years after its creation: classification of radioactive wastes; positioning and missions of the Agency; objectives for the industrial mission (safety, storage and disposal solutions, management solutions, continuation of the inventory work, optimization of disposal costs, memory and surveillance); objectives of the research mission (high scientific level projects, structuration of researches, reinforcement of the coordination between the 3 axes of the 1991 law, exploitation and management of underground laboratories, spreading out of scientific results); objectives of the information mission (inventory and localization of wastes, realization of a reference inventory, contribution to the local information, proposal for a clear and verifiable information); international policy objectives (promotion of contacts and cooperations with foreign partners, representation of the Agency among the big international organizations, punctual missions for the valorization of the Agency competencies); evaluation and quality assurance inside the Agency (safety evaluation, scientific and technical evaluation, quality policy and environment, ethics, contract follow up). (J.S.)

  6. Permanent Disposal of Nuclear Waste in Salt

    Science.gov (United States)

    Hansen, F. D.

    2016-12-01

    Salt formations hold promise for eternal removal of nuclear waste from our biosphere. Germany and the United States have ample salt formations for this purpose, ranging from flat-bedded formations to geologically mature dome structures. Both nations are revisiting nuclear waste disposal options, accompanied by extensive collaboration on applied salt repository research, design, and operation. Salt formations provide isolation while geotechnical barriers reestablish impermeability after waste is placed in the geology. Between excavation and closure, physical, mechanical, thermal, chemical, and hydrological processes ensue. Salt response over a range of stress and temperature has been characterized for decades. Research practices employ refined test techniques and controls, which improve parameter assessment for features of the constitutive models. Extraordinary computational capabilities require exacting understanding of laboratory measurements and objective interpretation of modeling results. A repository for heat-generative nuclear waste provides an engineering challenge beyond common experience. Long-term evolution of the underground setting is precluded from direct observation or measurement. Therefore, analogues and modeling predictions are necessary to establish enduring safety functions. A strong case for granular salt reconsolidation and a focused research agenda support salt repository concepts that include safety-by-design. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. Author: F. D. Hansen, Sandia National Laboratories

  7. Geological disposal in the Belgian context

    International Nuclear Information System (INIS)

    Heremans, R.H.; Baetsle, L.H.

    1985-01-01

    The way of studying the high-level and α-bearing waste burial problem can vary from one country to another. In Belgium, if the electronuclear power represents about 60% of the total electricity production, the installed capacity is however limited to 5500 MWe. Furthermore, Belgium is a small country, densely populated, and its geology does not allow a large choice of underground formations acceptable for safe waste disposal. In 1974, site specific investigations were started on a 700 hectares area in the NE part of the country where Belgium's main nuclear research center and some nuclear fuel cycle facilities are located. The formation considered is a tertiary age clay layer underlying the Mol-Dessel area. Study and research works were organized in the frame of successive five year programs. The main objectives of the research are presented. After 10 years of intensive field, laboratory and desk work the obtained results allowed to start of the drafting of Preliminary Safety and Feasibility report in view of the construction of a demonstration facility. The project was performed by the CEN/SCK in the frame of shared financing contracts with the CEC and ONDRAF/NIRAS

  8. 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.

  9. Evaluation of the effectiveness and safety of the thermo-treatment process to dispose of recombinant DNA waste from biological research laboratories

    International Nuclear Information System (INIS)

    Li Mengnan; Zheng Guanghong; Wang Lei; Xiao Wei; Fu Xiaohua; Le Yiquan; Ren Daming

    2009-01-01

    The discharge of recombinant DNA waste from biological laboratories into the eco-system may be one of the pathways resulting in horizontal gene transfer or 'gene pollution'. Heating at 100 deg. C for 5-10 min is a common method for treating recombinant DNA waste in biological research laboratories in China. In this study, we evaluated the effectiveness and the safety of the thermo-treatment method in the disposal of recombinant DNA waste. Quantitative PCR, plasmid transformation and electrophoresis technology were used to evaluate the decay/denaturation efficiency during the thermo-treatment process of recombinant plasmid, pET-28b. Results showed that prolonging thermo-treatment time could improve decay efficiency of the plasmid, and its decay half-life was 2.7-4.0 min during the thermo-treatment at 100 deg. C. However, after 30 min of thermo-treatment some transforming activity remained. Higher ionic strength could protect recombinant plasmid from decay during the treatment process. These results indicate that thermo-treatment at 100 deg. C cannot decay and inactivate pET-28b completely. In addition, preliminary results showed that thermo-treated recombinant plasmids were not degraded completely in a short period when they were discharged into an aquatic environment. This implies that when thermo-treated recombinant DNAs are discharged into the eco-system, they may have enough time to re-nature and transform, thus resulting in gene diffusion

  10. Evaluation of the effectiveness and safety of the thermo-treatment process to dispose of recombinant DNA waste from biological research laboratories.

    Science.gov (United States)

    Li, Meng-Nan; Zheng, Guang-Hong; Wang, Lei; Xiao, Wei; Fu, Xiao-Hua; Le, Yi-Quan; Ren, Da-Ming

    2009-01-01

    The discharge of recombinant DNA waste from biological laboratories into the eco-system may be one of the pathways resulting in horizontal gene transfer or "gene pollution". Heating at 100 degrees C for 5-10 min is a common method for treating recombinant DNA waste in biological research laboratories in China. In this study, we evaluated the effectiveness and the safety of the thermo-treatment method in the disposal of recombinant DNA waste. Quantitative PCR, plasmid transformation and electrophoresis technology were used to evaluate the decay/denaturation efficiency during the thermo-treatment process of recombinant plasmid, pET-28b. Results showed that prolonging thermo-treatment time could improve decay efficiency of the plasmid, and its decay half-life was 2.7-4.0 min during the thermo-treatment at 100 degrees C. However, after 30 min of thermo-treatment some transforming activity remained. Higher ionic strength could protect recombinant plasmid from decay during the treatment process. These results indicate that thermo-treatment at 100 degrees C cannot decay and inactivate pET-28b completely. In addition, preliminary results showed that thermo-treated recombinant plasmids were not degraded completely in a short period when they were discharged into an aquatic environment. This implies that when thermo-treated recombinant DNAs are discharged into the eco-system, they may have enough time to re-nature and transform, thus resulting in gene diffusion.

  11. Research and Development of a New Silica-Alumina Based Cementitious Material Largely Using Coal Refuse for Mine Backfill, Mine Sealing and Waste Disposal Stabilization

    Energy Technology Data Exchange (ETDEWEB)

    Henghu Sun; Yuan Yao

    2012-06-29

    Coal refuse and coal combustion byproducts as industrial solid waste stockpiles have become great threats to the environment. To activate coal refuse is one practical solution to recycle this huge amount of solid waste as substitute for Ordinary Portland Cement (OPC). The central goal of this project is to investigate and develop a new silica-alumina based cementitious material largely using coal refuse as a constituent that will be ideal for durable construction, mine backfill, mine sealing and waste disposal stabilization applications. This new material is an environment-friendly alternative to Ordinary Portland Cement. The main constituents of the new material are coal refuse and other coal wastes including coal sludge and coal combustion products (CCPs). Compared with conventional cement production, successful development of this new technology could potentially save energy and reduce greenhouse gas emissions, recycle vast amount of coal wastes, and significantly reduce production cost. A systematic research has been conducted to seek for an optimal solution for enhancing pozzolanic reactivity of the relatively inert solid waste-coal refuse in order to improve the utilization efficiency and economic benefit as a construction and building material.

