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Sample records for australian replacement research reactor

  1. The Australian Replacement Research Reactor

    Science.gov (United States)

    Kennedy, Shane; Robinson, Robert

    2004-03-01

    The 20-MW Australian Replacement Research Reactor represents possibly the greatest single research infrastructure investment in Australia's history. Construction of the facility has commenced, following award of the construction contract in July 2000, and the construction licence in April 2002. The project includes a large state-of-the-art liquid deuterium cold-neutron source and supermirror guides feeding a large modern guide hall, in which most of the instruments are placed. Alongside the guide hall, there is good provision of laboratory, office and space for support activities. While the facility has "space" for up to 18 instruments, the project has funding for an initial set of 8 instruments, which will be ready when the reactor is fully operational in July 2006. Instrument performance will be competitive with the best research-reactor facilities anywhere, and our goal is to be in the top 3 such facilities worldwide. Staff to lead the design effort and man these instruments have been hired on the international market from leading overseas facilities, and from within Australia, and 7 out of 8 instruments have been specified and costed. At present the instrumentation project carries 10contingency. An extensive dialogue has taken place with the domestic user community and our international peers, via various means including a series of workshops over the last 2 years covering all 8 instruments, emerging areas of application like biology and the earth sciences, and computing infrastructure for the instruments.

  2. Progress with the Australian replacement research reactor

    International Nuclear Information System (INIS)

    Construction of the new Australian Research Reactor, the replacement for the now 46 year old HIFAR research reactor, is approximately 80% completed. Construction of the reactor facility began in April 2002 at ANSTO's Lucas Heights site near Sydney and commissioning is still on track for late 2005. Some details of the progress of construction and licensing and an outline of ANSTO research related to the use of Zircaloy-4 in the core region and reflector vessel of the reactor are given. (author)

  3. Licensing of the Australian replacement research reactor

    International Nuclear Information System (INIS)

    The Australian Nuclear Science and Technology Organisation (ANSTO)'s Replacement Research Reactor has been submitted to a comprehensive licensing process of which peer review has been a fundamental part. Following Australian Regulation, an application for a site licence was the first step supported by an Environmental Impact Statement approved by The Minister for the Environment and Heritage, and a Reference Accident Analysis. After the site licence had been granted and the contract awarded to the Designer and Constructor, INVAP S.E:, a 2500 page Preliminary Safety Analysis Report was submitted by ANSTO to the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA), which conducted its review. ARPANSA requested that the PSAR be also reviewed by an experts mission from the International Atomic Energy Agency. The PSAR was also reviewed by the Argentine Regulatory Body, it was submitted to public examination in Australia and it was reviewed by international experts hired as consultants by several Australian organisations. A public forum was also held in Sydney. The Regulator, the applicant and the Designer-Constructor maintained constant interaction during the whole process, so that questions, comments and observations that arose from the review of the PSAR were fed back to the designers. This process allowed for a robust, safe design enriched by the results of the safety analysis and review process. (author)

  4. Neutron beam facilities at the Australian Replacement Research Reactor

    International Nuclear Information System (INIS)

    Australia is building a research reactor to replace the HIFAR reactor at Lucas Heights by the end of 2005. Like HIFAR, the Replacement Research Reactor will be multipurpose with capabilities for both neutron beam research and radioisotope production. It will be a pool-type reactor with thermal neutron flux (unperturbed) of 4 x 1014 n/cm2/sec and a liquid D2 cold neutron source. Cold and thermal neutron beams for neutron beam research will be provided at the reactor face and in a large neutron guide hall. Supermirror neutron guides will transport cold and thermal neutrons to the guide hall. The reactor and the associated infrastructure, with the exception of the neutron beam instruments, is to be built by INVAP S.E. under contract. The neutron beam instruments will be developed by ANSTO, in consultation with the Australian user community. This status report includes a review the planned scientific capabilities, a description of the facility and a summary of progress to date. (author)

  5. Replacement research reactor for Australia

    International Nuclear Information System (INIS)

    In 1992, the Australian Government commissioned a review into the need for a replacement research reactor. That review concluded that in about years, if certain conditions were met, the Government could make a decision in favour of a replacement reactor. A major milestone was achieved when, on 3 September 1997, the Australian Government announced the construction of a replacement research reactor at the site of Australia's existing research reactor HIFAR, subject to the satisfactory outcome of an environmental assessment process. The reactor will be have the dual purpose of providing a first class facility for neutron beam research as well as providing irradiation facilities for both medical isotope production and commercial irradiations. The project is scheduled for completion before the end of 2005. (author)

  6. The replacement research reactor

    International Nuclear Information System (INIS)

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  7. Report on neutron powder diffraction for the Australian Replacement Research Reactor

    International Nuclear Information System (INIS)

    There is a clear need for two neutron powder diffractometers at the Australian Replacement Research Reactor when it starts operation in 2005. The high-intensity instrument should be capable of measuring a 10mg sample of moderate complexity, or perform single-shot time-resolved experiments with 1-second time slices, or perform stroboscopic measurements with time slices of order 50 microseconds. The high-resolution instrument should have a target resolution of Δd/d∼6x10-4, and be capable of collecting data at this resolution within 1-48 hours depending on sample size and crystal complexity. Key questions that need to be answered in the next 9 months include: (1) a detailed study of monochromator options, (2) analysing the detector options for the high-intensity machine and exploring ways in which the solid angle can be maximised for both instruments, (3) whether the instruments are better situated at the reactor face or on super mirror guides, (4) how to integrate the two instruments (physically, if they are only the same guide), and scientifically as regards detailed performance specifications. The user community clearly wants a wide range of sample-environment options, and these are listed in the report. Combinations of these options will be important

  8. The replacement research reactor

    International Nuclear Information System (INIS)

    The contract for the design, construction and commissioning of the Replacement Research Reactor was signed in July 2000. This was followed by the completion of the detailed design and an application for a construction licence was made in May 2001. This paper will describe the main elements of the design and their relation to the proposed applications of the reactor. The future stages in the project leading to full operation are also described

  9. Report on inelastic neutron scattering for the Australian Replacement Research Reactor

    International Nuclear Information System (INIS)

    The Replacement Reactor Project includes a sub project, the Neutron Beam Instrument project, to construct a suite of eight leading edge neutron scattering instruments to be ready at reactor start up in 2005. Amongst these will be an inelastic scattering instrument and this workshop explored the options that would best serve the future needs of the Australian neutron scattering community.Considering the dynamic range of each of these instruments and the ability to address the needs of the widest group of problems, the workshop endorsed the recommendation of the Beam Facilities Consultative Group to build a thermal neutron three-axis spectrometer, which offers the project the best opportunity and flexibility in terms of the available wave-vector and energy range. It was also recommend that priority consideration be given to developing cold neutron three-axis and time-of-flight spectrometers, perhaps in collaboration with outside organisations, after completion of the initial project. thermal neutron three axis spectrometer. The workshop recommended that such an instrument should be built at the reactor face on a thermal beam, using a double-focussing monochromator and analyser. Polarisation analysis should be available as an option and that the instrument perform at or close to world's best level. Recommendations were received on sample environment requirements and low temperature, high temperature and strong magnetic fields are seen as necessary

  10. The residual-stress diffractometer for the Australian replacement research reactor

    International Nuclear Information System (INIS)

    Full text: Many residual stress-related problems exist in a wide variety of fields in industry, such as the manufacturing industries, mining, oil and gas, rail transport, defense and life extension. Stress scanning at the new Replacement Research Reactor will provide a tool for solving problems to complement facilities at the major research institutes in Australia, CSIRO, AMIRA, DSTO, ANSTO and the universities. Typically, the spacing of the crystal lattice provides a natural gauge of the state of strain, and hence stress, locked within an engineering component. For this reason, diffraction measurements have been performed for at least seventy years to measure residual strains. These complement mechanical, but destructive, methods of measuring strains and have comparable accuracy. Stress plays an acknowledged role in welding technologies. Stresses are the precursor to the distortions occurring upon welding. As well, tensile stresses can concentrate hydrogen near a weld and provides the driving force for crack growth. The extent of the stress-field in a weld matches the spatial resolution easily available with strain scanning and provides information over the whole weld, near the surface as well as at depth. Strain scanning provides a diagnostic tool to optimize post-weld heat treatment to bring the stresses to acceptable levels since the same sample can be repeatedly tested. At present all efforts are taken in order to optimize the residual-stress diffractometer which will belong to the first generation of instruments for the Replacement Research Reactor and the results will be presented

  11. Australia's replacement research reactor project

    International Nuclear Information System (INIS)

    HIFAR, a 10 MW tank type DIDO Class reactor has operated at the Lucas Heights Science and Technology Centre for 43 years. HIFAR and the 10 kW Argonaut reactor 'Moata' which is in the Care and Maintenance phase of decommissioning are Australia's only nuclear reactors. The initial purpose for HIFAR was for materials testing to support a nuclear power program. Changing community attitude through the 1970's and a Government decision not to proceed with a planned nuclear power reactor resulted in a reduction of materials testing activities and a greater emphasis being placed on neutron beam research and the production of radioisotopes, particularly for medical purposes. HIFAR is not fully capable of satisfying the expected increase in demand for medical radiopharmaceuticals beyond the next 5 years and the radial configuration of the beam tubes severely restricts the scope and efficiency of neutron beam research. In 1997 the Australian Government decided that a replacement research reactor should be built by the Australian Nuclear Science and Technology Organisation at Lucas Heights subject to favourable results of an Environmental Impact Study. The Ei identified no reasons on the grounds of safety, health, hazard or risk to prevent construction on the preferred site and it was decided in May 1999 that there were no environmental reasons why construction of the facility should not proceed. In recent years ANSTO has been reviewing the operation of HIFAR and observing international developments in reactor technology. Limitations in the flexibility and efficiency achievable in operation of a tank type reactor and the higher intrinsic safety sought in fundamental design resulted in an early decision that the replacement reactor must be a pool type having cleaner and higher intensity tangential neutron beams of wider energy range than those available from HIFAR. ANSTO has chosen to use it's own resources supported by specialised external knowledge and experience to identify

  12. Report on polarised and inelastic cold neutron scattering at the Australian Replacement Research Reactor

    International Nuclear Information System (INIS)

    The ANSTO's Instrument Workshop on Polarised and Inelastic Cold Neutron Scattering, was held at Lucas Heights on 27-28 January. 30 participants attended, from 6 Australian Universities, 3 ANSTO Divisions, and 5 overseas countries in Asia, Europe and North America. All participants had the opportunity to give their vision for work in 2005 and beyond. The recommendation was that ANSTO proceed with a monochromator/ shield/ polariser system and appropriate dance floor on a cold guide, in such a way that alternative secondary spectrometers (3-axis, LONGPOL-type, reflectometry) can be installed. If the National Science Council of Taiwan proceeds with its cold 3-axis project, ANSTO should then implement the LONGPOL / polarised-beam reflectometry option. If not, ANSTO should implement the cold 3-axis spectrometer. The workshop came to the following additional conclusions: There was a strong sense that any 3-axis spectrometer should have a multi-analyser/multidetector combination, or at least an upgrade path to this. At this stage, there is no case for 2 cold-neutron triple-axis spectrometers at the RRR. The desired Q-range is 0.02-5 Angstroms-1; with an energy transfer range of 20 μeV - 15 meV. The instrument is likely to run unpolarised for 2/3 of the time and polarised for the remainder, and the instrument(s) should be designed to allow easy changeover between polarised and unpolarised operation. We expect roughly equal interest/demand in studying single crystals, powders, surfaces/interfaces and naturally disordered systems. There was a strong sense that the facility should eventually have a cold-neutron time-of-flight spectrometer of the IN5 or IN6 type, with a polarised incident beam option, and designed in such a way that polarisation analysis could be implemented if inexpensive large-area analysers become available. This should be a high priority for the next wave of instruments that ANSTO plans to build after 2005

  13. Report on neutron reflectometry for the Australian Replacement Reactor

    International Nuclear Information System (INIS)

    There is a clear need for at least one neutron reflectometer at the Australian Replacement Research Reactor when it commences operation in 2005. The participants at the reflectometry workshop have identified that the neutron reflectometer to be built at the Australian Replacement Research Reactor must be capable of the study of: 1. Specular scattering from air/solid, solid/liquid and in particular 'free liquid' samples; and 2. Off-specular' scattering from the above sample types. 3. Kinetics phenomena on a minute or slower time scale; 4. A range of samples of differing thicknesses, ranging from ultra-thin films to thousand angstrom thick films. In order to achieve this the reflectometer should have the capacity to vary its resolution. Interest was also expressed at the ability to conduct glancing-angle and wide-angle scattering studies for the investigation of short length scale, in-plane structures. There was little interest expressed by the workshop participants for polarised neutron reflectometry. This report contains a scientific case for a neutron reflectometer to be built at the Australian Replacement Research Reactor on a cold neutron guide, which is based on the areas of scientific research expressed by the workshop participants. In addition, trends in neutron reflectometry research conducted at major overseas neutron facilities are noted. The new neutron Reflectometer should: 1. Be based on the Time-of-Flight method; 2. Have a vertical scattering plane (i.e. operate for horizontal samples); 3. Be located on the end of a cold neutron guide, or be built off the guide axis using a bender, 4. Have a position sensitive area detector, 5. Be similar in spirit to the new D17 reflectometer at the ILL. Basic aspects of a reflectometer design are discussed which meet the above-stated scientific criteria and include a preliminary list of instrument specifications, capabilities and ancillary equipment requested by the workshop participants. A preliminary instrument

  14. Safety Features of the Replacement Research Reactor

    International Nuclear Information System (INIS)

    The paper presents a general description of the development and application of basic safety criteria and the implementation of specific safety features in the design of the 20 MW pool-type research reactor currently being built by INVAP for the Australian Nuclear Science and Technology Organisation (ANSTO). A summary of the results of the preliminary deterministic safety analysis and the probabilistic safety assessment prepared by INVAP on ANSTO's behalf are presented as part of demonstrating the robustness of the design to the wide range of postulated initiating events considered. The paper also briefly describes the licensing process with respect to the way in which the licensing and regulatory regime within Australia influenced the design of the replacement research reactor (RRR). In particular, the reasoning for safety design features that have been incorporated as a result of the specific requirements of ANSTO and the Australian regulator is described. (author)

  15. Licensing of ANSTO's Replacement Research Reactor

    International Nuclear Information System (INIS)

    This paper presents a general description of the licensing of the 20 MW Pool-type Replacement Research Reactor (RRR) currently being built by the Australian Nuclear Science and Technology Organisation (ANSTO) at their Lucas Heights site. The following aspects will be addressed: 1) The influence of ARPANSA's (the Australian regulator) Regulatory Assessment Principles and Design Criteria on the design of the RRR. 2) The Site Licence Application, including the EIS and the supporting siting documentation. 3) The Construction Licence Application, including the PSAR and associated documentation. 4) The review process, including the IAEA Peer Review and the Public Submissions as well as ARPANSA's own review. 5) The interface between ANSTO, INVAP and ARPANSA in relation to the ongoing compliance with ARPANS Regulation 51 and 54. 6) The future Operating Licence Application, including the draft FSAR and associated documentation. These aspects are all addressed from the point of view of the licensee ANSTO and the RRR Project. Particular emphasis will be given to the way in which the licensing process is integrated into the overall project program and how the licensing and regulatory regime within Australia influenced the design of the RRR. In particular, the safety design features that have been incorporated as a result of the specific requirements of ANSTO and the Australian regulator will be briefly described. The paper will close with a description of how the RRR meets, and in many aspects exceeds the requirements of ANSTO and the Australian regulator. (author)

  16. Report on the workshop on neutrons for engineering and its conclusions regarding the residual-stress diffractometer at the Australian Replacement Research Reactor

    International Nuclear Information System (INIS)

    The purpose of the workshop was to: inform the Australian research organizations and universities of the capabilities of an engineering and materials science instrument; promote the use of neutron diffraction to map and investigate strains/stresses in materials and components for industrial applications and research; identify the future needs and opportunities in this area; present the options for a stress mapping diffractometer at the Replacement Research Reactor and receive feedback on these options; identify the ancillary equipment and facilities required. Presented papers and discussions at the workshop indicated that there are a number of important benefits to Australia in the building of a first-class instrument for materials science and engineering and many residual stress-related problems in a wide variety of fields in Australia, such as the manufacturing industries, mining, oil and gas, rail transport, defense and life extension. Stress scanning provides another tool for solving problems to complement facilities at the major research institutes, CSIRO, AMIRA, DSTO, ANSTO and the universities. It will create a regional pool of experts who may tap into the pool of expertise internationally. The turn around time for tests for Australian customers will be reduced thus avoiding having to go overseas to have the tests performed. From an educational perspective the instrument will build expertise in Australia and will help to attract graduates into engineering. A detailed list of the attendees and affiliations is in Appendix C

  17. The importance of project networking for the replacement research reactor

    International Nuclear Information System (INIS)

    When the HIFAR research reactor was commissioned in 1958 it was both constructed and regulated by the then Australian Atomic Energy Commission. The situation now is much more complicated, with an independent regulator, The Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) and oversight by national security agencies and the Australian Safeguards and Non proliferation Organisation (ASNO). In July 2000 ANSTO contracted INVAP SE a suitably qualified and experienced nuclear organisation based in Argentina to provide the Replacement Research Reactor (RRR). INVAP subcontracted an Australian entity, a joint venture between John Holland and Evans Deakin Industries (JHEDI) to provide resources in Australia. There is an international network of over 100 subcontractors providing services, products and materials to INVAP and JHEDI and a significant number of contractors providing project support services to ANSTO. The interaction of all these entities to provide the RRR is a significant networking challenge, involving a complex network of legal, contractual and functional relationships and communication processes

  18. The nuclear safety case for the replacement research reactor

    International Nuclear Information System (INIS)

    This paper presents a broad overview of the safety case being used in the licensing of Australia's Replacement Research Reactor. The reactor is a 20 MW pool-type research reactor and is being constructed at the Lucas Heights Science and Technology Centre in Sydney's south. It will be owned and operated by the Australian Nuclear Science and Technology Organisation (ANSTO) and will take over the duties currently performed by HIFAR, a DIDO-type reactor currently operating at the site. The safety case for the RRR considers all aspects of normal operation and anticipated occurrences and will be subject to periodic review and updated in line with evolving methodologies and modifications to plant and procedures. Its scope and degree of detail ensure that the risk posed to members of the public, operators and environment are all adequately low and well in the regulatory limits

  19. Reactor training simulator for the Replacement Research Reactor (RRR)

    International Nuclear Information System (INIS)

    The main features of the ANSTO Replacement Research Reactor (RRR) Reactor Training Simulator (RTS) are presented.The RTS is a full-scope and partial replica simulator.Its scope includes a complete set of plant normal evolutions and malfunctions obtained from the plant design basis accidents list.All the systems necessary to implement the operating procedures associated to these transients are included.Within these systems both the variables connected to the plant SCADA and the local variables are modelled, leading to several thousands input-output variables in the plant mathematical model (PMM).The trainee interacts with the same plant SCADA, a Foxboro I/A Series system.Control room hardware is emulated through graphical displays with touch-screen.The main system models were tested against RELAP outputs.The RTS includes several modules: a model manager (MM) that encapsulates the plant mathematical model; a simulator human machine interface, where the trainee interacts with the plant SCADA; and an instructor console (IC), where the instructor commands the simulation.The PMM is built using Matlab-Simulink with specific libraries of components designed to facilitate the development of the nuclear, hydraulic, ventilation and electrical plant systems models

  20. Replacement Nuclear Research Reactor: Draft Environmental Impact Statement. Vol. 1. Main report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The Draft Environmental Impact Statement (EIS) for the replacement of the Australian Research reactor has been released. An important objective of the EIS process is to ensure that all relevant information has been collected and assessed so that the Commonwealth Government can make an informed decision on the proposal. The environmental assessment of the proposal to construct and operate a replacement reactor described in the Draft EIS has shown that the scale of environmental impacts that would occur would be acceptable, provided that the management measures and commitments made by ANSTO are adopted. Furthermore, construction and operation of the proposed replacement reactor would result in a range of benefits in health care, the national interest, scientific achievement and industrial capability. It would also result in a range of benefits derived from increased employment and economic activity. None of the alternatives to the replacement research reactor considered in the Draft EIS can meet all of the objectives of the proposal. The risk from normal operations or accidents has been shown to be well within national and internationally accepted risk parameters. The dose due to reactor operations would continue to be small and within regulatory limits. For the replacement reactor, the principle of `As Low As Reasonably Achievable` would form an integral part of the design and licensing process to ensure that doses to operators are minimized. Costs associated with the proposal are $286 million (in 1997 dollars) for design and construction. The annual operating and maintenance costs are estimated to be $12 million per year, of which a significant proportion will be covered by commercial activities. The costs include management of the spent fuel from the replacement reactor as well as the environmental management costs of waste management, safety and environmental monitoring. Decommissioning costs for the replacement reactor would arise at the end of its lifetime

  1. Progress with OPAL, the new Australian research reactor

    Indian Academy of Sciences (India)

    R A Robinson

    2008-11-01

    Australian science is entering a new `golden age', with the start-up of bright new neutron and photon sources in Sydney and Melbourne, in 2006 and 2007 respectively. The OPAL reactor and the Australian Synchrotron can be considered as the greatest single investment in scientific infrastructure in Australia's history. They will essentially be `sister' facilities, with a common open user ethos, and a vision to play a major role in international science. Fuel was loaded into the reactor in August 2006, and full power was (20 MW) achieved in November 2006. The first call for proposals was made in 2007, and commissioning experiments have taken place well before then. The first three instruments in operation are high-resolution powder diffractometer (for materials discovery), high-intensity powder diffractometer (for kinetics experiments and small samples) and a strain scanner (for mechanical engineering and industrial applications). These are closely followed by four more instruments with broad application in nanoscience, condensed matter physics and other scientific disciplines. Instrument performance will be competitive with the best research-reactor facilities anywhere. To date there is committed funding for nine instruments, with a capacity to install a total of ∼ 18 beamlines. An update will be given on the status of OPAL, its thermal and cold neutron sources, its instruments and the first results.

  2. Neutron beam facilities at the Replacement Research Reactor, ANSTO

    International Nuclear Information System (INIS)

    The exciting development for Australia is the construction of a modern state-of-the-art 20-MW Replacement Research Reactor which is currently under construction to replace the aging reactor (HIFAR) at ANSTO in 2006. To cater for advanced scientific applications, the replacement reactor will provide not only thermal neutron beams but also a modern cold-neutron source moderated by liquid deuterium at approximately -250 deg C, complete with provision for installation of a hot-neutron source at a later stage. The latest 'supermirror' guides will be used to transport the neutrons to the Reactor Hall and its adjoining Neutron Guide Hall where a suite of neutron beam instruments will be installed. These new facilities will expand and enhance ANSTO's capabilities and performance in neutron beam science compared with what is possible with the existing HIFAR facilities, and will make ANSTO/Australia competitive with the best neutron facilities in the world. Eight 'leading-edge' neutron beam instruments are planned for the Replacement Research Reactor when it goes critical in 2006, followed by more instruments by 2010 and beyond. Up to 18 neutron beam instruments can be accommodated at the Replacement Research Reactor, however, it has the capacity for further expansion, including potential for a second Neutron Guide Hall. The first batch of eight instruments has been carefully selected in conjunction with a user group representing various scientific interests in Australia. A team of scientists, engineers, drafting officers and technicians has been assembled to carry out the Neutron Beam Instrument Project to successful completion. Today, most of the planned instruments have conceptual designs and are now being engineered in detail prior to construction and procurement. A suite of ancillary equipment will also be provided to enable scientific experiments at different temperatures, pressures and magnetic fields. This paper describes the Neutron Beam Instrument Project and gives

  3. Replacement Nuclear Research Reactor: Draft Environmental Impact Statement. Vol. 1. Main report

    International Nuclear Information System (INIS)

    The Draft Environmental Impact Statement (EIS) for the replacement of the Australian Research reactor has been released. An important objective of the EIS process is to ensure that all relevant information has been collected and assessed so that the Commonwealth Government can make an informed decision on the proposal. The environmental assessment of the proposal to construct and operate a replacement reactor described in the Draft EIS has shown that the scale of environmental impacts that would occur would be acceptable, provided that the management measures and commitments made by ANSTO are adopted. Furthermore, construction and operation of the proposed replacement reactor would result in a range of benefits in health care, the national interest, scientific achievement and industrial capability. It would also result in a range of benefits derived from increased employment and economic activity. None of the alternatives to the replacement research reactor considered in the Draft EIS can meet all of the objectives of the proposal. The risk from normal operations or accidents has been shown to be well within national and internationally accepted risk parameters. The dose due to reactor operations would continue to be small and within regulatory limits. For the replacement reactor, the principle of 'As Low As Reasonably Achievable' would form an integral part of the design and licensing process to ensure that doses to operators are minimized. Costs associated with the proposal are $286 million (in 1997 dollars) for design and construction. The annual operating and maintenance costs are estimated to be $12 million per year, of which a significant proportion will be covered by commercial activities. The costs include management of the spent fuel from the replacement reactor as well as the environmental management costs of waste management, safety and environmental monitoring. Decommissioning costs for the replacement reactor would arise at the end of its lifetime

  4. A risk perspective for the replacement research reactor in Australia

    International Nuclear Information System (INIS)

    Full text: A Probabilistic Safety Assessment (PSA) was performed for the Australian Replacement Research Reactor (RRR) as a complement to its Safety Analyses. The PSA perspective is that based on risk, not only qualitatively but also quantitatively. The PSA attempts to determine all the possible combinations of how the plant could respond to an initiating event, group all the possible outcomes, obtain conservative estimates of the frequency, and bounding estimates of the consequences (i.e., doses to the worst exposed individual of the public). The frequency and consequence constitute the risk, and when evaluated for all possible events can be compared against the safety objectives set out in the regulatory principles. The PSA studies have been performed in parallel with the basic engineering phase of the project. Therefore, preliminary results from 'the risk point of view' were used as input to the design process, thus permitting improvements to be made to the design, and resulting in an effective reduction of the residual risk. To perform the PSA studies several methodological developments were made, in order to obtain a representative list of internal and external initiating events, to treat component and human-related failures, to consider common-cause failures, and to consider some specific aspects of the design (i.e., fail-safe components, passive systems, and lack of need for support systems). The overall results of the PSA indicate a very low residual risk for the RRR, and provide a valuable tool to analyse detailed engineering alternatives. From the regulatory point of view, the safety objectives have been fulfilled. Several design characteristics of the RRR contribute to the very low risk estimations (i.e., the existence of two completely independent shutdown systems, the lack of need for support systems for the safety functions, the absence of in-core experiments, the redundancy on the cooling modes, etc.) The PSA proved to be a valuable tool to increase

  5. Proposed replacement nuclear research reactor, Lucas Heights, NSW

    International Nuclear Information System (INIS)

    On 17 February 1999, the House of Representatives referred to the Parliamentary Standing Committee on Public Works for consideration and report the proposed replacement nuclear research reactor at Lucas Heights, New South Wales. The Committee received a written submission from ANSTO and took evidence from ANSTO officials at public hearings held at Parliament House. It has also received submissions and took evidence from a number of organisations and individuals. Prior to the first day of public hearings, the Committee undertook an extensive inspection of the facilities at Lucas Heights. The Committee's main conclusion and recommendations are as follows: 1) A need exists to replace HIFAR with a modern research reactor. The need for the replacement of HIFAR arises as a consequence of national interest considerations, research and development requirements and the need to sustain the local production of radiopharmaceuticals.The comparative costs of locating the replacement research reactor at Lucas Heights or a green fields site favour the former by a considerable margin. The refurbishing HIFAR of would not provide an enhancement of its research and operational capabilities which are considered by the scientific community to be limited. Such limitations have led to a reduction in national research and development opportunities. It is estimated that the new national research reactor must be operational some time before HIFAR is decommissioned. Provided all recommendations and commitments contained in the Environment Assessment Report are implemented during construction and commissioning and for the expected life of the research reactor, the Committee believes, based on the evidence, that all known risks have been identified and their impact on public safety will be as low as technically possible. It is recommended that during the licensing, construction and commissioning phases ANSTO should provide the Committee with six-monthly reports on progress and that removal of

  6. Relevant thermal-hydraulic aspects in the design of the RRR (Replacement Research Reactor)

    International Nuclear Information System (INIS)

    A description of the main thermal-hydraulic features and challenges of the Replacement Research Reactor, for the Australian Nuclear Science and Technology Organization (ANSTO), is presented. Different hydraulic and thermal-hydraulic aspects are considered, core cooling during full power operation and the way it affects the design, design criteria, engineered safety features and computational tools, amongst others. A special section is devoted to the thermal-hydraulic aspects inside the reflector tank, as well as the cooling of irradiation facilities, particularly, the Molybdenum production facility. (author)

  7. The replacement research reactor description and progress report

    International Nuclear Information System (INIS)

    A contract for the design, construction and commissioning of the Replacement Research Reactor was signed in July 2000 between Australia authorities and INVAP from Argentina. Since then the detailed design has been completed, an application for a construction license was made in May 2001 and granted in April 2002. The construction and manufacturing phase is presently underway, with full operation of the facility being scheduled for 2006. This paper explains the safety philosophy embedded into the design together with the approach taken for main elements of the design and their relation to the proposed applications of the reactor. Also information is provided on the suit of neutron beam facilities and irradiation facilities being constructed. Finally it is presented an outline of the project management organisation, project planing, schedule, licensing and general project progress

  8. A Risk Perspective for the Replacement Research Reactor in Australia

    International Nuclear Information System (INIS)

    In July 2000, the Australian Nuclear Science and Technology Organisation (ANSTO) signed a contract with the company INVAP S.E. of Argentina for the design, construction and commissioning of a replacement research reactor (RRR). INVAP contracted CEDIAC to prepare the probabilistic safety assessment (PSA) for the RRR in support of the ANSTO application for the construction licence. The PSA is complementary to the safety analysis, in the sense that it asks questions such as ''What if the postulated initiating events were to occur and more than one piece of equipment were to fail? What if several things were to go wrong?''The PSA attempts to determine all the possible combinations of how the plant could respond to an initiating event, group all the possible outcomes, obtain conservative estimates of the frequency, and bounding estimates of the consequences (i.e. doses to the worst exposed individual of the public). The frequency and consequence constitute the risk, and when evaluated for all possible events, can be compared against the safety objectives set out in the regulatory principles. Besides the basic objective of the PSA, which is the quantitative evaluation of the risks associated with the RRR, and its comparison to the regulatory objectives, the PSA studies have been performed in parallel with the basic engineering phase of the project. Therefore, preliminary results from the 'risk point of view' were used as input to the design process, thus permitting improvements to be made to the design, and resulting in an effective reduction of the residual risk. To perform the PSA studies, several methodological developments were made in order to obtain a representative list of internal and external initiating events, to treat component and human related failures, to consider common-cause failures, and to consider some specific aspects of the design (i.e. fail safe components, passive systems, and lack of need for support systems). The PSA studies were performed to

  9. Neutronic Design of the First Core of the Replacement Research Reactor

    International Nuclear Information System (INIS)

    The paper describes the general neutronic characteristics of the first core of the replacement research reactor (RRR) for the Australian Nuclear Science and Technology Organisation (ANSTO). A compact core with 16 FA has been designed to fulfil all the very demanding neutronic requirements of the RRR facility. The contractual performance parameters must be verified for the equilibrium core; a very important design effort was carried out in the initial fresh core to have a similar performance. The description covers different aspects of the neutronic design: a detailed nuclear design of U3Si2 first core, the design calculation tools, together with a comparison of the first core performance against the core design criteria and the equilibrium core performance. (author)

  10. A proposed irradiation-research facility to replace the NRU reactor

    International Nuclear Information System (INIS)

    This report describes the replacement of the National Research Universal (NRU) reactor with a dual purpose irradiation research facility to test CANDU fuels and materials, and to perform materials research using neutrons

  11. Final guidelines for an Environmental Impact Statement on the proposed construction and operation of a replacement nuclear research reactor at the Lucas Heights Science and Technology Centre

    International Nuclear Information System (INIS)

    These guidelines are based on the requirements of paragraphs 4.1 and 4.3 of the Administrative Procedures under the Commonwealth Environment Protection (Impact of Proposals) Act 1974 (EPIP Act).The Australian Nuclear Science and Technology Organisation (ANSTO) has been designated as proponent under the EPIP Act in relation to the proposed replacement nuclear research reactor at the Lucas Heights Science and Technology Centre (LHSTC). The term 'environment' refers to all aspects of the surroundings of human beings, whether affecting human beings as individuals or in social groupings. It includes the natural environment, the built environment, and social aspects of our surroundings. The definition covers such factors as air, water, soils, flora,fauna, buildings, roads, employment, hazards and risks, and safety. As set out in the guidelines, the scope of this assessment shall encompass those issues and alternatives directly related to the construction and operation of a replacement nuclear research reactor at the LHSTC. The EIS will need to make clear the site selection criteria used, and the basis, in assessing Lucas Heights as being suitable for a new reactor. While the EIS will address all aspects of the construction and operation of a replacement nuclear research reactor, it will not address issues associated with the treatment of spent nuclear fuel rods from the existing High Flux Australian Reactor (HIFAR facility). The EIS will also address issues associated with the eventual decommissioning of the proposed replacement reactor, and eventual decommissioning of the existing HIFAR facility

  12. Final guidelines for an Environmental Impact Statement on the proposed construction and operation of a replacement nuclear research reactor at the Lucas Heights Science and Technology Centre

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    These guidelines are based on the requirements of paragraphs 4.1 and 4.3 of the Administrative Procedures under the Commonwealth Environment Protection (Impact of Proposals) Act 1974 (EPIP Act).The Australian Nuclear Science and Technology Organisation (ANSTO) has been designated as proponent under the EPIP Act in relation to the proposed replacement nuclear research reactor at the Lucas Heights Science and Technology Centre (LHSTC). The term `environment` refers to all aspects of the surroundings of human beings, whether affecting human beings as individuals or in social groupings. It includes the natural environment, the built environment, and social aspects of our surroundings. The definition covers such factors as air, water, soils, flora,fauna, buildings, roads, employment, hazards and risks, and safety. As set out in the guidelines, the scope of this assessment shall encompass those issues and alternatives directly related to the construction and operation of a replacement nuclear research reactor at the LHSTC. The EIS will need to make clear the site selection criteria used, and the basis, in assessing Lucas Heights as being suitable for a new reactor. While the EIS will address all aspects of the construction and operation of a replacement nuclear research reactor, it will not address issues associated with the treatment of spent nuclear fuel rods from the existing High Flux Australian Reactor (HIFAR facility). The EIS will also address issues associated with the eventual decommissioning of the proposed replacement reactor, and eventual decommissioning of the existing HIFAR facility.

  13. Australian regulatory licensing and compliance monitoring of the construction of a research reactor

    International Nuclear Information System (INIS)

    Full text: The Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) was established by the Australian Radiation Protection and Nuclear Safety Act 1998 to perform a number of specific functions. Licensing and Compliance Monitoring of those activities involving radiation, that are undertaken by Commonwealth entities, are two of these functions. When making a decision on whether to issue a licence, the CEO of ARPANSA is obliged by the ARPANS Act to take into account a number of matters. The information that the CEO may request to assist make his decision includes (but is not limited to): (a) The design of the controlled facility, including ways in which the design deals with the physical and environmental characteristics of the site; (b) Any fundamental difficulties that will need to be resolved before any future authorisation is given; (c) The construction plan and schedule; (d) A preliminary safety analysis report that demonstrates the adequacy of the design of the facility and identifies structure, components and systems that are safety related items; (e) The arrangements for testing and commissioning safety related items. A licence granted by the CEO of ARPANSA is subject to a number of licence conditions. These licence conditions fall into three categorises: (1) Licence conditions prescribed by the Act and Regulations; (2) Licence conditions imposed by the CEO at the time of making the licence decision; (3) Licence conditions imposed by the CEO at a time after the licence has been granted. The regulatory compliance monitoring of these conditions during the construction of the ANSTO Replacement Research Reactor will be described. Two licence conditions of significance during the construction process are: (1) The holder of a licence must seek the CEO's prior approval to make a relevant change that will have significant implications for safety. (2) The holder of a licence, or person covered by a licence, must only construct an item that is important

  14. Commissioning of the Open Pool Australian Lightwater (OPAL) research reactor - A health physics perspective

    International Nuclear Information System (INIS)

    During 2006 and 2007 the Australian Nuclear Science and Technology Organisation (ANSTO) commissioned OPAL, a 20 MW open pool Research Reactor. This commissioning involved three stages; Stage A, testing the reactors systems prior to fuel loading, Stage B, first loading of fuel, achieving first criticality, reactor characterisation and systems testing up to 400kW, and Stage C, raising the power of the reactor in steps, up to its full operating power of 20MW. Prior to and following fuel loading a series of radiation measurements were made throughout the plant. These included dose rates, radioactivity in air, on surfaces and in cooling and shielding liquids. Installed continuous monitoring and portable equipment were used. Health physics measurements were repeated at increasing reactor power levels to check engineering design features and design of plant for radiation protection aspects. A Radiation Protection Plan and associated monitoring programs were implemented, including establishing and maintaining area, task and personnel monitoring regimes in the facility. Health Physics assessments and advice at each stage, played a major role in this commissioning process. This paper discusses the health physics experience of commissioning the OPAL Research Reactor and describes health physics results, actions taken and lessons learned during commissioning. (author)

  15. Commissioning of the Open Pool Australian Light water (OPAL) research reactor: a health physics perspective

    International Nuclear Information System (INIS)

    During 2006 and 2007 the Australian Nuclear Science and Technology Organisation (ANSTO) commissioned OPAL, a 20 MW open pool Research Reactor. This commissioning involved three stages: Stage A: testing the reactors systems prior to fuel loading; Stage B: first loading of fuel, achieving first criticality, reactor characterisation and systems testing up to 400 kw; and Stage C: raising the power of the reactor in steps, up to its full operating power of 20 MW. Prior to and following fuel loading a series of radiation measurements were made throughout the plant. These included dose rates, radioactivity in air, on surfaces and in cooling and shielding liquids. Installed continuous monitoring and portable equipment were used. Health physics measurements were repeated at increasing reactor power levels to check engineering design features and design of plant for radiation protection aspects. A Radiation Protection Plan and associated monitoring programs were implemented, including establishing and maintaining area, task and personnel monitoring regimes in the facility. Health Physics assessments and advice at each stage, played a major role in this commissioning process. This paper discusses the health physics experience of commissioning the OPAL Research Reactor and describes health physics results, actions taken and lessons learned during commissioning. (author)

  16. Replacement Nuclear Research Reactor: Draft Environmental Impact Statement. Vol. 2. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The appendices contains additional relevant information on: Environment Australia EIS Guidelines, composition of the Study Team, Consultation Activities and Resuits, Relevant Legislation and Regulatory Requirements, Exampies of Multi-Purpose Research Reactors, Impacts of Radioactive Emissions and Wastes Generated at Lucas Heights Science and Technology Centre, Technical Analysis of the Reference Accident, Flora and Fauna Species Lists, Summary of Environmental Commitments and an Outline of the Construction Environmental Management Plan Construction Environmental Management Plan figs., ills., refs. Prepared for Australian Nuclear Science and Technology Organisation (ANSTO)

  17. Australian Research Council

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    @@ Introduction The Australian Research Council(ARC) is the Australian Government's main agency for allocating research funding to academics and researchers in Australian universities.Its mission is to deliver policy and programs that advance Australian research and innovation globally and benefit the community.