  12. Peculiarities of the High-Level Concrete-Encased Radwaste Repository Disposition at the Radwaste Disposal Site of the Russian Research Center 'Kurchatov Institute'

    International Nuclear Information System (INIS)

    Volkov, V.G.; Ponomarev-Stepnoi, N.N.; Gorodetsky, G.G.; Zverkov, Yu.A.; Ivanov, O.P.; Lemus, A.V.; Semenov, S.G.; Stepanov, V.E.; Chesnokov, A.V.; Shisha, A.D.

    2006-01-01

    The paper presents peculiarities of organization and performance of activities on disposition of the old repository that contained high-level waste and located at the radwaste disposal site of the Russian Research Center 'Kurchatov Institute' in Moscow. The repository was constructed in the late 1950's. A large number of cases with high-level waste were placed in the repository along with low- and intermediate-level waste. When the repository was filled in 1973, the entire radwaste mass was encased in concrete matrix which caused difficulties with the radwaste extraction and made the work on the repository disposition highly hazardous in terms of radiation conditions. Based on results of the preliminary radiation survey of the repository, technologies and equipment to be used in disposition works were selected, and a decision on construction of external radiation shielding around the repository to maintain normal radiation conditions during these works was made. Specific features of the selected radiation shielding design constructed around the repository and of a technology used for the radwaste extraction from the repository are provided. According to the technology, conventional construction machines equipped with a hydraulic hammer or a clamshell were used for destruction of the concrete-encased radwaste mass and extraction of low-level waste. Intermediate- and high-level waste was extracted by remotely controlled robots operating inside the radiation shielding structure. Video cameras and a gamma imager were used for detection of high-level waste or fragments of such radwaste in the mass concrete being destroyed and for guiding remotely controlled robots. Peculiarities of rapid control of changes in radiation conditions in the working areas are presented. This control was performed using a gamma locator with on-line transmission of its data to a PC for their processing. With disposition of this not easily accessible repository, the stage of remediation of old

  13. HLW Disposal System Development

    Energy Technology Data Exchange (ETDEWEB)

    Choi, J. W.; Choi, H. J.; Lee, J. Y. (and others)

    2007-06-15

    A KRS is suggested through design requirement analysis of the buffer and the canister which are the constituent of disposal system engineered barrier and HLW management plans are proposed. In the aspect of radionuclide retention capacity, the thickness of the buffer is determined 0.5m, the shape to be disc and ring and the dry density to be 1.6 g/cm{sup 3}. The maximum temperature of the buffer is below 100 .deg. which meets the design requirement. And bentonite blocks with 5 wt% of graphite showed more than 1.0 W/mK of thermal conductivity without the addition of sand. The result of the thermal analysis for proposed double-layered buffer shows that decrease of 7 .deg. C in maximum temperature of the buffer. For the disposal canister, the copper for the outer shell material and cast iron for the inner structure material is recommended considering the results analyzed in terms of performance of the canisters and manufacturability and the geochemical properties of deep groundwater sampled from the research area with granite, salt water intrusion, and the heavy weight of the canister. The results of safety analysis for the canister shows that the criticality for the normal case including uncertainty is the value of 0.816 which meets subcritical condition. Considering nation's 'Basic Plan for Electric Power Demand and Supply' and based on the scenario of disposing CANDU spent fuels in the first phase, the disposal system that the repository will be excavated in eight phases with the construction of the Underground Research Laboratory (URL) beginning in 2020 and commissioning in 2040 until the closure of the repository is proposed. Since there is close correlation between domestic HLW management plans and front-end/back-end fuel cycle plans causing such a great sensitivity of international environment factor, items related to assuring the non-proliferation and observing the international standard are showed to be the influential factor and acceptability

  14. 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...

  15. 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.)

  16. Waste-Mixes Study for space disposal

    International Nuclear Information System (INIS)

    McCallum, R.F.; Blair, H.T.; McKee, R.W.; Silviera, D.J.; Swanson, J.L.

    1983-01-01

    The Wastes Mixes Study is a component of Cy-1981 and 1982 research activities to determine if space disposal could be a feasible complement to geologic disposal for certain high-level (HLW) and transuranic wastes (TRU). The objectives of the study are: to determine if removal of radionuclides from HLW and TRU significantly reduces the long-term radiological risks of geologic disposal; to determine if chemical partitioning of the waste for space disposal is technically feasible; to identify acceptable waste forms for space disposal; and to compare improvements in geologic disposal system performance to impacts of additional treatment, storage, and transportation necessary for space disposal. To compare radiological effects, five system alternatives are defined: Reference case - All HLW and TRU to a repository. Alternative A - Iodine to space, the balance to a repository. Alternative B - Technetium to space, the balance to a repository. Alternative C - 95% of cesium and strontium to a repository; the balance of HLW aged first, then to space; plutonium separated from TRU for recycle; the balance of the TRU to a repository. Alternative D - HLW aged first, then to space, plutonium separated from TRU for recycle; the balance of the TRU to a repository. The conclusions of this study are: the incentive for space disposal is that it offers a perception of reduced risks rather than significant reduction. Suitable waste forms for space disposal are cermet for HLW, metallic technetium, and lead iodide. Space disposal of HLW appears to offer insignificant safety enhancements when compared to geologic disposal; the disposal of iodine and technetium wastes in space does not offer risk advantages. Increases in short-term doses for the alternatives are minimal; however, incremental costs of treating, storing and transporting wastes for space disposal are substantial

  17. The social impacts of the final disposal of spent nuclear fuel from the point of view of the inhabitants. Interview research; Kaeytetyn ydinpolttoaineen loppusijoituksen sosiaaliset vaikutukset kuntalaisten naekoekulmasta. Haastattelututkimus

    Energy Technology Data Exchange (ETDEWEB)

    Viinikainen, T. [Helsinki Univ. of Technology, Otaniemi (Finland). Centre for Urban and Regional Studies

    1998-12-01

    The research studied the social impacts of the final disposal of spent nuclear fuel by the means of qualitative methods. The principal research material consisted of 49 theme interviews carried out in four municipalities, Eurajoki, Kuhmo, Loviisa and Aeaenekoski, all of which have a candidate site for spent fuel disposal. The interviews covered residents living near the possible disposal site, local authorities from different sectors of the municipality, social workers, youth workers and teachers, local businesses, trade and other organisations as well as environmental and citizen movements. When considering the risk conceptions and worries over safety, a fairly consistent view on the safety of the different phases of the project can be identified in all the municipalities. The transportation of nuclear waste aroused definitely the most worries over safety, especially because of the danger of sabotage and traffic accidents. When considering the encapsulation stage` the interviews revealed that risks are associated with this stage because it entails a `human factor`: the treatment of a dangerous substance in a disposal site above ground is considered hazardous. When considering the time after the closing of the disposal system, an opinion could be formed on the basis of the interviews that a final disposal system in hard bedrock would probably perform adequately in the short term but there can be no certain knowledge of risks in the long term. Confidence or lack of confidence in the safety of the project appeared as the most important factor causing social impacts. As a summary of the results, it can be concluded that especially (1) familiarity of the risk and (2) the possibility that taking risks are advantageous to oneself increase the acceptability of the risk. These are also the factors which distinguish the municipalities with nuclear power plants (Loviisa and Eurajoki) from the other two municipalities. The fair allocation of risks as well as the division of

  18. Crystalline and Crystalline International Disposal Activities

    Energy Technology Data Exchange (ETDEWEB)

    Viswanathan, Hari S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chu, Shaoping [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reimus, Paul William [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Makedonska, Nataliia [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hyman, Jeffrey De' Haven [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Karra, Satish [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dittrich, Timothy M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-12-21

    This report presents the results of work conducted between September 2014 and July 2015 at Los Alamos National Laboratory in the crystalline disposal and crystalline international disposal work packages of the Used Fuel Disposition Campaign (UFDC) for DOE-NE’s Fuel Cycle Research and Development program.

  19. Contract theory and EU Contract Law

    NARCIS (Netherlands)

    Hesselink, M.W.; Twigg-Flesner, C.

    2016-01-01

    This paper explores the relationship between contract theory and European contract law. In particular, it confronts the leading contract law theories with the main characteristics of EU contract law. The conclusion is that the two do not match well. In particular, monist normative contract theories

  20. Hybrid disposal systems and nitrogen removal in individual sewage disposal systems

    Energy Technology Data Exchange (ETDEWEB)

    Franks, A.L.

    1993-06-01

    The use of individual disposal systems in ground-water basins that have adverse salt balance conditions and/or geologically unsuitable locations, has become a major problem in many areas of the world. There has been much research in design of systems for disposal of domestic sewage. This research includes both hybrid systems for disposal of domestic sewage. This research includes both hybrid systems for disposal of the treated waste in areas with adverse geologic conditions and systems for the removal of nitrogen and phosphorus prior to percolation to the ground water. This paper outlines the history of development and rationale for design and construction of individual sewage disposal systems and describes the designs and limitations of the hybrid and denitrification units. The disposal systems described include Mounds, Evapotranspiration and Evapotranspiration/Infiltration systems. The denitrification units include those using methanol, sulfur and limestone, gray water and secondary treated wastewater for energy sources.

  1. Muscle Contraction.

    Science.gov (United States)

    Sweeney, H Lee; Hammers, David W

    2018-02-01

    SUMMARYMuscle cells are designed to generate force and movement. There are three types of mammalian muscles-skeletal, cardiac, and smooth. Skeletal muscles are attached to bones and move them relative to each other. Cardiac muscle comprises the heart, which pumps blood through the vasculature. Skeletal and cardiac muscles are known as striated muscles, because the filaments of actin and myosin that power their contraction are organized into repeating arrays, called sarcomeres, that have a striated microscopic appearance. Smooth muscle does not contain sarcomeres but uses the contraction of filaments of actin and myosin to constrict blood vessels and move the contents of hollow organs in the body. Here, we review the principal molecular organization of the three types of muscle and their contractile regulation through signaling mechanisms and discuss their major structural and functional similarities that hint at the possible evolutionary relationships between the cell types. Copyright © 2018 Cold Spring Harbor Laboratory Press; all rights reserved.

  2. 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

  3. 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.

  4. Contract design

    International Nuclear Information System (INIS)

    Bradley, P.

    2006-01-01

    The current state of the electric power industry in Ontario was discussed with particular reference to the procurement of contracts and why the Ontario Power Authority (OPA) must be contracting to resolve many of Ontario's electricity issues. As Ontario increasingly relies on imports and natural gas-fired generation, the price of electricity continues to rise given that supply is at a low level. In addition to the generation gap, there are also several transmission constrained areas in Ontario, particularly in the Greater Toronto Area (GTA). The OPA announced 2 projects totalling 1900 MW to relieve congestion. According to the Independent Electricity System Operator (IESO), the total potential opportunity for new generation by 2015 is about 5,000 to 7,000 megawatts. OPA is expected to launch procurement processes for up to 1000 MW of cogeneration, 250 MW of province-wide conservation initiatives, 1900 MW of generation in the western part of the GTA, and 600 MW of generation in downtown Toronto. New nuclear capacity is also anticipated in addition to renewables and conservation/demand management (CDM) initiatives. The OPA's competitive procurement processes will include requests for expressions of interest, requests for qualifications and requests for proposals. The challenge of balancing the technical complexities and realities of procuring generation assets with the need for a fair procurement process was discussed. Contracts will be designed to react to market signals and will include 3 styles: tariff style, tolling style and standard offer contract. OPA will make every effort to balance generator and ratepayer interests. 6 figs

  5. 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

  6. Using customer relationships to acquire technological innovation: a value-chain analysis of supplier contracts with scientific research institutions

    CERN Multimedia

    2003-01-01

    "In this exploratory research, a value-chain analysis is used to investigate how industrial suppliers working with the European Research Laboratory for Particle Physics (CERN) gain benefits resulting from technological innovation".

  7. Contracts for field projects and supporting research on enhanced oil recovery: Progress review No. 74, Quarter ending March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    Accomplishments for the past quarter are presented for the following tasks: chemical flooding--supporting research; gas displacement--supporting research; thermal recovery--supporting research; geoscience technology; resource assessment technology; microbial technology; field demonstrations in high-priority reservoir classes; and novel technology. A list of available publication is also provided.

  8. Contracts for field projects and supporting research on enhanced oil recovery. Progress review No. 71, quarter ending June 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    Progress reports are presented for the following tasks: chemical flooding--supporting research; gas displacement--supporting research; thermal recovery--supporting research; geoscience technology; resource assessment technology; microbial technology; and novel technology. A list of available publication is also provided.

  9. 2005 dossier: granite. Tome: architecture and management 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 geologic disposal of high-level and long-lived radioactive wastes in granite formations. Content: 1 - Approach of the study: main steps since the December 30, 1991 law, ANDRA's research program on disposal in granitic formations; 2 - high-level and long-lived (HLLL) wastes: production scenarios, waste categories, inventory model; 3 - disposal facility design in granitic environment: definition of the geologic disposal functions, the granitic material, general facility design options; 4 - general architecture of a disposal facility in granitic environment: surface facilities, underground facilities, disposal process, operational safety; 5 - B-type wastes disposal area: primary containers of B-type wastes, safety options, concrete containers, disposal alveoles, architecture of the B-type wastes disposal area, disposal process and feasibility aspects, functions of disposal components with time; 6 - C-type wastes disposal area: C-type wastes primary containers, safety options, super-containers, disposal alveoles, architecture of the C-type wastes disposal area, disposal process in a reversibility logics, functions of disposal components with time; 7 - spent fuels disposal area: spent fuel assemblies, safety options, spent fuel containers, disposal alveoles, architecture of the spent fuel disposal area, disposal process in a reversibility logics, functions of disposal components with time; 8 - conclusions: suitability of the architecture with various types of French granites, strong design, reversibility taken into consideration. (J.S.)

  10. Mixed waste disposal facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Wells, M.N.; Bailey, L.L.

    1991-01-01

    The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission

  11. Compilation of contract research for the Materials Engineering Branch, Division of Engineering: Annual report for FY 1987

    International Nuclear Information System (INIS)

    1988-06-01

    This compilation of annual reports by contractors to the Materials Engineering Branch of the NRC Office of Research concentrates on achievements in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators, nondestructive examination of primary components, and in safety research for decommissioning and decontamination, on-site storage, and engineered safety features. This report, covering research conducted during Fiscal Year 1987 is the sixth volume of the series of NUREG-0975, ''Compilation of Contractor Research for the Materials Engineering Branch, Division of Engineering.''