  18. Research and the user program at OPAL, the new Australian Research Reactor

    International Nuclear Information System (INIS)

    Australian science entered a new “golden age”, with the startup of bright new neutron and photon sources in Sydney (2006) and Melbourne (2007), respectively. The OPAL reactor and the Australian Synchrotron can together be considered the greatest single investment in scientific infrastructure in Australia’s history. Fuel was loaded into the OPAL reactor in August 2006, and full power (20MW) achieved in November 2006. The formal user commenced in 2007, and fully analysed data sets have now been taken on eleven instruments. At the time of the conference, the 16th proposal round will be open. 2 further instruments are in various states of construction, and substantial additional investment is also being made in sample-environment, extra instrumental options, polarised-neutron technology, and both chemical and bio-deuteration facilities. An update will be given on the status of OPAL, the performance of its thermal and cold neutron sources and instruments, together with a selection of recent scientific results and future plans.

  19. Project to replace the control and protection system at the WWR-K research reactor

    International Nuclear Information System (INIS)

    The WWR-K is a tank-type, light water moderated and cooled multipurpose research reactor with a nominal power rating of 6 MW and a peak thermal neutron flux of over 1014 n/cm2s. The reactor is operated by the Institute of Nuclear Physics of the National Nuclear Center of the Republic of Kazakhstan (INP), and is located at Alatau, near Almaty, the largest city in Kazakhstan. The reactor was commissioned in 1967 with a power rating of 10 MW, then shut down between 1988 and 1998 while seismic safety upgrades were completed. Currently, INP is undertaking the planning and technical work to allow the reactor to be converted from HEU fuel with a U-235 content of 36% to LEU fuel with a U-235 content of 19.7%. The reactor has an important role in Kazakhstan, and is producing isotopes for medical and industrial uses, providing material testing services and neutron activation analysis. Replacement of reactor control and protection system (CPS) is a part of the wider program of the reactor modifications related to its conversion from HEU to LEU fuel, supported by the US Department of Energy, the Nuclear Threat Initiative and the Kazakhstan government. The program includes development of a new LEU fuel assembly design and re-configuration of the reactor core, with change in number and positions of the control rods, which requires modification of the CPS. Furthermore, replacement of the existing instrumentation, some of which is 40 years old, will improve reactor safety, bring the CPS up to current international standards, and provide an upgraded control interface. The existing CPS at the WWR-K relies to a large extent on old designs of detectors and electronic equipment that are no longer in production and the system as a whole does not meet the necessary standards for prolonged operation of the reactor. Consequently, the Kazakhstan Atomic Energy Committee (KAEC), the nuclear regulatory body of Kazakhstan has mandated that the project for conversion of the WWR-K to use LEU fuel

  20. A description of the Canadian irradiation-research facility proposed to replace the NRU reactor

    International Nuclear Information System (INIS)

    To replace the aging NRU reactor, AECL has developed the concept for a dual-purpose national Irradiation Research Facility (IRF) that tests fuel and materials for CANDU (CANada Deuterium Uranium) reactors and performs materials research using extracted neutron beams. The IRF includes a MAPLE reactor in a containment building, experimental facilities, and support facilities. At a nominal reactor power of 40 MWt, the IRF will generate powers up to 1 MW in natural-uranium CANDU bundles, fast-neutron fluxes up to 1.4 x 1018 n·m-2·s-1 in Zr-alloy specimens, and thermal-neutron fluxes matching those available to the NRU beam tubes. (author). 9 refs., 5 tabs., 2 figs

  1. A description of the Canadian irradiation-research facility proposed to replace the NRU reactor

    International Nuclear Information System (INIS)

    To replace the aging NRU reactor, AECL has developed the concept for a dual-purpose national Irradiation Research Facility (IRF) that tests fuel and materials for CANDU (CANada Deuterium Uranium) reactors and performs materials research using extracted neutron beams. The IRF includes a MAPLE reactor in a containment building, experimental facilities, and support facilities. At a nominal reactor power of 40 MWt, the IRF will generate powers up to 1 MW in natural-uranium CANDU bundles, fast-neutron fluxes up to 1.4 x 1018 N·m-2·s-1 in Zr-alloy specimens, and thermal-neutron fluxes matching those available to the NRU beam tubes. (author). 9 refs., 5 tabs., 2 figs

  2. Replacement of the Core Beryllium Reflector in the SAFARI-1 Research Reactor

    International Nuclear Information System (INIS)

    The SAFARI-1 Research Reactor is a 20 MW high flux MTR and has been continuously operational for more than 46 years. In this period, the core beryllium reflector had never been replaced. An ageing management action to replace the reflector received priority due to the risks involved with failure or deformation of elements. This paper elaborates on the actions taken to replace the old and manage the new reflector. To this extent a reflector replacement procedure, backed up by core neutronic calculations and a test plan, was developed for the safe replacement of the reflector. A reflector management programme will ensure that records of reflector elements are kept and used to optimally manage usage of every element. Due to the historic nature of reflector utilisation in the SAFARI-1 core, deformation of the elements was unavoidable. These deformations will be monitored in the management programme for the new reflector. Deformation measurement of the old reflector is planned and could yield interesting comparisons with analytical results. The action plan for final disposal of the old reflector, although still in development, is also mentioned in this paper. (author)

  3. Media and Australia's replacement reactor project

    International Nuclear Information System (INIS)

    In September 1997, the Commonwealth Government of Australia announced a proposal to build a replacement nuclear research reactor at Lucas Heights in Sydney. Extensive public consultation, parliamentary debate and independent reports were prepared to ensure that the new facility would meet strict international requirements, national safety and environmental standards, and performance specifications servicing the needs of Australia - for decades to come. On 6 June 2000, Argentine company INVAP SE was announced as the preferred tenderer. In July 2000 contracts were signed between INVAP and the Australian Nuclear Science and Technology Organisation for the construction the replacement reactor, due to be completed in 2005. In order to retain a strong local presence, INVAP undertook a joint venture with two of Australia's foremost heavy construction businesses. Briefly the new research reactor will be a replacement for the ageing Australian Reactor (HIFAR). Nuclear science and technology, in Australia, is no stranger to media controversy and misinformation. Understandably the announcement of a preferred tenderer followed by the signing of contracts, attracted significant national and international media attention. However in the minds of the media, the issue is far from resolved and is now a constant 'news story' in the Australian media. Baseless media stories have made claims that the project will cost double the original estimates; question the credibility of the contractors; and raise issues of international security. The project is currently linked with Australia's requirements for long term nuclear waste management and there has been an attempt to bring national Indigenous People's issues into play. Some of these issues have been profiled in the press internationally. So, just to set the record straight and give you an appropriate impression of what's 'really happening' I would like to highlight a few issues, how ANSTO dealt with these, and what was finally reported

  4. Project to replace the control and protection system at the WWR-K research reactor

    International Nuclear Information System (INIS)

    Replacement of reactor control and protection system (CPS) is a part of the wider program of the reactor modifications related to its conversion from HEU to LEU fuel, supported by the US Department of Energy, the Nuclear Threat Initiative and the Kazakhstan government. The program includes development of a new LEU fuel assembly design and re-configuration of the reactor core, with change in number and positions of the control rods, which requires modification of the CPS. Furthermore, replacement of the existing instrumentation, some of which is 40 years old, will improve reactor safety, bring the CPS up to current international standards, and provide an upgraded control interface

  5. The replacement of research reactors with a compact proton linac for neutron radiography

    International Nuclear Information System (INIS)

    The work presented here examines a neutron radiography facility, based on accelerator-driven compact neutron source, in order to find a suitable replacement for the facilities, which is based on research nuclear reactors. High-quality neutrons beam can be produced via the 9Be(p,n)9B reaction at proton energies of about 4 MeV. Except for the Be target the materials considered were compatible with the European Union Directive on ‘Restriction of Hazardous Substances’ (RoHS) 2002/95/EC. According to this directive some common materials in radiography units such as lead and cadmium have been excluded. The suggested facility has been simulated with an extensive range of parameters, which characterizes the neutron radiography, and the results specify that an accelerator-based neutron source is an attractive alternative to research nuclear reactors. - Highlights: ► Accelerator-driven source as an alternative to nuclear reactors for neutron radiography. ► Neutron beam can be produced via the 9Be(p,n)9B reaction at proton energies of 4 MeV. ► The presence of sapphire filter improves parameters associated with neutron radiography

  6. Replacement Nuclear Research Reactor. Supplement to Draft Environmental Impact Statement. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-01-01

    The Draft Environmental Impact Statement for a replacement research reactor at Lucas Heights, was available for public examination and comment for some three months during 1998. A Supplement to the Draft Environmental Impact Statement (Draft EIS) has been completed and was lodged with Environment Australia on 18 January 1999. The Supplement is an important step in the overall environmental assessment process. It reviews submissions received and provides the proponent`s response to issues raised in the public review period. General issues extracted from submissions and addressed in the Supplement include concern over liability issues, Chernobyl type accidents, the ozone layer and health issues. Further studies, relating to issues raised in the public submission process, were undertaken for the Supplementary EIS. These studies confirm, in ANSTO`s view, the findings of the Draft EIS and hence the findings of the Final EIS are unchanged from the Draft EIS

  7. Replacement Nuclear Research Reactor. Supplement to Draft Environmental Impact Statement. Volume 3

    International Nuclear Information System (INIS)

    The Draft Environmental Impact Statement for a replacement research reactor at Lucas Heights, was available for public examination and comment for some three months during 1998. A Supplement to the Draft Environmental Impact Statement (Draft EIS) has been completed and was lodged with Environment Australia on 18 January 1999. The Supplement is an important step in the overall environmental assessment process. It reviews submissions received and provides the proponent's response to issues raised in the public review period. General issues extracted from submissions and addressed in the Supplement include concern over liability issues, Chernobyl type accidents, the ozone layer and health issues. Further studies, relating to issues raised in the public submission process, were undertaken for the Supplementary EIS. These studies confirm, in ANSTO's view, the findings of the Draft EIS and hence the findings of the Final EIS are unchanged from the Draft EIS

  8. The scientific and technical requirements for biology at Australia's Replacement Research Reactor

    International Nuclear Information System (INIS)

    A Symposium and Workshop on Neutrons for Biology was held in the School of Biochemistry and Molecular Biology at the University of Melbourne, under the auspices of AINSE, Univ of Melbourne and ANSTO. Invited talks were given on the subjects of Genome, small-angle neutron scattering (SANS) as a critical framework for understanding bio-molecular, neutron diffraction at high and low resolution, and the investigation of viruses and large-scale biological structures using neutrons. There were also talks from prominent NMR practitioners and X-ray protein crystallographers, with substantial discussion about how the various methods might fit together in the future. Significant progress was made on defining Australia's needs, which include a strong push to use SANS and reflectometry for the study of macromolecular complexes and model membranes, and a modest network of supporting infrastructure in Brisbane, Melbourne and the Sydney Basin. Specific recommendations were that the small-angle neutron scattering and reflectometry instruments in the Replacement Research Reactor (RRR) be pursued with high priority, that there be no specific effort to provide high-resolution protein-crystallography facilities at the RRR, but that a watching brief be kept on instrumentation and sample-preparation technologies elsewhere. A watch be kept on inelastic and quasielastic neutron scattering capabilities elsewhere, although these methods will not initially be pursued at the RRR and that should be input from this community into the design of the biochemistry/chemistry laboratories at the Replacement Research Reactor. It was also recommended that a small number of regional facilities be established (or enhanced) to allow users to perform deuteration of biomolecules. These facilities would be of significant value to the NMR and neutron scattering communities

  9. The regulatory role of the Australian Radiation Protection and Nuclear Safety Agency in relation to spent fuel arising from research reactors in Australia

    International Nuclear Information System (INIS)

    This work describes the approach and role of the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) in the regulatory management of spent fuel arising from research reactors in Australia, with particular emphasis on the regulatory oversight of the safe transport of spent fuel arising from the research reactors in Australia, in accordance with the International Atomic Energy Agency Regulations for the Safe Transport of Radioactive Material. (author)

  10. Replacement of the Electronic Part of Instrumentation and Control of the WWR-SM Research Reactor

    International Nuclear Information System (INIS)

    WWR-SM research reactor was put into operation in 1959. Since that time the reactor has been very effectively operated, but all electronic equipment of I&C is now outdated. On 7 December 2009 a contract among the International Atomic Energy Agency, Joint Stock Company 'SNIIP-SYSTEMATOM' and the Institute of Nuclear Physics of the Academy of Sciences of the Republic of Uzbekistan concerning design, manufacturing, delivery and commissioning of a complex control and protection system equipment for the nuclear research reactor WWR SM was signed. The implementation of this contract started in 2010. (author)

  11. Residual stress diffractometer KOWARI at the Australian research reactor OPAL: Status of the project

    International Nuclear Information System (INIS)

    Neutron scattering using diffraction techniques is now recognized as the most precise and reliable method of mapping sub-surface residual stresses in materials or even components, which are not only of academic but also of industrial-economic relevance. The great potential of neutrons in the field of residual stresses was recognized by ANSTO and its external Beam Instrument Advisory Group for the new research reactor OPAL. The recommendation was to build the dedicated strain scanner KOWARI among the first suite of instruments available to users. We give an update on the overall project and present the current status of the diffractometer. It is anticipated that the instrument will be commissioned in mid 2006 and available to users at the end of the OPAL project

  12. Replacement Nuclear Research Reactor: Draft Environmental Impact Statement. Vol. 2. Appendices

    International Nuclear Information System (INIS)

    The appendices contains additional relevant information on: Environment Australia EIS Guidelines, composition of the Study Team, Consultation Activities and Resuits, Relevant Legislation and Regulatory Requirements, Exampies of Multi-Purpose Research Reactors, Impacts of Radioactive Emissions and Wastes Generated at Lucas Heights Science and Technology Centre, Technical Analysis of the Reference Accident, Flora and Fauna Species Lists, Summary of Environmental Commitments and an Outline of the Construction Environmental Management Plan Construction Environmental Management Plan

  13. Determination of the f parameter for k0-neutron activation analysis at the Australian 20 MW OPAL research reactor

    International Nuclear Information System (INIS)

    In the k0 method of standardisation in neutron activation analysis (k0-NAA), the ratio of thermal to epithermal neutrons, a value known as f, is fundamental in accurately determining the concentration of elements within the sample. Research into determining this f value via the cadmium ratio method was undertaken for two positions within the 20 MW Open Pool Australian Light water (OPAL) research reactor (Lucas Heights, NSW, Australia). A short irradiation and long irradiation position were assessed via two methods; the conventional cadmium ratio method based on the Hogdahl formalism, with f values of 2,666 ± 255 and 1,538 ± 258 being calculated respectively for the short and long positions, and an ASTM-INVAP-based cadmium ratio method, which allows for the higher neutron temperature of OPAL to be accounted for, with f values of 3,057 ± 318 and 1,755 ± 312 being calculated respectively. These values were validated by analysis of NIST standard reference materials (SRMTM), with good agreement between experimental values and reference and literature values being observed, showing the accuracy and suitability of these values for OPAL. Additionally, the high values of f shown endorse the strength of performing k0-NAA at OPAL. This manuscript publishes the first values of f from OPAL and provides a detailed description of the method employed.

  14. Nuclear research centres in the 21st century: The Australian experience

    International Nuclear Information System (INIS)

    The main mandate of the Australian Nuclear Science and Technology Organisation (ANSTO) is to provide benefits of nuclear science and technology to a variety of applications in agriculture, medicine and industry. It is expected that HIFAR reactor, which will complete 47 years of operation, will be replaced by a new multipurpose reactor in 2005. ANSTO also has a strong programme on accelerators for producing medical radioisotopes and for physics research. In the area of environment, ANSTO's programme includes isotope studies related to global climate change, pollution monitoring, and coastal and marine chemistry. ANSTO would continue to work for the improvement of the quality of life of all Australians. (author)

  15. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Martens, Frederick H. [Argonne National Laboratory; Jacobson, Norman H.

    1968-09-01

    This booklet discusses research reactors - reactors designed to provide a source of neutrons and/or gamma radiation for research, or to aid in the investigation of the effects of radiation on any type of material.

  16. Research reactors

    International Nuclear Information System (INIS)

    There are currently 284 research reactors in operation, and 12 under construction around the world. Of the operating reactors, nearly two-thirds are used exclusively for research, and the rest for a variety of purposes, including training, testing, and critical assembly. For more than 50 years, research reactor programs have contributed greatly to the scientific and educational communities. Today, six of the world's research reactors are being shut down, three of which are in the USA. With government budget constraints and the growing proliferation concerns surrounding the use of highly enriched uranium in some of these reactors, the future of nuclear research could be impacted

  17. Research reactors

    International Nuclear Information System (INIS)

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  18. Design research of the possible replacement of IVG.1M reactor core fuel into U - Mo alloy

    International Nuclear Information System (INIS)

    Results of neutron-physics calculations, characteristics of IVG. 1M reactor in case of core fuel replacement to low enrichment fuel from U-Mo alloy was represented. By means of MCNP/4B design code, assigned for radioactive transport in three-dimensional geometry task solving, effective multiplication factor for reactor, initial reactivity margin, relative neutron flux density, specific energy release were defined. (author)

  19. Determination of the replacement cooling tower capability at the ETRR-2 research reactor

    International Nuclear Information System (INIS)

    The ETRR-2 replacement cooling tower capability has been evaluated by the thermal acceptance test performed in June 2003. All instruments used were calibrated prior to the test. The measured data are collected at regular intervals in accordance with the acceptance test code for water cooling towers of the cooling tower institute recommendations. Both the characteristic curve and the performance curve methods were used to evaluate the tower capability. The test results yield a tower capability of about 105% and so the tower is thermally accepted. (orig.)

  20. The regulatory role of the Australian Radiation Protection and Nuclear Safety Agency in relation to spent fuel arising from research reactors in Australia

    International Nuclear Information System (INIS)

    This paper will describe the elements and performance of ARPANSA's regulatory management of spent fuel arising in Australia, with particular emphasis on the experience of ensuring compliance with the Code of Practice Code of Practice for Safe Transport of Radioactive Materials in relation to in land surface transport of spent fuel within Australia. The Australian Radiation Protection and Nuclear Safety Agency is the regulatory authority for Commonwealth entities, such as the Australian Nuclear Science and Technology Organisation (ANSTO), who operate nuclear installations in Australia.. Nuclear installations that operate under ARPANSA facility licence include research reactors and plants for the storage and management of research reactor fuel. ANSTO is the only operator of nuclear installations in Australia. The Australian Radiation Protection and Nuclear Safety Agency is also the competent Authority for inland surface transport. ARPANSA has adopted the IAEA Safety Regulations for Safe Transport of Radioactive Materials domestically in the form of the ARPANSA Code of Practice for Safe Transport of Radioactive Materials (RPS 2). s the competent authority ARPANSA approves the shipment and design of a new cask, validate original certificate applying the requirements of the RPS 2. RPANSA's regulatory oversight of compliance with the requirements of its own legislation and the requirements of the Code emphasises assurance of safety in the operation of nuclear installations and the shipment of spent fuel is achieved principally by prior assessment of the operator/consignors safety case, and by compliance monitoring through regular reporting (quarterly and annually), as well as planned and reactive inspections. During the operating life of these facilities for several decades there have been no incidents which have had off-site or significant on-site, consequences. This paper will examine that experience and in particular focus on the regulatory experience of oversight of

  1. Proposed replacement nuclear research reactor at Lucas Heights Science and Technology Centre, NSW. Statement of evidence to the Parliamentary Standing Committee on Public Works

    International Nuclear Information System (INIS)

    This submission demonstrates the manner in which the replacement research reactor project is to be undertaken in accordance with all relevant Commonwealth requirements and standards. Successive submissions to Government have shown that the construction and operation of the replacement reactor will result in a range of significant benefits to Australia in the areas of health care, the national interest, scientific achievement and in industrial applications. ANSTO is confident that the construction and operation of the replacement research reactor will: meet the identified needs for an ongoing neutron source for Australia into the next century in a cost-effective manner; be effectively managed to ensure that the project is delivered to the agreed schedule and budget; involve an effective community consultation process with ongoing community consultation a feature of ANSTO's approach; will have negligible environmental and public health implications taking account of the environmental management measures and commitments made by ANSTO in the Environmental Impact Statement and the stringent licensing arrangement by ARPANSA

  2. Single-crystal neutron diffraction at the Australian Replacement Research Reactor

    International Nuclear Information System (INIS)

    The purpose of the workshop was to: identify the future needs and opportunities for single-crystal neutron diffraction, and specify instrument requirements. important number of experiments. The conclusion of the workshop deliberation was that Australia has a diverse community of users of single-crystal neutron diffraction. A (quasi)-Laue image-plate diffractometer allows the fastest throughput by far, but would exclude an important number of experiments. Most of these could be covered by the additional possibility to locate the image-plate detector on a monochromatic beam. Therefore it was recommend both a white thermal beam and a monochromatic beam (λ= 1 to 2.4 Angstroms) for an image-plate detector. At little additional cost the existing 2TanA instrument could be located semi-permanently on the same monochromatic beam, thus offering three quite different types of single-crystal instruments. Small improvements could be made to the 2TanA instrument to cater for the remaining experiments not suited to an image-plate diffractometer: exchange of the Eulerian cradle for an automated tilt goniometer for extremely bulky sample environment (cryomagnets, large pressure cells), optional larger area detector, analyser crystal. It was recommended that an Instrument Advisory Team will be assembled, and will help in specifying, designing and commissioning the instrument

  3. Research Output of Australian Universities

    OpenAIRE

    Malcolm Abbot; Hristos Doucouliagos

    2003-01-01

    Research plays an important role in underpinning a country’s economic and social life. Universities are at the centre of the research and human capital generating process. The aim of this paper is to explore the links between research output, research income, academic and non-academic labour and some of the characteristics of Australian universities. The results indicate that research income, academic staff and post-graduates are all positively associated with research output. There are notic...

  4. Research Reactors that Look Similar But are Quite Different

    International Nuclear Information System (INIS)

    At the end of 1997, the 22 MW ETRR-2 was started up and in November 2001, the 20 MW design, offered by INVAP, was selected by the Australian Nuclear Science and Technology Organisation (ANSTO) to be the new replacement research reactor. Overall, both reactors generate practically the same power and the primary cooling system presents similarities that can be considered as the use of a proven technique. However, the required core configuration introduces some important challenges in the design. The paper is intended to show the experience of INVAP in the thermal-hydraulic design of two 'similar' research reactors specified with different requirements and fulfilling the same safety standards. (author)

  5. Proposed replacement nuclear research reactor at Lucas Heights Science and Technology Centre, NSW. Statement of evidence to the Parliamentary Standing Committee on Public Works

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-02-01

    This submission demonstrates the manner in which the replacement research reactor project is to be undertaken in accordance with all relevant Commonwealth requirements and standards. Successive submissions to Government have shown that the construction and operation of the replacement reactor will result in a range of significant benefits to Australia in the areas of health care, the national interest, scientific achievement and in industrial applications. ANSTO is confident that the construction and operation of the replacement research reactor will: meet the identified needs for an ongoing neutron source for Australia into the next century in a cost-effective manner; be effectively managed to ensure that the project is delivered to the agreed schedule and budget; involve an effective community consultation process with ongoing community consultation a feature of ANSTO`s approach; will have negligible environmental and public health implications taking account of the environmental management measures and commitments made by ANSTO in the Environmental Impact Statement and the stringent licensing arrangement by ARPANSA 24 refs., 8 tabs., 5 figs.

  6. Reliability tests for reactor internals replacement technology

    International Nuclear Information System (INIS)

    Structural damage due to aging degradation of LWR reactor internals has been reported in several nuclear plants. NUPEC has started a project to test the reliability of the technology for replacing reactor internals, which was directed at preventive maintenance before damage and repair after damage for the aging degradation. The project has been funded by the Ministry of International Trade and Industry (MITI) of Japan since 1995, and it follows the policy of a report that the MITI has formally issued in April 1996 summarizing the countermeasures to be considered for aging nuclear plants and equipment. This paper gives an outline of the whole test plans and the test results for the BWR reactor internals replacement methods; core shroud, ICM housing, and CRD Housing and stub tube. The test results have shown that the methods were reliable and the structural integrity was appropriate based on the evaluation. (author)

  7. New research reactor for Australia

    International Nuclear Information System (INIS)

    HIFAR, Australia's major research reactor was commissioned in 1958 to test materials for an envisaged indigenous nuclear power industry. HIFAR is a Dido type reactor which is operated at 10 MW. With the decision in the early 1970's not to proceed to nuclear power, HIFAR was adapted to other uses and has served Australia well as a base for national nuclear competence; as a national facility for neutron scattering/beam research; as a source of radioisotopes for medical diagnosis and treatment; and as a source of export revenue from the neutron transmutation doping of silicon for the semiconductor industry. However, all of HIFAR's capabilities are becoming less than optimum by world and regional standards. Neutron beam facilities have been overtaken on the world scene by research reactors with increased neutron fluxes, cold sources, and improved beams and neutron guides. Radioisotope production capabilities, while adequate to meet Australia's needs, cannot be easily expanded to tap the growing world market in radiopharmaceuticals. Similarly, neutron transmutation doped silicon production, and export income from it, is limited at a time when the world market for this material is expanding. ANSTO has therefore embarked on a program to replace HIFAR with a new multi-purpose national facility for nuclear research and technology in the form of a reactor: a) for neutron beam research, - with a peak thermal flux of the order of three times higher than that from HIFAR, - with a cold neutron source, guides and beam hall, b) that has radioisotope production facilities that are as good as, or better than, those in HIFAR, c) that maximizes the potential for commercial irradiations to offset facility operating costs, d) that maximizes flexibility to accommodate variations in user requirements during the life of the facility. ANSTO's case for the new research reactor received significant support earlier this month with the tabling in Parliament of a report by the Australian Science

  8. Nuclear research reactors

    International Nuclear Information System (INIS)

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.)

  9. Alternatives to proposed replacement production reactors

    International Nuclear Information System (INIS)

    To insure adequate supplies of plutonium and tritium for defense purposes, an independent evaluation was made by Los Alamos National Laboratory of the numerous alternatives to the proposed replacement production reactors (RPR). This effort concentrated on the defense fuel cycle operation and its technical implications in identifying the principal alternatives for the 1990s. The primary options were identified as (1) existing commercial reactors, (2) existing and planned government-owned facilities (not now used for defense materials production), and (3) other RPRs (not yet proposed) such as CANDU or CANDU-type heavy-water reactors (HWR) for both plutonium and tritium production. The evaluation considered features and differences of various options that could influence choice of RPR alternatives. Barring a change in the US approach to civilian and defense fuel cycles and precluding existing commercial reactors at government-owned sites, the most significant alternatives were identified as a CANDU-type HWR at Savannah River Plant (SRP) site or the Three Mile Island commercial reactor with reprocessing capability at Barnwell Nuclear Fuel Plant and at SRP

  10. Research reactors - an overview

    Energy Technology Data Exchange (ETDEWEB)

    West, C.D.

    1997-03-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

  11. Report on the ANSTO application for a licence to construct a Replacement Research Reactor, addressing seismic analysis and seismic design accident analysis, spent fuel and radioactive wastes

    International Nuclear Information System (INIS)

    The Report of the Nuclear Safety Committee (NSC) covers specific terms of reference as requested by the Chief Executive Officer of ARPANSA. The primary issue for the Working Group(WG) consideration was whether ANSTO had demonstrated: (i) that the overall approach to seismic analysis and its implementation in the design is both conservative and consistent with the international best practice; (ii) whether the full accident analysis in the Probabilistic Safety Assesment Report (PSAR) satisfies the radiation dose/frequency criteria specified in ARPANSA's regulatory assessment principle 28 and the assumptions used in the Reference Accident for the siting assessment have been accounted for in the PSAR; and (iii) the adequacy of the strategies for managing the spent fuel as proposed to be used in the Replacement Research Reactor and other radioactive waste (including emissions, taking into account the ALARA criterion) arising from the operation of the proposed replacement reactor and radioisotope production. The report includes a series of questions that were asked of the Applicant in the course of working group deliberations, to illustrate the breadth of inquiries that were made. The Committee noted that replies to some questions remain outstanding at the date of this document. The NSC makes a number of recommendations that appear in each section of the document, which has been compiled in three parts representing the work of each group. The NSC notes some lack of clarity in what was needed to be considered at this approval stage of the project, as against information that would be required at a later stage. While not in the original work plan, recent events of September 11, 2001 also necessitated some exploration of issues relating to construction security. Copyright (2002) Commonwealth of Australia

  12. Polarized neutrons for Australian scientific research

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, Shane J. [Australian Nuclear Science and Technology Organisation, New Illawarra Road, Lucas Heights, NSW 2234 (Australia)]. E-mail: sjk@ansto.gov.au

    2005-02-15

    Polarized neutron scattering has been a feature at ANSTO's HIFAR research reactor since the first polarization analysis (PA) spectrometer Longpol began operation over 30 years ago. Since that time, we have improved performance of Longpol and added new capabilities in several reincarnations of the instrument. Most of the polarized neutron experiments have been in the fields of magnetism and superconductivity, and most of that research has involved PA. Now as we plan our next generation neutron beam facility, at the Replacement Research Reactor (RRR), we intend to continue the tradition of PA but with a far broader scope in mind. Our new capabilities will combine PA and energy analysis with both cold and thermal neutron source spectra. We will also provide capabilities for research with polarized neutrons in small-angle neutron scattering and in neutron reflectometry. The discussion includes a brief historical account of the technical developments with a summary of past and present applications of polarized neutrons at HIFAR, and an outline of the polarized neutron capabilities that will be included in the first suite of instruments, which will begin operation at the new reactor in 2006.

  13. Research Nuclear Reactors

    International Nuclear Information System (INIS)

    Published in English and in French, this large report first proposes an overview of the use and history of research nuclear reactors. It discusses their definition, and presents the various types of research reactors which can be either related to nuclear power (critical mock-ups, material test reactors, safety test reactors, training reactors, prototypes), or to research (basic research, industry, health), or to specific particle physics phenomena (neutron diffraction, isotope production, neutron activation, neutron radiography, semiconductor doping). It reports the history of the French research reactors by distinguishing the first atomic pile (ZOE), and the activities and achievements during the fifties, the sixties and the seventies. It also addresses the development of instrumentation for research reactors (neutron, thermal, mechanical and fission gas release measurements). The other parts of the report concern the validation of neutronics calculations for different reactors (the EOLE water critical mock-up, the MASURCA air critical mock-up dedicated to fast neutron reactor study, the MINERVE water critical mock-up, the CALIBAN pulsed research reactor), the testing of materials under irradiation (OSIRIS reactor, laboratories associated with research reactors, the Jules Horowitz reactor and its experimental programs and related devices, irradiation of materials with ion beams), the investigation of accident situations (on the CABRI, Phebus, Silene and Jules Horowitz reactors). The last part proposes a worldwide overview of research reactors

  14. Survey of research reactors

    International Nuclear Information System (INIS)

    A survey of reasearch reactors based on the IAEA Nuclear Research Reactor Data Base (RRDB) was done. This database includes information on 273 operating research reactors ranging in power from zero to several hundred MW. From these 273 operating research reactors 205 reactors have a power level below 5 MW, the remaining 68 reactors range from 5 MW up to several 100 MW thermal power. The major reactor types with common design are: Siemens Unterrichtsreaktors, 1.2 Argonaut reactors, Slowpoke reactors, the miniature neutron source reactors, TRIGA reactors, material testing reactors and high flux reactors. Technical data such as: power, fuel material, fuel type, enrichment, maximum neutron flux density and experimental facilities for each reactor type as well as a description of their utilization in physics and chemistry, medicine and biology, academic research and teaching, training purposes (students and physicists, operating personnel), industrial application (neutron radiography, silicon neutron transmutation doping facilities) are provided. The geographically distribution of these reactors is also shown. As conclusions the author discussed the advantages (low capital cost, low operating cost, low burn up, simple to operate, safe, less restrictive containment and sitting requirements, versatility) and disadvantages (lower sensitivity for NAA, limited radioisotope production, limited use of neutron beams, limited access to the core, licensing) of low power research reactors. 24 figs., refs. 15, Tab. 1 (nevyjel)

  15. Safeguarding research reactors

    International Nuclear Information System (INIS)

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  16. Analysis of higher power research reactors' parameters

    International Nuclear Information System (INIS)

    The objective of this monograph was to analyze and compare parameters of different types of research reactors having higher power. This analysis could be used for decision making and choice of a reactor which could possibly replace the existing ageing RA reactor in Vinca. Present experimental and irradiation needs are taken into account together with the existing reactors operated in our country, RB and TRIGA reactor

  17. Research nuclear reactors

    International Nuclear Information System (INIS)

    Since the divergence of the first nuclear reactor in 1942, about 600 research or test reactors have been built throughout the world. Today 255 research reactors are operating in 57 countries and about 70% are over 25 years old. Whereas there are very few reactor types for power plants because of rationalization and standardisation, there is a great diversity of research reactors. We can divide them into 2 groups: heavy water cooled reactors and light water moderated reactors. Heavy water cooled reactors are dedicated to the production of high flux of thermal neutrons which are extracted from the core by means of neutronic channels. Light water moderated reactors involved pool reactors and slightly pressurized closed reactors, they are polyvalent but their main purposes are material testing, technological irradiations, radionuclide production and neutron radiography. At the moment 8 research reactors are being built in Canada, Germany, Iran, Japan, Kazakhstan, Morocco, Russia and Slovakia and 8 others are planned in 7 countries (France, Indonesia, Nigeria, Russia, Slovakia, Thailand and Tunisia. Different research reactors are described: Phebus, Masurca, Phenix and Petten HFR. The general principles of nuclear safety applied to test reactors are presented. (A.C.)

  18. The Australian Centre for Minesite Rehabilitation Research

    International Nuclear Information System (INIS)

    The Australian Centre for Minesite Rehabilitation Research (ACMRR) is a joint venture between the Australian mining industry through the Australian Mineral Industries Research Association Ltd. (AMIRA) and three of the organizations working most actively in this area in Australia: CSIRO Minesite Rehabilitation Research Program; University of Queensland Centre for Mined Land Rehabilitation; and Curtin University Mulga Research Centre. The ACMRR was established in July 1993 to provide a national framework to conduct Strategic Research into minesite rehabilitation. It is an industry led and funded initiative. The Goals of the Centre include: to conduct strategic research into minesite rehabilitation to provide sustainable environmental solutions which are acceptable to industry, government and the community; to be recognized as a center of excellence undertaking commissioned research on minesite rehabilitation in an independent and thorough manner; to provide scientific and technological foundations to facilitate industry and government in setting acceptable standards; to act as networking and communications focus; and to enhance education and training in minesite rehabilitation. Strategic Research Programs in: Water Systems--downstream surface and groundwater quality; Land--the long-term behavior and stability of constructed landforms; Ecosystems--the long-term sustainability of constructed landforms; Waste--the long-term treatment and disposal of waste products; will allow the ACMRR to achieve these goals through specific research projects in these areas, developed with industry sponsors. This paper will discuss their progress to date, research projects underway, and plans for the future

  19. A requirement for Australian research: access to 'big science' facilities, a report by the Australian National Committee for crystallography

    International Nuclear Information System (INIS)

    Two types of 'Big Science' research facility - synchrotron radiation sources and intense neutron beams - are now recognised as essential resources for a wide range of research activities in chemistry, physics and biology. The cost of such facilities and the lack of a sufficiently large user base will probably preclude their construction in Australia in the foreseeable future. The needs of Australian crystallographers for access to such facilities are assessed. In relation to synchrotron radiation sources, the Committee considered only the question of access to such facilities overseas. In relation to neutron beam sources, the Committee's inquiries included not only the question of access to powerful facilities overseas but also the special problems which confront Australian crystallographers as a result of the obsolescence of the HIFAR reactor. The arguments about, and options for, funding Australian use of facilities overseas are presented. The Committee concluded there is a strong case for the purchase of a beam-line at an overseas synchrotron radiation facility and a strong, though less urgent, case for substantial Australian involvement in an overseas neutron beam facility. The Committee recommended that the Australian HIFAR reactor be refurbished in its present shell, retaining the present flux and power levels, and that in the upgrading of the neutron scattering instrumentation at HIFAR special consideration be given to including items which are sufficiently specialised to attract the international neutron scattering community

  20. Assessing the Research Performance of Australian Universities

    OpenAIRE

    Valadkhani, Abbas; Worthington, Andrew

    2006-01-01

    This paper identifies new classifications of Australian universities based on their total and per-academic staff research outputs using the data for the period 1998-2002. We define research performance in terms of audited numbers of PhD completions, publications and grants (in accordance with rules established by the Department of Education, Science and Training). Our analysis indicates that (a) the highest achievers consists of the seven Group of Eight (Go8) universities; (b) the top-three...