  12. The Meuse-Haute Marne underground research laboratory. A scientific research tool for the study of deep geologic disposal of radioactive wastes

    International Nuclear Information System (INIS)

    2006-01-01

    The Meuse-Haute Marne underground research laboratory, is an essential scientific tool for the achievement of one of the ANDRA's mission defined in the framework of the law from December 30, 1991 about the long-term management of high-level and long-living radioactive wastes. This document presents this laboratory: site characterization, characteristics of the Callovo-Oxfordian clay, and laboratory creation, coordinated experiments carried out at the surface and in depth, and the results obtained (published in an exhaustive way in the 'Clay 2005' dossier). (J.S.)

  13. Compilation of contract research for the Materials Engineering Branch, Division of Engineering Technology. Annual report for FY 1985. Volume 4

    International Nuclear Information System (INIS)

    1986-03-01

    The compilation of annual reports by contractors to the Materials Engineering Branch of the NRC Office of Research, concentrates on achievements in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators and for non-destructive examination of primary system components. This report, covering research conducted during Fiscal Year 1985, is the fourth volume of the series of NUREG-0975, Compilation of Contractor Research for the Materials Engineering Branch, Division of Engineering Technology

  14. Compilation of contract research for the Materials Engineering Branch, Division of Engineering Technology. Annual report for FY 1984. Volume 3

    International Nuclear Information System (INIS)

    1985-04-01

    This compilation of annual reports by contractors to the Materials Engineering Branch of the NRC Office of Research, concentrates on achievments in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators and for non-destructive examination of primary system components. This report, covering research conducted during Fiscal Year 1984, is the third volume of the series of NUREG-0975, compilation of Contractor Research for the Materials Engineering Branch, Division of Engineering Technology

  15. An introduction to the Transport Properties Research Laboratory at the British Geological Survey and its 50+ years' experience in geological disposal research

    Energy Technology Data Exchange (ETDEWEB)

    Zihms, S.G.; Shaw, R.P.; Harrington, J.F.; Cuss, R.J.; Graham, C.C.; Wiseall, A.; McEvoy, F. [British Geological Survey, Nickerhill Keyworth (United Kingdom)

    2015-07-01

    The Transport Properties Research Laboratory (TPRL) is one of the leading centers in Europe for the study of fluid movement in ultra-low permeability media. The facility is well known for long-term high quality experimental work and process-based interpretation. Focus is on multi-phase flow in natural and engineered, low permeability geomaterials (e.g. caprocks, well bore cements and engineered clays), and their associated deformation behavior. Measurements include: saturation and consolidation properties; intrinsic permeability (or transmissivity); anisotropy; specific storage; coupled flow parameters (e.g. osmotic permeability); capillary entry, breakthrough and threshold pressures; gas permeability function; drained and undrained compressibilities; and rheological (creep) properties. Laboratory experiments are performed under simulated in-situ conditions (stress, pore pressure, temperature and chemical environment). Three key areas explored are: (i) baseline characterization of hydromechanical properties, (ii) influence of stress path and stress history on transport properties and (iii) transmissivity of fractures, faults and discontinuities (e.g., wellbore interfaces). Tests are designed to provide quantitative data for mathematical modeling of ultra-low permeability materials, together with process understanding of key transport mechanisms. Key equipment includes: high pressure isotropic permeameters (70 MPa); constant volume permeameters (70 MPa); high pressure triaxial permeameter (70 MPa); heavy-duty, high-precision shear-rigs; high temperature, high pressure geochemical flow reactor (130 MPa at 140 C); and novel tracer systems (nanoparticle injection or radiological tagging of gas) to characterize and identify potential migration pathways. The key achievements from the TPRL at the BGS include generation of new conceptual models applied throughout Europe, transfer of skills and knowledge to other complex geoscience problems (e.g. shale gas, CCS). The TPRL

  16. Retractable Contracts

    Directory of Open Access Journals (Sweden)

    Franco Barbanera

    2016-02-01

    Full Text Available In calculi for modelling communication protocols, internal and external choices play dual roles. Two external choices can be viewed naturally as dual too, as they represent an agreement between the communicating parties. If the interaction fails, the past agreements are good candidates as points where to roll back, in order to take a different agreement. We propose a variant of contracts with synchronous rollbacks to agreement points in case of deadlock. The new calculus is equipped with a compliance relation which is shown to be decidable.

  17. Compilation of contract research for the Materials Engineering Branch, Division of Engineering: Annual report for FY 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This compilation of annual reports by contractors to the Materials Engineering Branch of the NRC Office of Research concentrates on achievements in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators, nondestructive examination of primary components, and in safety research for decommissioning and decontamination, on-site storage and engineered safety features. The Materials Engineering Branch assembles abbreviated reports from all the branch contractors and publishes them in a single annual report as soon after the end of the year as possible so that the information developed throughout the year can be promptly used in the safety-regulatory process. This report, covering research conducted during Fiscal Year 1988 is the seventh volume of the series of NUREG-0975, ''Compilation of Contractor Research for the Materials Engineering Branch, Division of Engineering.'' Individual projects are processed separately for the data bases

  18. Contracting for Complex Products

    Science.gov (United States)

    2010-05-01

    asymmetries, and barriers to market entry and exit (e.g., Mankiw , et al., 2002). Goods may be non-rivalrous or non-excludable so that transferable property...investments. Expenditures are asset specific to the extent they have no economic value outside the product being produced (Williamson, 2005). For...example, some research in the US space program produced economic value outside the contract (e.g., Tang), while other research produced little value

  19. Review of very low level radioactive waste disposal

    International Nuclear Information System (INIS)

    Wang Jinsheng; Guo Minli; Tian Hao; Teng Yanguo

    2005-01-01

    Very low level waste (VLLW) is a new type of radioactive wastes proposed recently. No widely acceptable definition and disposal rules have been established for it. This paper reviews the definition of VLLW in some countries where VLLW was researched early, as well as the disposal policies and methods of VLLW that the IAEA and these countries followed. In addition, the safety assessment programs for VLLW disposal are introduced. It is proved the research of VLLW is urgent and essential in china through the comparison of VLLW disposal between china and these counties. At last, this paper points out the future development of VLLW disposal research in China. (authors)

  20. 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.

  1. Contracting knowledge: the organizational limits to interdisciplinary energy efficiency research and development in the US and the UK

    Energy Technology Data Exchange (ETDEWEB)

    Lutzenhiser, Loren [Washington State Univ., Pullman, WA (United States); Shove, Elizabeth [Lancaster Univ., Centre for Science Studies, Lancaster (United Kingdom)

    1999-04-01

    Comparison of the organization and management of government funded energy efficiency research and development in the United States and the United Kingdom reveals a number of common features as well as as some important differences. The UK pattern is one of centralized agenda-setting and competition in which rival research contractors bid for small, pre-determined, ``bite-sized`` pieces of work. By contrast, the US approach involves complex negotiations between federal energy and environmental policy agencies and semi-entrepreneurial national laboratories. How do these differing research environments influence the knowledge we have of energy efficiency? How do these organizational features affect the shaping of research agendas, the definition of research problems and the management and dissemination of resulting expertise? More specifically, what consequences do these arrangements have for the conduct of needed social science studies within this conventionally technical field? In exploring these questions, the paper identifies a variety of ways in which opportunities for inter-disciplinarity are inadvertently structured by the mechanics of research management. (Author)

  2. Defense Threat Reduction Agency > Contracts > Contract Award Data

    Science.gov (United States)

    Integration Command Senior Enlisted Leader Media News News Archive Strategic Plan Videos Mission Research Support Center Contact Us FAQ Sheet Links Success Stories Contracts Business Opportunities Current Justifications & Approvals Careers Who We Are Our Values Strategic Recruiting Programs Professional

  3. Decommissioning and disposal of foreign uranium mine and mill facilities

    International Nuclear Information System (INIS)

    Pan Yingjie; Xue Jianxin; Yuan Baixiang; Xu Lechang

    2012-01-01

    Disposal techniques in decommissioning of foreign uranium mine and mill facilities are systematically discussed, including covering of uranium tailing impoundment, drainaging and consolidation of uranium tailing, and treatment of mining waste water and polluted groundwater, and the costs associated with disposal are analyzed. The necessity of strengthening the decommissioning disposal technology research and international exchanges and cooperation is emphasized. (authors)

  4. Instructive for disposal of fluorescent

    International Nuclear Information System (INIS)

    Salazar Vargas, Gerlin

    2014-01-01

    An instructive is established for the management system of waste fluorescent lamps, ensuring the storage, collection, transportation, and final disposal. The lamp is changed by an official of the Seccion de Matenimiento Construccion of the Oficina de Servicios Generales or is produced with the support of an official of the unit. The fluorescent should be deposited in stock of materials of the building maintenance section or unit specified with the help of a staff and in appropriate conditions. The fluorescent lamp is transported according to the guidelines in the manual. A responsible company is contracted by la Vicerrectoria de Administracion of the Universidad de Costa Rica dedicated to the transport and proper handling of fluorescent lamps [es

  5. 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)

  6. Radioactive waste disposal in W.A

    International Nuclear Information System (INIS)

    Hartley, B.M.

    1983-01-01

    Radioactive waste in Western Australia arises primarily from medical diagnosis and treatment and from scientific research mainly with a medical orientation. Waste is classified before disposal depending on its level and type of radioactivity and then disposed of either to municipal land fill sites, to the sewerage system or by incineration. The amounts of radioactive materials which may be disposed of to the sewers and air are set by the Radiation Safety Act (1975) Regulations, and the land fill operations are controlled to ensure isolation of the material. Other waste such as unwanted sources used in industrial applications are stored for future disposal. Discussions are being held between officers of the State and Australian Governments aimed at providing suitable disposal methods for sources of this kind

  7. Educational and Nonprofit Institutions Receiving Prime Contract Awards for RDT&E (Research, Development, Test and Evaluation), Fiscal Year 1981.

    Science.gov (United States)

    1981-01-01

    SCIENCE & TECH 162 - UNITED KINGDOM MINISTRY OF DEFENCE 2,670 - UN KINGDOM 162 UN KINGDOM 2,670 INSTITUT FUER ATMOSPHAERISCHE 25 - UNIVERSITE RENE ... DESCARTES 10 - GERMANY 25 FRANCE 10 INVERESK RESEARCH INTERNATIONAL 106 - 8,602 UN KINGDOM 106 ISRAEL INSTITUTE OF TECHNOLOGY 55 - ISRAEL 55 KEELE UNIVERSITY

  8. Research highlights under Contract DE-AC02-76ER03072, February 1, 1981-July 31, 1981

    International Nuclear Information System (INIS)

    Shoemaker, F.C.

    1981-01-01

    Research projects are highlighted including: a study of rare muon induced reactions; a search for eta/sub c/ mesons; hadronic production of charmed particles; production of high-mass dimuons by pions; forward production of massive particles; the crystal ball project at SPEAR; parallel plate avalanche chamber development; and tests of quantum mechanics

  9. Types of contracts and contracting procedures

    International Nuclear Information System (INIS)

    Zijl, N.A. van

    1977-01-01

    Contracting for a nuclear power plant can be carried out in many different ways, from a bilateral agreement between two countries to an international open bidding competition. Also the kind of contracts (turnkey, split-package or multi-contract type) are discussed with their pros and cons as well as the contracting procedures which can be followed to come to the conclusion of a contract. (orig.) [de

  10. 41 CFR 102-33.370 - What must we do to dispose of military FSCAP or life-limited parts?

    Science.gov (United States)

    2010-07-01

    ... before you exchange or sell the aircraft or engine (see rules for disposing of uninstalled life-limited... dispose of military FSCAP or life-limited parts? 102-33.370 Section 102-33.370 Public Contracts and... Aircraft Parts Special Requirements for Disposing of Flight Safety Critical Aircraft Parts (fscap) and Life...

  11. Iterative Contracts as Proactive Law Instruments

    DEFF Research Database (Denmark)

    Henschel, René Franz

    2012-01-01

    The purpose of this article is to analyse the use of proactive law in contracts illustrated by the use of a particular type of contract within the IT industry, the so-called iterative contract. This type of contract has its root in a special software development process called iterative and incre...... the potential to create more business success. However, empirical research still needs to be done in order to confirm that these types of contracts are better at securing business success than traditional contract forms....

  12. Final disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Anon,

    1995-10-01

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK).

  13. Final disposal of nuclear waste

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK)

  14. 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

  15. Study on reciprocal relation of pore water pressure with genetic algorithm and neural network model (Contract research)

    International Nuclear Information System (INIS)

    Seno, Shoji; Nakajima, Makoto; Toida, Masaru; Kunimaru, Takanori; Watanabe, Kunio; Sohail Ahmed Rai

    2009-12-01

    Horonobe Underground Research Center has carried out the Horonobe Underground Research Laboratory Project which is a comprehensive research project to investigate the deep geological environment within sedimentary rock. In this project, long-term observation of the pore water pressure has been conducted with monitoring systems introduced in 9 of 11 boreholes drilled in phase I (surface-based investigation). Since August 2003 the monitoring systems have been settled successively in the boreholes, and a certain amount of the pore water pressure data has been already accumulated. Using 6 borehole data (HDB-1,3,6,7,8,9) among this, this report summarized the result of a study on reciprocal relation of pore water pressure to investigate the hydrogeological environment of this site. At first, to exclude the influences of working of nature such as tide and atmospheric pressure from the source data, an analysis with Bayesian model was progressed. As the result of the estimation of these influences calculated by BAYTAP-G (Bayesian Tidal Analysis Program Grouping Model), it was found that the influence of the atmospheric pressure was comparatively large and that of tide was comparatively small. Secondly, an analysis on the reciprocal relation of the pore water pressure was carried out to investigate the relation between the different depth points of the same borehole and the relation between different boreholes. As the result of the calculations with genetic algorithm (GA) and neural network models (BPANN, GAANN), it was found that estimation by GA models was better than other models in the case where analyzing data included radical changes. And the result also showed that in regions lower than GL.-400m of HDB-3,6,7,8, the pore water pressures change in the same manner. These results indicate the effectiveness of this analysis method. (author)

  16. Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Co's RDandD Programme 2004. Programme for Research, Development and Demonstration of Methods for the Management and Disposal of Nuclear Waste, including Social Science Research

    International Nuclear Information System (INIS)