  1. A multipurpose research reactor design using MCNP

    International Nuclear Information System (INIS)

    The Australian Replacement Research Reactor (RRR) is one of the most recently built advanced neutron research facilities. It is a 20 megawatt open-pool reactor fueled with low enriched uranium and cooled by forced light water. The core is located inside a chimney, surrounded by heavy water as reflector. This paper describes modeling and simulation of the RRR using MCNP. Three changes in the core design are also suggested and simulated. Neutron flux distribution and k(eff) for each model is calculated and compared with those of the original model. Model A is the original RRR design. It is modeled as close as possible to the original design for benchmark and comparison purposes. In the second model (Model B), a vertical square cavity is added in the center of the core, thus providing an irradiation channel with high harder-spectrum neutron flux. A simulation shows that a fast flux as high as 3.0*1014 n/cm2.s is available in a cavity whose area is 64 cm2 while minimally disturbing the rest of the core. The original central cross-shaped control blade is split into four smaller pieces and moved to outer regions. In the third model (Model C), control blades are placed asymmetrically, leading to higher thermal flux in some locations in the reflector, which can be used, for example, for cold neutron source. In the last model (Model D), the control blades never occupy the central part of the core leading to a flux trap and higher harder-spectrum flux around z-equals-0 plane in the central cavity. Individual or combination of these changes may be incorporated in future research reactor designs

  2. Multipurpose research reactors

    International Nuclear Information System (INIS)

    The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  3. Advanced heavy water reactor pressure tube-easy replaceability

    International Nuclear Information System (INIS)

    Advanced Heavy Water Reactor (AHWR) is a 300 MWe vertical pressure tube type reactor. A coolant channel consists of pressure tube, made of Zr-2.5 % Nb, which is separated from cold calandria tube using garter spring spacers. The principal function of pressure tube is to support and locate the fuel assembly and allows light water coolant through fuel assembly by natural circulation. Since AHWR is designed for life of 100 years, it necessitates the replacement of pressure tubes during service life. Easy replaceability of pressure tube, along with surveillance requirements, has major bearing on the design of coolant channel assembly. The several systems and tools have been conceptualised to cater the needs for easy and quick replacement of a pressure tube during reactor shut down. This paper gives the highlights of the innovative design features of coolant channel, preliminary design and pre-requisites for replacement, and experimental programme for demonstration of easy replaceability. (author)

  4. Replacement of the Advanced Test Reactor control room

    International Nuclear Information System (INIS)

    The control room for the Advanced Test Reactor has been replaced to provide modern equipment utilizing current standards and meeting the current human factors requirements. The control room was designed in the early 1960 era and had not been significantly upgraded since the initial installation. The replacement did not change any of the safety circuits or equipment but did result in replacement of some of the recorders that display information from the safety systems. The replacement was completed in concert with the replacement of the control room simulator which provided important feedback on the design. The design successfully incorporates computer-based systems into the display of the plant variables. This improved design provides the operator with more information in a more usable form than was provided by the original design. The replacement was successfully completed within the scheduled time thereby minimizing the down time for the reactor

  5. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

  6. Ageing of research reactors

    International Nuclear Information System (INIS)

    Historically, many of the research institutions were centred on a research reactor facility as main technological asset and major source of neutrons for research. Important achievements were made in time in these research institutions for development of nuclear materials technology and nuclear safety for nuclear energy. At present, ageing of nuclear research facilities among these research reactors and ageing of staff are considerable factors of reduction of competence in research centres. The safe way of mitigation of this trend deals with ageing management by so called, for power reactors, Plant Life Management and new investments in staff as investments in research, or in future resources of competence. A programmatic approach of ageing of research reactors in correlation with their actual and future utilisation, will be used as a basis for safety evaluation and future spending. (author)

  7. Computer analysis of thermal hydraulics for nuclear reactor safety

    International Nuclear Information System (INIS)

    This paper gives an overview of ANSTO's capability and recent research and development activities in thermal hydraulic modelling for nuclear reactor safety analysis, particularly for our research reactor, HIFAR (High Flux Australian Reactor) and its intended replacement, the Replacement Research Reactor (RRR). Several tools contribute to ANSTO's capability in thermal hydraulic modelling, including RELAP (developed in US) - a code for reactor system thermal-hydraulic analysis; CFS (developed in UK) - a general computational fluid dynamics code , which was used for thermal hydraulic analysis in reactor fuel elements; and HIZAPP (developed at ANSTO) - for coupling neutronics with thermal-hydraulics for reactor transient analysis

  8. Reactor Materials Research

    International Nuclear Information System (INIS)

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  9. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2001-04-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  10. INVAP's Research Reactor Designs

    International Nuclear Information System (INIS)

    INVAP, an Argentine company founded more than three decades ago, is today recognized as one of the leaders within the research reactor industry. INVAP has participated in several projects covering a wide range of facilities, designed in accordance with the requirements of our different clients. For complying with these requirements, INVAP developed special skills and capabilities to deal with different fuel assemblies, different core cooling systems, and different reactor layouts. This paper summarizes the general features and utilization of several INVAP research reactor designs, from subcritical and critical assemblies to high-power reactors IAEA safety

  11. Safety benefits from CANDU reactor replacement. A case study

    International Nuclear Information System (INIS)

    Both total core replacement and core retubing have been used in the CANDU industry. For future plant refurbishments, based on experience both in new construction and in recent refurbishments, the concept of total core replacement has been revisited. This builds on practices for replacement of other large plant equipment like boilers. The Bruce CANDU reactors, with their local shield tanks built around the Calandria and containment closely located around that Calandria Shield Tank Assembly (CSTA), are believed to be good candidates for core replacement. A structured process was used to design a replacement CSTA suitable for Bruce A use. The work started with a study of opportunities for safety enhancements in the core. This progressed into design studies and related design assist safety analysis on the reactor. A key element of the work involved consideration of how verified features from later CANDU designs, and from our new reactor design work, could be tailored to fit this replacement core. The replacement reactor core brings in structural improvements in both calandria and end shield, and safety improvements like the natural circulation enhancing moderator cooling layout and further optimized reactivity layouts to improve shutdown system performance. Bruce Power are currently studying the business implications of this and retube techniques as part of preparation for future refurbishments. The work explained in this paper is in the context of the safety related changes and the work to choose and quantify them. (author)

  12. Safety benefits from CANDU reactor replacement - a case study

    International Nuclear Information System (INIS)

    Both total core replacement and core retubing have been used in the CANDU industry. For future plant refurbishments, based on experience both in new construction and in recent refurbishments, the concept of total core replacement has been revisited. This builds on practices for replacement of other large plant equipment like boilers. The Bruce CANDU reactors, with their local shield tanks built around the Calandria and containment closely located around that Calandria Shield Tank Assembly (CSTA), are believed to be good candidates for core replacement. A structured process was used to design a replacement CSTA suitable for Bruce A use. The work started with a study of opportunities for safety enhancements in the core. This progressed into design studies and related design assist safety analysis on the reactor. A key element of the work involved consideration of how verified features from later CANDU designs, and from our new reactor design work, could be tailored to fit this replacement core. The replacement reactor core brings in structural improvements in both calandria and end shield, and safety improvements like the natural circulation enhancing moderator cooling layout and further optimized reactivity layouts to improve shutdown system performance. Bruce Power are currently studying the business implications of this and retube techniques as part of preparation for future refurbishments. The work explained in this paper is in the context of the safety related changes and the work to choose and quantify them. (author)

  13. Replacement steam generators for pressurized water reactors

    International Nuclear Information System (INIS)

    Babcock and Wilcox Canada has developed an Advanced Series steam generator for PWR Systems. This design incorporates all of the features that have contributed to the successful CANDU steam generator performance. This paper presents an overview of the design features and how the overall design relates to the requirements of a PWR reactor system

  14. High flux testing reactor Petten. Replacement of the reactor vessel and connected components. Overall report

    International Nuclear Information System (INIS)

    The project of replacing the HFR originated in 1974 when results of several research programmes confirmed severe neutron embrittlement of aluminium alloys suggesting a limited life of the existing facility. This report contains the detailed chronology of events concerning preparation and execution of the replacement. After a 14 months' outage the reactor resumed routine operation on 14th February, 1985. At the end of several years of planning and preparation the reconstruction proceded in the following steps: unloading of the old core, decay of short-lived radioactivity in December 1983, removal of the old tank and of its peripheral equipment in January-February 1984, segmentation and waste disposal of the removed components in March-April, decontamination of the pools, bottom penetration overhauling in May-June, installation of the new tank and other new components in July-September, testing and commissioning, including minor modifications in October-December, and, trials runs and start-up preparation in January-February 1985. The new HFR Petten features increased and improved experimental facilities. Among others the obsolete thermal columns was replaced by two high flux beam tubes. Moreover the new plant has been designed for future increases of reactor power and neutron fluxes. For the next three to four years the reactor has to cope with a large irradiation programme, claiming its capacity to nearly 100%

  15. Safety of research reactors

    International Nuclear Information System (INIS)

    The number of research reactors that have been constructed worldwide for civilian applications is about 651. Of the reactors constructed, 284 are currently in operation, 258 are shut down and 109 have been decommissioned. More than half of all operating research reactors worldwide are over thirty years old. During this long period of time national priorities have changed. Facility ageing, if not properly managed, has a natural degrading effect. Many research reactors face concerns with the obsolescence of equipment, lack of experimental programmes, lack of funding for operation and maintenance and loss of expertise through ageing and retirement of the staff. Other reactors of the same vintage maintain effective ageing management programmes, conduct active research programmes, develop and retain high calibre personnel and make important contributions to society. Many countries that operate research reactors neither operate nor plan to operate power reactors. In most of these countries there is a tendency not to create a formal regulatory body. A safety committee, not always independent of the operating organization, may be responsible for regulatory oversight. Even in countries with nuclear power plants, a regulatory regime differing from the one used for the power plants may exist. Concern is therefore focused on one tail of a continuous spectrum of operational performance. The IAEA has been sending missions to review the safety of research reactors in Member States since 1972. Some of the reviews have been conducted pursuant to the IAEA' functions and responsibilities regarding research reactors that are operated within the framework of Project and Supply Agreements between Member States and the IAEA. Other reviews have been conducted upon request. All these reviews are conducted following procedures for Integrated Safety Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety

  16. Research reactor support

    International Nuclear Information System (INIS)

    Research reactors (RRs) have been used in a wide range of applications including nuclear power development, basic physics research, education and training, medical isotope production, geology, industry and other fields. However, many research reactors are fuelled with High Enriched Uranium (HEU), are underutilized and aging, and have significant quantities of spent fuel. HEU inventories (fresh and spent) pose security risks Unavailability of a high-density-reprocessable fuel hinders conversion and limits back-end options and represents a survival dilemma for many RRs. Improvement of interim spent fuel storage is required at some RRs. Many RRs are under-utilized and/or inadequately funded and need to find users for their services, or permanently shut down and eventually decommission. Reluctance to decommission affect both cost and safety (loss of experienced staff ) and many shut down but not decommissioned RR with fresh and/or spent fuel at the sites invoke serious concern. The IAEA's research reactor support helps to ensure that research reactors can be operated efficiently with fuels and targets of lower proliferation and security concern and that operators have appropriate technology and options to manage RR fuel cycle issues, especially on long term interim storage of spent research reactor fuel. Availability of a high-density-reprocessable fuel would expand and improve back end options. The International Atomic Energy Agency provides assistance to Member States to convert research reactors from High Enriched Uranium fuel and targets (for medical isotope production) to qualified Low Enriched Uranium fuel and targets while maintaining reactor performance levels. The assistance includes provision of handbooks and training in the performance of core conversion studies, advice for the procurement of LEU fuel, and expert services for LEU fuel acceptance. The IAEA further provides technical and administrative support for countries considering repatriation of its

  17. Evaluation of research reactors

    International Nuclear Information System (INIS)

    The present status of research reactors with highly enriched (93%) uranium fuel at JAERI, JRR-2 and JMTR is described. JRR-2 is a heterogeneous type of reactor, using heavy water as moderator and coolant. It uses both MTR type and cylindrical type of fuel elements. The maximum thermal power and the thermal neutron flux are 10 MW and 2x1014 n/cm2 see respectively. The reactor has been used for various experiments such as solid state physics, material irradiation, reactor fuel irradiation and radioisotope production. The JMTR is a multi-purpose tank type material testing reactor, and light water moderator and coolant, operated at 50 MW. The evaluation of lower enriched fuel and its consequences for both reactors is considered more especially

  18. Thai research reactor

    International Nuclear Information System (INIS)

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  19. Safety of research reactors (Design and Operation)

    International Nuclear Information System (INIS)

    The primary objective of this thesis is to conduct a comprehensive up-to-date literature review on the current status of safety of research reactor both in design and operation providing the future trends in safety of research reactors. Data and technical information of variety selected historical research reactors were thoroughly reviewed and evaluated, furthermore illustrations of the material of fuel, control rods, shielding, moderators and coolants used were discussed. Insight study of some historical research reactors was carried with considering sample cases such as Chicago Pile-1, F-1 reactor, Chalk River Laboratories,. The National Research Experimental Reactor and others. The current status of research reactors and their geographical distribution, reactor category and utilization is also covered. Examples of some recent advanced reactors were studied like safety barriers of HANARO of Korea including safety doors of the hall and building entrance and finger print identification which prevent the reactor from sabotage. On the basis of the results of this research, it is apparent that a high quality of safety of nuclear reactors can be attained by achieving enough robust construction, designing components of high levels of efficiency, replacing the compounds of the reactor in order to avoid corrosion and degradation with age, coupled with experienced scientists and technical staffs to operate nuclear research facilities.(Author)

  20. Nuclear research reactors activities in INVAP

    International Nuclear Information System (INIS)

    This presentation describes the different activities in the research reactor field that are being carried out by INVAP. INVAP is presently involved in the design of three new research reactors in three different countries. The RA-10 is a multipurpose reactor, in Argentina, planned as a replacement for the RA-3 reactor. INVAP was contracted by CNEA for carrying out the preliminary engineering for this reactor, and has recently been contracted by CNEA for the detailed engineering. CNEA groups are strongly involved in the design of this reactor. The RMB is a multipurpose reactor, planned by CNEN from Brazil. CNEN, through REDETEC, has contracted INVAP to carry out the preliminary engineering for this reactor. As the user requirements for RA-10 and RMB are very similar, an agreement was signed between Argentina and Brasil governments to cooperate in these two projects. The agreement included that both reactors would use the OPAL reactor in Australia, design and built by INVAP, as a reference reactor. INVAP has also designed the LPRR reactor for KACST in Saudi Arabia. The LPRR is a 30 kw reactor for educational purposes. KACST initially contracted INVAP for the engineering for this reactor and has recently signed the contract with INVAP for building the reactor. General details of these three reactors will be presented

  1. Nuclear research reactors activities in INVAP

    Energy Technology Data Exchange (ETDEWEB)

    Ordonez, Juan Pablo [INVAP, Bariloche (Argentina)

    2013-07-01

    This presentation describes the different activities in the research reactor field that are being carried out by INVAP. INVAP is presently involved in the design of three new research reactors in three different countries. The RA-10 is a multipurpose reactor, in Argentina, planned as a replacement for the RA-3 reactor. INVAP was contracted by CNEA for carrying out the preliminary engineering for this reactor, and has recently been contracted by CNEA for the detailed engineering. CNEA groups are strongly involved in the design of this reactor. The RMB is a multipurpose reactor, planned by CNEN from Brazil. CNEN, through REDETEC, has contracted INVAP to carry out the preliminary engineering for this reactor. As the user requirements for RA-10 and RMB are very similar, an agreement was signed between Argentina and Brasil governments to cooperate in these two projects. The agreement included that both reactors would use the OPAL reactor in Australia, design and built by INVAP, as a reference reactor. INVAP has also designed the LPRR reactor for KACST in Saudi Arabia. The LPRR is a 30 kw reactor for educational purposes. KACST initially contracted INVAP for the engineering for this reactor and has recently signed the contract with INVAP for building the reactor. General details of these three reactors will be presented.

  2. Research reactor DHRUVA

    International Nuclear Information System (INIS)

    DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 1014 n/cm2/sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

  3. TRIGA research reactors

    International Nuclear Information System (INIS)

    TRIGA (Training, Research, Isotope production, General-Atomic) has become the most used research reactor in the world with 65 units operating in 24 countries. The original patent for TRIGA reactors was registered in 1958. The success of this reactor is due to its inherent level of safety that results from a prompt negative temperature coefficient. Most of the neutron moderation occurs in the nuclear fuel (UZrH) because of the presence of hydrogen atoms, so in case of an increase of fuel temperature, the neutron spectrum becomes harder and neutrons are less likely to fission uranium nuclei and as a consequence the power released decreases. This inherent level of safety has made this reactor fit for training tool in university laboratories. Some recent versions of TRIGA reactors have been designed for medicine and industrial isotope production, for neutron therapy of cancers and for providing a neutron source. (A.C.)

  4. Dossier: research reactors

    International Nuclear Information System (INIS)

    Research reactors are used at the CEA (the French atomic energy commission) since many years. Their number has been reduced but they remain unique tools that CEA valorize continuously. The results of the programs involving such reactors are of prime importance for the operation of Electricite de France (EdF) park of existing power plants but also for the design of future nuclear power plants and future research reactors. This dossier presents three examples of research reactors in use at the CEA: Osiris and Orphee (CEA-Saclay), devoted to nuclear energy and fundamental research, respectively, and the critical mockups Eole, Minerve and Masurca (CEA-Cadarache) devoted to nuclear data libraries and neutronic calculation. (J.S.)

  5. Reactor Core Internals Replacement of Ikata Units 1 and 2

    International Nuclear Information System (INIS)

    Ikata Units 1 and 2 have been in operation for a very long time. Unit 1, in particular, is one of the longest operating PWRs in Japan. In view of this history, preventive and proactive strategy has been adopted for the maintenance of major primary system components. Both units successfully completed the replacement of steam generators and reactor vessel heads approximately ten years ago. With regard to the reactor core internals, baffle former bolts (BFBs) were found to have been damaged by stress corrosion cracking (SCC) in 1989 at Bugey 2 in France. Since then, similar incidents have been reported in other European and U.S. plants, resulting in the replacement of failed BFBs. The BFB issue can be dealt with either by replacing bolts when damage is found or by replacing the entire core internals with those of a new design. Ikata Units 1 and 2 chose the latter and carried it out in 2004 and 2005, respectively.

  6. Research Reactor Benchmarks

    International Nuclear Information System (INIS)

    A criticality benchmark experiment performed at the Jozef Stefan Institute TRIGA Mark II research reactor is described. This experiment and its evaluation are given as examples of benchmark experiments at research reactors. For this reason the differences and possible problems compared to other benchmark experiments are particularly emphasized. General guidelines for performing criticality benchmarks in research reactors are given. The criticality benchmark experiment was performed in a normal operating reactor core using commercially available fresh 20% enriched fuel elements containing 12 wt% uranium in uranium-zirconium hydride fuel material. Experimental conditions to minimize experimental errors and to enhance computer modeling accuracy are described. Uncertainties in multiplication factor due to fuel composition and geometry data are analyzed by sensitivity analysis. The simplifications in the benchmark model compared to the actual geometry are evaluated. Sample benchmark calculations with the MCNP and KENO Monte Carlo codes are given

  7. Is Mixed Methods Research Used in Australian Career Development Research?

    Science.gov (United States)

    Cameron, Roslyn

    2010-01-01

    Mixed methods research has become a substantive and growing methodological force that is growing in popularity within the human and social sciences. This article reports the findings of a study that has systematically reviewed articles from the "Australian Journal of Career Development" from 2004 to 2009. The aim of the study was to provide a…

  8. First Algerian research reactor

    International Nuclear Information System (INIS)

    In 1985, both the Algerian Commissariat of New Energies and the Argentine National Atomic Energy Commission plus the firm INVAP S.E., started a series of mutual visits aimed at defining the mechanisms for cooperation in the nuclear field. Within this framework, a commercial contract was undersigned covering the supply of a low-power reactor (RUN), designed for basic and applied research in the fields of reactor physics and nuclear engineering. The reactor may also be used for performing experiences with neutron beams, for the irradiation of several materials and for the training of technicians, scientists and operators

  9. Proposal of a synchro panel meter instrument to replace the obsolete Synchro/Resolver reading device used as position indicator of safety rods assembly of the Brazilian IEA-R1 Nuclear Research Reactor

    International Nuclear Information System (INIS)

    IPEN (Instituto de Pesquisas Energeticas e Nucleares) was founded in 1956 (as Atomic Energy Institute - IEA) as a facility complex, for the research, development and application, in the nuclear technology field. The institute is recognized as a national leader in nuclear research and development (R and D), including the areas of reactor operation, radiopharmaceuticals, industrial and laboratory applications, materials science and laser technologies and applications. IPEN's main facility is the IEA-R1, nuclear research reactor (NRR), today, the only one in Brazil with a power level suitable for applications in physics, chemistry, biology and engineering. Some radioisotopes are also produced in IEA-R1, for medical and other applications. A common problem faced in the IEA-R1 maintenance is instrumentation obsolescence; spare parts are no more available, because of discontinued production, and an updating program is mandatory, aiming at modernization of old-aged I and C systems. In the presented context, an electronic system is here proposed, as a replacement for the reactor safety (shim) rods assembly position indicator, based on an open-source physical computing platform called Arduino, which includes a simple microcontroller board and a software-code development environment. A mathematical algorithm for the synchro-motor signal processing was developed, and the obtained resolution was better than 1.5%. (author)

  10. Proposal of a synchro panel meter instrument to replace the obsolete Synchro/Resolver reading device used as position indicator of safety rods assembly of the Brazilian IEA-R1 Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Toledo, Fabio de; Brancaccio, Franco; Cardenas, Jose Patricio N., E-mail: fatoledo@ipen.br, E-mail: fbrancac@ipen.br, E-mail: ahiru@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    IPEN (Instituto de Pesquisas Energeticas e Nucleares) was founded in 1956 (as Atomic Energy Institute - IEA) as a facility complex, for the research, development and application, in the nuclear technology field. The institute is recognized as a national leader in nuclear research and development (R and D), including the areas of reactor operation, radiopharmaceuticals, industrial and laboratory applications, materials science and laser technologies and applications. IPEN's main facility is the IEA-R1, nuclear research reactor (NRR), today, the only one in Brazil with a power level suitable for applications in physics, chemistry, biology and engineering. Some radioisotopes are also produced in IEA-R1, for medical and other applications. A common problem faced in the IEA-R1 maintenance is instrumentation obsolescence; spare parts are no more available, because of discontinued production, and an updating program is mandatory, aiming at modernization of old-aged I and C systems. In the presented context, an electronic system is here proposed, as a replacement for the reactor safety (shim) rods assembly position indicator, based on an open-source physical computing platform called Arduino, which includes a simple microcontroller board and a software-code development environment. A mathematical algorithm for the synchro-motor signal processing was developed, and the obtained resolution was better than 1.5%. (author)

  11. Reactor Materials Research

    International Nuclear Information System (INIS)

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel

  12. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2002-04-01

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel.

  13. Developments in the regulation of research reactors

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has data on over 670 research reactors in the world. Fewer than half of them are operational and a significant number are in a shutdown but not decommissioned state. The International Nuclear Safety Advisory Group (INSAG) has expressed concerns about the safety of many research reactors and this has resulted in a process to draw up an international Code of Conduct on the Safety of Research Reactors. The IAEA is also reviewing its safety standards applying to research reactors. On the home front, regulation of the construction of the Replacement Research Reactor continues. During the construction phase, regulation has centred around the consideration of Requests for Approval (RFA) for the manufacture and installation of systems, structures and components important for safety. Quality control of construction of systems, structures and components is the central issue. The process for regulation of commissioning is under consideration

  14. The "Paradox of Interdisciplinarity" in Australian Research Governance

    Science.gov (United States)

    Woelert, Peter; Millar, Victoria

    2013-01-01

    This paper identifies what can be called the "paradox of interdisciplinarity" (Weingart 2000) in Australian higher education research governance and explores some of its constitutive dimensions. In the Australian context, the paradox of interdisciplinarity primarily concerns the proliferation of a programmatic discourse of…

  15. Gaseous fuel reactor research

    Science.gov (United States)

    Thom, K.; Schneider, R. T.

    1977-01-01

    The paper reviews studies dealing with the concept of a gaseous fuel reactor and describes the structure and plans of the current NASA research program of experiments on uranium hexafluoride systems and uranium plasma systems. Results of research into the basic properties of uranium plasmas and fissioning gases are reported. The nuclear pumped laser is described, and the main results of experiments with these devices are summarized.

  16. PROTEUS research reactor

    International Nuclear Information System (INIS)

    The PROTEUS zero power reactor at the Paul Scherrer Institute (PSI) in Switzerland achieved first criticality in 1968 and since then has been operated as an experimental tool for reactor physics research on test lattices representative of a wide range of reactor concepts. Reactor design codes and their associated data libraries are validated on the basis of the experimental results obtained. PROTEUS is normally configured as a driven system, in which a subcritical test zone is made critical by the surrounding driver zones. The advantages of driven systems can be summarized as follows: - Smaller amount of test fuel is required; - Large range of test zone conditions (including k∞ < 1 states) can be investigated by changes in the driver loading alone, thus avoiding undesirable perturbations to the test zone which would influence the measurement conditions and thus affect the interpretability of the results; - Necessary reactor control and instrumentation equipment (usually perturbing from the experimental viewpoint) can be located in the outer driver regions, thereby avoiding disturbance of the test lattice

  17. Operational experience with research reactors in Trombay

    International Nuclear Information System (INIS)

    The research reactors Apsara and Cirus, located at the Bhabha Atomic Research Centre, Trombay, Bombay have recently completed 30 years and 26 years of successful operation respectively. Both reactors have been used extensively for research, isotope production and manpower training. Several measures have been taken towards achieving this long successful operation. These include preventive maintenance, meticulous control on chemistry of fluid systems, proper physics management, surveillance measures and modifications to system and equipment based on experience. Extensive training of O and M personnel has been another important factor contributing towards this. Major topics detailed in this paper include detection of one leaky reactor vessel lattice tube in Cirus and its successful plugging, replacement of old control system hardware consisting of vacuum tubes with modern solid state devices in both the reactors, installation of S.S.liner in Apsara reactor pool and certain modifications towards improving fuel performance in Cirus. Some aspects of preventive maintenance are also dealt with. (author)

  18. Fast breeder reactor research

    International Nuclear Information System (INIS)

    reactors of the future, the body of research aimed at developing liquid metal cooled fast reactors, national plans for work in 1976 on developing fast reactors - these were some of the topics discussed in connection with the national programmes. The development of power reactors involves a wide range of problems in the fields of nuclear and reactor physics, the thermophysics, chemistry, physics and technology of the cooling system, structural materials and nuclear fuel, the fabrication of reliable fuel elements and operating equipment, reactor monitoring and control, spent fuel reprocessing, the economics of constructing fast power reactors, nuclear safety, etc. The IWGFR, as at previous meetings, therefore paid great attention to the matter of holding international specialists' meetings. The working group recommended that the IAEA should organize the following IWGFR meetings in 1976: (1) In-Service Inspection and Monitoring (Bensberg, FRG, March 1976). (2) Cavitation in Sodium and Studies of Analogy with Water as Compared to Sodium (Cadarache, France, April 1976). (3) High Temperature Structural Design Technology (United States, May 1976) (4) Aerosol Formation, Vapour Deposits and Sodium Vapour Trapping (France, September-December 1976). The Group welcomed the IAEA's proposal to hold specialists' meetings on 'Fast Reactor Instrumentation' and 'Fuel Reprocessing and Recycling Techniques' within the framework of the Agency's programme of working groups in 1976. After discussing questions of co-ordinating and organizing international conferences on fast reactors, the IWGFR agreed to send representatives to the joint meeting of the American Nuclear Society and the American Institute of Metallurgical Engineers on 'Liquid Metal Technology', to be held at Champion, Pennsylvania, U.S.A. from 3-6 May 1976, and recommended that the IAEA should organize an international symposium on the 'Design, Construction and Operating Experience of Demonstration Fast Power Reactors' at Bologna

  19. "A deep fragrance of academia": the Australian Tobacco Research Foundation

    OpenAIRE

    Chapman, S; Carter, S.; Peters, M

    2003-01-01

    Objectives: (1) To review the history of the tobacco industry supported Australian Tobacco Research Foundation (ATRF)(1970–1994) for evidence of the industry's use of the Foundation to further its objectives that "more research was needed" on smoking and health and to promulgate the view that nicotine was not addictive. (2) To review efforts by public health advocates to discredit the ATRF as a public relations tool used by the Australian industry.

  20. Research Reactors of Ukraine

    International Nuclear Information System (INIS)

    Ukraine today operates two nuclear research reactors: WWR-M (total capacity of 10 MW), which is located on the site of the Kyiv Nuclear Research Institute of the National Academy of Sciences of Ukraine, and IR-100 (total capacity of 200 kW), which is located on the site of Sevastopol National University of Nuclear Energy and Industry. Both of them have been in operation since the 1960s. The operation project period of WWR-M for which it is licensed is limited to 31 December 2013. In order to improve safety at WWR-M several modernization projects, development of the reactor vessel and the first loop equipment ageing management programme were conducted. According to the license for operation of IR-100 the operation period of the reactor depends upon results from assessments of critical safety elements such as the tank, control and protection system, cable lines and electrical switchgear. Currently the operation period of this equipment has been justified until 2013. (author)

  1. Australian RRRP seismic design and qualification

    International Nuclear Information System (INIS)

    The present paper focuses on the structural design and qualification that has been carried out for the safety against seismic events at the Australian RRRP (Replacement Research Reactor Project). The RRRP is a 20 MW multi-purpose nuclear research reactor designed and constructed by INVAP from Argentina, for ANSTO (Australian Nuclear Science and Technology Organisation) in Sydney, Australia. On account of the site characteristics, the australian regulations and the engineering and design standards applicable to the project, the design requirements for the reactor included very stringent and clear guidelines that should be observed to ensure that appropriate levels of protection are provided against seismic events. Despite the fact of being a research reactor with a thermal power two orders of magnitude lower than that of nuclear power plants, the methodology used in the seismic qualification was based on the one used for NPPs instead of using simplified methods as suggested by the literature on research reactors. With this in mind, the regulatory and engineering frame was based on IAEA standards for power reactors and complementary guides for specific issues. The paper describes the Design Basis Ground Motion, Seismic Levels, Seismic Classification and the particular design criteria and qualification methods used for systems as: Civil, Mechanical, Process, Instrumentation and Control, Electrical, HVAC, etc. (authors)

  2. Inspection and replacement of baffle assembly screws inside American reactor vessels

    International Nuclear Information System (INIS)

    The baffle assembly inside the vessel of a 900 MWe reactor designed by Framatome, is made up of 44 plates fixed on 8 horizontal supports by a system of about 1000 screws. These plates undergo high neutron flux and the problem of screw cracking appeared at the end of the eighties in the first-generation reactors. The first operation on a large scale concerning the screws of a Westinghouse type reactor, was performed on the Tihange-1 power plant where Framatome controlled 960 screws and replaced 91. In 1997 as a consequence of the Belgian and French feedback experience, American plant operators launched a vast program of preventive actions: material analysis, inspection of baffle plate screws and replacement of defective screws. This program was held in cooperation with EPRI (electric power research institute) and under the control of NRC (nuclear regulatory commission). Framatome Technologies Inc (FTI) was in charge of the in-situ inspection and replacement of the screws. FTI designed special tools and equipment adapted to the 2-loop American reactors but the basis ideas were those applied on the Tihange reactor. The successful experience of FTI has allowed the firm to be commissioned for 6 2-loops American reactors. (A.C.)

  3. Decommissioning of research reactors

    International Nuclear Information System (INIS)

    Research reactors of WWR-S type were built in countries under Soviet influence in '60, last century and consequently reached their service life. Decommissioning implies removal of all radioactive components, processing, conditioning and final disposal in full safety of all sources on site of radiological pollution. The WWR-S reactor at Bucuresti-Magurele was put into function in 1957 and operated until 1997 when it was stopped and put into conservation in view of decommissioning. Presented are three decommissioning variants: 1. Reactor shut-down for a long period (30-50 years) what would entail a substantial decrease of contamination with lower costs in dismantling, mechanical, chemical and physical processing followed by final disposal of the radioactive wastes. The drawback of this solution is the life prolongation of a non-productive nuclear unit requiring funds for personnel, control, maintenance, etc; 2. Decommissioning in a single stage what implies large funds for a immediate investment; 3. Extending the operation on a series of stages rather phased in time to allow a more convenient flow of funds and also to gather technical solutions, better than the present ones. This latter option seems to be optimal for the case of the WWR-S Research at Bucharest-Magurele Reactor. Equipment and technologies should be developed in order to ensure the technical background of the first operations of decommissioning: equipment for scarification, dismantling, dismemberment in a highly radioactive environment; cutting-to-pieces and disassembling technologies; decontamination modern technologies. Concomitantly, nuclear safety and quality assurance regulations and programmes, specific to decommissioning projects should be implemented, as well as a modern, coherent and reliable system of data acquisition, recording and storing. Also the impact of decommissioning must be thoroughly evaluated. The national team of specialists will be assisted by IAEA experts to ensure the

  4. Applications of Research Reactors

    International Nuclear Information System (INIS)

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property'. The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The purpose of the earlier publication, The Application of Research Reactors, IAEA-TECDOC-1234, was to present descriptions of the typical forms of research reactor use. The necessary criteria to enable an application to be performed were outlined for each one, and, in many cases, the minimum as well as the desirable requirements were given. This revision of the publication over a decade later maintains the original purpose and now specifically takes into account the changes in service requirements demanded by the relevant stakeholders. In particular, the significant improvements in

  5. Modern research reactors in the world and RA research reactor

    International Nuclear Information System (INIS)

    This paper covers the following topics: fundamentals of research reactors, thermal neutron flux density, classification of research reactors in the world, properties of research reactors of higher power in the world according to IAEA data for 1995, their application, and trend of development, experimental feasibility and status of RA reactor. Trend of research reactors development in the world (after 1980) is directed towards increasing the neutron production quality factor, i.e. ratio between thermal neutron flux density and reactor power, which is achieved by designing compact reactor cores. With the aim of renewal of RA reactor (without analysis of reactor components and staff aging, possibility of restart and commercialization), according to the analysis in this paper, it can be concluded: there is very few reactors under construction in the world, all the important countries in Europe have research reactors; RA reactor is not very interesting for development of reactor physics; nowadays RA reactor is in the group of reactors which are 30-40 years old; its inventories of fuel and heavy water are enough for about 20 years of operation; it has achieved high quality factor of neutron production with low and highly enriched fuel; core transfer from low highly enriched to low enriched fuel should be carefully studies from operation, experimental and economical point of view; it is necessary to use the advantages of RA reactor (minimum investment): volume of the core and reflector which enables availability of neutron flux for the users (numerous experimental loops), fuel in shape of slugs enabling efficient fuel management and flexible neutron flux distribution in the core in the reflector, reactor operation should be directed towards commercial applications. Bibliography of more than 140 relevant papers used is included in this paper

  6. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    The Ohio State University research reactor (OSURR) is undergoing improvements in its research and educational capabilities. A computer-based digital data acquisition system, including a reactor system mimic, will be installed as part of these improvements. The system will monitor the reactor system parameters available to the reactor operator either in digital parameters available to the reactor operator either in digital or analog form. The system includes two computers. All the signals are sent to computer 1, which processes the data and sends the data through a serial port to computer 2 with a video graphics array VGA monitor, which is utilized to display the mimic system of the reactor

  7. MINT research reactor safety program

    Energy Technology Data Exchange (ETDEWEB)

    Mohamad Idris bin Taib [Division of Special Project, Malaysian Institute for Nuclear Technology Research (MINT), Bangi (Malaysia)

    2000-11-01

    Malaysian Institute for Nuclear Technology Research (MINT) Research Reactor Safety Program has been done along with Reactor Power Upgrading Project, Reactor Safety Upgrading Project and Development of Expert System for On-Line Nuclear Process Control Project. From 1993 up to date, Neutronic and Thermal-hydraulics analysis, Probabilistic Safety Assessment as well as installation of New 2 MW Secondary Cooling System were done. Installations of New Reactor Building Ventilation System, Reactor Monitoring System, Updating of Safety Analysis Report and Upgrading Primary Cooling System are in progress. For future activities, Reactor Modeling will be included to add present activities. (author)

  8. Replacement of secondary heat transport system components in the experimental fast reactor JOYO

    International Nuclear Information System (INIS)

    A recently completed major upgrade of the JOYO experimental sodium-cooled fast reactor, to the MK-III design, increased its irradiation capability. One major change was a 40% increase in thermal power to 140 MWt, which necessitated the replacement of the cooling system. Major challenges in the replacement of secondary components were control of impurity ingress and assurance of welding integrity. Damage to existing systems was avoided during replacement operations by taking measures to prevent ingress of air into the sodium systems. The long exposure of the used pipes made of ferritic low-alloy steel to hot sodium was a concern because previous research showed that this material changes its mechanical property in sodium hotter than 673 K. Used pipe, heat transfer tubes and welds were subjected to material tests. These tests did not show notable material problems. The replacement of components was completed without major troubles, demonstrating the effectiveness of the methods used. (authors)

  9. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  10. Physical security at research reactors

    International Nuclear Information System (INIS)

    Of the 84 non-power research facilities licensed under 10 CFR Part 50, 73 are active (two test reactors, 68 research reactors and three critical facilities) and are required by 10 CFR Part 73.40 to provide physical protection against theft of SNM and against industrial sabotage. Each licensee has developed a security plan required by 10 CFR Part 50.34(c) to demonstrate the means of compliance with the applicable requirements of 10 CFR Part 73. In 1974, the Commission provided interim guidance for the organization and content of security plans for (a) test reactors, (b) medium power research and training reactors, and (c) low power research and training reactors. Eleven TRIGA reactors, with power levels greater than 250 kW and all other research and training reactors with power levels greater than 100 kW and less than or equal to 5,000 kW are designated as medium power research and training reactors. Thirteen TRIGA reactors with authorized power levels less than 250 kW are considered to be low power research and training reactors. Additional guidance for complying with the requirements of 73.50 and 73.60, if applicable, is provided in the Commission's Regulatory Guides. The Commission's Office of Inspection and Enforcement inspects each licensed facility to assure that an approved security plan is properly implemented with appropriate procedures and physical protection systems

  11. A Ten Year Citation Analysis of Major Australian Research Institutions

    Science.gov (United States)

    Batterham, Robin J.

    2011-01-01

    The introduction of the Excellence in Research for Australia scheme has heightened debate amongst research institutions over the use of metrics such as citations, especially given the ready availability of citation data. An analysis is presented of the citation performance of nine Australian universities and the Commonwealth Scientific, Industrial…

  12. Management of research reactor ageing

    International Nuclear Information System (INIS)

    As of December 1993, about one quarter of the operating research reactors were over 30 years old. The long life of research reactors has raised some concern amongst research reactor operators, regulators and, to some extent, the general public. The International Atomic Energy Agency commenced activities on the topic of research reactor ageing by appointing an internal working group in 1988 and convening a Consultants Meeting in 1989. The subject was also discussed at an international symposium and a regional seminar held in 1989 and 1992 respectively. A draft document incorporating information and experience exchanged at the above meetings was reviewed by a Technical Committee Meeting held in Vienna in 1992. The present TECDOC is the outcome of this meeting and contains recommendations, guidelines and information on the management of research reactor ageing, which should be used in conjunction with related publications of the IAEA Research Reactor Safety Programme, which are referenced throughout the text. This TECDOC will be of interest to operators and regulators involved with the safe operation of any type of research reactor to (a) understand the behaviour and influence of ageing mechanisms on the reactor structures, systems and components; (b) detect and assess the effect of ageing; (c) establish preventive and corrective measures to mitigate these effects; and (d) make decisions aimed at the safe and continued operation of a research reactor. 32 refs, tabs

  13. Research reactors and alternative devices for research

    International Nuclear Information System (INIS)

    This report includes papers on research reactors and alternatives to the research reactors - radioisotopic neutron sources, cyclotrons, D-T neutron generators and small accelerators, used for radioisotope production, neutron activation analysis, material science, applied and basic research using neutron beams. A separate abstract was prepared for each of the 7 papers

  14. Facility modernization Annular Core Research Reactor

    International Nuclear Information System (INIS)

    The Annular Core Research Reactor (ACRR) has undergone numerous modifications since its conception in response to program needs. The original reactor fuel, which was special U-ZrH TRIGA fuel designed primarily for pulsing, has been replaced with a higher pulsing capacity BeO fuel. Other advanced operating modes which use this increased capability, in addition to the pulse and steady state, have been incorporated to tailor power histories and fluences to the experiments. Various experimental facilities have been developed that range from a radiography facility to a 50 cm diameter External Fuel Ring Cavity (FREC) using 180 of the original ZrH fuel elements. Currently a digital reactor console is being produced with GA, which will give enhanced monitoring capabilities of the reactor parameters while leaving the safety-related shutdown functions with analog technology. (author)

  15. Fusion reactor research

    International Nuclear Information System (INIS)

    This work covers four separate areas: (1) development of technology for processing liquid lithium from blankets, (2) investigation of hydrogen isotope permeation in candidate structural metals and alloys for near-term fusion reactors, (3) analytical studies encompassing fusion reactor thermal hydraulics, tritium facility design, and fusion reactor safety, and (4) studies involving dosimetry and damage analysis. Recent accomplishments in each of these areas are summarized

  16. Improvement of research reactor sustainability

    International Nuclear Information System (INIS)

    The Research Reactors as is well known have numerous applications in a wide range of science technology, nuclear power development, medicine, to enumerate only the most important. The requirements of clients and stack-holders are fluctuating for the reasons out of control of Research Reactor Operating Organization, which may ensure with priority the safety of facility and nuclear installation. Sustainability of Research Reactor encompasses several aspects which finally are concentrated on safety of Research Reactor and economical aspects concerning operational expenses and income from external resources. Ensuring sustainability is a continuous, permanent activity and also it requests a strategic approach. The TRIGA - 14 MW Research Reactor detains a 30 years experience of safe utilization with good performance indicators. In the last 4 years the reactor benefited of a large investment project for modernization, thus ensuring the previous performances and opening new perspectives for power increase and for new applications. The previous core conversion from LEU to HEU fuel accomplished in 2006 ensures the utilization of reactor based on new qualified European supplier of TRIGA LEU fuel. Due to reduction of number of performed research reactors, the 14 MW TRIGA modernized reactor will play a significant role for the following two decades. (author)

  17. Safety upgrades to the NRU research reactor

    International Nuclear Information System (INIS)

    The NRU (National Research Universal) Reactor is a 135 MW thermal research facility located at Chalk River Laboratories, and is owned and operated by Atomic Energy of Canada Limited. One of the largest and most versatile research reactors in the world, it serves as the R and D workhorse for Canada's CANDU business while at the same time filling the role as one of the world's major producers of medical radioisotopes. AECL plans to extend operation of the NRU reactor to approximately the year 2005 when a new replacement, the Irradiation Research Facility (IRF) will be available. To achieve this, AECL has undertaken a program of safety reassessment and upgrades to enhance the level of safety consistent with modem requirements. An engineering assessment/inspection of critical systems, equipment and components was completed and seven major safety upgrades are being designed and installed. These upgrades will significantly reduce the reactor's vulnerability to common mode failures and external hazards, with particular emphasis on seismic protection. The scheduled completion date for the project is 1999 December at a cost approximately twice the annual operating cost. All work on the NRU upgrade project is planned and integrated into the regular operating cycles of the reactor; no major outages are anticipated. This paper describes the safety upgrades and discusses the technical and managerial challenges involved in extending the operating life of the NRU reactor. (author)

  18. Replacement superheaters and reheaters for the prototype fast reactor

    International Nuclear Information System (INIS)

    The Prototype Fast Reactor (PFR) at Dounreay first went into service in 1974. Heat from the reactor core is transferred to three identical liquid sodium circuits which in turn are coupled to three steam generator circuits. As designed, each of the three steam generator circuits comprises an evaporator designed to produce steam at a pressure of 17.85 MN/m2, a superheater and a reheater, each capable of raising the steam to a temperature of 5400C. The steam is used to drive a conventional turbo-alternator capable of generating 250 MW(e). During the early life of the plant, two leaks developed in tube-to-tubeplate welds in two of the superheaters and in one of the reheaters. The two superheaters were repaired and returned to service by explosive plugging of the leaking tubes, but in the case of the reheater, the tubeplate was so badly cracked by caustic products formed by the ingress of steam to the sodium that the reheater was unsuitable for further use. Because of this unexpected failure mechanism it was considered prudent to provide a set of spare units, so in 1979 six replacement tube bundles were ordered, three superheaters and three reheaters. The design, installation and testing of these are described. (author)

  19. International topical meeting. Research Reactor Fuel Management (RRFM) and meeting of the International Group on Reactor Research (IGORR)

    International Nuclear Information System (INIS)

    Nuclear research and test reactors have been in operation for over 60 years, over 270 research reactors are currently operating in more than 50 countries. This meeting is dedicated to different aspects of research reactor fuels: new fuels for new reactors, the conversion to low enriched uranium fuels, spent fuel management and computational tools for core simulation. About 80 contributions are reported in this document, they are organized into 7 sessions: 1) international topics and overview on new projects and fuel, 2) new projects and upgrades, 3) fuel development, 4) optimisation and research reactor utilisation, 5) innovative methods in research reactors physics, 6) safety, operation and research reactor conversion, 7) fuel back-end management, and a poster session. Experience from Australian, Romanian, Libyan, Syrian, Vietnamese, South-African and Ghana research reactors are reported among other things. The Russian program for research reactor spent fuel management is described and the status of the American-driven program for the conversion to low enriched uranium fuels is presented. (A.C.)

  20. The Australian nuclear reactor, HIFAR, its past present and future

    International Nuclear Information System (INIS)

    The role of the AAEC's reactor, HIFAR has changed from support for the development of an indigenous power reactor to radioisotope producer and neutron beam source. An account is given of the last twenty-four years' operating experience. A brief review of modernisation programs for reactors of the DIDO class is followed by details of the current HIFAR refurbishing program

  1. Phelan's Bibliometric Analysis of the Impact of Australian Educational Research

    Science.gov (United States)

    Bates, Richard

    2003-01-01

    Phelan (2000) has produced a complex bibliometric analysis of the international contribution of Australian educational research based upon publications and citations reported in the journals indexed by the Institute for Scientific Information--the Standard & Poors of the academic world. This paper examines Phelan's analysis, showing its strengths…

  2. The research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    Paper dwells upon the design and the operation of one of the German test reactors, namely, the TRIGA Mainz one (TRIGA: Training Research Isotope Production General Atomic). The TRIGA reactor is a pool test reactor the core of which contains a graphite reflector and is placed into 2 m diameter and 6.25 m height aluminum vessel. There are 75 fuel elements in the reactor core, and any of them contains about 36 g of 235U. The TRIGA reactors under the stable operation enjoy wide application to ensure tests and irradiation, namely: neutron activation analysis, radioisotope production, application of a neutron beam to ensure the physical, the chemical and the medical research efforts. Paper presents the reactor basic experimental program lines

  3. Advances in reactor safety research

    International Nuclear Information System (INIS)

    The Nuclear Safety Project is an important part of the German reactor safety research programme. It works on problems concerning safety and environemental risks of LWR reactors and reprocessing plants and investigates accident consequences. At the 1978 annual meeting, the core behaviour on cooling and reactivity disturbances was discussed, as well as release, retention, and possible radiological effects of radioactive pollutants. Among other subjects, fission product retention in LWR reactors and reprocessing plants were reported on as well as hypothetic core meltdown. (orig.)

  4. Research reactor decommissioning

    International Nuclear Information System (INIS)

    Full text: Of the ∼ 800 research reactors constructed worldwide to date, ∼50% have been shut down and are at various stages of decommissioning. Many reached the end of their design lives or were shut down due to strategic, economic or regulatory considerations. 27% of those in operation are over 40 years old and will need to be decommissioned soon. Decommissioning normally takes the facility permanently out of service and subjects it to progressive hazard reduction, dismantling and decontamination in a safe, secure economically viable way, using best practicable means to meet the best practicable environmental option, such that the risks and doses to workers and the general public are maintained as low as reasonably practicable. Whilst most decommissioning techniques are well established there are still some challenging and important issues that need resolution. Perhaps the most challenging issue is radioactive waste management and storage. It is vitally important that all local and national waste classification, transportation, storage and end point requirements are known, as the adopted strategy will be heavily influenced by these factors. Other equally important but softer issues include the requirement for early decommissioning plans, adequate funding/cost estimates and the involvement of all relevant stakeholders. A comprehensive decommissioning plan should be produced up front that encompasses an early radiological characterisation survey of the facility/site. An appropriate funding mechanism needs to be assured. Whilst regular revisions of the decommissioning cost study should help to determine required funds, it is important to validate these cost estimates by benchmarking other decommissioning projects and accumulated experience. The use of appropriate 'stakeholder dialogue' methods by the facility operator to inform and communicate with all interested parties, such as government and non-government organisations, regulators, trades unions, anti

  5. Research Reactors Coalitions

    International Nuclear Information System (INIS)

    When considering the potential role of an existing RR or possibly the construction of a new RR, it is clear that a nuclear science and technology programme (including nuclear power) could benefit provided the RR is safely and competently managed, well utilised and adequately funded. Based on MSs experience, a domestic RR may not be required to develop a nuclear power programme, provided the decision takes advantage of foreign expertise, including access to foreign RRs facilities and RRs regional/international networks. If a country decides to gain access to a foreign research reactor, it may need considering the potential risk of change in the political relationship with the host country that could compromise the achievement of its national relevant objectives. This risk may be offset by availability of many options within one or more regional/international RRs networks and coalitions. Examples include the use of existing RRs in vendor, non-vendor countries and, in some cases non-nuclear power countries, to develop human resources in support of the introduction of nuclear power elsewhere. International RR networking trends are most evident with high flux, higher capability, and more complex fuel and material testing RRs being shared through international partnerships. However, networks involving low-medium power RRs for education and training purposes are also gaining a more prominent role to support nuclear capacity building in newcomer MSs. Networking through the internet seems also to be a promising way to support, as complementary offer to direct access to RRs facilities, MSs nuclear capacity building objectives (e.g. the IRL project)

  6. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.)

  7. Enrichment reduction for research reactors

    International Nuclear Information System (INIS)

    The worldwide activities on enrichment reduction for research reactors are reviewed and the national and international programs are described. Especially the following points are discussed: Benchmark calculations, reactor safety, fuel element development, irradiation tests, post irradiation examinations, full core demonstrations, activities of the GKSS and economical questions. (orig.)

  8. Ageing management for research reactors

    International Nuclear Information System (INIS)

    During the past several years, ageing of research reactor facilities continues to be an important safety issue. Despite the efforts exerted by operating organizations and regulatory authorities worldwide to address this issue, the need for an improved strategy as well as the need for establishing and implementing a systematic approach to ageing management at research reactors was identified. This paper discusses, on the basis of the IAEA Safety Standards, the effect of ageing on the safety of research reactors and presents a proactive strategy for ageing management. A systematic approach for ageing management is developed and presented together with its key elements, along with practical examples for their application. (author)

  9. Ranking and Clustering Australian University Research Performance, 1998-2002

    OpenAIRE

    Valadkhani, Abbas; Worthington, Andrew

    2005-01-01

    This paper clusters and ranks the research performance of thirty-seven Australian universities over the period 1998-2002. Research performance is measured according to audited numbers of PhD completions, publications and grants (in accordance with rules established by the Department of Education, Science and Training) and analysed in both total and per academic staff terms. Hierarchical cluster analysis supports a binary division between fifteen higher and twenty-two lower-performing universi...

  10. IAEA safeguards at research reactors

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency applies safeguards to almost 150 facilities classified as research reactors. From a safeguards point of view, these facilities present a spectrum of features that must be addressed both from the nuclear material and from the operational viewpoints. The nuclear fuel used by these reactors varies from high enriched uranium (NEU), up to 93 U-235, to natural uranium and the thermal power output from over 100 megawatt to less than ten watts. Research reactors are also used for a wide variety of purposes, including materials testing, radiosotope production, training and nuclear physics studies. The effort spent by the Agency in safeguarding these reactors is dependant upon the thermal power of the reactor and on the quantity and type of nuclear material present. On some research reactors, the Agency devotes more inspection effort than on a large power reactor. On others, very little effort is reguired. Safeguards that are applied are done so according to Agency State agreements and consist of a combiination of nuclear material accounting and containment and surveillance. In this paper, the safeguards activities performed by the State and by the Agency will be reviewed for a large (≤50MWt) and for a small (≥ 1 MWt) reactor according to the most common type agreement. (author)

  11. Engineering change management during replacement and up-gradation of reactor systems of Dhruva

    International Nuclear Information System (INIS)

    Dhruva, 100 MWth, tank type research reactor has been operating since 1985 at Mumbai, India with maximum thermal neutron flux of 1.8 Χ 1014 n/cm2/sec. Natural metallic uranium is used as fuel and heavy water as coolant, moderator and reflector. The reactor has been well utilized for over 27 years with high availability and excellent safety record. Initial design of SSCs of Dhruva was carried out with stringent specifications and strict quality control to assure safe and reliable operation for the entire service life. During operational phase, a well formulated in service inspection and surveillance programme has been put in place to provide timely feedback on the healthiness of systems, structures and components (SSC) important to safety. Based on systematic inservice inspection (ISI) programme, insights from regular surveillance programme and structured system performance monitoring and review, certain incipient degradations in the reactor systems could be noted in time and replacement of certain systems/components, like secondary coolant heat exchangers, certain portion of emergency cooling water pipelines have been undertaken. Technological obsolescence has necessitated some of the replacement/up-gradation actions for power supply and controls and instrumentation systems of the reactor. Replacement of 150 kVA class II MA set with 250 kVA MA set, up-gradation of 20 kVA class II inverters, complete up-gradation of control room and fuelling machine instrumentation was taken up, without significantly affecting the reactor availability. While implementing these changes in the reactor systems, although the initial and the final system configuration were well analyzed and well established, during the transition phase adequate care had to be exercised in order to ensure that the system configuration does not lead to an unsafe state, taking into account various possible failures in the system under commissioning. Further, in order to ensure this requirement, the system

  12. Light water reactor safety research

    International Nuclear Information System (INIS)

    As the technology of light water reactors (LWR) was being commercialized, the German Federal Government funded the reactor safety research program, which was conducted by national research centers, universities, and industry, and which led to the establishment, in early 1972, of the Nuclear Safety Project in Karlsruhe. In the seventies, the PNS project mainly studied the loss-of-coolant accident. Numerous experiments were run and computer codes developed for this purpose. In the eighties, the Karlsruhe Nuclear Research Center contributed to the German Risk Study, investigating especially core meltdown accidents under the impact of the events at Three Mile Island-2 and Chernobyl-4. Safety research in the nineties is concentrated on the requirements of future reactor generations, such as the European Pressurized Water Reactor (EPR) or potential approaches which, at the present time, are discernible only as tentative theoretical designs. (orig.)

  13. Research funding for telemedicine: an Australian perspective.

    Science.gov (United States)

    Barnett, Adrian G; Campbell, Megan J; Burns, Clare L

    2016-04-01

    Winning research funding is one of the most difficult challenges faced by researchers, especially with falling success rates and shrinking budgets. Telemedicine researchers can find it especially hard to win funding as they are often researching small changes to the health system that whilst important for patient care are often not as competitive as proposals that promise to cure diseases. In a climate of both tight health funding and tight research funding, telemedicine researchers should emphasise the potential for their research to add value and lower costs in order to increase their chances of winning funding. PMID:26116853

  14. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  15. Strategic Capacity Building for Australian Educational Research: Creating Spaces for Action

    Science.gov (United States)

    Goodyear, Peter

    2013-01-01

    This paper provides some background information about the Strategic Capacity Building for Australian Educational Research initiative: a joint program of work sponsored by the Australian Association for Research in Education and the Australian Council of Deans of Education. In addition, it offers some broader analysis of the contexts within which…

  16. Neutron scattering science at the Australian Nuclear Science and Technology Organisation (ANSTO)

    International Nuclear Information System (INIS)

    Neutron scattering science at ANSTO is integrated into a number of fields in the Australian scientific and industrial research communities. The unique properties of the neutron are being used to investigate problems in chemistry, materials science, physics, engineering and biology. The reactor HIFAR at the Australian Nuclear Science and Technology Organisation research laboratories is the only neutron source in Australia suitable for neutron scattering science. A suite of instruments provides a range of opportunities for the neutron scattering community that extends throughout universities, government and industrial research laboratories. Plans to replace the present research reactor with a modern multi-purpose research reactor are well advanced. The experimental and analysis equipment associated with a modern research reactor will permit the establishment of a national centre for world class neutron science research focussed on the structure and functioning of materials, industrial irradiations and analyses in support of Australian manufacturing, minerals, petrochemical, pharmaceuticals and information science industries. A brief overview will be presented of all the instruments presently available at ANSTO with emphasis on the SANS instrument. This will be followed by a description of the replacement research reactor and its instruments. (author)

  17. Neutron scattering science at the Australian Nuclear Science and Technology Organisation (ANSTO)

    Energy Technology Data Exchange (ETDEWEB)

    Knott, Robert [Australian Nuclear Science and Technology Organisation (Australia)

    2000-10-01

    Neutron scattering science at ANSTO is integrated into a number of fields in the Australian scientific and industrial research communities. The unique properties of the neutron are being used to investigate problems in chemistry, materials science, physics, engineering and biology. The reactor HIFAR at the Australian Nuclear Science and Technology Organisation research laboratories is the only neutron source in Australia suitable for neutron scattering science. A suite of instruments provides a range of opportunities for the neutron scattering community that extends throughout universities, government and industrial research laboratories. Plans to replace the present research reactor with a modern multi-purpose research reactor are well advanced. The experimental and analysis equipment associated with a modern research reactor will permit the establishment of a national centre for world class neutron science research focussed on the structure and functioning of materials, industrial irradiations and analyses in support of Australian manufacturing, minerals, petrochemical, pharmaceuticals and information science industries. A brief overview will be presented of all the instruments presently available at ANSTO with emphasis on the SANS instrument. This will be followed by a description of the replacement research reactor and its instruments. (author)

  18. Replacement energy, capacity, and reliability costs for permanent nuclear reactor shutdowns

    Energy Technology Data Exchange (ETDEWEB)

    VanKuiken, J.C., Buehring, W.A.; Hamilton, S.; Kavicky, J.A.; Cavallo, J.D.; Veselka, T.D.; Willing, D.L. [Argonne National Lab., IL (United States)

    1993-10-01

    Average replacement power costs are estimated for potential permanent shutdowns of nuclear electricity-generating units. Replacement power costs are considered to include replacement energy, capacity, and reliability cost components. These estimates were developed to assist the US Nuclear Regulatory Commission in evaluating regulatory issues that potentially affect changes in serious reactor accident frequencies. Cost estimates were derived from long-term production-cost and capacity expansion simulations of pooled utility-system operations. Factors that affect replacement power cost, such as load growth, replacement sources of generation, and capital costs for replacement capacity, were treated in the analysis. Costs are presented for a representative reactor and for selected subcategories of reactors, based on estimates for 112 individual reactors.

  19. Application of Shuttle Remote Manipulator System technology to the replacement of fuel channels in the Pickering CANDU reactor

    International Nuclear Information System (INIS)

    Spar Aerospace Limited of Toronto was the prime contractor to the National Research Council of Canada for the design and development of the Shuttle Remote Manipulator (SRMS). Spar is presently under contract to Ontario Hydro to design and build a Remote Manipulation Control System to replace the fuel channels in the Pickering A Nuclear Generating Station. The equipment may be used to replace the fuel channels in six other early generation CANDU reactors

  20. Determination of research reactor safety parameters by reactor calculations

    International Nuclear Information System (INIS)

    Main research reactor safety parameters such as power density peaking factors, shutdown margin and temperature reactivity coefficients are treated. Reactor physics explanation of the parameters is given together with their application in safety evaluation performed as part of research reactor operation. Reactor calculations are presented as a method for their determination assuming use of widely available computer codes. (author)

  1. Modelling the Research Output of Australian Universities by Discipline

    OpenAIRE

    Valadkhani, Abbas; Ville, Simon

    2006-01-01

    This paper develops and estimates a cross-sectional model for forecasting research output across the Australian university system. It builds upon an existing literature that focuses either on institutional comparisons or studies of specific subjects, by providing discipline-specific results across all of the ten major disciplinary areas as defined by Australia’s Department of Education, Science and Training (DEST). The model draws upon four discipline-specific explanatory variables; staff siz...

  2. Australia's new high performance research reactor

    International Nuclear Information System (INIS)

    A contract for the design and construction of the Replacement Research Reactor was signed in July 2000 between ANSTO and INVAP from Argentina. Since then the detailed design has been completed, a construction authorization has been obtained, and construction has commenced. The reactor design embodies modern safety thinking together with innovative solutions to ensure a highly safe and reliable plant. Also significant effort has been placed on providing the facility with diverse and ample facilities to maximize its use for irradiating material for radioisotope production as well as providing high neutron fluxes for neutron beam research. The project management organization and planing is commensurate with the complexity of the project and the number of players involved. (author)

  3. A new fuel for research reactors

    International Nuclear Information System (INIS)

    The Replacement Research Reactor (RRR) to be constructed at Lucas Heights will use fuel containing low enriched uranium (LEU), 235U, whereas its predecessor HIFAR operates with fuel fabricated from high-enriched uranium (HEU). The fuel will be based on uranium silicide (U3Si2) with a density of 4.8 g U/cm3. This fuel has been qualified and in use in 20 research reactors worldwide for over 12 years A brief description is given of the metallurgy, behaviour under irradiation, and fabrication methods, all of which are well-understood Progress on development of new, higher density LEU fuel based on uranium molybdenum alloys is also described and the implications for the RRR discussed briefly

  4. Neutrons down-under: Australia's research reactor review

    International Nuclear Information System (INIS)

    Australian research reactor review commenced in September 1992, the Review had the following Terms of Reference: Whether, on review of the benefits and costs for scientific, commercial, industrial and national interest reasons, Australia has a need for a new reactor; a review of the present reactor, HIFAR, to include: an assessment of national and commercial benefits and costs of operations, its likely remaining useful life and its eventual closure and decommissioning; if Australia has a need for a new nuclear research reactor, the Review will consider: possible locations for a new reactor, its environmental impact at alternative locations, recommend a preferred location, and evaluate matters associated with regulation of the facility and organisational arrangements for reactor-based research. From the Review findings the following recommendations were stated: keep HIFAR going; commission a PRA to ascertain HIFAR's remaining life and refurbishment possibilities; identify and establish a HLW repository; accept that neither HIFAR nor a new reactor can be completely commercial; any decision on a new neutron source must rest primarily on benefits to science and Australia's national interest; make a decision on a new neutron source in about five years' time (1998). Design Proposals for a New Reactor are specified

  5. Utilization of nuclear research reactors

    International Nuclear Information System (INIS)

    Full text: Report on an IAEA interregional training course, Budapest, Hungary, 5-30 November 1979. The course was attended by 19 participants from 16 Member States. Among the 28 training courses which the International Atomic Energy Agency organized within its 1979 programme of technical assistance was the Interregional Training Course on the Utilization of Nuclear Research Reactors. This course was held at the Nuclear Training Reactor (a low-power pool-type reactor) of the Technical University, Budapest, Hungary, from 5 to 30 November 1979 and it was complemented by a one-week Study Tour to the Nuclear Research Centre in Rossendorf near Dresden, German Democratic Republic. The training course was very successful, with 19 participants attending from 16 Member States - Bangladesh, Bolivia, Czechoslovakia, Ecuador, Egypt, India, Iraq, Korean Democratic People's Republic, Morocco, Peru, Philippines, Spain, Thailand, Turkey, Vietnam and Yugoslavia. Selected invited lecturers were recruited from the USA and Finland, as well as local scientists from Hungarian institutions. During the past two decades or so, many research reactors have been put into operation around the world, and the demand for well qualified personnel to run and fully utilize these facilities has increased accordingly. Several developing countries have already acquired small- and medium-size research reactors mainly for isotope production, research in various fields, and training, while others are presently at different stages of planning and installation. Through different sources of information, such as requests to the IAEA for fellowship awards and experts, it became apparent that many research reactors and their associated facilities are not being utilized to their full potential in many of the developing countries. One reason for this is the lack of a sufficient number of trained professionals who are well acquainted with all the capabilities that a research reactor can offer, both in research and

  6. Research reactor education and training

    International Nuclear Information System (INIS)

    CORYS T.E.S.S. and TECHNICATOME present in this document some of the questions that can be rightfully raised concerning education and training of nuclear facilities' staffs. At first, some answers illustrate the tackled generic topics: importance of training, building of a training program, usable tools for training purposes. Afterwards, this paper deals more specifically with research reactors as an actual training tool. The pedagogical advantages they can bring are illustrated through an example consisting in the description of the AZUR facility training capabilities followed by the detailed experiences CORYS T.E.S.S. and TECHNICATOME have both gathered and keeps on gaining using research reactors for training means. The experience shows that this incomparable training material is not necessarily reserved to huge companies or organisations' numerous personnel. It offers enough flexibility to be adapted to the specific needs of a thinner audience. Thus research reactor staffs can also take advantages of this training method. (author)

  7. Research reactor modernization and refurbishment

    International Nuclear Information System (INIS)

    Many recent, high profile research reactor unplanned shutdowns can be directly linked to different challenges which have evolved over time. The concept of ageing management is certainly nothing new to nuclear facilities, however, these events are highlighting the direct impact unplanned shutdowns at research reactors have on various stakeholders who depend on research reactor goods and services. Provided the demand for these goods and services remains strong, large capital projects are anticipated to continue in order to sustain future operation of many research reactors. It is within this context that the IAEA organized a Technical Workshop to launch a broader Agency activity on research reactor modernization and refurbishment (M and R). The workshop was hosted by the operating organization of the HOR Research Reactor in Delft, the Netherlands, in October 2006. Forty participants from twenty-three countries participated in the meeting: with representation from Africa, Asia Pacific, Eastern Europe, North America, South America and Western Europe. The specific objectives of this workshop were to present facility reports on completed, existing and planned M and R projects, including the project objectives, scope and main characteristics; and to specifically report on: - the project impact (planned or actual) on the primary and key supporting motivation for the M and R project; - the project impact (planned or actual) on the design basis, safety, and/or regulatory-related reports; - the project impact (planned or actual) on facility utilization; - significant lessons learned during or following the completion of M and R work. Contributions from this workshop were reviewed by experts during a consultancy meeting held in Vienna in December 2007. The experts selected final contributions for inclusion in this report. Requests were also distributed to some authors for additional detail as well as new authors for known projects not submitted during the initial 2006 workshop

  8. Socially responsible genetic research with descendants of the First Australians

    Directory of Open Access Journals (Sweden)

    van Holst Pellekaan Sheila M

    2012-11-01

    Full Text Available Abstract Aboriginal Australians, one of the world’s indigenous peoples now outnumbered through colonization, are the most under-represented in genetic research because they feel that the benefits do not outweigh the social cost of involvement. Descendants of the First Australians have survived a period of European occupation during which time they were dispossessed of land, language and cultural identity resulting in inequities in health, education, and employment opportunities. Compared to Maori and Native American peoples, the ability to form organizations that help to control their affairs is very recent. The desire to control is understandably strong yet the ‘gate-keeping’ role of some organizations risks shifting the control away from smaller communities and has become increasingly politicized. In the past, research practices by Western scientists were poorly presented and have resulted in resistance to proposals that are perceived to have no beneficial outcomes for participants. In this age of advanced technological expertise in genetics, benefits to all humanity are clear to those carrying out research projects, yet not always to those being asked to participate, presenting extra challenges. Excellent guidelines for ethical conduct in research are available to assist researchers, prospective participants, and ethics committees or review boards that approve and monitor procedures. The essence of these guidelines are that research should be carried out with a spirit of integrity, respect, reciprocity, parity, recognition of survival and protection of social and cultural values, a need for control and shared responsibility. Specific Aboriginal organizations, with which researchers need to work to negotiate partnerships, vary within and between Australian states and will always expect Aboriginal personnel to be involved. People experienced in the consultation process are necessary as part of a team. By working patiently through lengthy

  9. Upgrading the NRU research reactor

    International Nuclear Information System (INIS)

    After a nearly two-year long detailed review, AECL Research decided that its NRU research reactor will complete its mission around the turn of the century. The company's original intentions for major refurbishment have been revised and upgrading work will now mainly comprise add-ons to existing systems - so that research projects and isotope production schedules can be met - and procedure modifications to ensure continued safe operation. (Author)

  10. Cross-sectional analysis of association between socioeconomic status and utilization of primary total hip joint replacements 2006–7: Australian Orthopaedic Association National Joint Replacement Registry

    Directory of Open Access Journals (Sweden)

    Brennan Sharon L

    2012-04-01

    Full Text Available Abstract Background The utilization of total hip replacement (THR surgery is rapidly increasing, however few data examine whether these procedures are associated with socioeconomic status (SES within Australia. This study examined primary THR across SES for both genders for the Barwon Statistical Division (BSD of Victoria, Australia. Methods Using the Australian Orthopaedic Association National Joint Replacement Registry data for 2006–7, primary THR with a diagnosis of osteoarthritis (OA among residents of the BSD was ascertained. The Index of Relative Socioeconomic Disadvantage was used to measure SES; determined by matching residential addresses with Australian Bureau of Statistics census data. The data were categorised into quintiles; quintile 1 indicating the most disadvantaged. Age- and sex-specific rates of primary THR per 1,000 person years were reported for 10-year age bands using the total population at risk. Results Females accounted for 46.9% of the 642 primary THR performed during 2006–7. THR utilization per 1,000 person years was 1.9 for males and 1.5 for females. The highest utilization of primary THR was observed in those aged 70–79 years (males 6.1, and females 5.4 per 1,000 person years. Overall, the U-shaped pattern of THR across SES gave the appearance of bimodality for both males and females, whereby rates were greater for both the most disadvantaged and least disadvantaged groups. Conclusions Further work on a larger scale is required to determine whether relationships between SES and THR utilization for the diagnosis of OA is attributable to lifestyle factors related to SES, or alternatively reflects geographic and health system biases. Identifying contributing factors associated with SES may enhance resource planning and enable more effective and focussed preventive strategies for hip OA.

  11. A new high performance research reactor

    International Nuclear Information System (INIS)

    A contract for the design, construction and commissioning of the Replacement Research Reactor was signed in July 2000 between Australia authorities and INVAP from Argentina. Since then the detailed design has been completed, an application for a construction license was made in May 2001 and the construction authorisation was issued on 4th April 2002. This paper explains the safety philosophy embedded into the design together with the approach taken for main elements of the design and their relation to the proposed applications of the reactor. Also information is provided on the suit of neutron beam facilities and irradiation facilities being constructed. Finally it is presented an outline of the project management organisation, project planing and schedule. (author)

  12. Research reactors: design, safety requirements and applications

    International Nuclear Information System (INIS)

    There are two types of reactors: research reactors or power reactors. The difference between the research reactor and energy reactor is that the research reactor has working temperature and fuel less than the power reactor. The research reactors cooling uses light or heavy water and also research reactors need reflector of graphite or beryllium to reduce the loss of neutrons from the reactor core. Research reactors are used for research training as well as testing of materials and the production of radioisotopes for medical uses and for industrial application. The difference is also that the research reactor smaller in terms of capacity than that of power plant. Research reactors produce radioactive isotopes are not used for energy production, the power plant generates electrical energy. In the world there are more than 284 reactor research in 56 countries, operates as source of neutron for scientific research. Among the incidents related to nuclear reactors leak radiation partial reactor which took place in three mile island nuclear near pennsylvania in 1979, due to result of the loss of control of the fission reaction, which led to the explosion emitting hug amounts of radiation. However, there was control of radiation inside the building, and so no occurred then, another accident that lead to radiation leakage similar in nuclear power plant Chernobyl in Russia in 1986, has led to deaths of 4000 people and exposing hundreds of thousands to radiation, and can continue to be effect of harmful radiation to affect future generations. (author)

  13. Impact in Vocational Education and Training Research: The Case of the Australian VET Research Consortium

    Science.gov (United States)

    Harris, Roger; Clayton, Berwyn

    2010-01-01

    "Impact" is a notion that is not very well understood in research. Within Australian higher education, it has been bandied about within such frameworks as the "Research Quality Framework" ("RQF") and Excellence in Research for Australia (ERA). Vocational education and training (VET) research is not immune from these movements, and increasingly,…

  14. Fast reactor research in Switzerland

    International Nuclear Information System (INIS)

    The small Swiss research program on fast reactors serves to further understanding of the role of LMFR for energy production and to convert radioactive waste to more environmentally benign forms. These activities are on the one hand the contribution to the comparison of advanced nuclear systems and bring on the other to our physical and engineers understanding. (author)

  15. 2012 review of French research reactors

    International Nuclear Information System (INIS)

    Proposed by the French Reactor Operators' Club (CER), the meeting and discussion forum for operators of French research reactors, this report first gives a brief presentation of these reactors and of their scope of application, and a summary of highlights in 2012 for each of them. Then, it proposes more detailed presentations and reviews of characteristics, activities, highlights, objectives and results for the different types of reactors: neutron beam reactors (Orphee, High flux reactor-Laue-Langevin Institute or HFR-ILL), technological irradiation reactors (Osiris and Phenix), training reactors (Isis and Azur), reactors for safety research purposes (Cabri and Phebus), reactors for neutronic studies (Caliban, Prospero, Eole, Minerve and Masurca), and new research reactors (the RES facility and the Jules Horowitz reactor or JHR)

  16. Rationalization and future planning for AECL's research reactor capability

    International Nuclear Information System (INIS)

    AECL's research reactor capability has played a crucial role in the development of Canada's nuclear program. All essential concepts for the CANDU reactors were developed and tested in the NRX and NRU reactors, and in parallel, important contributions to basic physics were made. The technical feasibility of advanced fuel cycles and of the organic-cooled option for CANDU reactors were also demonstrated in the two reactors and the WR-1 reactor. In addition, an important and growing radio-isotope production industry was established and marketed on a world-wide basis. In 1984, however, it was recognized that a review and rationalization of the research reactor capability was required. The commercial success of the CANDU reactor system had reduced the scope and size of the required development program. Limited research and development funding and competition from other research facilities and programs, required that the scope be reduced to a support basis essential to maintain strategic capability. Currently, AECL, is part-way through this rationalization program and completion should be attained during 1992/93 when the MAPLE reactor is operational and decisions on NRX decommissioning will be made. A companion paper describes some of the unique operational and maintenance problems which have resulted from this program and the solutions which have been developed. Future planning must recognize the age of the NRU reactor (currently 32 years) and the need to plan for eventual replacement. Strategy is being developed and supporting studies include a full technical assessment of the NRU reactor and the required age-related upgrading program, evaluation of the performance characteristics and costs of potential future replacement reactors, particularly the advanced MAPLE concept, and opportunities for international co-operation in developing mutually supportive research programs

  17. Fuels for Canadian research reactors

    International Nuclear Information System (INIS)

    This paper includes some statements and remarks concerning the uranium silicide fuels for which there is significant fabrication in AECL, irradiation and defect performance experience; description of two Canadian high flux research reactors which use high enrichment uranium (HEU) and the fuels currently used in these reactors; limited fabrication work done on Al-U alloys to uranium contents as high as 40 wt%. The latter concerns work aimed at AECL fast neutron program. This experience in general terms is applied to the NRX and NRU designs of fuel

  18. Current activities at the MIT Research Reactor

    International Nuclear Information System (INIS)

    The MIT Research Reactor (MITR) is a MW nuclear research reactor that is owned and operated by the Massachusetts Institute of Technology to further its educational and research goals at both the undergraduate and graduate level. The reactor first achieved criticality in 1958. It was largely rebuilt in 1973/1974 by MIT staff and students, and its current license expires in August 1999. The current facility, which is designated as the MITR-H, uses a compact core with finned, aluminum-clad, plate-type fuel that is cooled and moderated by light water and reflected by heavy water. The reactor core can hold twenty-seven fuel elements. However, the normal configuration is twenty-four elements. A maximum of four fuel elements can be replaced with in-core experimental facilities. A unique feature of the MITR-II's design is that fixed absorber plates can be inserted in the upper half of the core. These cause the flux to peak in the lower half which benefits experimenters and also facilitates a fuel strategy that involves inversion of fuel elements midway through their life cycle. The MITR-II currently operates continuously for four weeks followed by shutdown of a few days for maintenance. This paper provides an overview of current activities at the MITR including preparations for re-licensing. The status of an on-going Phase-I clinical trial of boron neutron capture therapy for both glioblastoma multiforme and metastatic melanoma is described as well as the design of a fission converter facility for BNCT. Environmental research using neutron activation analysis is summarized as well as in-pile research focussed on LWR water chemistry and structural materials. (author)

  19. Towards meeting the research needs of Australian cancer consumers

    Directory of Open Access Journals (Sweden)

    Saunders Carla

    2012-12-01

    Full Text Available Abstract Background There is a growing amount of literature to support the view that active involvement in research by consumers, especially informed and networked consumers, benefits the quality and direction of research itself, the research process and, most importantly, people affected by cancer. Our exploratory project focuses on identifying their priorities and developing a process to assess the research needs of Australian cancer consumers which may be useful beyond the cancer scenario. Methods This project was consumer initiated, developed and implemented, with the assistance of a leading Australian cancer consumer advocacy group, Cancer Voices NSW (CVN. Such direct involvement is unusual and ensures that the priorities identified, and the process itself, are not influenced by other interests, regardless how well-intentioned they may be. The processes established, and data collection via a workshop, followed by a questionnaire to confirm and prioritise findings, and comparison with a similar UK exercise, are detailed in this paper. Results Needs across five topic areas reflecting cancer control domains (prevention and risk; screening and diagnosis; treatment; survivorship; and end of life were identified. Cancer consumers high priority research needs were found to be: earlier diagnosis of metastatic cancers; the extent of use of best practice palliative care guidelines; identifying barriers to cancer risk behaviour change; and environmental, nutrition and lifestyle risk factors for people with cancer. A process for identifying consumers’ research priorities was developed and applied; this may be useful for further investigation in this under-studied area. Conclusion The findings provide a model for developing a consumer derived research agenda in Australia which can be used to inform the strategic direction of cancer research. Consumers have been seeking a workable method to achieve this and have worked in collaboration with a major

  20. Research for enhancing reactor safety

    International Nuclear Information System (INIS)

    Recent research for enhanced reactor safety covers extensive and numerous experiments and computed modelling activities designed to verify and to improve existing design requirements. The lectures presented at the meeting report GRS research results and the current status of reactor safety research in France. The GRS experts present results concerning expert systems and their perspectives in safety engineering, large-scale experiments and their significance in the development and verification of computer codes for thermohydraulic modelling of safety-related incidents, the advanced system code ATHLET for analysis of thermohydraulic processes of incidents, the analysis simulator which is a tool for fast evaluation of accident management measures, and investigations into event sequences and the required preventive emergency measures within the German Risk Study. (DG)

  1. The Research of Artificial Cervical Disc Replacement

    Institute of Scientific and Technical Information of China (English)

    Zhao Zhua; Qiang Shenb

    2008-01-01

    Cervical arthroplasty after anterior decompression with insertion of a prosthetic total disc replacement has been suggested as an alternate to anterior cervical fusion. It develops quickly during recent years. Currently there are several cervical arthroplasty devices. Each device varies in terms of materials, range of motion and constraint. Early studies suggest that in the short term, the complication rate and efficacy is no worse than fusion surgery. Long-term results have not yet been reported. This review examines the current prostheses as well as discussing issues regarding indications and technique. It is hoped that an improvement of cervical arthroplasty occurs in terms of materials and design as spinal surgeons enter a new dines of the management of cervical spine disease.