    2005-12-01

    verify the models in time prior to a licence application. Furthermore, the authorities assume that more long-term biosphere issues are being taken into account in SKB's new plan of action. - In its biosphere research, SKB should take into account the possibility of using radionuclide concentrations and flows as complementary safety indicators. - SKB should more clearly explain how it will ensure that studied climate scenarios will shed light on the most important climate-related stresses on the barrier function. - It is justifiable for the research conducted by SKB and Sweden in the area of PandT to maintain its current level so that international developments can be followed and to maintain and develop scientific and technical expertise in areas of importance for nuclear safety. - A clarification of the account of deep boreholes prior to the ultimate choice of a method and prior to licensing under the Environmental Code is needed. A comparison should be made with the KBS-3 method which utilizes safety assessment methodology including simple calculations. - SKB needs to intensify the work on decommissioning issues and in order to present detailed plans and considerations in RDandD Programme 2007. - SKB should investigate the shortest time required for the start of a licensing process for the disposal of decommissioning waste. - In the next RDandD programme, SKB should provide a more detailed description of the programme for long-lived low and intermediate-level waste. - SKB should take into account the viewpoint that long-term interim storage of waste while waiting for the construction of a repository should, as far as possible, be avoided and take this into consideration in its planning. - It is positive that SKB has incorporated social science research into its programme, since the findings from the research should be useful for the stakeholders to apply the research findings in ongoing and future consultation processes for an encapsulation plant and repository

  17. Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Co's RDandD Programme 2004. Programme for Research, Development and Demonstration of Methods for the Management and Disposal of Nuclear Waste, including Social Science Research

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-12-15

    verify the models in time prior to a licence application. Furthermore, the authorities assume that more long-term biosphere issues are being taken into account in SKB's new plan of action. - In its biosphere research, SKB should take into account the possibility of using radionuclide concentrations and flows as complementary safety indicators. - SKB should more clearly explain how it will ensure that studied climate scenarios will shed light on the most important climate-related stresses on the barrier function. - It is justifiable for the research conducted by SKB and Sweden in the area of PandT to maintain its current level so that international developments can be followed and to maintain and develop scientific and technical expertise in areas of importance for nuclear safety. - A clarification of the account of deep boreholes prior to the ultimate choice of a method and prior to licensing under the Environmental Code is needed. A comparison should be made with the KBS-3 method which utilizes safety assessment methodology including simple calculations. - SKB needs to intensify the work on decommissioning issues and in order to present detailed plans and considerations in RDandD Programme 2007. - SKB should investigate the shortest time required for the start of a licensing process for the disposal of decommissioning waste. - In the next RDandD programme, SKB should provide a more detailed description of the programme for long-lived low and intermediate-level waste. - SKB should take into account the viewpoint that long-term interim storage of waste while waiting for the construction of a repository should, as far as possible, be avoided and take this into consideration in its planning. - It is positive that SKB has incorporated social science research into its programme, since the findings from the research should be useful for the stakeholders to apply the research findings in ongoing and future consultation processes for an encapsulation plant and repository.

  18. 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

  19. Beatty, Nevada: A section in U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990 (WRI 91-4084)

    Science.gov (United States)

    Andraski, Brian J.; Fisher, Jeffrey M.; Prudic, David E.; Trask, N.J.; Stevens, P.R.

    1991-01-01

    A low-level radioactive-waste disposal facility in the Amargosa Desert of Nevada, about 17 km southeast of Beatty and 169 km northwest of Las Vegas, has been operating since 1962. This was the first commercially operated radioactive waste disposal facility in the United States. Wastes at the facility are emplaced in 2 to 15-m deep trenches and covered by backfilling with previously excavated materials. Annual precipitation in the area averages about 112 mm. Vegetation is sparse with creosote bush (Larrea tridentata) being the dominant species. Soils in the area are skeletal and are underlain by more than 170 m of unconsolidated alluvial-fan, fluvial, and ephemeral-lake deposits. Depth to water is about 85 m.Initial field investigations (1976-1980) included monitoring of soil-water content and water potential in an unvegetated soil profile, and collection of meteorological data at the disposal facility. Design of additional hydrogeologic investigations and long-term studies of soil-water movement in a vegetated soil profile began in 1982 and field data collection has been ongoing since 1984. Studies to evaluate the modifying effects of trench construction on the natural site environment and to determine changes in trench structural stability began in 1987. Design of studies to measure gas and vapor movement in the trenches at the facility began in 1989.

  20. Contracts for field projects and supporting research on enhanced oil recovery. Progress review No. 80. Quarterly report, July--September, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    This report contains information on petroleum enhanced recovery projects. In addition to project descriptions, contract numbers, principal investigators and project management information is included.

  1. The disposal of radioactive waste on land

    Energy Technology Data Exchange (ETDEWEB)

    None

    1957-09-01

    A committee of geologists and geophysicists was established by the National Academy of Sciences-National Research Council at the request of the Atomic Energy Commission to consider the possibilities of disposing of high level radioactive wastes in quantity within the continental limits of the United States. The group was charged with assembling the existing geologic information pertinent to disposal, delineating the unanswered problems associated with the disposal schemes proposed, and point out areas of research and development meriting first attention; the committee is to serve as continuing adviser on the geological and geophysical aspects of disposal and the research and development program. The Committee with the cooperation of the Johns Hopkins University organized a conference at Princeton in September 1955. After the Princeton Conference members of the committee inspected disposal installations and made individual studies. Two years consideration of the disposal problems leads to-certain general conclusions. Wastes may be disposed of safely at many sites in the United States but, conversely, there are many large areas in which it is unlikely that disposal sites can be found, for example, the Atlantic Seaboard. Disposal in cavities mined in salt beds and salt domes is suggested as the possibility promising the most practical immediate solution of the problem. In the future the injection of large volumes of dilute liquid waste into porous rock strata at depths in excess of 5,000 feet may become feasible but means of rendering, the waste solutions compatible with the mineral and fluid components of the rock must first be developed. The main difficulties, to the injection method recognized at present are to prevent clogging of pore space as the solutions are pumped into the rock and the prediction or control of the rate and direction of movement.

  2. Performance test of ex-core high temperature and high pressure water loop test equipment (Contract research)

    International Nuclear Information System (INIS)

    Nakano, Hiroko; Uehara, Toshiaki; Takeuchi, Tomoaki; Shibata, Hiroshi; Nakamura, Jinichi; Matsui, Yoshinori; Tsuchiya, Kunihiko

    2016-03-01

    In Japan Atomic Energy Agency, we started research and development so as to monitor the situations in the Nuclear Plant Facilities during a severe accident, such as a radiation-resistant monitoring camera, a radiation-resistant transmission system for conveying the in-core information, and a heat-resistant signal cable. As a part of developments of the heat-resistant signal cable, we prepared ex-core high-temperature and high-pressure water loop test equipment, which can simulate the conditions of BWRs and PWRs, for evaluating reliability and properties of sheath materials of the cable. This equipment consists of autoclave, water conditioning tank, high-pressure metering pump, preheater, heat exchanger and water purification equipment, etc. This report describes the basic design and the performance test results of ex-core high-temperature and high-pressure water loop test equipment. (author)

  3. Development of in-vessel type control rod drive mechanism for a innovative small reactor (Contract research)

    Energy Technology Data Exchange (ETDEWEB)