  2. Research reactor's role in Korea

    International Nuclear Information System (INIS)

    After a TRIGA MARK-II was constructed in 1962, new research activity of a general nature, utilizing neutrons, prevailed in Korea. Radioisotopes produced from the MARK-II played a good role in the 1960's in educating people as to what could be achieved by a neutron source. Because the research reactor had implanted neutron science in the country, another TRIGA MARK-III had to be constructed within 10 years after importing the first reactor, due to increased neutron demand from the nuclear community. With the sudden growth of nuclear power, however, the emphasis of research changed. For a while research activities were almost all oriented to nuclear power plant technology. However, the specifics of nuclear power plant technology created a need for a more highly capable research reactor like HANARO 30MWt. HANARO will perform well with irradiation testing and other nuclear programs in the future, including: production of key radioisotopes, doping of silicon by transmutation, neutron activation analysis, neutron beam experiments, cold neutron source. 3 tabs., 2 figs

  3. Chronology of the beryllium replacement shutdown at the High Flux Isotope Reactor (HFIR), 1983

    International Nuclear Information System (INIS)

    In addition to the permanent beryllium reflector, several other components were replaced. The outer shroud and lower tracks were replaced. The new control rod access plugs and the upper tracks were installed. Replacement of collimator tubes for HB-1 and -2 are tentatively slated for the next permanent beryllium changeout. Inspection of the reactor vessel, the vessel-to-nozzle welds, core support structure, and vessel internal cladding showed them to be in acceptable condition. The highest, accumulative radiation doses received by Reactor Operations personnel during the shutdown, in mrem, were 665, 606, and 560; the highest for P and E personnel were 520, 505, and 475

  4. Neutronics design of upgraded JRR-3 research reactor

    International Nuclear Information System (INIS)

    The research reactor JRR-3 is currently planned to be upgraded by replacing the core and related cooling system. The proposed reactor is a water-moderated and -cooled pool type of 20 MW thermal output. The neutronics calculation was carried out on the core using 20% enriched U.Alsub(x) fuel. The results show that the core performances, such as reactivity, neutron flux, and burnup, are sufficient for beam experiments, material testing, and isotope production. (author)

  5. The research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    The TRIGA Mark II reactor at the Institut fuer Kernchemie became first critical on August 3rd, 1965. It can be operated in the steady state mode with a maximum power of 100 kWth and in the pulse mode with a peak power of 250 MWth. A survey of the research programmes performed at the TRIGA Mainz is given covering applications in basic research as well as applied science in nuclear chemistry and nuclear physics. Furthermore, the reactor is used for neutron activation analysis and for education and training of scientists, teachers, students and technical personal. Important projects for the future of the TRIGA Mainz are the UCN (ultra cold neutrons) experiment, fast chemical separation, medical applications and the use of the NAA as well as the use of the reactor facility for the training of students in the fields of nuclear chemistry, nuclear physics and radiation protection. Taking into account the past and future operation schedule and the typically low burn-up of TRIGA fuel elements (∝4 g U-235/a), the reactor can be operated for at least the next decade taking into account the fresh fuel elements on stock and without changing spent fuels. (orig.)

  6. Cracking the Code: Assessing Institutional Compliance with the Australian Code for the Responsible Conduct of Research

    Science.gov (United States)

    Morris, Suzanne E.

    2010-01-01

    This paper provides a review of institutional authorship policies as required by the "Australian Code for the Responsible Conduct of Research" (the "Code") (National Health and Medical Research Council (NHMRC), the Australian Research Council (ARC) & Universities Australia (UA) 2007), and assesses them for Code compliance. Institutional authorship…

  7. Relocation of a Research Reactor

    International Nuclear Information System (INIS)

    The research reactor RA-8 is placed in Pilcaniyeu Technological Centre (PTC) in the province of Rio Negro, approximately 70 km east from San Carlos de Bariloche city. The first time the reactor went critical was in June 1997 and it is out of operation since March 1999. Due to the intention to relocate the reactor in Bariloche Atomic Centre (BAC) a study has been done in order to assess the technical and economical feasibility. The scope of this study covers the disassembly and transport from PTC to BAC. Relocation of the reactor will reduce costs, time and difficulties in the transport of personnel (operators, researcher, and students) to Pilcaniyeu allowing the performance of nuclear research as well as academic application. The RA-8 is basically a critical facility of enriched uranium with light water as moderator. It is a pool type reactor with low thermal power, maximum 100 W and nominal 10 W. The principal assembly and the associated systems are placed in the reactor hall: consisting of a core, tanks, block, nuclear and conventional instrumentation, moderator system and the neutron source system. Also there is a control room with computers for monitoring together with the safety and control systems. The core is inside two stainless steel concentric tanks communicated with each other that contain water during the operation. The technical feasibility consists in: radiological characterization of the facility, visual inspection of the systems, structures and components, dismantling engineering, mass estimation for disassembly, packing, transport and storage. Economical feasibility has been done in order to evaluate time and costs necessaries for the disassembly and transport from Pilcaniyeu to Bariloche. Regulatory aspects that must be fulfilled were considered in this study. Nothing detectable was found in water samples from pipes of the pumps' well. The systems, structures and components of the RA-8 present in general a good condition of preservation that would

  8. Research Reactors Types and Utilization

    International Nuclear Information System (INIS)

    A nuclear reactor, in gross terms, is a device in which nuclear chain reactions are initiated, controlled, and sustained at a steady rate. The nuclei of fuel heavy atoms (mostly 235U or 239Pu), when struck by a slow neutron, may split into two or more smaller nuclei as fission products,releasing energy and neutrons in a process called nuclear fission. These newly-born fast neutrons then undergo several successive collisions with relatively low atomic mass material, the moderator, to become thermalized or slow. Normal water, heavy water, graphite and beryllium are typical moderators. These neutrons then trigger further fissions, and so on. When this nuclear chain reaction is controlled, the energy released can be used to heat water, produce steam and drive a turbine that generates electricity. The fission process, and hence the energy release, are controlled by the insertion (or extraction) of control rods through the reactor. These rods are strongly neutron absorbents, and thus only enough neutrons to sustain the chain reaction are left in the core. The energy released, mostly in the form of heat, should be continuously removed, to protect the core from damage. The most significant use of nuclear reactors is as an energy source for the generation of electrical power and for power in some military ships. This is usually accomplished by methods that involve using heat from the nuclear reaction to power steam turbines. Research reactors are used for radioisotope production and for beam experiments with free neutrons. Historically, the first use of nuclear reactors was the production of weapons grade plutonium for nuclear weapons. Currently all commercial nuclear reactors are based on nuclear fission. Fusion power is an experimental technology based on nuclear fusion instead of fission.

  9. Fuels for Canadian research reactors

    International Nuclear Information System (INIS)

    For a period of about 10 years AECL had a significant program looking into the possibility of developing U3Si as a high density replacement for the UO2 pellet fuel in use in CANDU power reactors. The element design consisted of a Zircaloy-clad U3Si rod containing suitable voidage to accommodate swelling. We found that the binary U3Si could not meet the defect criterion for our power reactors, i.e., one month in 300 degree C water with a defect in the sheath and no significant damage to the element. Since U3Si could not do the job, a new corrosion resistant ternary U-Si-Al alloy was developed and patented. Fuel elements containing this alloy came close to meeting the defect criterion and showed slightly better irradiation stability than U3Si. Shortly after this, the program was terminated for other reasons. We have made much of this experience available to the Low Enrichment Fuel Development Program and will be glad to supply further data to assist this program

  10. Accident analysis in research reactors

    International Nuclear Information System (INIS)

    With the sustained development in computer technology, the possibilities of code capabilities have been enlarged substantially. Consequently, advanced safety evaluations and design optimizations that were not possible few years ago can now be performed. The challenge today is to revisit the safety features of the existing nuclear plants and particularly research reactors in order to verify that the safety requirements are still met and - when necessary - to introduce some amendments not only to meet the new requirements but also to introduce new equipment from recent development of new technologies. The purpose of the present paper is to provide an overview of the accident analysis technology applied to the research reactor, with emphasis given to the capabilities of computational tools. (author)

  11. Licensing procedures and safety criteria for research reactors in France

    International Nuclear Information System (INIS)

    From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon

  12. Monitoring and reviewing research reactor safety in Australia

    International Nuclear Information System (INIS)

    Th research reactors operated by the Australian Nuclear Science and Technology Organization (ANSTO) comprise the 10 MW reactor HIFAR and the 100 kW reactor Moata. Although there are no power reactors in Australia the problems and issues of public concern which arise in the operation of research reactors are similar to those of power reactors although on a smaller scale. The need for independent safety surveillance has been recognized by the Australian Government and the ANSTO Act, 1987, required the Board of ANSTO to establish a Nuclear Safety Bureau (NSB) with responsibility to the Minister for monitoring and reviewing the safety of nuclear plant operated by ANSTO. The Executive Director of ANSTO operates HIFAR subject to compliance with requirements and arrangements contained in a formal Authorization from the Board of ANSTO. A Ministerial Direction to the Board of ANSTO requires the NSB to report to him, on a quarterly basis, matters relating to its functions of monitoring and reviewing the safety of ANSTO's nuclear plant. Experience has shown that the Authorization provides a suitable framework for the operational requirements and arrangements to be organised in a disciplined and effective manner, and also provides a basis for audits by the NSB by which compliance with the Board's safety requirements are monitored. Examples of the way in which the NSB undertakes its monitoring and reviewing role are given. Moata, which has a much lower operating power level and fission product inventory than HIFAR, has not been subject to a formal Authorization to date but one is under preparation

  13. Reactor safety research in Sweden

    International Nuclear Information System (INIS)

    Objectives, means and results of Swedish light water reactor safety research during the 1970s are reviewed. The expenditure is about 40 Million Swkr per year excluding industry. Large efforts have been devoted to experimental studies of loss of coolant accidents. Large scale containment response tests for simulated pipe breaks were carried out at the Marviken facility. At Studsvik a method for testing fuel during fast power changes has been developed. Stress corrosion, crack growth and the effect of irradiation on the strength ductility of Zircaloy tube was studied. A method for determining the fracture toughness of pressure vessel steel was developed and it was shown that the fracture toughness was lower than earlier assumed. The release of fission products to reactor water was studied and so was the release, transport and removal of airborne radioactive matter for Swedish BWRs and PWRs. Test methods for iodine filter systems were developed. A system for continuous monitoring of radioactive noble gas stack release was developed for the Ringhals plant. Attention was drawn to the importance of the human factor for reactor safety. Probabilistic methods for risk analysis were applied to the Barsebaeck 2 and Forsmark 3 boiling water reactors. Procedures and working conditions for operator personnel were investigated. (GBn)

  14. Research reactors in Austria - Present situation

    International Nuclear Information System (INIS)

    In the past decades Austria operated three research reactors, the 10 MW ASTRA reactor at Seibersdorf, the 250 kW TRIGA reactor at the Atominstitut and the 1 kW Argonaut reactor at the Technical University in Graz. Since the shut down of the ASTRA on July 31th, 1999 and its immediate decommissioning reactor and the shut down of the Argonaut reactor in Graz on August 31st, 2004 only one reactor remains operational for keeping nuclear competence in Austria which is the 250 kW TRIGA Mark II reactor. (author)

  15. Best Safety Practices for the Operation of Research Reactors

    International Nuclear Information System (INIS)

    A survey on administrative, organisational and technical aspects for the safe and efficient operation of a 250 kW TRIGA Mark II research reactor is given. The replacement of the I and C system is discussed, maintenance procedures are presented and the fuel management is described. (author)

  16. Current status of the world's research reactors

    International Nuclear Information System (INIS)

    Data from the IAEA's Research Reactor Database (RRDB) provides information with respect to the status of the world's research reactors. Some summary data are given. Recent initiatives by the IAEA regarding communications and information flow with respect to research reactors are discussed. Future plans and perspectives are also introduced. (author)

  17. Research nuclear reactor operation management

    International Nuclear Information System (INIS)

    Some aspects of reactor operation management are highlighted. The main mission of the operational staff at a testing reactor is to operate it safely and efficiently, to ensure proper conditions for different research programs implying the use of the reactor. For reaching this aim, there were settled down operating plans for every objective, and procedure and working instructions for staff training were established, both for the start-up and for the safe operation of the reactor. Damages during operation or special situations which can arise, at stop, start-up, maintenance procedures were thoroughly considered. While the technical skill is considered to be the most important quality of the staff, the organising capacity is a must in the operation of any nuclear facility. Staff training aims at gaining both theoretical and practical experience based on standards about staff quality at each work level. 'Plow' sheet has to be carefully done, setting clear the decision responsibility for each person so that everyone's own technical level to be coupled to the problems which implies his responsibility. Possible events which may arise in operation, e.g., criticality, irradiation, contamination, and which do not arise in other fields, have to be carefully studied. One stresses that the management based on technical and scientific arguments have to cover through technical, economical and nuclear safety requirements a series of interlinked subprograms. Every such subprograms is subject to some peculiar demands by the help of which the entire activity field is coordinated. Hence for any subprogram there are established the objectives to be achieved, the applicable regulations, well-defined responsibilities, training of the personnel involved, the material and documentation basis required and activity planning. The following up of positive or negative responses generated by experiments and the information synthesis close the management scope. Important management aspects

  18. Safe operation and maintenance of research reactor

    International Nuclear Information System (INIS)

    The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U3O8- Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

  19. Safe operation and maintenance of research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Munsorn, S. [Reactor Operation Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok (Thailand)

    1999-10-01

    The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U{sub 3}O{sub 8}- Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

  20. Myrrha, new polyvalent research reactor

    International Nuclear Information System (INIS)

    Myrrha (Multi-purpose hybrid research reactor for high-tech applications) is the first prototype of sub-critical nuclear reactor driven by a particle accelerator (an ADS, accelerator-driven system) at semi-industrial scale (50-100 MW), a safe and easy-to-control technology. In an interview, the manager of this project recalls his curriculum, presents and comments the characteristics of Myrrha, outlines why these ADS are so interesting to produce radio-isotopes, comments the variety of countries and companies involved in this project, outlines the peculiarities of Myrrha in terms of safety and the main technological challenges (a mixing of lead and bismuth for the coolant, control of corrosion by oxygen, an improved reliability based on redundant design and fault tolerance, MOX as fuel). He also evokes competing technologies

  1. Decommissioning of Salaspils Research Reactor

    International Nuclear Information System (INIS)

    The Salaspils Research Reactor (SRR) is out of operation since July 1998 and the decommissioning of SRR was started in 1999 according to the decision of the Government of Latvia. The main decommissioning activities up to 2006 were connected with collecting and conditioning of historical radioactive wastes from different storages outside and inside of reactor hall. The total amount of dismantled materials was about 700 tons, more than 77 tons were conditioned in concrete containers for disposal in repository. The radioactive wastes management technology is discussed in the paper. It was found, that additional efforts must be spent for immobilization of radionuclides in cemented matrix to be comply with the wastes acceptance criteria. The investigations of mechanical stability of water-cement matrix are described and discussed in the paper

  2. Operating experiences of the research reactors

    International Nuclear Information System (INIS)

    Nuclear research reactors are devices of wide importance, being used for different scientific research tasks, for testing and improving reactor systems and components, for the production of radioisotopes, for the purposes of defence, for staff training and for other purposes. There are three research reactors in Yugoslavia: RA, RB and TRIGA. Reactors RA and RB at the 'Boris Kidric' Institute of Nuclear Sciences are of heavy water type power being 6500 and 10 kW, and maximum thermal neutron flux of 1014 and 1011(n/cm2s), respectively. TRIGA reactor at the 'Jozef Stefan' Institute in Ljubljana is of 250 kW power and maximum thermal neutron flux of 1013(n/cm2s). Reactors RA and RB use soviet fuel in the form of uranium dioxide (80% enriched) and metallic uranium (2%). Besides, RB reactor operates with natural uranium too. TRIGA reactor uses american uranium fuel 70% and 20% enriched, uranium being mixed homogeneously with moderator (ZrH). Experiences in handling and controlling the fuel before irradiation in the reactor, in reactor and after it are numerous and valuable, involving either the commercial arrangements with foreign producers, or optimal burn up in reactor or fuel treatment after the reactor irradiation. Twenty years of operating experience of these reactors have great importance especially having in mind the number of trained staff. Maintenance of reactors systems and fluids in continuous operation is valuable experience from the point of view of water reactor utilization. The case of the RA reactor primary cycle cobalt decontamination and other events connected with nuclear and radiation security for all three reactors are also specially emphasized. Owing to our research reactors, numerous theoretical, numerical and experimental methods are developed for nuclear and other analyses and design of research and power reactors,as well as methods for control and protection of radiation. (author)

  3. Training and Certification of Research Reactor Personnel

    International Nuclear Information System (INIS)

    The safe operation of a research reactor requires that reactor personnel be fully trained and certified by the relevant authorities. Reactor operators at PUSPATI TRIGA Reactor underwent extensive training and are certified, ever since the reactor first started its operation in 1982. With the emphasis on enhancing reactor safety in recent years, reactor operator training and certification have also evolved. This paper discusses the changes that have to be implemented and the challenges encountered in developing a new training programme to be in line with the national standards. (author)

  4. Research nuclear reactor start-up simulator

    International Nuclear Information System (INIS)

    This work presents the design and FPGA implementation of a research nuclear reactor start-up simulator. Its aim is to generate a set of signals that allow replacing the neutron detector for stimulated signals, to feed the measurement electronic of the start-up channels, to check its operation, together with the start-up security logic. The simulator presented can be configured on three independent channels and adjust the shape of the output pulses. Furthermore, each channel can be configured in 'rate' mode, where you can specify the growth rate of the pulse frequency in %/s. Result and details of the implementation on FPGA of the different functional blocks are given. (author)

  5. Replacement of power supply for reactor control rod magnet

    International Nuclear Information System (INIS)

    The magnet power source supply panel for the control rod driving mechanism (CRDM) of JRR-3 adopted series system as a stable DC source required for the electromagnetic coil to hang the control rods by generating magnetic force. Since it had passed 25 years since its installation, it was updated by employing a switching method as countermeasure for aging and for eliminating high heat generation. This paper explains JRR-3 facilities, control rod drive mechanism, and overview of the magnet power supply panel for CRDM. Next, it takes up the replacement of the magnet power supply panel for CRDM, and explains the contents of changes in the power supply method, the contents of changes from existing current amplifier part to updated current amplifier, and resulting high efficiency. Moreover, as the improved points, it explains reduction in switching, and redundant configuration of cooling fan. The single testing and function testing of the apparatus were conducted to confirm the performance. (A.O.)

  6. Reliability studies in research reactors

    International Nuclear Information System (INIS)

    Fault trees and event trees are widely used in industry to model and to evaluate the reliability of safety systems. Detailed analyzes in nuclear installations require the combination of these two techniques. This study uses the methods of FT (Fault Tree) and ET (Event Tree) to accomplish the PSA (Probabilistic Safety Assessment) in research reactors. According to IAEA (lnternational Atomic Energy Agency), the PSA is divided into Level 1, Level 2 and Level 3. At the Level 1, conceptually, the security systems perform to prevent the occurrence of accidents, At the Level 2, once accidents happened, this Level seeks to minimize consequences, known as stage management of accident, and at Level 3 accident impacts are determined. This study focuses on analyzing the Level 1, and searching through the acquisition of knowledge, the consolidation of methodologies for future reliability studies. The Greek Research Reactor, GRR-1, is a case example. The LOCA (Loss of Coolant Accident) was chosen as the initiating event and from it, using ET, possible accidental sequences were developed, which could lead damage to the core. Moreover, for each of affected systems, probabilities of each event top of FT were developed and evaluated in possible accidental sequences. Also, the estimates of importance measures for basic events are presented in this work. The studies of this research were conducted using a commercial computational tool SAPHIRE. Additionally, achieved results thus were considered satisfactory for the performance or the failure of analyzed systems. (author)

  7. Seismic research on graphite reactor core

    International Nuclear Information System (INIS)

    Background: Reactors with graphite core structure include production reactor, water-cooled graphite reactor, gas-cooled reactor, high-temperature gas-cooled reactor and so on. Multi-body graphite core structure has nonlinear response under seismic excitation, which is different from the response of general civil structure, metal connection structure or bolted structure. Purpose: In order to provide references for the designing and construction of HTR-PM. This paper reviews the history of reactor seismic research evaluation from certain countries, and summarizes the research methods and research results. Methods: By comparing the methods adopted in different gas-cooled reactor cores, inspiration for our own HTR seismic research was achieved. Results and Conclusions: In this paper, the research ideas of graphite core seismic during the process of designing, constructing and operating HTR-10 are expounded. Also the project progress of HTR-PM and the research on side reflection with the theory of similarity is introduced. (authors)

  8. Overview on New Research Reactors in China

    International Nuclear Information System (INIS)

    In China, 2 research reactors are now under construction. Correspondingly, this paper consists of 2 parts. Part 1 will focus on China Advanced Research Reactor (CARR), the reactor characteristics, utilization, safety related systems and other main systems will be described in this part. Part 2 will focus on China Experiment Fast Reactor(CEFR), the general design and the safety features in particular will be illustrated in this part. (author)

  9. The DALAT nuclear research reactor operation and conversion status

    International Nuclear Information System (INIS)

    This paper presents operation and conversion status of the DALAT Nuclear Research Reactor (DNRR). The DNRR is a pool type research reactor which was reconstructed from the 250 kW TRIGA-MARK II reactor. The core is loaded with Soviet-designed standard type WWR-M2 fuel assemblies with 36% enrichment. The reconstructed reactor reached its initial criticality in November 1983 and attained its nominal power of 500 kW in February 1984. The DNRR is operated mainly in continuous runs of 100 hours, once every 4 weeks, for radioisotope production, neutron activation analyses, training and research purposes. The remaining time between two continuous runs, is devoted to maintenance activities and to short runs. Until now 4 fuel reloading were executed. The reactor control and instrumentation system was upgraded in 1994. And now the reactor control system is being replaced by new one, the replacement will be fulfilled in March 2007. The study on fuel conversion has been done on the basis of a new LEU of 19.75% with UO2-Al dispersion fuel meat instead of the current HEU of 36% with aluminium-uranium alloy. The results of the study show that operation time of mixed core by inserting 36 LEU fuel assemblies lasts much longer than by inserting 36 HEU fuel assemblies (14.5 instead of 10.5 years). Neutron flux performances at irradiation positions are not significantly changed. Now we are working for realizing fuel conversion of the DNRR

  10. An Analysis of 27 Years of Research into Computer Education Published in Australian Educational Computing

    Science.gov (United States)

    Zagami, Jason

    2015-01-01

    Analysis of three decades of publications in Australian Educational Computing (AEC) provides insight into the historical trends in Australian educational computing, highlighting an emphasis on pedagogy, comparatively few articles on educational technologies, and strong research topic alignment with similar international journals. Analysis confirms…

  11. Defence Science Research, Higher Education and the Australian Quest for the Atomic Bomb, 1945-60.

    Science.gov (United States)

    Reynolds, Wayne

    1997-01-01

    Recounts the efforts of the Australian government to create an atomic research and development program after World War II. Describes initial cooperation with Britain and the push for the transformation of Australian higher and secondary education in service of national scientific development. Discusses effects of the end of Commonwealth…

  12. Australians from a Non-English Speaking Background with Intellectual Disability: The Importance of Research

    Science.gov (United States)

    Brolan, Claire E.; Gomez, Miriam Taylor; Lennox, Nicholas G.; Ware, Robert S.

    2013-01-01

    The authors review available data on Australians from a non-English speaking background (NESB) with intellectual disability (ID). They find that intellectual disability in the Australian NESB community has received limited attention in terms of both qualitative and quantitative research. The existing literature is over 10 years old and is relevant…

  13. Safe Operation of Research Reactors in Germany

    International Nuclear Information System (INIS)

    In Germany, experience was gained in the field of safe operation of research reactors during the last five decades. In this time, in total 46 research reactors were built and operated safely. Concerning the design, there is, or has been, a very broad range of different types of research reactors. The variety of facilities includes large pool or tank reactors with a thermal power of several tens of megawatt as well as small educational reactors with a negligible thermal power and critical assemblies. At present, 8 research reactors are still in operation. The other facilities are permanently shutdown, in decommissioning or have already been dismantled completely and released from regulatory control. In this paper, four selected facilities still being operated are presented as examples for safe operation of research reactors in Germany, including especially a description of the safety reviews and safety upgrades for the older facilities. (author)

  14. Industrial structure at research reactor suppliers

    International Nuclear Information System (INIS)

    Due to the recent joining of the forces of Framatome S. A. from France and the Nuclear Division of Siemens AG Power Generation (KWU) from Germany to a Joint Venture named Framatome Advanced Nuclear Power S.A.S., the issue of the necessary and of the optimal industrial structure for nuclear projects as a research reactor is, was discussed internally often and intensively. That discussion took place also in the other technical fields such as Services for NPPs but also in the field of interest here, i. e. Research Reactors. In summarizing the statements of this presentation one can about state that: Research Reactors are easier to build than NPPs, but not standardised; Research Reactors need a wide spectrum of skills and experiences; to design and build Research Reactors needs an experienced team especially in terms of management and interfaces; Research Reactors need background from built reference plants more than from operating plants; Research Reactors need knowledge of suitable experienced subsuppliers. Two more essential conclusions as industry involved in constructing and upgrading research reactors are: Research Reactors by far are more than a suitable core that generates a high neutron flux; every institution that designs and builds a Research Reactor lacks quality or causes safety problems, damages the reputation of the entire community

  15. Application of research reactors for radiation education

    International Nuclear Information System (INIS)

    Nuclear research Reactors are, as well as being necessary for research purposes, indispensable educational tools for a country whose electric power resources are strongly dependent on nuclear energy. Both large and small research reactors are available, but small ones are highly useful from the viewpoint of radiation education. This paper oders a brief review of how small research reactors can, and must, be used for radiation education for high school students, college and graduate students, as well as for the public. (author)

  16. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The purpose of this technical paper is to provide status of the United State domestic Research Reactor Infrastructure (RRI) Program at the Idaho National Laboratory. This paper states the purpose of the program, lists the universities operating TRIGA reactors that are supported by the program, identifies anticipated fresh fuel needs for the reactor facilities, discusses spent fuel activities associated with the program, and addresses successes and planned activities for the program. (author)

  17. Euratom research supporting reactor safety

    International Nuclear Information System (INIS)

    This paper focuses on the way the Fifth Framework Programme (FP5) of the European Atomic Energy Community (Euratom) (1998-2002) contributed to the overall effort supporting LWR safety and on the prospects of FP6 (2002-2006) to achieve the additional goal of contributing to the creation of the European Research Area (ERA). The objectives of the FP5 Community research are discussed, topic per topic, with reference to the relevant projects contributing to their achievement while emphasising the role and expectations of the end-users. 71 research projects have been carried out in FP5 with a total cost of 85.4 million Euro, out of which 43.5 million Euro are contributed by the EU. Economic aspects and needs for nuclear knowledge management throughout the EU-25 countries are briefly discussed as well as future Euratom research needs and nuclear stakeholders' interests. Implementation aspects and prospects of Euratom FP6 are discussed bearing in mind the challenging additional objective. Very ambitious S/T actions have been undertaken supporting reactor safety not only by their technical achievements but also by their structuring effect in the European research picture. (authors)

  18. Development of plastic capsule for research reactor irradiation

    International Nuclear Information System (INIS)

    New irradiation capsule for the research reactor was developed using a radiation resistant polymer, Polyethylene-2, 6-Naphthalate (PEN). This capsule has several merits such as low activity after irradiation, low price by mass production using injection moulding, and good irradiation performance for application to 12 hours irradiation in Japan Research Reactor No. 4 (JRR-4). Using this capsule, more efficient irradiation can be done because the sample can be taken off from the capsule immediately after irradiation, and this PEN capsule can be replaced with ordinary aluminum capsule for JRR-4 irradiation. This report describes the development of PEN capsule and the irradiation tests. (author)

  19. RB research reactor Safety Report

    International Nuclear Information System (INIS)

    This RB reactor safety report is a revised and improved version of the Safety report written in 1962. It contains descriptions of: reactor building, reactor hall, control room, laboratories, reactor components, reactor control system, heavy water loop, neutron source, safety system, dosimetry system, alarm system, neutron converter, experimental channels. Safety aspects of the reactor operation include analyses of accident causes, errors during operation, measures for preventing uncontrolled activity changes, analysis of the maximum possible accident in case of different core configurations with natural uranium, slightly and highly enriched fuel; influence of possible seismic events

  20. Fuel element reshuffling and fuel follower control rods (FFCR) replacement for PUSPATI TRIGA reactor

    International Nuclear Information System (INIS)

    The PUSPATI TRIGA Reactor has been utilized for more than 25 years using the same fuel elements and control rods. Generally, there are four control rods being used to control the neutron production inside the reactor core. A maintenance program has been developed to ensure its integrity, capability and safety of the reactor and it has been maintained twice a year since the first operation in 1982. The activities involve during the maintenance period including fuel elements and control rods inspections, electronics and mechanical systems, and others related works. During the maintenance in August 2008, there are some irregularities found on the fuel follower control rods and needed to be replaced. Even though the irregularities was not contributed into any unwanted incident, it were decided to replace with new control rods to avoid any potential hazards and unsafe condition occurred during operation later. Replacing any of the control rods would involved in imbalance of neutron flux and power distribution inside the core. Therefore, a number of fuel elements need to be reshuffled in order to compensate the neutron flux and power distribution as well as to balance the fuel elements burn-up in the core. This paper will described the fuel elements reshuffling and fuel follower control rods (FFCR) replacement for PUSPATI TRIGA Reactor. (Author)

  1. Health physics research reactor reference dosimetry

    International Nuclear Information System (INIS)

    Reference neutron dosimetry is developed for the Health Physics Research Reactor (HPRR) in the new operational configuration directly above its storage pit. This operational change was physically made early in CY 1985. The new reference dosimetry considered in this document is referred to as the 1986 HPRR reference dosimetry and it replaces any and all HPRR reference documents or papers issued prior to 1986. Reference dosimetry is developed for the unshielded HPRR as well as for the reactor with each of five different shield types and configurations. The reference dosimetry is presented in terms of three different dose and six different dose equivalent reporting conventions. These reporting conventions cover most of those in current use by dosimetrists worldwide. In addition to the reference neutron dosimetry, this document contains other useful dosimetry-related data for the HPRR in its new configuration. These data include dose-distance measurements and calculations, gamma dose measurements, neutron-to-gamma ratios, ''9-to-3 inch'' ratios, threshold detector unit measurements, 56-group neutron energy spectra, sulfur fluence measurements, and details concerning HPRR shields. 26 refs., 11 figs., 31 tabs

  2. Immigrant Australians and Education. A Review of Research. Australian Education Review Number 22.

    Science.gov (United States)

    Sturman, Andrew

    This review examines whether immigrant Australians are disadvantaged educationally or vocationally by the education they receive, and whether their educational experiences are of a high quality and relevant to their needs. First, data is provided on the patterns of post-war immigration, along with information about the changing attitudes of…

  3. Strategic planning for research reactors. Guidance for reactor managers

    International Nuclear Information System (INIS)

    The purpose of this publication is to provide guidance on how to develop a strategic plan for a research reactor. The IAEA is convinced of the need for research reactors to have strategic plans and is issuing a series of publications to help owners and operators in this regard. One of these covers the applications of research reactors. That report brings together all of the current uses of research reactors and enables a reactor owner or operator to evaluate which applications might be possible with a particular facility. An analysis of research reactor capabilities is an early phase in the strategic planning process. The current document provides the rationale for a strategic plan, outlines the methodology of developing such a plan and then gives a model that may be followed. While there are many purposes for research reactor strategic plans, this report emphasizes the use of strategic planning in order to increase utilization. A number of examples are given in order to clearly illustrate this function

  4. Replacement of the reactor protection and control system of the Beznau nuclear power station

    International Nuclear Information System (INIS)

    The Beznau nuclear power station comprises two almost identical pressurized water reactor units; the plant is located in the lower Aare river area. Its aggregate electric power is 760 MW. The plant is operated by Nordostschweizerische Kraftwerke (NOK). In 2000 and 2001, the reactor protection and control systems of both units of the Beznau nuclear power plant were replaced by a modern digital safety instrumentation and control system. That exchange had become necessary because it had become increasingly more difficult to obtain spare parts and maintain the systems. In addition, the expense involved in testing and inspection was to be reduced and fault detection in safety I and C was to be improved. Consistent splitting of the reactor protection system into four physically separate redundancies allowed the safety standard to be raised further, and fire protection to be improved. Continuous backfitting and renewal of the plant in an effort to keep it at the latest level of technical safety has been continued in an impressive way in replacing the old reactor protection and control system by the latest computer-based technology. ''PRESSURE'', the project of replacing the reactor protection and control system, went through several busy phases extending back as far as 1990. Project management was entrusted to a project team of KKB in-house project engineers with expert knowledge in I and C technology and, in addition, detailed knowledge of the processes in the existing plant. (orig.)

  5. Light water reactor safety research project

    International Nuclear Information System (INIS)

    The research and development activities for the safety of Light Water Power Reactors carried out 1979 at the Swiss Federal Institute for Reactor Research are described. Considerations concerning the necessity, objectives and size of the Safety Research Project are presented, followed by a detailed discussion of the activities in the five tasks of the program, covering fracture mechanics and nondestructive testing, thermal-hydraulics, reactor noise analysis and pressure vessel steel surveillance. (Auth.)

  6. Study on reactor vessel replacement (RVR) for 1100 MW class BWR plants in Japan

    International Nuclear Information System (INIS)

    Plant Life Management (PLM) is being studied in Japan, and reactor vessel replacement (RVR) is being considered as one option. Since reactor internals, except for reusable parts, and the reactor pressure vessel (RPV) are replaced, the RVR provides an effective technology for extending the service life of nuclear power plants substantially. At ICONE 7, we reported on the technical viability of the RVR for BWR4-type 800 MWe class plants. This time, we rationalized the RVR method through a study for BWR5-type 1100 MWe class plants to reduce the RVR duration and evaluated the technical viability and the economic efficiency of the method. In addition, we discuss how to dispose of the RPV to complete a scenario of the process from the RVR to its final disposal. (author)

  7. Safety of research reactors - A regulator's perspective

    International Nuclear Information System (INIS)

    Due to historical reasons research reactors have received less regulatory attention in the world than nuclear power plants. This has given rise to several safety issues which, if not addressed immediately, may result in an undesirable situation. However, in Pakistan, research reactors and power reactors have received due attention from the regulatory authority. The Pakistan Research Reactor-1 has been under regulatory surveillance since 1965, the year of its commissioning. The second reactor has also undergone all the safety reviews and checks mandated by the licensing procedures. A brief description of the regulatory framework, the several safety reviews carried out have been briefly described in this paper. Significant activities of the regulatory authority have also been described in verifying the safety of research reactors in Pakistan along with the future activities. The views of the Pakistani regulatory authority on the specific issues identified by the IAEA have been presented along with specific recommendations to the IAEA. We are of the opinion that there are more Member States operating nuclear research reactors than nuclear power plants. Therefore, there should be more emphasis on the research reactor safety, which somehow has not been the case. In several recommendations made to the IAEA on the specific safety issues the emphasis has been, in general, to have a similar documentation and approach for maintaining and verifying operational safety at research reactors as is currently available for nuclear power reactors and may be planned for nuclear fuel cycle facilities. (author)

  8. Status report on the back end of the fuel cycle for research reactors

    International Nuclear Information System (INIS)

    U.S. DOE suspended its reprocessing policy for research reactors at the end of 1988 due to environmental concerns. The available restricted alternatives cannot replace U.S. DOE. Most of the research reactor operators have up till now no alternative to close their fuel cycle and are worried about this uncertain situation. The consequences of this situation are discussed. (author)

  9. The rehabilitation/upgrading of Philippine Research Reactor

    International Nuclear Information System (INIS)

    The Philippine Research Reactor (PRR-1) is the only research reactor in the Philippines. It was acquired through the Bilateral Agreement with the United States of America. The General Electric (G.E.) supplied PRR-1 first become operational in 1963 and used MTR plate type fuel. The original one-megawatt G.E. reactor was shutdown and converted into a 3 MW TRIGA PULSING REACTOR in 1984. The conversion includes the upgrading of the cooling system, replacement of new reactor coolant pumps, heat exchanger, cooling tower, replacement of new nuclear instrumentation and standard TRIGA console, TRIGA fuel supplied by General Atomic (G.A.). Philippine Nuclear Research Institute (PNRI) provided the old reactor, did the detailed design of the new cooling system, provided the new non-nuclear instrumentation and electrical power supply system and performed all construction, installation and modification work on site. The TRIGA conversion fuel is contained in a shrouded 4-rod cluster which fit into the original grid plate. The new fuel is a E1-U-Z1-H1.6 TRIGA fuel, has a 20% wt Uranium loading with 19.7% U-235 enrichment and about 0.5 wt % Erbium. The Start-up, calibration and Demonstration of Pulsing and Full Power Operation were completed during a three week start-up phase which were performed last March 1968. A few days after, a leak in the pool liner was discovered. The reactor was shutdown again for repair and up to present the reactor is still in the process of rehabilitation. This paper will describe the rehabilitation/upgrading done on the PRR-1 since 1988 up to present. (author)

  10. The rehabilitation/upgrading of Philippine Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Renato, T. Banaga [Philippines Nuclear Research Inst., Quezon (Philippines)

    1998-10-01

    The Philippine Research Reactor (PRR-1) is the only research reactor in the Philippines. It was acquired through the Bilateral Agreement with the United States of America. The General Electric (G.E.) supplied PRR-1 first become operational in 1963 and used MTR plate type fuel. The original one-megawatt G.E. reactor was shutdown and converted into a 3 MW TRIGA PULSING REACTOR in 1984. The conversion includes the upgrading of the cooling system, replacement of new reactor coolant pumps, heat exchanger, cooling tower, replacement of new nuclear instrumentation and standard TRIGA console, TRIGA fuel supplied by General Atomic (G.A.). Philippine Nuclear Research Institute (PNRI) provided the old reactor, did the detailed design of the new cooling system, provided the new non-nuclear instrumentation and electrical power supply system and performed all construction, installation and modification work on site. The TRIGA conversion fuel is contained in a shrouded 4-rod cluster which fit into the original grid plate. The new fuel is a E{sub 1}-U-Z{sub 1}-H{sub 1.6} TRIGA fuel, has a 20% wt Uranium loading with 19.7% U-235 enrichment and about 0.5 wt % Erbium. The Start-up, calibration and Demonstration of Pulsing and Full Power Operation were completed during a three week start-up phase which were performed last March 1968. A few days after, a leak in the pool liner was discovered. The reactor was shutdown again for repair and up to present the reactor is still in the process of rehabilitation. This paper will describe the rehabilitation/upgrading done on the PRR-1 since 1988 up to present. (author)

  11. Life Satisfaction of Young Australians: Relationships between Further Education, Training and Employment and General and Career Satisfaction. Longitudinal Surveys of Australian Youth Research Report 43

    Science.gov (United States)

    Hillman, Kylie; McMillan, Julie

    2005-01-01

    Prepared by the Australian Council for Educational Research (ACER) under an agreement with the Australian Government Department of Education, Science and Training (DEST), this report has three broad aims: (1) To describe the relationship between life satisfaction and participation in a range of post-school education, training and labour market…

  12. Research nuclear reactor RA - Annual Report 2000

    International Nuclear Information System (INIS)

    Activities related to revitalisation of the RA reactor started in 1986 were fulfilled except the exchange of the complete reactor instrumentation. Since 1992, due to economic and political reasons, RA reactor is in a difficult situation. The old RA reactor instrumentation was dismantled. Decision about the future status of the reactor should be made because the aging of all the components is becoming dramatic. Control and maintenance of the reactor components was done regularly and efficiently. The most important activity and investment in 1998 was improvement of conditions for spent fuel storage in the existing pools at the RA reactor. Russian company ENTEK and IAEA are involved in this activity which was initiated 1997. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. Research reactor RA Annual report for year 2000 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection

  13. Research nuclear reactor RA - Annual Report 1998

    International Nuclear Information System (INIS)

    Activities related to revitalisation of the RA reactor started in 1986 were fulfilled except the exchange of the complete reactor instrumentation. Since 1992, due to economic and political reasons, RA reactor is in a difficult situation. The old RA reactor instrumentation was dismantled. Decision about the future status of the reactor should be made because the aging of all the components is becoming dramatic. Control and maintenance of the reactor components was done regularly and efficiently. The most important activity and investment in 1998 was improvement of conditions for spent fuel storage in the existing pools at the RA reactor. Russian company ENTEK and IAEA are involved in this activity which was initiated 1997. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. Research reactor RA Annual report for year 1998 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection

  14. Research nuclear reactor RA - Annual Report 1999

    International Nuclear Information System (INIS)

    Activities related to revitalisation of the RA reactor started in 1986 were fulfilled except the exchange of the complete reactor instrumentation. Since 1992, due to economic and political reasons, RA reactor is in a difficult situation. The old RA reactor instrumentation was dismantled. Decision about the future status of the reactor should be made because the aging of all the components is becoming dramatic. Control and maintenance of the reactor components was done regularly and efficiently. The most important activity and investment in 1998 was improvement of conditions for spent fuel storage in the existing pools at the RA reactor. Russian company ENTEK and IAEA are involved in this activity which was initiated 1997. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. Research reactor RA Annual report for year 1998 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection

  15. Educational Research: The State of Sweden and the Australian 2.2 World

    Science.gov (United States)

    Foss Lindblad, Rita; Lindblad, Sverker

    2013-01-01

    Current tendencies in educational research in Sweden are presented and compared to Australia. We here refer to; organization of research, research allocation, publication patterns, and assessments of research qualities. Different trajectories of educational research were identified, where Australian research was organized as a field of study,…

  16. Usage of burnable poison on research reactors

    International Nuclear Information System (INIS)

    The fuel assemblies with burnable poison are widely used on power reactors, but there are not commonly used on research reactors. This paper shows a neutronic analysis of the advantages and disadvantages of the burnable poison usage on research reactors. This paper analyses both burnable poison design used on research reactors: Boron on the lateral wall and Cadmium wires. Both designs include a parametric study on the design parameters like the amount and geometry of the burnable poison. This paper presents the design flexibility using burnable poisons, it does not find an optimal or final design, which it will strongly depend on the core characteristics and fuel management strategy. (author)

  17. The Canadian research reactor spent fuel situation

    International Nuclear Information System (INIS)

    This paper summarizes the present research reactor spent fuel situation in Canada. The research reactors currently operating are listed along with the types of fuel that they utilize. Other shut down research reactors contributing to the storage volume are included for completeness. The spent fuel storage facilities associated with these reactors and the methods used to determine criticality safety are described. Finally the current inventory of spent fuel and where it is stored is presented along with concerns for future storage. (author). 3 figs

  18. The Berkeley TRIGA Mark III research reactor

    International Nuclear Information System (INIS)

    The Berkeley Research Reactor went critical on August 10, 1966, and achieved licensed operating power of 1000 kW shortly thereafter. Since then, the reactor has operated, by and large, trouble free on a one-shift basis. The major use of the reactor is in service irradiations, and many scientific programs are accommodated, both on and off campus. The principal off-campus user is the Lawrence Radiation Laboratory at Berkeley. The reactor is also an important instructional tool in the Nuclear Engineering Department reactor experiments laboratory course, and as a source of radioisotopes for two other laboratory courses given by the Department. Finally, the reactor is used in several research programs conducted within the Department, involving studies with neutron beams and in reactor kinetics

  19. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  20. United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support

    Energy Technology Data Exchange (ETDEWEB)

    Douglas Morrell

    2011-03-01

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  1. Research reactor and its application in Thailand

    International Nuclear Information System (INIS)

    The first Thai Research Reactor (TRR-1) was established in 1961. TRR-1 had been operated with power of 1 MW from 1962 to 1975 and was shut down for modification during 1975 to 1977. The Thai Research Reactor1/modification1 (TRR-1/M1) is a multipurpose reactor with nominal power of 2 MW. Since 1977 TRR-1/M1 has been operated and utilized for various applications such as neutron activation analysis, radioisotope production, gem irradiation, neutron radiography and research works. To expand and promote the utilization of research reactor, the new 10 MW Research Reactor will be established in the Ongkarak Nuclear Research Center (ONRC) project and the project will be finished in the near future. (author)

  2. IAEA programme on research reactor safety

    International Nuclear Information System (INIS)

    This paper describes the IAEA programme on research reactor safety and includes the safety related areas of conversions to the use of low enriched uranium (LEU) fuel. The program is based on the IAEA statutory responsibilities as they apply to the requirements of over 320 research reactors operating around the world. The programme covers four major areas: (a) the development of safety documents; (b) safety missions to research reactor facilities; (c) support of research programmes on research reactor safety; (d) support of Technical Cooperation projects on research reactor safety issues. The demand for these activities by the IAEA member states has increased substantially in recent years especially in developing countries with increasing emphasis being placed on LEU conversion matters. In response to this demand, the IAEA has undertaken an extensive programme for each of the four areas above. (author)

  3. Partial dismantling of research reactor-Sofia prior its refurbishment into low power reactor

    International Nuclear Information System (INIS)

    The strategy for the Research Reactor IRT-Sofia, after decision of the Government for its refurbishment, is a partial dismantling of the old systems and equipment. Removal of the reactor core and replacement of old equipment will not pose any significant problems for dismantling. For most efficient use of resources there is a need for implementation of the engineering project, 'Plan for partial dismantling of equipment of the IRT-Sofia as a part of its refurbishment and conversion into low power RR', which has been already prepared. (author)

  4. Overview of research reactor operation within AECL

    International Nuclear Information System (INIS)

    This paper presents information on reactor operations within the Research Company of Atomic Energy of Canada (AECL) today relative to a few years ago, and speculates on future operations. In recent years, the need for Research Company reactors has diminished. This, combined with economic pressures, has led to the shutdown of some of the company's major reactors. However, compliance with the government agenda to privatize government companies in Canada, and a Research Company policy of business development, has led to some offsetting activities. The building of a pool-type 10 MWt MAPLE (Multipurpose Applied Physics Lattice Experimental) reactor for isotope production will assist in the sale of the AECL isotopes marketing company. A Low Enriched Uranium (LEU) fuel fabrication facility and a Tritium Extraction Plant (TEP), both currently under construction, are needed in support of the NRU (National Research Universal) reactor and are in line with business development strategies. The research program demands on NRU stretch many years into the future and the strategies for achieving effective operation of this aging reactor, now 32 years old, are discussed. The repair of the leaking light-water reflector of the NRU reactor is highlighted. The isotope business requires that a second reactor be available for back-up production and the operation of the 42 year old NRX (National Research Experimental) reactor in its present 'hot standby' mode is believed to be unique in the world

  5. Design of a multipurpose research reactor

    International Nuclear Information System (INIS)

    The availability of a research reactor is essential in any endeavor to improve the execution of a nuclear programme, since it is a very versatile tool which can make a decisive contribution to a country's scientific and technological development. Because of their design, however, many existing research reactors are poorly adapted to certain uses. In some nuclear research centres, especially in the advanced countries, changes have been made in the original designs or new research prototypes have been designed for specific purposes. These modifications have proven very costly and therefore beyond the reach of developing countries. For this reason, what the research institutes in such countries need is a single sufficiently versatile nuclear plant capable of meeting the requirements of a nuclear research programme at a reasonable cost. This is precisely what a multipurpose reactor does. The Mexican National Nuclear Research Institute (ININ) plans to design and build a multipurpose research reactor capable at the same time of being used for the development of reactor design skills and for testing nuclear materials and fuels, for radioisotopes production, for nuclear power studies and basic scientific research, for specialized training, and so on. For this design work on the ININ Multipurpose Research Reactor, collaborative relations have been established with various international organizations possessing experience in nuclear reactor design: Atomehnergoeksport of the USSR: Atomic Energy of Canada Limited (AECL); General Atomics (GA) of the USA; and Japan Atomic Energy Research Institute

  6. Utilisation of British University Research Reactors.

    Science.gov (United States)

    Duncton, P. J.; And Others

    British experience relating to the employment of university research reactors and subcritical assemblies in the education of nuclear scientists and technologists, in the training of reactor operators and for fundamental pure and applied research in this field is reviewed. The facilities available in a number of British universities and the uses…

  7. Problems of Decommissioning Research Reactor IR-100

    International Nuclear Information System (INIS)

    The research reactor IR-100 with a thermal power of 200 kW is assigned to conduct science research and training activities in the fields of nuclear and molecular physics, radiation chemistry, radioactive isotope production, material, irradiation in neutron and gamma fields of devices and equipment, as well as for training of specialists for nuclear reactor operation

  8. Consumer input into research: the Australian Cancer Trials website

    Directory of Open Access Journals (Sweden)

    Butow Phyllis N

    2011-06-01

    Full Text Available Abstract Background The Australian Cancer Trials website (ACTO was publicly launched in 2010 to help people search for cancer clinical trials recruiting in Australia, provide information about clinical trials and assist with doctor-patient communication about trials. We describe consumer involvement in the design and development of ACTO and report our preliminary patient evaluation of the website. Methods Consumers, led by Cancer Voices NSW, provided the impetus to develop the website. Consumer representative groups were consulted by the research team during the design and development of ACTO which combines a search engine, trial details, general information about trial participation and question prompt lists. Website use was analysed. A patient evaluation questionnaire was completed at one hospital, one week after exposure to the website. Results ACTO's main features and content reflect consumer input. In February 2011, it covered 1, 042 cancer trials. Since ACTO's public launch in November 2010, until the end of February 2011, the website has had 2, 549 new visits and generated 17, 833 page views. In a sub-study of 47 patient users, 89% found the website helpful for learning about clinical trials and all respondents thought patients should have access to ACTO. Conclusions The development of ACTO is an example of consumers working with doctors, researchers and policy makers to improve the information available to people whose lives are affected by cancer and to help them participate in their treatment decisions, including consideration of clinical trial enrolment. Consumer input has ensured that the website is informative, targets consumer priorities and is user-friendly. ACTO serves as a model for other health conditions.

  9. The future role of research reactors

    International Nuclear Information System (INIS)

    The decline of neutron source capacity in the next decades urges for the planning and construction of new neutron sources for basic and applied research with neutrons. Modern safety precautions of research reactors make them competitive with other ways of neutron production using non-chain reactions for many applications. Research reactors consequently optimized offer a very broad range of possible applications in basic and applied research. Research reactors at universities also in the future have to play an important role in education and training in basic and applied nuclear science. (orig.)

  10. Nuclear data usage for research reactors

    International Nuclear Information System (INIS)

    In the department of research reactor, many neutronics calculations have been performed to construct, to operate and to modify research reactors of JAERI with several kinds of nuclear data libraries. This paper presents latest two neutronic analyses on research reactors. First one is design work of a low enriched uranium (LEU) fuel for JRR-4 (Japan Research Reactor No.4). The other is design of a uranium silicon dispersion type (silicide) fuel of JRR-3M (Japan Research Reactor No.3 Modified). Before starting the design work, to estimate the accuracy of computer code and calculation method, experimental data are calculated with several nuclear data libraries. From both cases of calculations, it is confirmed that JENDL-3.2 gives about 1 %Δk/k higher excess reactivity than JENDL-3.1. (author)

  11. Development of a remote handling system for replacement of armor tiles in the Fusion Experimental Reactor

    International Nuclear Information System (INIS)

    The armor tiles of the Fusion Experimental Reactor (FER) planned by JAERI are categorized as scheduled maintenance components, since they are damaged by severe heat and particle loads from the plasma during operation. A remote handling system is thus required to replace a large number of tiles rapidly in the highly activated reactor. However, the simple teaching-playback method cannot be adapted to this system because of deflection of the tiles caused by thermal deformation and so on. We have developed a control system using visual feedback control to adapt to this deflection and an end-effector for a single arm. We confirm their performance in tests. (orig.)

  12. Research reactor job analysis - A project description

    International Nuclear Information System (INIS)

    Addressing the need of the improved training in nuclear industry, nuclear utilities established training program guidelines based on Performance-Based Training (PBT) concepts. The comparison of commercial nuclear power facilities with research and test reactors owned by the U.S. Department of Energy (DOE), made in an independent review of personnel selection, training, and qualification requirements for DOE-owned reactors pointed out that the complexity of the most critical tasks in research reactors is less than that in power reactors. The U.S. Department of Energy (DOE) started a project by commissioning Oak Ridge Associated Universities (ORAU) to conduct a job analysis survey of representative research reactor facilities. The output of the project consists of two publications: Volume 1 - Research Reactor Job Analysis: Overview, which contains an Introduction, Project Description, Project Methodology,, and. An Overview of Performance-Based Training (PBT); and Volume 2 - Research Reactor Job Analysis: Implementation, which contains Guidelines for Application of Preliminary Task Lists and Preliminary Task Lists for Reactor Operators and Supervisory Reactor Operators

  13. Software development for research reactors

    International Nuclear Information System (INIS)

    The Texas A and M University Nuclear Science Center, in a program jointly sponsored with the International Atomic Energy Agency, is developing a series of computer software programs of use at research reactor facilities. The programs cover a wide range of topics including activation and shielding calculations, control rod calibrations, power calorimetrics, and fuel inventory including burnup. Many of the programs are modified and improved versions of programs already in use at the NSC that ran on outdated computing equipment. All of the new versions were written in Fortran77 on the NSC's new TI Pro microcomputer and are IBM-compatible. This paper describes the development and translation efforts in preparing the programs for use by other facilities, and gives an overview of the aim of the development effort. A brief description of each program that has been or is to be written is given including the required inputs and the resulting outputs. This paper also addresses the original needs that brought about the development program and the benefits to facility operations that each program provides. The programs discussed are available to interested parties in a hard-copy listing as requested. (author)

  14. The concept of a research fusion reactor

    International Nuclear Information System (INIS)

    Thus,for advancement towards a commercial fusion reactor,we have proposed here as a next step a steady state operated research fusion reactor with an increased plasma-wall detachment so as to further guarantee not only the production but also a long-term (for many years) confinement of a self-sustained plasma at the existing technology level. We consider the primary goal of the research fusion reactor is the provision of full-scale conditions for carrying out materials science experiments to create and test 1 st wall materials for the commercial fusion reactor

  15. RA Research nuclear reactor - Annual report 1987

    International Nuclear Information System (INIS)

    Annual report concerning the project 'RA research nuclear reactor' for 1987, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities

  16. RA Research reactor, Annual report 1988

    International Nuclear Information System (INIS)

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities

  17. Research nuclear reactor RA - Annual Report 1989

    International Nuclear Information System (INIS)

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities

  18. A Level 1+ Probabilistic Safety Assessment of the High Flux Australian Reactor. Vol 1

    International Nuclear Information System (INIS)

    The Department of Industry, Science and Tourism selected PLG, an EQE International Company, to systematically and independently evaluate the safety of the High Flux Australian Reactor (HIFAR), located at Lucas Heights, New South Wales. PLG performed a comprehensive probabilistic safety assessment (PSA) to quantify the risks posed by operation of HIFAR . The PSA identified possible accident scenarios, estimated their likelihood of occurrence, and assigned each scenario to a consequence category; i.e., end state. The accident scenarios developed included the possible release of radioactive material from irradiated nuclear fuel and of tritium releases from reactor coolant. The study team developed a recommended set of safety criteria against which the results of the PSA may be judged. HIFAR was found to exceed one of the two primary safety objectives and two of the five secondary safety objectives. Reactor coolant leaks, earthquakes, and coolant pump trips were the accident initiators that contributed most to scenarios that could result in fuel overheating. Scenarios initiated by earthquakes were the reason the frequency criterion for the one primary safety objective was exceeded. Overall, the plant safety status has been shown to be generally good with no evidence of major safety-related problems from its operation. One design deficiency associated with the emergency core cooling system was identified that should be corrected as soon as possible. Additionally, several analytical issues have been identified that should be investigated further. The results from these additional investigations should be used to determine whether additional plant and procedural changes are required, or if further evaluations of postulated severe accidents are warranted. Supporting information can be found in Appendix A for the seismic analysis and in the Appendix B for selected other external events

  19. A Level 1+ Probabilistic Safety Assessment of the High Flux Australian Reactor. Vol 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    The Department of Industry, Science and Tourism selected PLG, an EQE International Company, to systematically and independently evaluate the safety of the High Flux Australian Reactor (HIFAR), located at Lucas Heights, New South Wales. PLG performed a comprehensive probabilistic safety assessment (PSA) to quantify the risks posed by operation of HIFAR . The PSA identified possible accident scenarios, estimated their likelihood of occurrence, and assigned each scenario to a consequence category; i.e., end state. The accident scenarios developed included the possible release of radioactive material from irradiated nuclear fuel and of tritium releases from reactor coolant. The study team developed a recommended set of safety criteria against which the results of the PSA may be judged. HIFAR was found to exceed one of the two primary safety objectives and two of the five secondary safety objectives. Reactor coolant leaks, earthquakes, and coolant pump trips were the accident initiators that contributed most to scenarios that could result in fuel overheating. Scenarios initiated by earthquakes were the reason the frequency criterion for the one primary safety objective was exceeded. Overall, the plant safety status has been shown to be generally good with no evidence of major safety-related problems from its operation. One design deficiency associated with the emergency core cooling system was identified that should be corrected as soon as possible. Additionally, several analytical issues have been identified that should be investigated further. The results from these additional investigations should be used to determine whether additional plant and procedural changes are required, or if further evaluations of postulated severe accidents are warranted. Supporting information can be found in Appendix A for the seismic analysis and in the Appendix B for selected other external events refs., 139 tabs., 85 figs. Prepared for Department of Industry, Science and Tourism

  20. Advanced research reactor fuel development

    International Nuclear Information System (INIS)

    The fabrication technology of the U3Si fuel dispersed in aluminum for the localization of HANARO driver fuel has been launches. The increase of production yield of LEU metal, the establishment of measurement method of homogeneity, and electron beam welding process were performed. Irradiation test under normal operation condition, had been carried out and any clues of the fuel assembly breakdown was not detected. The 2nd test fuel assembly has been irradiated at HANARO reactor since 17th June 1999. The quality assurance system has been re-established and the eddy current test technique has been developed. The irradiation test for U3Si2 dispersed fuels at HANARO reactor has been carried out in order to compare the in-pile performance of between the two types of U3Si2 fuels, prepared by both the atomization and comminution processes. KAERI has also conducted all safety-related works such as the design and the fabrication of irradiation rig, the analysis of irradiation behavior, thermal hydraulic characteristics, stress analysis for irradiation rig, and thermal analysis fuel plate, for the mini-plate prepared by international research cooperation being irradiated safely at HANARO. Pressure drop test, vibration test and endurance test were performed. The characterization on powders of U-(5.4 ∼ 10 wt%) Mo alloy depending on Mo content prepared by rotating disk centrifugal atomization process was carried out in order to investigate the phase stability of the atomized U-Mo alloy system. The γ-U phase stability and the thermal compatibility of atomized U-16at.%Mo and U-14at.%Mo-2at.%X(: Ru, Os) dispersion fuel meats at an elevated temperature have been investigated. The volume increases of U-Mo compatibility specimens were almost the same as or smaller than those of U3Si2. However the atomized alloy fuel exhibited a better irradiation performance than the comminuted alloy. The RERTR-3 irradiation test of nano-plates will be conducted in the Advanced Test Reactor(ATR). 49

  1. Advanced research reactor fuel development

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chang Kyu; Pak, H. D.; Kim, K. H. [and others

    2000-05-01

    The fabrication technology of the U{sub 3}Si fuel dispersed in aluminum for the localization of HANARO driver fuel has been launches. The increase of production yield of LEU metal, the establishment of measurement method of homogeneity, and electron beam welding process were performed. Irradiation test under normal operation condition, had been carried out and any clues of the fuel assembly breakdown was not detected. The 2nd test fuel assembly has been irradiated at HANARO reactor since 17th June 1999. The quality assurance system has been re-established and the eddy current test technique has been developed. The irradiation test for U{sub 3}Si{sub 2} dispersed fuels at HANARO reactor has been carried out in order to compare the in-pile performance of between the two types of U{sub 3}Si{sub 2} fuels, prepared by both the atomization and comminution processes. KAERI has also conducted all safety-related works such as the design and the fabrication of irradiation rig, the analysis of irradiation behavior, thermal hydraulic characteristics, stress analysis for irradiation rig, and thermal analysis fuel plate, for the mini-plate prepared by international research cooperation being irradiated safely at HANARO. Pressure drop test, vibration test and endurance test were performed. The characterization on powders of U-(5.4 {approx} 10 wt%) Mo alloy depending on Mo content prepared by rotating disk centrifugal atomization process was carried out in order to investigate the phase stability of the atomized U-Mo alloy system. The {gamma}-U phase stability and the thermal compatibility of atomized U-16at.%Mo and U-14at.%Mo-2at.%X(: Ru, Os) dispersion fuel meats at an elevated temperature have been investigated. The volume increases of U-Mo compatibility specimens were almost the same as or smaller than those of U{sub 3}Si{sub 2}. However the atomized alloy fuel exhibited a better irradiation performance than the comminuted alloy. The RERTR-3 irradiation test of nano

  2. Research reactor records in the INIS database

    International Nuclear Information System (INIS)

    This report presents a statistical analysis of more than 13,000 records of publications concerned with research and technology in the field of research and experimental reactors which are included in the INIS Bibliographic Database for the period from 1970 to 2001. The main objectives of this bibliometric study were: to make an inventory of research reactor related records in the INIS Database; to provide statistics and scientific indicators for the INIS users, namely science managers, researchers, engineers, operators, scientific editors and publishers, decision-makers in the field of research reactors related subjects; to extract other useful information from the INIS Bibliographic Database about articles published in research reactors research and technology. (author)

  3. Manual for the operation of research reactors

    International Nuclear Information System (INIS)

    The great majority of the research reactors in newly established centres are light-water cooled and are often also light-water moderated. Consequently, the IAEA has decided to publish in its Technical Reports Series a manual dealing with the technical and practical problems associated with the safe and efficient operation of this type of reactor. Even though this manual is limited to light-water reactors in its direct application and presents the practices and experience at one specific reactor centre, it may also be useful for other reactor types because of the general relevance of the problems discussed and the long experience upon which it is based. It has, naturally, no regulatory character but it is hoped that it will be found helpful by staff occupied in all phases of the practical operation of research reactors, and also by those responsible for planning their experimental use. 23 refs, tabs

  4. Performance of a multipurpose research electrochemical reactor

    Energy Technology Data Exchange (ETDEWEB)

    Henquin, E.R. [Programa de Electroquimica Aplicada e Ingenieria Electroquimica (PRELINE), Facultad de Ingenieria Quimica, Universidad Nacional del Litoral, Santiago del Estero 2829, S3000AOM Santa Fe (Argentina); Bisang, J.M., E-mail: jbisang@fiq.unl.edu.ar [Programa de Electroquimica Aplicada e Ingenieria Electroquimica (PRELINE), Facultad de Ingenieria Quimica, Universidad Nacional del Litoral, Santiago del Estero 2829, S3000AOM Santa Fe (Argentina)

    2011-07-01

    Highlights: > For this reactor configuration the current distribution is uniform. > For this reactor configuration with bipolar connection the leakage current is small. > The mass-transfer conditions are closely uniform along the electrode. > The fluidodynamic behaviour can be represented by the dispersion model. > This reactor represents a suitable device for laboratory trials. - Abstract: This paper reports on a multipurpose research electrochemical reactor with an innovative design feature, which is based on a filter press arrangement with inclined segmented electrodes and under a modular assembly. Under bipolar connection, the fraction of leakage current is lower than 4%, depending on the bipolar Wagner number, and the current distribution is closely uniform. When a turbulence promoter is used, the local mass-transfer coefficient shows a variation of {+-}10% with respect to its mean value. The fluidodynamics of the reactor responds to the dispersion model with a Peclet number higher than 10. It is concluded that this reactor is convenient for laboratory research.

  5. IAEA Guidelines for New Research Reactor Projects

    International Nuclear Information System (INIS)

    In recent years, the interest of the IAEA Member States in developing research reactor (RR) programmes has been steadily growing. Currently a number of Member States are in different stages of new research reactor projects. Some of these Member States are building their first research reactor as their country's introduction to nuclear science and technology infrastructure. To support Member States in such efforts, the IAEA published in 2012 a Nuclear Energy Series Report NP-T-5.1: 'Specific Considerations and Milestones for a New Research Reactor Project'. This publication provides guidance on the timely preparation of a research reactor project through a sequential development process. It includes a detailed description of the range of infrastructure issues that need to be addressed and the expected level of achievement (or milestones) at the end of each phase of the project. The publication provides a discussion of the mechanisms for justification of a research reactor, and for building stakeholder support. It includes both the technical, legal, regulatory and safety infrastructure, and the development of qualified human resources needed for a research reactor. The publication also addresses the evolution of infrastructure needs from the time a Member State first considers a research reactor and its associated facilities, through the stages of planning, bid preparation, construction, start-up, and preparation for commissioning. The subsequent stages of operation, decommissioning, spent fuel and waste management issues are addressed in the publication to the degree necessary for appropriate planning prior to research reactor commissioning. The feedback from the IAEA activities, in particular from Member States establishing their first research reactor, indicated the need for further guidance on the development of the technical specifications for the bidding process of a research reactor project. In responding to these needs, a Nuclear Energy Series Report on

  6. Education and Training on ISIS Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Foulon, F.; Badeau, G.; Lescop, B.; Wohleber, X. [French Atomic Energy and Alternative Energies Commission, Paris (France)

    2013-07-01

    In the frame of academic and vocational programs the National Institute for Nuclear Science and Technology uses the ISIS research reactor as a major tool to ensure a practical and comprehensive understanding of the nuclear reactor physics, principles and operation. A large set of training courses have been developed on ISIS, optimising both the content of the courses and the pedagogical approach. Programs with duration ranging from 3 hours (introduction to reactor operation) to 24 hours (full program for the future operators of research reactors) are carried out on ISIS reactor. The reactor is operated about 350 hours/year for education and training, about 40 % of the courses being carried out in English. Thus, every year about 400 trainees attend training courses on ISIS reactor. We present here the ISIS research reactor and the practical courses that have been developed on ISIS reactor. Emphasis is given to the pedagogical method which is used to focus on the operational and safety aspects, both in normal and incidental operation. We will present the curricula of the academic and vocational courses in which the practical courses are integrated, the courses being targeted to a wide public, including operators of research reactors, engineers involved in the design and operation of nuclear reactors as well as staff of the regulatory body. We address the very positive impact of the courses on the development of the competences and skills of participants. Finally, we describe the Internet Reactor Laboratories (IRL) that are under development and will consist in broadcasting the training courses via internet to remote facilities or institutions.

  7. Education and Training on ISIS Research Reactor

    International Nuclear Information System (INIS)

    In the frame of academic and vocational programs the National Institute for Nuclear Science and Technology uses the ISIS research reactor as a major tool to ensure a practical and comprehensive understanding of the nuclear reactor physics, principles and operation. A large set of training courses have been developed on ISIS, optimising both the content of the courses and the pedagogical approach. Programs with duration ranging from 3 hours (introduction to reactor operation) to 24 hours (full program for the future operators of research reactors) are carried out on ISIS reactor. The reactor is operated about 350 hours/year for education and training, about 40 % of the courses being carried out in English. Thus, every year about 400 trainees attend training courses on ISIS reactor. We present here the ISIS research reactor and the practical courses that have been developed on ISIS reactor. Emphasis is given to the pedagogical method which is used to focus on the operational and safety aspects, both in normal and incidental operation. We will present the curricula of the academic and vocational courses in which the practical courses are integrated, the courses being targeted to a wide public, including operators of research reactors, engineers involved in the design and operation of nuclear reactors as well as staff of the regulatory body. We address the very positive impact of the courses on the development of the competences and skills of participants. Finally, we describe the Internet Reactor Laboratories (IRL) that are under development and will consist in broadcasting the training courses via internet to remote facilities or institutions

  8. Reactor containment research and development

    Energy Technology Data Exchange (ETDEWEB)

    Weil, N. A.

    1963-06-15

    An outline is given of containment concepts, sources and release rates of energy, responses of containment structures, effects of projectiles, and leakage rates of radioisotopes, with particular regard to major reactor accidents. (T.F.H.)

  9. Replacement of outboard main steam isolation valves in a boiling water reactor plant

    Energy Technology Data Exchange (ETDEWEB)

    Schlereth, J.R.; Pennington, D.

    1996-12-01

    Most Boiling Water Reactor plants utilize wye pattern globe valves for main steam isolation valves for both inboard and outboard isolation. These valves have required a high degree of maintenance attention in order to pass the plant local leakage rate testing (LLRT) requirements at each outage. Northern States Power made a decision in 1993 to replace the outboard valves at it`s Monticello plant with double disc gate valves. The replacement of the outboard valves was completed during the fall outage in 1994. During the spring outage in April of 1996 the first LLRT testing was performed with excellent results. This presentation will address the decision process, time requirements and planning necessary to accomplish the task as well as the performance results and cost effectiveness of replacing these components.

  10. Replacement of outboard main steam isolation valves in a boiling water reactor plant

    International Nuclear Information System (INIS)

    Most Boiling Water Reactor plants utilize wye pattern globe valves for main steam isolation valves for both inboard and outboard isolation. These valves have required a high degree of maintenance attention in order to pass the plant local leakage rate testing (LLRT) requirements at each outage. Northern States Power made a decision in 1993 to replace the outboard valves at it's Monticello plant with double disc gate valves. The replacement of the outboard valves was completed during the fall outage in 1994. During the spring outage in April of 1996 the first LLRT testing was performed with excellent results. This presentation will address the decision process, time requirements and planning necessary to accomplish the task as well as the performance results and cost effectiveness of replacing these components

  11. Impact of proposed research reactor standards on reactor operation

    International Nuclear Information System (INIS)

    A Standards Committee on Operation of Research Reactors, (ANS-15), sponsored by the American Nuclear Society, was organized in June 1971. Its purpose is to develop, prepare, and maintain standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training. Of the 15 original members, six were directly associated with operating TRIGA facilities. This committee developed a standard for the Development of Technical Specifications for Research Reactors (ANS-15.1), the revised draft of which was submitted to ANSI for review in May of 1973. The Committee then identified 10 other critical areas for standards development. Nine of these, along with ANS-15.1, are of direct interest to TRIGA owners and operators. The Committee was divided into subcommittees to work on these areas. These nine areas involve proposed standards for research reactors concerning: 1. Records and Reports (ANS-15.3) 2. Selection and Training of Personnel (ANS-15.4) 3. Effluent Monitoring (ANS-15.5) 4. Review of Experiments (ANS-15.6) 5. Siting (ANS-15.7) 6. Quality Assurance Program Guidance and Requirements (ANS-15.8) 7. Restrictions on Radioactive Effluents (ANS-15.9) 8. Decommissioning (ANS-15.10) 9. Radiological Control and Safety (ANS-15.11). The present status of each of these standards will be presented, along with their potential impact on TRIGA reactor operation. (author)

  12. Research reactor utilization in chemistry programmes

    International Nuclear Information System (INIS)

    The establishment and roles of the Philippines Atomic Energy Commission in promoting and regulating the use of atomic energy are explained. The research reactor, PRR-1 is being converted to TRIGA to meet the increasing demands of high-flux. The activities of PAEC in chemistry research programs utilizing reactor are discussed in detail. The current and future plans of Research and Development programs are also included. (A.J.)

  13. MIT research reactor. Power uprate and utilization

    International Nuclear Information System (INIS)

    The MIT Research Reactor (MITR) is a university research reactor located on MIT campus. and has a long history in supporting research and education. Recent accomplishments include a 20% power rate to 6 MW and expanding advanced materials fuel testing program. Another important ongoing initiative is the conversion to high density low enrichment uranium (LEU) monolithic U-Mo fuel, which will consist of a new fuel element design and power increase to 7 MW. (author)

  14. Establishment of the Neutron Beam Research Facility at the OPAL Reactor

    International Nuclear Information System (INIS)

    Full text: Australia's first research reactor, HIFAR, reached criticality in January 1958. At that time Australia's main agenda was establishment of a nuclear power program. HIFAR operated for nearly 50 years, providing a firm foundation for the establishment of Australia's second generation research Reactor OPAL, which reached criticality in August 006. In HIFAR's early years a neutron beam facility was established for materials characterization, partly in aid of the nuclear energy agenda and partly in response to interest from Australia's scientific community. By the time Australia's nuclear energy program ceased (in the 1970s), radioisotope production and research had also been established at Lucas Heights. Also, by this time the neutron beam facility for scientific research had evolved into a major utilization programme, warranting establishment of an independent body to facilitate scientific access (the Australian Institute for Nuclear Science and Engineering). In HIFAR's lifetime, ANSTO established a radiopharmaceuticals service for the Australian medical community and NDT silicon production was also established and grew to maturity. So when time came to determine the strategy for nuclear research in Australia into the 21st century, it was clear that the replacement for HIFAR should be multipurpose, with major emphases on scientific applications of neutron beams and medical isotope production. With this strategy in mind, ANSTO set about to design and build OPAL with a world-class neutron beam facility, capable of supporting a large and diverse scientific research community. The establishment of the neutron beam facility became the mission of the Bragg Institute management team. This journey began in 1997 with establishment of a working budget, and reached its first major objective when OPAL reached 20 MW thermal power nearly one decade later (in 2006). The first neutron beam instruments began operation soon after (in 2007), and quickly proved themselves to be

  15. Safety of Ghana Research Reactor (GHARR-1)

    International Nuclear Information System (INIS)

    The Ghana Research Reactor, GHARR-1 is a low power research rector with maximum thermal power lever of 30kW. The reactor is inherently safe and uses highly enriched uranium (HEU) as fuel, light water as moderator and beryllium as a reflector. The construction, commissioning and operation of this reactor have been subjected to the system of authorization and inspection developed by the Regulatory Authority, the Radiation Protection Board (RPB) with the assistance of the International Atomic Energy Agency. The reactor has been regulated by the preparation of an Interim Safety Analysis Report (SAR) based upon International Atomic Energy Agency standards. An International Safety Assessment peer review and safe inspections have confirmed a high level of operational safety of the reactor since it started operation in 1994. Since its operation there has been no significant reported incident/accidents. Several studies have validated the inherent safety of the reactor. The reactor has been used for neutron activation analysis of various samples, research and teaching. About 1000 samples are analysed annually. The final Safety Analysis Report (SAR) was submitted (after five years of extensive research on the operational reactor) to the Regulatory Authority for review in June 2000. (author)

  16. Utilization of the SLOWPOKE-2 research reactor

    International Nuclear Information System (INIS)

    SLOWPOKEs are typically low power research reactors that have a limited number of applications. However, a significant range of NAA can be performed with such reactors. This paper describes a SLOWPOKE-based NAA program that is performing a valuable series of studies in Jamaica, including geological mapping and pollution assessment. (author)

  17. No small fry: Decommissioning research reactors

    International Nuclear Information System (INIS)

    To get a permit to build a research reactor, would-be operators need to submit an initial decommissioning plan for the eventual shutdown of their new facility. This, however, was not a requirement back in the 1950s, 60s and 70s when most research reactors that are now nearing the end of their working lives were built. The result: many unused reactors sit idle in the middle of university campuses, research parks and hospital compounds, because their operators lack the proper plans to decommission them

  18. Effective utilization and management of research reactors

    International Nuclear Information System (INIS)

    The problem of utilizing a research reactor effectively is closely related to its management and therefore should not be considered separately. Too often, attention has been focused on specific techniques and methods rather than on the overall programme of utilization, with the result that skills and equipment have been acquired without any active continuing programme of applications and services. The seminar reported here provided a forum for reactor managers, users, and operators to discuss their experience. At the invitation of the Government of Malaysia, it was held at the Asia Pacific Development Centre, Kuala Lumpur, from 7 to 11 November 1983. It was attended by about 50 participants from 19 Member States; it is hoped that a report on the seminar, including papers presented, can be published and thus reach a wider audience. Thirty-one lectures and contributions were presented at a total of seven sessions: Research reactor management; Radiation exposure and safety; Research reactor utilization (two sessions); PUSPATI Research Reactor Project Development; Core conversion to low-enriched uranium, and safeguards; Research reactor technology. In addition, a panel discussed the causes and resolutions of the under-utilization of research reactors

  19. The first university research reactor in India

    International Nuclear Information System (INIS)

    As the first university research reactor in India, the low power, pool type with fixed core and low enriched uranium fuel research reactor is under construction in the Andhra university campus, Andhra Pradesh, India. The reactor is expected to be commissioned during 2001-2002. The mission of the reactor is to play the research center as a regional research facility catering to the needs of academic institutions and industrial organizations of this region of the country. Further, to encourage interdisplinary and multidisplinary research activities, to supply radioisotope and labelled compounds to the user institutions and to create awareness towards the peaceful uses of atomic energy. This report describes its objectives, status and future plans in brief. (H. Itami)

  20. Gaseous fuel nuclear reactor research

    Science.gov (United States)

    Schwenk, F. C.; Thom, K.