    Yoritsune, Tsutomu; Ishida, Toshihisa [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    Although the control rod drive mechanism of an existing large scale light water reactor is generally installed outside the reactor vessel, an in-vessel type control rod drive mechanism (INV-CRDM) is installed inside the reactor vessel. The INV-CRDM contributes to compactness and simplicity of the reactor system, and it can eliminate the possibility of a rod ejection accident. Therefore, INV-CRDM is an important technology adopted in an innovative small reactor. Japan Atomic Energy Research Institute (JAERI) has developed this type of CRDM driven by an electric motor, which can work under high temperature and high pressure water for the advanced marine reactor. On the basis of this research result, a driving motor coil and a bearing were developed to be used under the high temperature steam, severe condition for an innovative small reactor. About the driving motor, we manufactured the driving motor available for high temperature steam and carried out performance test under room temperature atmosphere to confirm the electric characteristic and coolability of the driving coil. With these test results and the past test results under high temperature water, we analyzed and evaluated the electric performance and coolability of the driving coil under high temperature steam. Concerning bearing, we manufactured the test pieces using some candidate material for material characteristic test and carried out the rolling wear test under high temperature steam to select the material. Consequently, we confirmed that performance of the driving coil for the advanced type driving motor, is enough to be used under high temperature steam. And, we evaluated the performance of the bearing and selected the material of the bearing, which can be used under high temperature steam. From these results, we have obtained the prospect that the INV-CRDM can be used for an innovative small reactor under steam atmosphere could be developed. (author)

  4. 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.

  5. 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

  6. RD and D-Programme 2001. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

    International Nuclear Information System (INIS)

    2001-09-01

    the Aespoe HRL will contain six deposition holes with canisters, and the test will proceed for 20 years. Material and methods for backfilling, closure and sealing of boreholes are also being developed at Aespoe. KBS-3 is the basis, but we will also examine variants of the concept. Such a variant is Medium Long Holes (MLH), whereby the canisters are deposited horizontally. The encapsulation plant where the spent fuel is to be placed in copper canisters, is still on the drawing board. The technology for welding on the copper lid is being developed at the Canister Laboratory in Oskarshamn. The technology for examining the weld joint is also being developed there. Elsewhere, different fabrication methods for the different parts of the canister are being tested. SKB has decided to monitor the development of the two alternatives partitioning and transmutation and deposition in Very Deep Holes. SKB is conducting general studies of decommissioning to ensure that competence exists and that the costs are correctly estimated. The aim during the coming six-year period is to develop methods for dry interim storage of core components, introduce systems for registration of the waste, review the decommissioning logistics, estimate doses in conjunction with decommissioning, and carry out preliminary safety assessments of final disposal. An important element in this work is monitoring of foreign activities. Long-lived waste from decommissioning in the form of reactor internals and core components also have to be disposed of in a final repository. This repository must also accommodate long-lived LILW (low-and intermediate-level waste) from research, industry and medicine. A preliminary design of the repository for long-lived LILW has been studied and a safety assessment has been conducted. The repository does not have to be put into operation for another 45 years

  7. Low level radioactive waste disposal

    International Nuclear Information System (INIS)

    Balaz, J.; Chren, O.

    2015-01-01

    The Mochovce National Radwaste Repository is a near surface multi-barrier disposal facility for disposal of processed low and very low level radioactive wastes (radwastes) resulting from the operation and decommissioning of nuclear facilities situated in the territory of the Slovak Republic and from research institutes, laboratories, hospitals and other institutions (institutional RAW) which are in compliance with the acceptance criteria. The basic safety requirement of the Repository is to avoid a radioactive release to the environment during its operation and institutional inspection. This commitment is covered by the protection barrier system. The method of solution designed and implemented at the Repository construction complies with the latest knowledge and practice of the repository developments all over the world and meets requirements for the safe radwaste disposal with minimum environmental consequences. All wastes are solidified and have to meet the acceptance criteria before disposal into the Repository. They are processed and treated at the Bohunice RAW Treatment Centre and Liquid RAW Final Treatment Facility at Mochovce. The disposal facility for low level radwastes consists of two double-rows of reinforced concrete vaults with total capacity 7 200 fibre reinforced concrete containers (FCCs) with RAW. One double-row contains 40 The operation of the Repository was started in year 2001 and after ten years, in 2011 was conducted the periodic assessment of nuclear safety with positive results. Till the end of year 2014 was disposed to the Repository 11 514 m 3 RAW. The analysis of total RAW production from operation and decommissioning of all nuclear installation in SR, which has been carried out in frame of the BIDSF project C9.1, has showed that the total volume estimation of conditioned waste is 108 thousand m 3 of which 45.5 % are low level waste (LLW) and 54,5 % very low level waste (VLLW). On the base of this fact there is the need to build 7

  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. Assessment of uncertainties associated with characterization of geological environment in the Tono area. Japanese fiscal year, 2006 (Contract research)

    International Nuclear Information System (INIS)

    Toida, Masaru; Suyama, Yasuhiro; Seno, Shoji; Atsumi, Hiroyuki; Ogata, Nobuhisa

    2008-03-01

    'Geoscientific research' performed at the Tono Geoscience Center is developing site investigation, characterization and assessment techniques for understanding of geological environment. Their important themes are to establish a methodology for analyzing uncertainties in heterogeneous geological environment, and to develop investigation techniques for reducing the uncertainties efficiently. This study proposes a new approach where all the possible options in the models and data-sets that cannot be excluded in the light of the evidence available, are identified. This approach enables uncertainties associated with the understanding at a given stage of the site characterization to be made explicitly using an uncertainty analysis technique based on Fuzzy geostatistics. This, in turn, supports the design of the following investigation stage to reduce the uncertainties efficiently. In the study, current knowledge had been compiled, and the technique had been advanced through geological modeling and groundwater analyses in the Tono area. This report systematized the uncertainty analysis methodology associated with the characterization of the geological environment, and organized the procedure of the methodology with the application examples in the study. This report also dealt with investigation techniques for reducing the uncertainties efficiently, and underground facility design options for handling geological uncertainties based on the characterization of the geological environment. (author)

  11. Thermal and chemical analysis on steam reforming in an out-of-pile test facility (Contract research)

    Energy Technology Data Exchange (ETDEWEB)

    Haga, Katsuhiro [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Suyama, Kazumasa; Inagaki, Yoshiyuki; Hayashi, Kohji; Ogawa, Masuro

    1999-08-01

    An out-of-pile test facility of a hydrogen production system whose scale is 1/30th of the HTTR hydrogen production system is presently under construction at the Oarai Establishment of the Japan Atomic Energy Research Institute. In this system, a steam generator works as a thermal buffer for mitigating the heat consumption fluctuation in a steam reformer so as not to affect an operation of the reactor system. To control the thermal buffer system properly, it is important to evaluate the effect of the steam reforming parameters on the heat fluctuation in advance. So, using the mass and thermal balance analysis code developed for a simulation of the out-of-pile test facility, the heat consumption fluctuation in the steam reformer was analyzed by various changes of the process gas flow rate, the process gas inlet temperature, the process gas composition etc. From the analytical results, it was found that the heat transfer augmentation of the reformer tube by using repeated fins was effective in increasing the hydrogen production rate of up to 12.5%. Also, the fluctuation of the process gas flow rate tended to greatly affect the heat consumption rate for the steam reforming reaction, so that the helium gas temperature increased from 586degC to 718degC. (author)

  12. Release behavior of smoke and clogging characteristics of the ventilation filter under the fire accident. Contract research

    Energy Technology Data Exchange (ETDEWEB)