    1975-01-01

    Gaseous-fuel nuclear reactors are described; their distinguishing feature is the use of fissile fuels in a gaseous or plasma state, thereby breaking the barrier of temperature imposed by solid-fuel elements. This property creates a reactor heat source that may be able to heat the propellant of a rocket engine to 10,000 or 20,000 K. At this temperature level, gas-core reactors would provide the breakthrough in propulsion needed to open the entire solar system to manned and unmanned spacecraft. The possibility of fuel recycling makes possible efficiencies of up to 65% and nuclear safety at reduced cost, as well as high-thrust propulsion capabilities with specific impulse up to 5000 sec.

  1. Higher power density TRIGA research reactors

    International Nuclear Information System (INIS)

    The uranium zirconium hydride (U-ZrH) fuel is the fundamental feature of the TRIGA family of reactors that accounts for its widely recognized safety, good performance, economy of operation, and its acceptance worldwide. Of the 65 TRIGA reactors or TRIGA fueled reactors, several are located in hospitals or hospital complexes and in buildings that house university classrooms. These examples are a tribute to the high degree of safety of the operating TRIGA reactor. In the early days, the majority of the TRIGA reactors had power levels in the range from 10 to 250 kW, many with pulsing capability. An additional number had power levels up to 1 MW. By the late 1970's, seven TRIGA reactors with power levels up to 2 MW had been installed. A reduction in the rate of worldwide construction of new research reactors set in during the mid 1970's but construction of occasional research reactors has continued until the present. Performance of higher power TRIGA reactors are presented as well as the operation of higher power density reactor cores. The extremely safe TRIGA fuel, including the more recent TRIGA LEU fuel, offers a wide range of possible reactor configurations. A long core life is assured through the use of a burnable poison in the TRIGA LEU fuel. In those instances where large neutron fluxes are desired but relatively low power levels are also desired, the 19-rod hexagonal array of small diameter fuel rods offers exciting possibilities. The small diameter fuel rods have provided extremely long and trouble-free operation in the Romanian 14 MW TRIGA reactor

  2. Decommissioning of the Neuherberg Research Reactor (FRN)

    International Nuclear Information System (INIS)

    The Neuherberg Research Reactor is of type TRIGA MARK III with 1 MW steady state power and pulsable up to 2000 MW. During more than ten years of operation 12000 MWh and 6000 reactor pulses had been performed. In spite of its good technical condition and of permanent safe operation without any failures, the decommissioning of the Neuherberg research reactor was decided by the GSF board of directors to save costs for maintaining and personnel. As the mode of decommissioning the safe enclosure was chosen which means that the fuel elements will be transferred back to the USA. All other radioactive reactor components will be enclosed in the reactor block. Procedures for licensing of the decommissioning, dismantling procedures and time tables are presented

  3. Conceptual design of multipurpose compact research reactor

    International Nuclear Information System (INIS)

    Conceptual design of the high-performance and low-cost multipurpose compact research reactor which will be expected to construct in the nuclear power plant introduction countries, started from 2010 in JAEA and nuclear-related companies in Japan. The aims of this conceptual design are to achieve highly safe reactor, economical design, high availability factor and advanced irradiation utilization. One of the basic reactor concept was determined as swimming pool type, thermal power of 10MW and water cooled and moderated reactor with plate type fuel element same as the JMTR. It is expected that the research reactors are used for human resource development, progress of the science and technology, expansion of industry use, lifetime extension of LWRs and so on. (author)

  4. Power Control Method for Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Baang, Dane; Suh, Yongsuk; Park, Cheol [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Considering safety-oriented design concept and other control environment, we developed a simple controller that provides limiting function of power change- rate as well as fine tracking performance. The design result has been well-proven via simulation and actual application to a TRIGA-II type research reactor. The proposed controller is designed to track the PDM(Power Demand) from operator input as long as maintaining the power change rate lower than a certain value for stable reactor operation. A power control method for a TRIGA-II type research reactor has been designed, simulated, and applied to actual reactor. The control performance during commissioning test shows that the proposed controller provides fine control performance for various changes in reference values (PDM), even though there is large measurement noise from neutron detectors. The overshoot at low power level is acceptable in a sense of reactor operation.

  5. Australian University Research Commercialisation: Perceptions of Technology Transfer Specialists and Science and Technology Academics

    Science.gov (United States)

    Harman, Grant

    2010-01-01

    Australian governments in recent years have invested substantially in innovation and research commercialisation with the aim of enhancing international economic competitiveness, making research findings more readily available to research users, and supporting economic and social development. Although there have been a number of evaluations of…

  6. Mentoring Australian Emerging Researchers in Aging: Evaluation of a Pilot Mentoring Scheme

    Science.gov (United States)

    Henwood, Tim; Bartlett, Helen; Carroll, Matthew

    2011-01-01

    A survey of Australian emerging researchers in aging identified the need for greater professional development and networking opportunities. To address this, a formal mentorship scheme was developed and evaluated. Fourteen postgraduate researchers (proteges) were matched by discipline and research interest to experienced academics (mentors).…

  7. The PALLAS research and isotope reactor project status

    International Nuclear Information System (INIS)

    In the European Union the first generation research reactors is nearing their end of life condition. Several committees recommend a comprehensive set of reactors in the EU, amongst them the replacement for the HFR research and isotope reactor in Petten: PALLAS. The business case for PALLAS supports a future for a research and isotope reactor in Petten as a perfect fit for the future EU set of test reactors. The tender for PALLAS started in 2007, following the EU rules for tendering complex objects with the competitive dialogue. This procedure involved an extensive consultation phase between individual tendering companies and NRG, resulting in definitive specifications in summer 2008. The evaluation of offers, including conceptual designs, took place in summer 2009. At present NRG is still active in the acquisition of the funding for the project. The licensing path has been started in autumn 2009 with a initiation note on the environmental impact assessment, EIA. The public hearings held in the lead to the advice from the national EIA committee for the approach of the assessment. The PALLAS project team in Petten will guide the design and build processes. It is also responsible for the licensing of the building and operation of PALLAS. The team also manages the design and construction for the infrastructure, such as cooling devices, including remnant heat utilization, and utility provisions. A particular responsibility for the team is the design and construction of experimental and isotope capsules, based on launch customer requirements. (author)

  8. Technical specifications: Health Physics Research Reactor

    International Nuclear Information System (INIS)

    These technical specifications define the key limitations that must be observed for safe operation of the Health Physics Research Reactor (HPRR) and an envelope of operation within which there is assurance that these limits will not be exceeded

  9. Refurbishment of research reactor IRT in Sofia

    International Nuclear Information System (INIS)

    A decommissioning strategy of the research reactor IRT-Sofia is subjected to a refurbishment into critical assembly is presented. The main stages in the planning and management of a partial decommissioning are exposed. (author)

  10. ANSTO: Australian Nuclear Science and Technology Organization

    International Nuclear Information System (INIS)

    The Australian Nuclear Science and Technology Organization conducts or is engaged in collaborative research and development in the application of nuclear science and associated technology. Through its Australian radio-isotopes unit, it markets radioisotopes, their products and other services for nuclear medicine industry and research. It also operates national nuclear facilities ( HIFAR and Moata research reactors), promote training, provide advice and disseminates information on nuclear science and technology. The booklet briefly outlines these activities. ills

  11. Problems and experience of research reactor decommissioning

    International Nuclear Information System (INIS)

    According to the IAEA research reactor database there are about 300 research reactors worldwide. At present above 30% of them have lifetime more than 35 years, 60% - more then 25 years. After the Chernobyl accident significant efforts have been made by many countries to modernize old research reactors aiming, first of all, at ensuring of its safe operation. However, a large number of aging research reactor will be facing shutdown in the near future. Before developing the design and planning of the works it is necessary to define the concept of the reactor decommissioning. It is defined by the time of the beginning of dismantling works after the reactor shutdown and the finite state of the reactor site.The concept of the reactor decommissioning provides 3 variants in a general case: reactor conservation, or partial dismantling, or complete dismantling to 'green field' state. Specialists of three International institutions (European Commission, IAEA and the Nuclear Energy Agency/Organization for Economic Cooperation and Development) have developed a detailed plan of all actions and operations on nuclear power plants decommissioning in the framework of a joint project for cost assessment. For the reactor decontamination the following main constructions, equipment and devices are necessary: temporary storage facility for the spent fuel; general site-dismantling equipment including manipulators and 'hot' cells; facilities for 'active' equipment, personnel, tooling and washing decontamination; equipment for concentration of liquid and compactness of solid radioactive waste; temporary storage facility for radioactive waste; instrumentation and radiometric devices including , α,β,γ-spectrometers; transportable containers and other means for transportation of fuel and radioactive materials

  12. Research reactor coalitions - Second year progress report

    International Nuclear Information System (INIS)

    The IAEA, in line with its statute and mandatory responsibilities to support its member states in the promotion of peaceful uses of nuclear energy, has an initiative to promote the formation of coalitions of research reactor operators and stakeholders. These networks of research reactors are conducting joint research or other shared activities, have the potential to increase research reactor utilization and thus to improve sustainability at the same time enhancing nuclear material security and non-proliferation objectives. This effort builds upon existing IAEA efforts to enhance research reactor strategic planning, to encourage formation of research reactor networks, and to promote regional and international cooperation between research reactors. The paper will describe the Agency's progress in the second year of activities to assist in the formation of research reactor coalitions. The paper will describe the Agency's efforts in serving a catalytic and 'match-making' role for the formation of new the coalition relationships, and its activities in organizing various missions and meetings for exploratory and organizational discussions on possible coalitions and networks. The paper presents the concrete progress that has been made during the past year, including new coalitions in Eastern Europe, the Caribbean, Latin America and Central Asia. These coalitions cover a wide range of activities, for example, enhancing the regional infrastructure and capabilities for neutron sciences, developing new supplies of medicinal radioisotopes, and expanding the reach of reactor physics training courses. The paper also outlines the path forward that has been established for 2009 to support these coalitions as they mature and develop toward self-sufficiency. (author)

  13. Nuclear Research Center IRT reactor dynamics calculation

    International Nuclear Information System (INIS)

    The main features of the code DIRT, for dynamical calculations are described in the paper. With the results obtained by the program, an analysis of the dynamic behaviour of the Research Reactor IRT of the Nuclear Research Center (CIN) is performed. Different transitories were considered such as variation of the system reactivity, coolant inlet temperature variation and also variations of the coolant velocity through the reactor core. 3 refs

  14. Safety review, assessment and inspection on research reactors, experimental reactors, nuclear heating reactors and critical facilities

    International Nuclear Information System (INIS)

    In 1998, the NNSA organized to complete the nuclear safety review on the test loop in-reactor operation of the High-flux Engineering Experimental Reactor (HFEER) and the re-operation of the China Pulsed Reactor and the Uranium-water Criticality Facility. The NNSA conducted the nuclear safety review on the CP application of the China Experimental Fast Reactor (CEFR) and the siting of China Advanced Research Reactor (CARR), and carried out the construction supervision on HTR-10, and dealt with the event about the technological tube breakage of HWRR and other events

  15. Current status and prospects of research reactors

    International Nuclear Information System (INIS)

    Full text: The first nuclear research reactors (RR) appeared in the 1940s. Their initial purpose was to provide knowledge of the main processes associated with neutron-induced nuclear reactions. Later, the rang of problems addressed expanded substantially. Besides fundamental research in the properties of matter, such reactors are successfully used for dealing with problems in the fields of materials science, nuclear engineering, medicine, isotope production, education, etc. Over the whole period of RR fleet growth, more than six hundred nuclear research facilities were built in 70 countries of the world. As of the end of 2008, the number of Russian research reactors in service was about 20% of the globally operating RR fleet. This paper discusses the current status of the world's RR fleet and describes the capabilities of the experimental reactor facilities existing in Russia. In the 21st century, research reactors will remain in demand to solve scientific and technological problems for innovative development of society. The emerging renaissance of nuclear power, the expanding RR uses for production of isotopes and other applications, the increase in the number of countries willing to use nuclear technologies in energy production, industry and science - all contribute to a rebirth of interest in research reactors. One of the ways to improve the experimental capabilities lies in radical upgrading of the reactor facilities with qualitative changes in the main neutronic characteristics of the core. The associated design approaches are illustrated with the example of the IBR-2M reactor at the JNRI in Dubna. The imperative need restricting the spread of nuclear threat leads us to give up using highly enriched uranium in most research reactors. Development of RR fuel with reduced enrichment in uranium has been one of the priority objectives of NIKIET for many years. This paper presents the latest results obtained along these lines, as applied to pool-type research

  16. Current status and prospects of research reactors

    International Nuclear Information System (INIS)

    Full text: The first nuclear research reactors (RR) appeared in the 1940s. Their initial purpose was to provide knowledge of the main processes associated with neutron-induced nuclear reactions. Later, the range of problems addressed expanded substantially. Besides fundamental research in the properties of matter, such reactors are successfully used for dealing with problems in the fields of materials science, nuclear engineering, medicine, isotope production, education, etc. Over the whole period of RR fleet growth, more than six hundred nuclear research facilities were built in 70 countries of the world. As of the end of 2008, the number of Russian research reactors in service was about 20% of the globally operating RR fleet. This paper discusses the current status of the world's RR fleet and describes the capabilities of the experimental reactor facilities existing in Russia. In the 21st century, research reactors will remain in demand to solve scientific and technological problems for innovative development of society. The emerging renaissance of nuclear power, the expanding RR uses for production of isotopes and other applications, the increase in the number of countries willing to use nuclear technologies in energy production, industry and science - all contribute to a rebirth of interest in research reactors. One of the ways to improve the experimental capabilities lies in radical upgrading of the reactor facilities with qualitative changes in the main neutronic characteristics of the core. The associated design approaches are illustrated with the example of the IBR-2M reactor at the JNRI in Dubna. The imperative need for restricting the spread of nuclear threat leads us to give up using highly enriched uranium in most research reactors. Development of RR fuel with reduced enrichment in uranium has been one of the priority objectives of NIKIET for many years. This paper presents the latest results obtained along these lines, as applied to pool-type research

  17. The reactor and cold neutron research facility at NIST

    International Nuclear Information System (INIS)

    The NIST Reactor (NBSR) is a 20 MW research reactor located at the Gaithersburg, MD site, and has been in operation since 1969. It services 26 thermal neutron facilities which are used for materials science, chemical analysis, nondestructive evaluation, neutron standards work, and irradiations. In 1987 the Department of Commerce and NIST began development of the CNRF - a $30M National Facility for cold neutron research -which will provide fifteen new experimental stations with capabilities currently unavailable in this country. As of May 1992, four of the planned seven guides and a cold port were installed, eight cold neutron experimental stations were operational, and the Call for Proposals for the second cycle of formally-reviewed guest-researcher experiments had been sent out. Some details of the performance of instrumentation are described, along with the proposed design of the new hydrogen cold source which will replace the present D2O/H2O ice cold source. (author)

  18. [Replacing of residue from production of palm Palm Royal Australian (Archontophoenix alexan- drae) in silage of sugar cane in diets of sheep].

    Science.gov (United States)

    Bayão, Geraldo Fábio Viana; Queiroz, Augusto César de; Freitas, Samuel Galvão de; Batalha, Camila Delveaux Araujo; Sousa, Katiene Régia Silva; Pimentel, Róberson Machado; Cardoso, Lucas Ladeira; Cardoso, Alex Junio da Silva

    2014-12-01

    The aim of this study was to evaluate the chemical composition, voluntary intake and apparent digestibility of the diets containing residue from palm heart of Australian Royal Palm (Archontophoenix alexandrae) to replace sugar cane on sheep. Twelve sheep were used with average live weight of 23.3 ± 2.8 Kg and they placed in metabolism cages and distributed in six latin square 2 x 2 in a factorial design 3 x 2 (three types of residue--sheet, bark and composed--and two levels of residue's replacement, 5% and 15%). It was observed higher intake of dry matter (DM), organic matter (OM), nonfiber carbohydrates (NFC) by substitution of composed residue. The average values of apparent digestibility of DM, OM, crude protein (CP), neutral detergent fibre correct for ash and protein (NDFap) and total digestible nutrients (TDN) were higher for sheet residue. There was interaction between type of residue and level of residue's replacement on the urinary excretion of total nitrogen (NUE), apparent nitrogen balance (BNA) and microbial nitrogen compost (NMIC). Residues from palm heart of Australian Royal Palm can be used as roughage in the ruminants'diet, and of these residues, the sheet and composed residue showed better response in the evaluated characteristics. PMID:26336723

  19. Supply of enriched uranium for research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, H. [NUKEM GmbH, Alzenau (Germany)

    1997-08-01

    Since the RERTR-meeting In Newport/USA in 1990 the author delivered a series of papers in connection with the fuel cycle for research reactors dealing with its front-end. In these papers the author underlined the need for unified specifications for enriched uranium metal suitable for the production of fuel elements and made proposals with regard to the re-use of in Europe reprocessed highly enriched uranium. With regard to the fuel cycle of research reactors the research reactor community was since 1989 more concentrating on the problems of its back-end since the USA stopped the acceptance of spent research reactor fuel on December 31, 1988. Now, since it is apparent that these back-end problem have been solved by AEA`s ability to reprocess and the preparedness of the USA to again accept physically spent research reactor fuel the author is focusing with this paper again on the front-end of the fuel cycle on the question whether there is at all a safe supply of low and high enriched uranium for research reactors in the future.

  20. Research nuclear reactor RA - Annual Report 1997

    International Nuclear Information System (INIS)

    RA reactor is not in operation since 1984, activities related to revitalisation of the RA reactor started in 1986. The planned actions related to renewal of the reactor components were finished except for the most important action, related to exchange of complete reactor instrumentation which was delayed. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the sanctions imposed to our country. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 42 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1997 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection

  1. Research nuclear reactor RA - Annual Report 1996

    International Nuclear Information System (INIS)

    Activities related to revitalisation of the RA reactor started in 1986, were continued in 1996. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 43 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1996 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection

  2. Status of Research Reactor Utilization in Brazil

    International Nuclear Information System (INIS)

    Brazil has four research reactors in operation: the IEA-R1, a pool type research reactor of 5 MW; the IPR-R1, a TRIGA Mark I type research reactor of 100 kW; the ARGONAUTA, an Argonaut type research reactor of 500 W; and the IPEN/MB-01 a critical facility of 100 W. Research reactor utilization has more than fifty years in Brazil. The first three reactors, constructed in the late 50's and early 60's at university campus in Sao Paulo, Belo Horizonte and Rio de Janeiro, had their utilization for training, teaching and nuclear research. The IPEN/MB-01, designed and constructed in IPEN in the late 80's, is utilized for the development and qualification of reactor physics calculation for PWR core application. The IEA-R1 has had its application and utilization increased through the years and it is presently used for radioisotope production, neutron beam application, neutrongraphy, neutron activation analysis, and limited fuel and material irradiation tests, besides the regular use for training and teaching. The low power of the reactor and the lack of hot cells for post irradiation analysis limits its technical application for the nuclear fuel industry. Brazil has two nuclear power plants in operation, one unit starting construction and four more units planned for the next two decades. Brazil has significant quantities of uranium ore and has expertise in all the fuel cycle steps, including uranium enrichment, and produces the fuel assemblies for the nuclear power plants. These industrial activities demand the need of material and fuel irradiation tests. IPEN produces radiopharmaceutical kits for the treatment of more than three million patients each year. The majority of the radiopharmaceutical kits is produced from imported radioisotopes. The increasing price and shortage of world supply of 99mTc leads also to the need of increasing the radioisotope production in Brazil. Due to these new demands, the Brazilian Nuclear Energy Commission is analyzing the costs and benefits

  3. Utilization of the Research Reactor ASTRA

    International Nuclear Information System (INIS)

    A short history and an overview over present research activities at the 10 MW Pool Type Reactor ASTRA of the Austrian Research Centre Seibersdorf are given. The projects comprise: medical and industrial isotope production, material irradiations (e.g. silicon doping), neutron activation analysis, geological dating and radiation induced mutation techniques for agricultural research. (author)

  4. Material test reactor fuel research at the BR2 reactor

    International Nuclear Information System (INIS)

    The construction of new, high performance material test reactor or the conversion of such reactors' core from high enriched uranium (HEU) to low enriched uranium (LEU) based fuel requires several fuel qualification steps. For the conversion of high performance reactors, high density dispersion or monolithic fuel types are being developed. The Uranium-Molybdenum fuel system has been selected as reference system for the qualification of LEU fuels. For reactors with lower performance characteristics, or as medium enriched fuel for high performance reactors, uranium silicide dispersion fuel is applied. However, on the longer term, the U-Mo based fuel types may offer a more efficient fuel alternative and-or an easier back-end solution with respect to the silicide based fuels. At the BR2 reactor of the Belgian nuclear research center, SCK-CEN in Mol, several types of fuel testing opportunities are present to contribute to such qualification process. A generic validation test for a selected fuel system is the irradiation of flat plates with representative dimensions for a fuel element. By flexible positioning and core loading, bounding irradiation conditions for fuel elements can be performed in a standard device in the BR2. For fuel element designs with curved plates, the element fabrication method compatibility of the fuel type can be addressed by incorporating a set of prototype fuel plates in a mixed driver fuel element of the BR2 reactor. These generic types of tests are performed directly in the primary coolant flow conditions of the BR2 reactor. The experiment control and interpretation is supported by detailed neutronic and thermal-hydraulic modeling of the experiments. Finally, the BR2 reactor offers the flexibility for irradiation of full size prototype fuel elements, as 200mm diameter irradiation channels are available. These channels allow the accommodation of various types of prototype fuel elements, eventually using a dedicated cooling loop to provide the

  5. FoR Codes Pendulum: Publishing Choices within Australian Research Assessment

    Science.gov (United States)

    Bennett, Dawn; Genoni, Paul; Haddow, Gaby

    2011-01-01

    This paper reports on an exploratory case study that considered the impacts of journal ranking and Fields of Research codes on the publishing decisions of Australian authors. The study also considered the level of alignment between authors' allocation of Fields of Research codes and the codes assigned to the journals in which they were published.…

  6. Co-managing public research in Australian fisheries through convergence–divergence processes

    NARCIS (Netherlands)

    Dentoni, D.; Klerkx, L.W.A.

    2015-01-01

    The participation of the industry in public research has been found essential to stimulate innovation in fisheries, but the actual design and implementation of co-management of fisheries research is still a critical and open topic. Based on the evidence of 35 project cases in Australian fisheries, t

  7. Thermal hydraulic analysis of nuclear research reactors

    International Nuclear Information System (INIS)

    A loss of coolant accident (LOCA) can cause total or partial core uncovery which is followed by substantial fuel element temperature increase due to fuel residual heat. It is essential to demonstrate that such a temperature increase does not lead to excessive core melting and to significant radioactive material release into the reactor building and consequently to the environment. The THEAP computer codes able to perform reliable analysis of such accidents have been developed. THEAP-I is a computer code developed with the aim to contribute to the safety analysis of the MTR open pool research reactors. THEAP-I is designed for three dimensional, transient thermal/hydraulic analysis of a thermally interacting channel bundle totally immersed into water or air, such as the reactor core. The mathematical and physical models and methods of the solution are given as well as the code description and the input data. A sample problem is included, referring to the Greek Research Reactor analysis, under a hypothetical severe loss of coolant accident. The micro computer version of the code is also described. More emphasis is given in the new features of the code (i.e. input data structure). A set of instructions for running in an IBM-AT2 computer with the microsoft FORTRAN V4.0 is included together with a sample problem referring to the Greek Research Reactor. THEAP-I can be used also for other MTR open pool research reactors. Refs and figs

  8. Description of the Korean multipurpose research reactor

    International Nuclear Information System (INIS)

    The Korean Multipurpose Research Reactor (KMRR) was still under construction at the time of the conference, and was scheduled for completion in 1994. It has since been completed. Owned by Korean Atomic Energy Research Institute (KAERI), KMRR is designed for fuel and materials testing, production of key nuclides (including 99Mo, 131I, 192Ir, 60Co, and transmutation doped Si), neutron activation analysis, and neutron radiography. KMRR is a 30 MWth open pool type research reactor, with a forced upward light water moderator and coolant flow, and a heavy water annular reflector. The fuel is made from low-enriched U-Si-Al alloy, with finned aluminum cladding. Two configurations of fuel bundle have been designed, namely, hexagonal 36 element and circular 18 element. The reactor has seven tangential beam tubes, the position of which has been carefully selected to maximize thermal neutron flux while minimizing fast neutrons and gamma. Heat is transported to two heat exchangers by the primary coolant circuit, and thence by the secondary coolant circuit to a set of cooling towers. The reactor regulating system has two stepping motors that drive four hafnium control rods. The control functions are performed by two redundant programmable controllers. The reactor protection system is equipped with four hafnium shutoff rods driven by a fail-safe hydraulic circuit. The design of KMRR uses leading edge technology, and it might well figure among the best multipurpose research reactors in the world. 5 figs., 1 tab

  9. Operational and research activities of Tsing Hua open pool reactor

    International Nuclear Information System (INIS)

    Tsing Hua Open Pool Reaction (THOR) is the first nuclear reactor to become operational in Taiwan. It reached its first critical on April 13, 1961. Until now, THOR has been operated successfully for 27 years. The major missions of THOR include radioisotope production, neutron activation analysis, nuclear science and engineering researches, education, and personnel training. The THOR was originally loaded with HEU MTR-type fuels. A gradual fuel replacing program using LEU TRIGA fuel to replace MTR started in 1977. By 1987, THOR was loaded with all TRIGA fuels. This paper gives a brief history of THOR, its current status, the core conversion work, some selected research topics, and its improvement plan. (author)

  10. Status report of Indonesian research reactor

    International Nuclear Information System (INIS)

    A general description of three Indonesian research reactor, its irradiation facilities and its future prospect are described. Since 1965 Triga Mark II 250 KW Bandung, has been in operation and in 1972 the design powers were increased to 1000 KW. Using core grid form Triga 250 KW BATAN has designed and constructed Kartini Reactor in Yogyakarta which started its operation in 1979. Both of this Triga type reactors have served a wide spectrum of utilization such as training manpower in nuclear engineering, radiochemistry, isotope production and beam research in solid state physics. Each of this reactor have strong cooperation with Bandung Institute of Technology at Bandung and Gajah Mada University at Yogyakarta which has a faculty of Nuclear Engineering. Since 1976 the idea to have high flux reactor has been foreseen appropriate to Indonesian intention to prepare infrastructure for nuclear industry for both energy and non-energy related activities. The idea come to realization with the first criticality of RSG-GAS (Multipurpose Reactor G.A. Siwabessy) in July 1987 at PUSPIPTEK Serpong area. It is expected that by early 1992 the reactor will reached its full power of 30 MW and by end 1992 its expected that irradiation facilities will be utilized in the future for nuclear scientific and engineering work. (author)

  11. Research reactor spent fuel management in Argentina

    International Nuclear Information System (INIS)

    The research reactor spent fuel (RRSF) management strategy will be presented as well as the interim storage experience. Currently, low-enriched uranium RRSF is in wet interim storage either at reactor site or away from reactor site in a centralized storage facility. High-enriched uranium RRSF from the centralized storage facility has been sent to the USA in the framework of the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The strategy for the management of the RRSF could implement the encapsulation for interim dry storage. As an alternative to encapsulation for dry storage some conditioning processes are being studied which include decladding, isotopic dilution, oxidation and immobilization. The immobilized material will be suitable for final disposal. (author)

  12. BNCT activities at Slovenian TRIGA research reactor

    International Nuclear Information System (INIS)

    It has been reported that satisfactory thermal/epithermal neutron beams for Boron Neutron Capture Therapy (BNCT) could be designed at TRIGA research reactors These reactors are generally perceived as being safe to install and operate in populated areas. This contribution presents the most recent BNCT research activities on the 'Jozef Stefan' Institute, where epithermal neutron beam for 'in-vitro' irradiation has been developed and experimentally verified. Furthermore, The Monte Carlo feasibility study of development of the epithermal neutron beam for BNCT clinical trials of human patients in thermalising column (TC) of TRIGA reactor has been carried out. The simulation results prove, that a BNCT irradiation facility with performances, comparable to existing beam throughout the world, could be installed in TC of the TRIGA reactor. (author)

  13. Nuclear reactor safety research in Kazakhstan

    International Nuclear Information System (INIS)

    Full text : The paper summarizes activities being implemented by the National Nuclear Center of the Republic of Kazakhstan in support of safe operation of nuclear reactors; shows its crucial efforts and further road map in this line. As is known, the world community considers nuclear reactor safety as one of the urgent research areas. Kazakhstan has been pursuing studies in support of nuclear energy safety since early 80s. The findings allow to coordinate available computational methods and design new ones while validating new NPP Projects and making analysis for reactor installations available

  14. Experiments of fuzzy logic control ion a nuclear research reactor

    International Nuclear Information System (INIS)

    The application of a fuzzy logic control scheme is presented in order to improve the power system stability of BR1 (Belgian Reactor 1) at the Belgian Nuclear Research Centre (SCK-CEN). The control scheme is developed based on OMRON's fuzzy hardware (C200H-FZ001) and the Fuzzy Support Software (FSS) because of their high performance and flexibility. The various possibilities are discussed to find the best or optimal fuzzy logic control scheme for controlling BR1. On basis of the previous researches 1,2,3, some experiments have been carried out in both the steady-state and dynamic operation conditions. The results reveal that the fuzzy logic control scheme has the potential to replace nuclear reactor operators in the control room. Hence, the entire control process can be automatic, simple and effective

  15. Making better use of research reactors

    International Nuclear Information System (INIS)

    Some 250 research reactors are in operation in the world today, and there are problems in putting them to the most fruitful use. The difficulties - of trained manpower, of auxiliary equipment, of satisfactory research programmes, of co-ordination, between the various disciplines - are common to all users. But as is only to be expected, they press more heavily on the newly-established centres, particularly those in the developing countries which are lacking in long experience in research and usually severely limited as to technical manpower and money. The IAEA has been turning its attention to this question for the past three or four years - ever since, in fact, its early assistance missions and other field operations brought it into close contact with the operations of numerous Member States. The task of providing assistance and advice in this matter is growing. Many centres have been building research reactors under bilateral arrangements; with the completion of their projects this form of aid usually ends, and they look to IAEA for help in operating the reactors. Although some critics consider that difficulties have been caused by premature construction of research reactors, before well-founded programmes of nuclear research had been developed in the countries concerned, several valid motives have led to the establishment of some of these centres at an early stage. A research reactor often provides an effective stimulant for scientific research in the country. It is a remarkably versatile tool for workers in many fields of science and technology. There have been instances where the establishment of a research reactor has had a great impact on the scientific education of a country and has led to a salutary reappraisal and reforms. A reactor is sometimes considered to be a particularly effective means of retaining in the country men trained in the nuclear field. This particular problem is common to most countries. In fact, it is a feature of the present age that

  16. Research on plasma core reactors

    Science.gov (United States)

    Jarvis, G. A.; Barton, D. M.; Helmick, H. H.; Bernard, W.; White, R. H.

    1976-01-01

    Experiments and theoretical studies are being conducted for NASA on critical assemblies with one-meter diameter by one-meter long low-density cores surrounded by a thick beryllium reflector. These assemblies make extensive use of existing nuclear propulsion reactor components, facilities, and instrumentation. Due to excessive porosity in the reflector, the initial critical mass was 19 kg U(93.2). Addition of a 17 cm thick by 89 cm diameter beryllium flux trap in the cavity reduced the critical mass to 7 kg when all the uranium was in the zone just outside the flux trap. A mockup aluminum UF6 container was placed inside the flux trap and fueled with uranium-graphite elements. Fission distributions and reactivity worths of fuel and structural materials were measured. Finally, an 85,000 cu cm aluminum canister in the central region was fueled with UF6 gas and fission density distributions determined. These results are to be used to guide the design of a prototype plasma core reactor which will test energy removal by optical radiation.