    Takada, Junichi; Watanabe, Koji; Tsukamoto, Michio; Tashiro, Shinsuke [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Hayashi, Shiro [Nippon Muki Corp., Tokyo (Japan); Takita, Koji [Sanzo Environment Engineering Corp., Tokyo (Japan); Abe, Hitoshi [Ministry of Economy Trade and Industry, Tokyo (Japan); Uchiyama, Gunzo [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

    2003-01-01

    In a part of building ventilating installation of reprocessing plant, the pre-filter is equipped in front of a HEPA filter. The pre-filter plays a role in protection and repression of clogging of HEPA filter. However, in a fire accident, it is considered that large smoke generation cause the pre-filter clogging due to smoke loading, increase of differential pressure and breakdown. In Japan Atomic Energy Research Institute, the demonstration tests to confirm the performance of ventilation filters by a fire accident were carried out. In the tests, smoke was generated from burning of the mock solid wastes (gloves made of rubber and/or cloth) or the mock recovered solvent (n-dodecane or tributyl phosphate / n-dodecane). The test data was acquired on generation of smoke, decrease evolution of smoke by transportation through the compositions of ventilation system (cell, duct, damper, filters) and clogging characteristics of the ventilation filters due to smoke loading. From the results, it was found that the performance of the whole of ventilation system was kept even if the pre-filter was breakdown. To adopt the analysis of the increase of differential pressure across the pre-filter using the safety analysis code, CELVA-1D, increase of differential pressure across the pre-filter was expressed by quadratic empirical equation with function of smoke loading per unit filtration area and it coefficients, ({alpha}, {beta}), were estimated. (author)

  13. [Good clinical practices in clinical trials: the responsibility of the researcher. A survey of 827 hospital physicians (I). Availability. Monitoring. Safety. Contract].

    Science.gov (United States)

    Dal-Ré, R

    1993-03-06

    The Law of Medicaments establishes that clinical trials (CT) with drugs must be carried out following the of Good Clinical Practice guidelines (GCP). The attitude of hospital physicians to the GCP prior to its implementation as mandatory in accordance with Spanish legislation was considered to be of interest. An anonymous survey was used with closed response questions. Questions referring to the responsibilities of the investigator included in the GCP were included. From December 1988 to February 1990 the survey was distributed among 1,706 hospital medical staff members, of any specialty, who had or had not participated in CT. In this article the results of the questions regarding the availability of the investigative team, CT monitorization, management of adverse reactions, the safety of the participants in the CT and the contract between the sponsor and the researcher are presented. A total of 827 hospital doctors replied to the survey. Fifty-nine percent had intervened in CT with drugs. At least 94% of those surveyed considered that the researcher must have the time and number of eligible patients which the CT requires. There was high acceptance (> or = 78%) of the clinical audits to be performed by the health authorities and the sponsor company of the CT. The need of urgent communication of the severe adverse reactions is admitted by a great majority (> or = 95%) of those surveyed. Eighty-five percent believe that patients should be insured against damage derived from CT with 76% considering that the investigator should sign a contract with the sponsor; 68% and 59% would hand in a copy of the same to the CT committee and the remainder of the research team, respectively. According to the Good Clinical Practice dealt with in this article, the responsibilities of the investigator have been widely accepted by the hospital physicians surveyed, therefore no problems should be expected upon the implementation of the same in this country. However, the economic

  14. Using Automation to Monitor and Report Hazardous Waste Disposal Costs: A Mission-Critical Obligation

    National Research Council Canada - National Science Library

    Hassrick, H

    1996-01-01

    Controlling, monitoring, and reporting hazardous waste disposal costs has become increasingly important as environmental problems arise, costs escalate, and budgets contract. In FY94, the U.S. Army, Europe (USAREUR), spent...

  15. Inventory of radioactive material entering the marine environment: Sea disposal of radioactive waste

    International Nuclear Information System (INIS)

    1991-03-01

    Variable amounts of packaged low level radioactive waste have been disposed at more than 50 sites in the northern parts of the Atlantic and Pacific Oceans. The last known disposal operation was in 1982, at a site about 550 km off the European continental shelf in the Atlantic Ocean. Since 1957, the IAEA has provided specific guidance and recommendations for ensuring that disposal of radioactive wastes into the sea will not result in unacceptable hazards to human health and marine organisms, damage to amenities or interference with other legitimate uses of the sea. In 1972, the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter designated the IAEA as the competent international authority in matters related to sea disposal of radioactive waste. The Contracting Parties requested the IAEA to develop an inventory of radioactive wastes entering the marine environment from all sources as an information base with which the impact of radioactive materials from disposal operations can be more adequately assessed. The continuous compilation of these data could ensure that the IAEA recommendations on the disposal rate in a single basin are not overstepped. The inventory shows that between 1946 to 1982 an estimated 46 PBq 1 (1.24 MCi) of radioactive waste coming from research, medicine, the nuclear industry and military activities were packaged, usually in metal drums lined with a concrete or bitumen matrix, and disposed of at sea. This inventory includes some unpackaged wastes and liquid wastes which were disposed of from 1950 to 1960. Beta-gamma emitters represent more than 98% of the total radioactivity of the waste and tritium alone represents one third of the total radioactivity disposed at the North East Atlantic sites. The other beta-gamma emitters radionuclides include 90 Sr, 137 Cs, 55 Fe, 58 Co, 60 Co, 125 I and 14 C. The wastes also contain low quantities of alpha-emitting nuclides with plutonium and americium isotopes representing

  16. 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.)

  17. 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

  18. 48 CFR 204.805 - Disposal of contract files.

    Science.gov (United States)

    2010-10-01

    ... Schedule 3 (Procurement, Supply, and Grant Records) and General Records Schedule 6 (Accountable Officers... Defense Acquisition Regulatory Council. Forward requests for deviations to both the Government... 15.403-4), for six years. If it is impossible to determine the final payment date in order to measure...

  19. Beatty, Nevada: A section in U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1983, 1984, and 1985 (WRI 87-4009)

    Science.gov (United States)

    Fischer, Jeffrey M.; Nichols, William D.; Dinwiddie, G.A.; Trask, N.J.

    1986-01-01

    A commercial low-level radioactive-waste disposal site has been operating near Beatty, Nevada, about 150 km northwest of Las Vegas, since 1962. The 32-ha site is situated in a desolate region of the Amargosa River Valley, sometimes referred to as the Amargosa Desert. Average annual precipitation is only about 114 mm. The site is underlain by 175 m of unconsolidated, generally coarse-grained, alluvial-fan and flood-plain deposits. The water table is at a depth of 90 m.

  20. Siting of geological disposal facilities

    International Nuclear Information System (INIS)

    1994-01-01

    Radioactive waste is generated from the production of nuclear energy and from the use of radioactive materials in industrial applications, research and medicine. The importance of safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. The Radioactive Waste Safety Standards (RADWASS) programme is the IAEA's contribution to establishing and promoting the basic safety philosophy for radioactive waste management and the steps necessary to ensure its implementation. This Safety Guide defines the process to be used and guidelines to be considered in selecting sites for deep geological disposal of radioactive wastes. It reflects the collective experience of eleven Member States having programmes to dispose of spent fuel, high level and long lived radioactive waste. In addition to the technical factors important to site performance, the Safety Guide also addresses the social, economic and environmental factors to be considered in site selection. 3 refs