  17. RA-10: A New Argentinian Multipurpose Research Reactor

    International Nuclear Information System (INIS)

    A new multipurpose research reactor to replace RA-3 reactor has been decided to be built in Argentina to satisfy the increasing national and regional demands for radioisotopes. The project, supported by the National Administration, has started in 2010 and is planned to be operative in 2018. The expertise acquired in the country, in the design and licensing of nuclear reactors, encourage the National Atomic Energy Commission (CNEA) to face the challenge. INVAP S.E. is involved in the design and construction of the reactor facility and related installations, playing the role of main contractor. The RA-10 is a 30 MW thermal power reactor and is designed to achieve high performance neutrons production to fulfill the stakeholder's requirements in compliance with stringent safety regulations. The principal objectives of the facility are: to consolidate and increase the radioisotope production in order to cover future demands, to provide fuel and material testing irradiation facilities to support national technology development on this field, to offer new applications in the field of science and technology based on modern neutron techniques. The reactor is an open-pool facility with a compact core with MTR (Material Testing Reactor) low enriched uranium (LEU) fuel assemblies consisting of uranium silicide fuel plates, cladded in aluminum. Reactivity control is performed by hafnium plates. A heavy water reflector tank surrounds the core. It provides a high thermal neutron flux adequate to house irradiation facilities. A diverse and independent shutdown system is engineered through its drainage. The fundamental safety objective of the design is the radiological protection of the public, the personnel and the environment and consequently the design is based in three main principles: responsibility in safety management, defense-in-depth and safety features. Engineered Safety Features are provided which are capable of maintaining the reactor in a safe condition under all

  18. RMB. The new Brazilian multipurpose research reactor

    International Nuclear Information System (INIS)

    Brazil has four research reactors (RR) in operation: IEA-R1, a 5 MW pool type RR; IPR-R1, a 100 kW TRIGA type RR; ARGONAUTA, a 500 W Argonaut type RR, and IPEN/MB-01, a 100 W critical facility. The first three were constructed in the 50's and 60's, for teaching, training, and nuclear research, and for many years they were the basic infrastructure for the Brazilian nuclear developing program. The last, IPEN/MB-01, is the result of a national project developed specifically for qualification of reactor physics codes. Considering the relative low power of Brazilian research reactors, with exception of IEAR1, none of the other reactors are feasible for radioisotope production, and even IEA-R1 has a limited capacity. As a consequence, since long ago, 100% of the Mo-99 needed to attend Brazilian nuclear medicine services has been imported. Because of the high dependence on external supply, the international Moly-99 supply crisis that occurred in 2008/2009 affected significantly Brazilian nuclear medicine services, and as presented in previous IAEA events, in 2010 Brazilian government formalized the decision to build a new research reactor. The new reactor named RMB (Brazilian Multipurpose Reactor) will be a 30 MW open pool type reactor, using low enriched uranium fuel. The facility will be part of a new nuclear research centre, to be built about 100 kilometres from Sao Paulo city, in the southern part of Brazil. The new nuclear research centre will have several facilities, to use thermal and cold neutron beams; to produce radioisotopes; to perform neutron activation analysis; and to perform irradiations tests of materials and fuels of interest for the Brazilian nuclear program. An additional facility will be used to store, for at least 100 years, all the fuel used in the reactor. The paper describes the main characteristics of the new centre, emphasising the research reactor and giving a brief description of the laboratories that will be constructed, It also presents the

  19. RMB. The new Brazilian multipurpose research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Perrotta, Jose Augusto; Soares, Adalberto Jose [Comissao Nacional de Energia Nuclear (CNEN) (Brazil)

    2015-01-15

    Brazil has four research reactors (RR) in operation: IEA-R1, a 5 MW pool type RR; IPR-R1, a 100 kW TRIGA type RR; ARGONAUTA, a 500 W Argonaut type RR, and IPEN/MB-01, a 100 W critical facility. The first three were constructed in the 50's and 60's, for teaching, training, and nuclear research, and for many years they were the basic infrastructure for the Brazilian nuclear developing program. The last, IPEN/MB-01, is the result of a national project developed specifically for qualification of reactor physics codes. Considering the relative low power of Brazilian research reactors, with exception of IEAR1, none of the other reactors are feasible for radioisotope production, and even IEA-R1 has a limited capacity. As a consequence, since long ago, 100% of the Mo-99 needed to attend Brazilian nuclear medicine services has been imported. Because of the high dependence on external supply, the international Moly-99 supply crisis that occurred in 2008/2009 affected significantly Brazilian nuclear medicine services, and as presented in previous IAEA events, in 2010 Brazilian government formalized the decision to build a new research reactor. The new reactor named RMB (Brazilian Multipurpose Reactor) will be a 30 MW open pool type reactor, using low enriched uranium fuel. The facility will be part of a new nuclear research centre, to be built about 100 kilometres from Sao Paulo city, in the southern part of Brazil. The new nuclear research centre will have several facilities, to use thermal and cold neutron beams; to produce radioisotopes; to perform neutron activation analysis; and to perform irradiations tests of materials and fuels of interest for the Brazilian nuclear program. An additional facility will be used to store, for at least 100 years, all the fuel used in the reactor. The paper describes the main characteristics of the new centre, emphasising the research reactor and giving a brief description of the laboratories that will be constructed, It also

  20. Determination of research reactor fuel burnup

    International Nuclear Information System (INIS)

    This report was prepared by a Consultants Group which met during 12-15 June 1989 at the Jozef Stefan Institute, Yugoslavia, and during 11-13 July 1990 at the IAEA Headquarters in Vienna, Austria, with subsequent contributions from the Consultants. The report is intended to provide information to research reactor operators and managers on the different, most commonly used methods of determining research reactor fuel burnup: 1) reactor physics calculations, 2) measurement of reactivity effects, and 3) gamma ray spectrometry. The advantages and disadvantages of each method are discussed. References are provided to assist the reactor operator planning to establish a programme for burnup determination of fuel. Destructive techniques are not included since such techniques are expensive, time consuming, and not normally performed by the reactor operators. In this report, TRIGA fuel elements are used in most examples to describe the methods. The same techniques however can be used for research reactors which use different types of fuel elements. 22 refs, 13 figs, 2 tabs

  1. An Ageing Management Programme for the SAFARI-1 Research Reactor

    International Nuclear Information System (INIS)

    The SAFARI-1 Research Reactor is a 20 MW high flux material test reactor and has been continuously operational for nearly 47 years. In this period, ageing of the facility has been addressed by means of various, mainly reactive, maintenance and upgrade initiatives to replace components that have become unmaintainable for various reasons such as wear, corrosion and obsolescence. With the facility now approaching 50 years of continuous operation, a programme has been implemented to assess, address and implement ageing management in a more formal and proactive manner. The programme conforms to the recently published IAEA Safety Guide SSG-10 Ageing Management for Research Reactors and makes extensive use of the guidelines set therein as well as other tools and methods developed in various international meetings and workshops at the IAEA for identifying ageing issues at the facility. The paper presents an outline of the methodology for implementing the ageing management programme at the SAFARI-1 research reactor. Identification of SSCs important to the safety and sustainability of the facility that are susceptible to ageing, the ageing mechanisms affecting them and the remedial actions identified to mitigate or remove the effects of ageing are discussed. A methodology for determining priorities is also elaborated. Remedial actions are divided into four groups: safety critical, mission critical, lifetime extension and organizational, and an implementation strategy is described. (author)

  2. Status report of Indonesian research reactors

    International Nuclear Information System (INIS)

    A general description of the three Indonesia research reactors, their irradiation facilities and future prospect are given. The 250 kW Triga Mark II in Bandung has been in operation since 1965 and in 1972 its designed power was increased to 1000 kW. The core grid from the previous 250 kW Triga Mark II was then used by Batan for designing and constructing the Kartini reactor in Yogyakarta. This reactor commenced its operation in 1979. Both Triga reactors have served a wide spectrum of utilization such as for manpower training in nuclear engineering, radiochemistry, isotope production, and beam research in solid state physics. The Triga reactor management in Bandung has a strong cooperation with the Bandung Institute of Technology and the one in Yogyakarta with the Gadjah Mada University which has a Nuclear Engineering Department at its Faculty of Engineering. In 1976 there emerged an idea to have a high flux reactor appropriate for Indonesia's intention to prepare an infrastructure for both nuclear energy and non-energy industry era. Such an idea was then realized with the achievement of the first criticality of the RSG-GAS reactor at the Serpong area. It is now expected that by early 1992 the reactor will reach its full 30 MW power level and by the end of 1992 the irradiation facilities be utilizable fully for future scientific and engineering work. As a part of the national LEU fuel development program a study has been underway since early 1989 to convert the RSG-GAS reactor core from using oxide fuel to using higher loading silicide fuel. (author)

  3. Safety requirements applied to research reactors in France

    International Nuclear Information System (INIS)

    , the safety requirements in this case are the resistance and leaktightness of the pool and the resistance of the containment building to the water column and overpressure due to this accident. A number of tests were performed to validate the safety demonstrations relating to these issues for the above-mentioned reactors. These tests were particularly aimed at: checking the mechanical strength of the pool structures in the event of a BORAX accident; determining the operating limits of the fuels used; examining the impact on the core of a pressurized irradiation loop rupture; validating the design of clad failure detection systems. The safety reviews systematically performed at the request of the safety authority, for reactors that have been in operation for more than 10 years have not called into question the above-mentioned safety requirements. The main requests of the safety authority following the assessments made by the IRSN and presented to the standing group of experts for the nuclear reactors have concerned the need for upgrading the facilities to take into account in particular the evolutions of the requirements relating to internal and external hazards. In particular, this has led to facilities being reinforced to increase their earthquake resistance, and to improvements concerning fire protection and the management of post-accident situations. The aging of facilities has been addressed by gradually refurbishing their equipment and replacing their instrumentation, their control and protection systems and those structures affected by high radiation doses. The operating experience feedback acquired from existing research reactors, the evolution of certain safety requirements, and the progress achieved in the methodology adopted for the study of research reactor safety have been taken into account in the design of the new RJH reactor (P = 100 MW) which is planned to be constructed in the Cadarache site. The final paper will provide the detailed presentation of the

  4. RRFM (European Research Reactor Conference) 2011 Transactions

    International Nuclear Information System (INIS)

    The RRFM conference is an international forum for researchers, operators and decision-makers to discuss all significant aspects of Research Reactor utilisation. In order to improve operational efficiency and fuel safety and contribute to the search for back-end solutions for spent fuel

  5. Event management in research reactors

    International Nuclear Information System (INIS)

    In the Radiological and Nuclear Safety field, the Nuclear Regulatory Authority of Argentina controls the activities of three investigation reactors and three critical groups, by means of evaluations, audits and inspections, in order to assure the execution of the requirements settled down in the Licenses of the facilities, in the regulatory standards and in the documentation of mandatory character in general. In this work one of the key strategies developed by the ARN to promote an appropriate level of radiological and nuclear safety, based on the control of the administration of the abnormal events that its could happen in the facilities is described. The established specific regulatory requirements in this respect and the activities developed in the entities operators are presented. (Author)

  6. Thermal reactor safety CNEN research programs

    International Nuclear Information System (INIS)

    A review of CNEN (National Committee for Nuclear Energy, Italy) programs in the field of thermal reactor safety research is given. The ASCOT program (research program on safety aspects of thermal reactor cores) is briefly described. ASCOT is a program aiming at studying fuel behavior under accident conditions; it is mainly focused on development and experimental testing of analytical models and computer codes relevant to thermohydraulic and mechanical behavior of fuel under transient conditions. The program, fully financed by CNEN, is carried out in CNEN laboratories, in CISE laboratories (particularly for thermohydraulic experiments) and in JRC Ispra Centre (in pile experiments, by ESSOR reactor). Other CNEN research programs in the field of water reactor safety are also described; they concern thermohydraulics and mechanics problems (model development and experimental tests on pressure suppression, ECCS, etc.) and are performed both in CNEN laboratories and in other Italian organizations, under CNEN sponsorship. A short description of some facilities used for ASCOT and other CNEN programs is given: SARA loop (a loop of ESSOR reactor, basically conceived for safety tests, including operation with failed fuel rods); CIRCE and IETI loops (CISE, large-scale facilities for thermohydraulic experiments on blow-down, ECCS, etc.); ADI (a CNEN, large-scale loop where pressure suppression experiments are performed), and so on. Finally, the report describes interesting safety researches on various types of reactors: researches on external events (seismology, etc.), radioactive effluent control (e.g., filtration, effects to environment); these researches also are carried out directly in CNEN laboratories or in other Italian organizations, under CNEN sponsorship. Information is given on a national seismological network and on other installations for these experimental researches

  7. Advanced fuel in the Budapest research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hargitai, T.; Vidovsky, I. [KFKI Atomic Energy Research Inst., Budapest (Hungary)

    1997-07-01

    The Budapest Research Reactor, the first nuclear facility of Hungary, started to operate in 1959. The main goal of the reactor is to serve neutron research, but applications as neutron radiography, radioisotope production, pressure vessel surveillance test, etc. are important as well. The Budapest Research Reactor is a tank type reactor, moderated and cooled by light water. After a reconstruction and upgrading in 1967 the VVR-SM type fuel elements were used in it. These fuel elements provided a thermal power of 5 MW in the period 1967-1986 and 10 MW after the reconstruction from 1992. In the late eighties the Russian vendor changed the fuel elements slightly, i.e. the main parameters of the fuel remained unchanged, however a higher uranium content was reached. This new fuel is called VVR-M2. The geometry of VVR-SM and VVR-M2 are identical, allowing the use to load old and new fuel assemblies together to the active core. The first new type fuel assemblies were loaded to the Budapest Research Reactor in 1996. The present paper describes the operational experience with the new type of fuel elements in Hungary. (author)

  8. EURATOM research framework programmes on reactor systems

    Energy Technology Data Exchange (ETDEWEB)

    Deffrennes, M.; Hugon, M.; Manolatos, P.; Van Goethem, G.; Webster, S. [European Commission, DG Research J2 Nuclear Fission and Radiation Protection CDMA 1/55, Brussels (Belgium)

    2007-07-01

    The activities of the European Commission (EC) in the field of nuclear energy are governed by the Treaty establishing the European Atomic Energy Community (EURATOM). The research activities of the European Union (EU) are designed as multi-annual Framework Programmes (FP) managed by the European Commission. The EURATOM Research and Training Programmes cover both nuclear Fusion and Fission. EURATOM-FP6 supports the following projects: -) NULIFE project: Nuclear Plant Life Prediction; -) COVERS project: VVER Safety Research; -) PERFECT project: Prediction of Irradiation Damage Effects on Reactor Components; -) NURESIM project: European Platform for Nuclear Reactor Simulations; -)EC-SARNET project: Sustainable Integration of European Research on Severe Accident Phenomenology; -) RAPHAEL project: Reactor for Process Heat, Hydrogen and Electricity Generation; -)GCFR project: Gas-Cooled Fast Reactor; -) EUROTRANS project: Transmutation of HLW in ADS; -) JHR-CA project: Jules Horowitz Reactor Co-ordination Action; and NEPTUNO project: Nuclear European Platform of Training and University Organisations. Other parts of the EURATOM FP, covering Waste Management and Radiation Protection, as well as Fusion Energy, are not detailed in this paper.

  9. EURATOM research framework programmes on reactor systems

    International Nuclear Information System (INIS)

    The activities of the European Commission (EC) in the field of nuclear energy are governed by the Treaty establishing the European Atomic Energy Community (EURATOM). The research activities of the European Union (EU) are designed as multi-annual Framework Programmes (FP) managed by the European Commission. The EURATOM Research and Training Programmes cover both nuclear Fusion and Fission. EURATOM-FP6 supports the following projects: -) NULIFE project: Nuclear Plant Life Prediction; -) COVERS project: VVER Safety Research; -) PERFECT project: Prediction of Irradiation Damage Effects on Reactor Components; -) NURESIM project: European Platform for Nuclear Reactor Simulations; -)EC-SARNET project: Sustainable Integration of European Research on Severe Accident Phenomenology; -) RAPHAEL project: Reactor for Process Heat, Hydrogen and Electricity Generation; -)GCFR project: Gas-Cooled Fast Reactor; -) EUROTRANS project: Transmutation of HLW in ADS; -) JHR-CA project: Jules Horowitz Reactor Co-ordination Action; and NEPTUNO project: Nuclear European Platform of Training and University Organisations. Other parts of the EURATOM FP, covering Waste Management and Radiation Protection, as well as Fusion Energy, are not detailed in this paper

  10. Performance of a multipurpose research electrochemical reactor

    International Nuclear Information System (INIS)

    Highlights: → For this reactor configuration the current distribution is uniform. → For this reactor configuration with bipolar connection the leakage current is small. → The mass-transfer conditions are closely uniform along the electrode. → The fluidodynamic behaviour can be represented by the dispersion model. → This reactor represents a suitable device for laboratory trials. - Abstract: This paper reports on a multipurpose research electrochemical reactor with an innovative design feature, which is based on a filter press arrangement with inclined segmented electrodes and under a modular assembly. Under bipolar connection, the fraction of leakage current is lower than 4%, depending on the bipolar Wagner number, and the current distribution is closely uniform. When a turbulence promoter is used, the local mass-transfer coefficient shows a variation of ±10% with respect to its mean value. The fluidodynamics of the reactor responds to the dispersion model with a Peclet number higher than 10. It is concluded that this reactor is convenient for laboratory research.

  11. Decommissioning of the Salaspils Research Reactor

    Directory of Open Access Journals (Sweden)

    Abramenkovs Andris

    2011-01-01

    Full Text Available In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor and to dispense with nuclear energy in the future. The reactor has been out of operation since July 1998. A conceptual study on the decommissioning of the Salaspils Research Reactor was drawn up by Noell-KRC-Energie- und Umwelttechnik GmbH in 1998-1999. On October 26th, 1999, the Latvian government decided to start the direct dismantling to “green-field” in 2001. The upgrading of the decommissioning and dismantling plan was carried out from 2003-2004, resulting in a change of the primary goal of decommissioning. Collecting and conditioning of “historical” radioactive wastes from different storages outside and inside the reactor hall became the primary goal. All radioactive materials (more than 96 tons were conditioned for disposal in concrete containers at the radioactive wastes depository “Radons” at the Baldone site. Protective and radiation measurement equipment of the personnel was upgraded significantly. All non-radioactive equipment and materials outside the reactor buildings were released for clearance and dismantled for reuse or conventional disposal. Contaminated materials from the reactor hall were collected and removed for clearance measurements on a weekly basis.

  12. Corrosion Minimization for Research Reactor Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Eric Shaber; Gerard Hofman

    2005-06-01

    Existing university research reactors are being converted to use low-enriched uranium fue to eliminate the use of highly-enriched uranium. These conversions require increases in fuel loading that will result in the use of elements with more fuel plates, resulting in a net decrease in the water annulus between fuel plates. The proposed decrease in the water annulus raises questions about the requirements and stability of the surface hydroxide on the aluminum fuel cladding and the potential for runaway corrosion resulting in fuel over-temperature incidents. The Nuclear Regulatory Commission (NRC), as regulator for these university reactors, must ensure that proposed fuel modifications will not result in any increased risk or hazard to the reactor operators or the public. This document reviews the characteristics and behavior of aluminum hydroxides, analyzes the drivers for fuel plate corrosion, reviews relevant historical incidents, and provides recommendations on fuel design, surface treatment, and reactor operational practices to avoid corrosion issues.

  13. Research nuclear reactor RA - Annual report 1992

    International Nuclear Information System (INIS)

    Research reactor RA Annual report for year 1992 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. Second annex B is a paper by Z. Vukadin 'Recurrence formulas for evaluating expansion series of depletion functions' published in 'Kerntechnik' 56, (1991) No.6 (INIS record no. 23024136. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data

  14. Research nuclear reactor RA, Annual Report 2001

    International Nuclear Information System (INIS)

    During 2001, activities at the RA research nuclear reactor in were performed according to the Contract about financing of the RA reactor for the period January-December 2001, signed by the Ministry of Science, technology and development of the Republic of Serbia. RA reactor was not operated since shutdown in August 1984. Although, the most of the planned reconstruction activities were finished until 1991, the most important, which was concerned with exchange of the reactor instrumentation, financed by the IAEA, was interrupted due to international sanctions imposed on the country. Since 1992, all the renewal and reconstruction activities were ceased. Continuous aging and degradation of the equipment and facilities demand decision making about the future status of the Ra reactor. Until this decision is made it is an obligation to maintain control and maintenance of ventilation system, power supply, internal transportation system, spent fuel storage, hot cells, electronic fuel surveillance system, and part of the stationary dosimetry system. In 2001, apart from the mentioned activities, actions were undertaken related to maintenance of the reactor building and installations. The most important tasks fulfilled were: protection of the roof of the ventilation system building, purchase and installing the fire protection system and twelve new battery cells in the reactor building. There were no actions concerned with improvement of the conditions for intermediate spent fuel storage. With the support of IAEA, actions were initiated for possible transport of the spent fuel tu Russia. At the end of 2001, preparations were started for possible future decommissioning of the RA reactor. After, renewal of the membership of our country in the IAEA, the Government of Yugoslavia has declared its attitude about the intention of RA reactor decommissioning at the General Conference in September 2001

  15. Research nuclear reactor RA - Annual Report 1994

    International Nuclear Information System (INIS)

    Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Activities related to improvement of Russian project were continued in 1994. Control and maintenance of the reactor components was done regularly and efficiently. Extensive repair of the secondary coolant loop is almost finished and will be completed in the first part of 1995 according to existing legal procedures and IAEA recommendations. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 47 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection

  16. Defining Educational Research: A Perspective of/on Presidential Addresses and the Australian Association for Research in Education

    Science.gov (United States)

    Lingard, Bob; Gale, Trevor

    2010-01-01

    This paper is concerned with the definition of the field of educational research and the changing and developing role of the Australian Association for Research in Education (AARE) in representing and constituting this field. The evidence for the argument is derived from AARE Presidential Addresses across its 40-year history. The paper documents…

  17. Research and development in oil spill response: The Australian view

    International Nuclear Information System (INIS)

    Significant oil spill events in Australia are, fortunately, infrequent events. In recent years, the 33,000 dwt tonne phosphate carrier Sanko Harvest grounded and broke up losing all of its 740 tonnes of fuel oil bunkers off the small south west port of Esperance. Since that incident only one further casualty has occurred, that of the tanker KIRKI which lost some 18,000 tonnes of its crude oil cargo when the fore part of the vessel broke away and sank in heavy seas and subsequently during the tow to quieter waters off the north west coast of Australia. Whilst public interest in oil spills, when they occur, is understandably high, the national government budget for response to ship sourced marine oil spills is in proportion to assessment of the risk and approximates $Aus 2 million annually. The Australian Maritime Safety Authority (AMSA), is the Federal authority under whose responsibility revenue for the Federal/State arrangement, known as the National Plan to Combat Pollution of the Sea by Oil, is managed. This revenue is obtained directly from the shipping industry in the form of a small tax known as the oil pollution levy. Funds from this source are allocated to the States nationally for purchase of spill response equipment and approved dispersants, production of coastal resource atlases, training programs, maintenance and administration of the National Plan. It will be readily understood that a relatively small budget precludes all but the smallest of R ampersand D programs. Most spills occur in waters over which an Australian state has jurisdiction and are generally managed by state administrations using equipment and decision support resources provided by AMSA

  18. Experience at SAPHIR Research Reactor, Switzerland

    International Nuclear Information System (INIS)

    The former SAPHIR research reactor has been dismantled completely without any significant difficulty. There are several factors underpinning the successful dismantling of SAPHIR: – Good housekeeping during operation and after shutdown; – Good maintenance of the infrastructure before and after shutdown; – Experienced personnel with knowledge of the reactor history; – Stable legal framework; – Close cooperation with the regulatory authority; – Excellent infrastructure of a large research centre; – Stable financing; – Stable organization, motivated personnel; – Support from skilful local companies; – Waste conditioning and treatment routes on-site and approved by the regulatory authority

  19. United States Domestic Research Reactor Infrastructure - TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The purpose of the United State Domestic Research Reactor Infrastructure Program is to provide fresh nuclear reactor fuel to United States universities at no, or low, cost to the university. The title of the fuel remains with the United States government and when universities are finished with the fuel, the fuel is returned to the United States government. The program is funded by the United States Department of Energy - Nuclear Energy division, managed by Department of Energy - Idaho Field Office, and contracted to the Idaho National Laboratory's Management and Operations Contractor - Battelle Energy Alliance. Program has been at Idaho since 1977 and INL subcontracts with 26 United States domestic reactor facilities (13 TRIGA facilities, 9 plate fuel facilities, 2 AGN facilities, 1 Pulstar fuel facility, 1 Critical facility). University has not shipped fuel since 1968 and as such, we have no present procedures for shipping spent fuel. In addition: floor loading rate is unknown, many interferences must be removed to allow direct access to the reactor tank, floor space in the reactor cell is very limited, pavement ends inside our fence; some of the surface is not finished. The whole approach is narrow, curving and downhill. A truck large enough to transport the cask cannot pull into the lot and then back out (nearly impossible / refused by drivers); a large capacity (100 ton), long boom crane would have to be used due to loading dock obstructions. Access to the entrance door is on a sidewalk. The campus uses it as a road for construction equipment, deliveries and security response. Large trees are on both sides of sidewalk. Spent fuel shipments have never been done, no procedures approved or in place, no approved casks, no accident or safety analysis for spent fuel loading. Any cask assembly used in this facility will have to be removed from one crane, moved on the floor and then attached to another crane to get from the staging area to the reactor room. Reactor

  20. Australian Council for Educational Research. Fifty-first Annual Report, 1980-81.

    Science.gov (United States)

    Australian Council for Educational Research, Hawthorn.

    The introduction to this annual report traces the history, activities, and growth of the Australian Council for Educational Research (ACER), and notes future challenges facing ACER. Abstracts are presented of seven papers which were delivered at the Invitational Conference on Societal Change held in August l980 at the University of Melbourne.…

  1. Preparing for Portfolio Careers in Australian Music: Setting a Research Agenda

    Science.gov (United States)

    Bartleet, Brydie-Leigh; Bennett, Dawn; Bridgstock, Ruth; Draper, Paul; Harrison, Scott; Schippers, Huib

    2012-01-01

    In the twenty-first century, Australian musicians increasingly maintain "portfolio" careers, in which they combine diverse employment arrangements and activities. Often, these incorporate industry sectors outside of music. This career pattern is widespread but not well understood, largely because of the limitations of existing research. The lack…

  2. Irradiation testing of miniature fuel plates for the RERTR program. [Reduced Enrichment Research and Test Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Senn, R.L.; Martin, M.M.

    1981-07-01

    An irradiation test facility, which provides a test bed for irradiating a variety of miniature fuel plates (miniplates) for the Reduced Enrichment Research and Test Reactors (RERTR) program, has been placed into operation. These tests screen various candidate fuel materials on their suitability for replacing the highly enriched uranium fuel materials currently used by the world's test and research reactors with a lower enrichment fuel material, without significantly degrading reactor operating characteristics and power levels. The use of low uranium enrichment of about 20% /sup 235/U in place of highly enriched fuel for these reactors would reduce the potential for /sup 235/U diversion. The irradiation test facility, designated as HFED, is operating in core position E-7 in the Oak Ridge Research Reactor (ORR), a 30-MW water-moderated reactor. The miniplates will achieve burnups of up to approx. 2.2 x 10/sup 27/ fissions/m/sup 3/ of fuel.

  3. Research reactors: a tool for science and medicine

    International Nuclear Information System (INIS)

    The types and uses of research reactors are reviewed. After an analysis of the world situation, the demand of new research reactors of about 20 MW is foreseen. The experience and competitiveness of INVAP S.E. as designer and constructor of research reactors is outlined and the general specifications of the reactors designed by INVAP for Egypt and Australia are given

  4. Fuel-failure detection system for Pakistan Research Reactor-1

    Energy Technology Data Exchange (ETDEWEB)

    Ayazuddin, S.K.; Hayat, Tariq; Qureshi, A.A.; Khan, H.A. [Pakistan Inst. of Nuclear Science and Technology, Nuclear Engineering Div., Islamabad (Pakistan)

    1997-12-01

    After the conversion and upgrading of Pakistan Research Reactor-1 (PARR-1), it was decided to install a fuel-failure detection system to confirm the performance and integrity of the new fuel elements. The fuel-failure detection is based on monitoring of delayed neutrons emitted from fission products leaking into the primary coolant loop from the fuel. For this purpose, two neutron detectors (BF{sub 3}) were replaced in the graphite moderator blocks that were installed at the outlet coolant pipe in the valve pit. The fuel-failure detection system was tested and calibrated at a miniature neutron source reactor (PARR-2) which provided the basis for alarm limits setting in the event of fuel failure. (author).

  5. Fuel-failure detection system for Pakistan Research Reactor-1

    International Nuclear Information System (INIS)

    After the conversion and upgrading of Pakistan Research Reactor-1 (PARR-1), it was decided to install a fuel-failure detection system to confirm the performance and integrity of the new fuel elements. The fuel-failure detection is based on monitoring of delayed neutrons emitted from fission products leaking into the primary coolant loop from the fuel. For this purpose, two neutron detectors (BF3) were replaced in the graphite moderator blocks that were installed at the outlet coolant pipe in the valve pit. The fuel-failure detection system was tested and calibrated at a miniature neutron source reactor (PARR-2) which provided the basis for alarm limits setting in the event of fuel failure. (author)

  6. Integrative Research in the University Context: Centre for Resource and Environmental Studies, The Australian National University

    OpenAIRE

    Robert J Wasson; Stephen Dovers

    2005-01-01

    At a time of increasing interest and advocacy in integrated and policy-oriented research, this paper offers an empirically-based view of the intellectual and practical challenges of undertaking such research. It analyses the experience of a long-standing university research and postgraduate training centre from 1973-2004: the Centre for Resource and Environmental Studies at The Australian National University. The paper discusses staff development issues, cross-disciplinary understanding, orga...

  7. Ranking of Australian Economics Departments Based on Their Total and Per Academic Staff Research Output

    OpenAIRE

    Joan R. Rodgers; Valadkhani, Abbas

    2005-01-01

    This study uses cluster analysis to classify twenty-seven Australian economics teaching departments into groups that have similar quantities of research output, measured by two different publication counts, and similar quality of research output, measured by a citation count. Three distinct groups of departments are identified and factor analysis is used to rank the groups. Whether research output is measured in total or on a per staff basis, Melbourne is in the group that ranks first, the re...

  8. Fuel behavior comparison for a research reactor

    Science.gov (United States)

    Negut, Gh.; Mladin, M.; Prisecaru, I.; Danila, N.

    2006-06-01

    The paper presents the behavior and properties analysis of the low enriched uranium fuel, which will be loaded in the Romanian TRIGA 14 MW steady state research reactor compared with the original high enriched uranium fuel. The high and low enriched uranium fuels have similar thermal properties, but different nuclear properties. The research reactor core was modeled with both fuel materials and the reactor behavior was studied during a reactivity insertion accident. The thermal hydraulic analysis results are compared with that obtained from the safety analysis report for high enriched uranium fuel core. The low enriched uranium fuel shows a good behavior during reactivity insertion accident and a revised safety analysis report will be made for the low enriched uranium fuel core.

  9. Fuel behavior comparison for a research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Negut, Gh. [Institute for Nuclear Research (ICN), 1, Campului Street, P.O. Box 78, 0300 Mioveni, Pitesti (Romania)]. E-mail: joenegut@yahoo.com; Mladin, M. [Institute for Nuclear Research (ICN), 1, Campului Street, P.O. Box 78, 0300 Mioveni, Pitesti (Romania); Prisecaru, I. [University Politehnica Bucharest (Romania); Danila, N. [University Politehnica Bucharest (Romania)

    2006-06-30

    The paper presents the behavior and properties analysis of the low enriched uranium fuel, which will be loaded in the Romanian TRIGA 14 MW steady state research reactor compared with the original high enriched uranium fuel. The high and low enriched uranium fuels have similar thermal properties, but different nuclear properties. The research reactor core was modeled with both fuel materials and the reactor behavior was studied during a reactivity insertion accident. The thermal hydraulic analysis results are compared with that obtained from the safety analysis report for high enriched uranium fuel core. The low enriched uranium fuel shows a good behavior during reactivity insertion accident and a revised safety analysis report will be made for the low enriched uranium fuel core.

  10. Research reactor instrumentation and control technology. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    The majority of research reactors operating today were put into operation 20 years ago, and some of them underwent modifications, upgrading and refurbishing since their construction to meet the requirements for higher neutron fluxes. However, a few of these ageing research reactors are still operating with their original instrumentation and control systems (I and C) which are important for reactor safety to guard against abnormal occurrences and reactor control involving startup, shutdown and power regulation. Worn and obsolete I and C systems cause operational problems as well as difficulties in obtaining replacement parts. In addition, satisfying the stringent safety conditions laid out by the nuclear regulatory bodies requires the modernization of research reactors I and C systems and integration of additional instrumentation units to the reactor. In order to clarify these issues and to provide some guidance to reactor operators on state-of-art technology and future trends for the I and C systems for research reactors, a Technical Committee Meeting on Technology and Trends for Research Reactor Instrumentation and Controls was held in Ljubljana, Slovenia, from 4 to 8 December 1995. This publication summarizes the discussions and recommendations resulting from that meeting. This is expected to benefit the research reactor operators planning I and C improvements. Refs, figs, tabs

  11. Research nuclear reactor RA - Annual Report 1991

    International Nuclear Information System (INIS)

    Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Construction of some support elements is almost finished by the local staff. The Institute has undertaken this activity in order to speed up the ending of the project. If all the planned instrumentation would not arrive until the end of March 1992, it would not be possible to start the RA reactor testing operation in the first part of 1993, as previously planned. In 1991, 53 staff members took part in the activities during 1991, which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection

  12. Proceedings of the Conference on research reactors application in Yugoslavia

    International Nuclear Information System (INIS)

    The Conference on research reactors operation was organised on the occasion of 20 anniversary of the RB zero power reactor start-up. The presentations showed that research reactors in Yugoslavia, RB, RA and TRIGA had an important role in development of nuclear sciences and technology in Yugoslavia. The reactors were applied in non-destructive testing of materials and fuel elements, development of reactor noise techniques, safety analyses, reactor control methods, neutron activation analysis, neutron radiography, dosimetry, isotope production, etc

  13. Neutronics conceptual design of the innovative research reactor core using uranium molybdenum fuel

    International Nuclear Information System (INIS)

    The multipurpose of research reactor utilization make many countries build the new research reactor. Trend of this reactor for this moment is multipurpose reactor type with a compact core to get high neutron flux at the low or medium level of power. The research newest. Reactor in Indonesia right now is already 25 year old. Therefore, it is needed to design a new research reactor, called innovative research reactor (IRR) and then as an alternative to replace the old research reactor. The aim of this research is to get the optimal configuration of equilibrium core with the acceptance criteria are minimum thermal neutron flux is 2.5E14 n/cm2 s at the power level of 20 MW (minimum), length of cycle of more than 40 days, and the most efficient of using fuel in the core. Neutronics design has been performed for new fuel of U-9Mo-AI with various fuel density and reflector. Design calculation has been performed using WIMSD-5B and BATAN-FUEL computer codes. The calculation result of the conceptual design shows four core configurations namely 5x5, 5x7, 6x5 and 6x6. The optimalization result for equilibrium core of innovative research reactor is the 5x5 configuration with 450 gU fuel loading, berilium reflector, maximum thermal neutron flux at reflector is 3.33E14 n/cm2 sand length of cycle is 57 days is the most optimal of IRR. (author)

  14. Technical specifications: Health Physics Research Reactor

    International Nuclear Information System (INIS)

    The technical specifications define the key limitations that must be observed for safe operation of the Health Physics Research Reactor (HPRR) and an envelope of operation within which there is assurance that these limits will not be exceeded. The specifications were written to satisfy the requirements of the Department of Energy (DOE) Manual Chapter 0540, September 1, 1972

  15. Fast reactor systems for deep sea research

    International Nuclear Information System (INIS)

    Fast reactor (FR) systems have been studied as power units for unmanned bases and research submersibles to monitor various phenomena and as a thermal source for the unmanned base to feed useful microorganisms in the deep sea region. The systems, which are set in pressure hulls, comprise of the FR's and secondary gas loops. Concepts and arrangements of the systems are presented. (author)

  16. Safety status of Russian research reactors

    International Nuclear Information System (INIS)

    Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety at nuclear research facilities, including research reactors, critical assemblies and sub-critical assemblies. It implies implementing three major activities: 1) establishing the laws and safety standards in the field of research reactors nuclear and radiation safety; 2) research reactors licensing; and 3) inspections (or license conditions tracking and inspection). The database on nuclear research facilities has recently been updated based on the actual status of all facilities. It turned out that many facilities have been shutdown, whether temporary or permanently, waiting for the final decision on their decommissioning. Compared to previous years the situation has been inevitably changing. Now we have 99 nuclear research facilities in total under Gosatomnadzor of Russia supervision (compared to 113 in previous years). Their distribution by types and operating organizations is presented. The licensing and conduct of inspection processes are briefly outlined with emphasis being made on specific issues related to major incidents that happened in 2000, spent fuel management, occupational exposure, effluents and emissions, emergency preparedness and physical protection. Finally, a summary of problems at current Russian research facilities is outlined. (author)

  17. Current status of restoration work for obstacle and upper core structure in reactor vessel of experimental fast reactor 'JOYO'. 2. Replacement of upper core structure

    International Nuclear Information System (INIS)

    In the experimental fast reactor Joyo, it was confirmed that the top of the irradiation test sub-assembly of MARICO-2 (material testing rig with temperature control) had bent onto the in-vessel storage rack as an obstacle and had damaged the upper core structure (UCS) in 2007. As a part of the restoration work, UCS replacement was begun at March 24, 2014 and was completed at December 17. In-vessel repair (including observation) for sodium-cooled fast reactors (SFRs) is distinct from that for light water reactors and necessitates independent development. Application of developed in-vessel repair techniques to operation and maintenance of SFRs enhanced their safety and integrity. There is little UCS replacement experience in the world and this experience and insights, which were accumulated in the replacement work of in-vessel large structure (UCS) used for more than 30 years, are expected to improve the in-vessel repair techniques in SFRs. (author)

  18. Condition of research reactor spent nuclear fuel in wet storage

    International Nuclear Information System (INIS)

    The condition of spent nuclear fuel (SNF) in wet storage at ten Soviet-designed research reactors has been assessed in the light of international experience in order to identify any associated safety issues. These reactors use Al-clad UO2-Al or U-Al alloy dispersion fuels of ≥20% enrichment that were fabricated in Russia; the reactors have been in operation since 1955-70. Although originally sent for reprocessing, much of the SNF generated over the last 25-30 years has been stored in fuel storage pools (FSPs) of variable water quality. The external condition of wet-stored SNF assemblies from the reactors surveyed varied from significant failure due to galvanic corrosion that was driven by poor water quality, through gradual pitting caused by slightly impure water, to a stable condition of no observable change in the oxidized Al alloy surface of the irradiated fuel. SNF stability in wet storage seems to depend on three factors: Al being the sole metal in the FSP (to avoid galvanic action); good water chemistry to suppress attack of the oxide layer by aggressive ions like Cl-, and gentle handling to limit physical damage to the oxide layer. If one of these factors is not satisfied, SNF degradation will take place; if more than one factor is not satisfied, failure of the Al cladding may occur. In general, however, even SNF failure in wet storage does not appear to raise significant safety concerns. A possible exception is where galvanic corrosion combined with poor water quality has caused massive fuel failure, as at the RA reactor in Belgrade. A potential safety problem was identified at reactors where unalloyed Al liners had been used in the FSPs. Unlike SNF that develops a protective oxide layer in-reactor, these Al liners were unprotected and prone to significant corrosion during an ill-defined early period of poor water quality. The risk of losing water from FSPs due to liner failure should be evaluated for all research reactors. Where the risk of FSP failure

  19. Condition of research reactor spent nuclear fuels in wet storage

    International Nuclear Information System (INIS)

    Full text: The condition of spent nuclear fuel (SNF) in wet storage at ten Soviet-designed research reactors has been assessed in the light of international experience in order to identify any associated safety issues. These reactors use Al-clad UO2-Al or U-Al alloy dispersion fuels of ≥20% enrichment that were fabricated in Russia; the reactors have been in operation since 1955-70. Although originally sent for reprocessing, much of the SNF generated over the last 25-30 years has been stored in fuel storage pools (FSPs) of variable water quality. The external condition of wet-stored SNF assemblies from the reactors surveyed varied from significant failure due to galvanic corrosion that was driven by poor water quality, through gradual pitting caused by slightly impure water, to a stable condition of no observable change in the oxidized Al alloy surface of the irradiated fuel. SNF stability in wet storage seems to depend on three factors: Al being the sole metal in the FSP (to avoid galvanic action); good water chemistry to suppress attack of the oxide layer by aggressive ions like Cl-, and gentle handling to limit physical damage to the oxide layer. If one of these factors is not satisfied, SNF degradation will take place; if more than one factor is not satisfied, failure of the Al cladding may occur. In general, however, even SNF failure in wet storage does not appear to raise significant safety concerns. A possible exception is where galvanic corrosion combined with poor water quality has caused massive fuel failure, as at the RA reactor in Belgrade. A potential safety problem was identified at reactors where unalloyed Al liners had been used in the FSPs. Unlike SNF that develops a protective oxide layer in-reactor, these Al liners were unprotected and prone to significant corrosion during an ill-defined early period of poor water quality. The risk of losing water from FSPs due to liner failure should be evaluated for all research reactors. Where the risk of

  20. Safety upgrades to the NRU research reactor

    International Nuclear Information System (INIS)

    The NRU (National Research Universal) Reactor is a 135 MW thermal research facility located at Chalk River Laboratories. AECL owns and operates the multi-purpose research reactor that serves as the primary R and D facility for supporting the CANDU business. The reactor is also a major producer of the world's medical radioisotopes. Since NRU was started up in 1957, it has operated in a consistent and safe manner with an overall annual capacity factor of approximately 80 %. The demands on the operation to perform experiments and produce radioisotopes were increased significantly when the NRX (National Research Experimental) shut down in 1992. Radioisotope customers demand an uninterrupted supply of short-lived radioisotopes e g Molybdenum-99, while experimental researchers require frequent shutdowns to accommodate fuel and materials programs. A two year systematic review and assessment of NRU to determine the condition and state of the facility was completed in 1991. This engineering assessment was complemented by safety analyses which focused on systems and components critical to safety. Reactor aging, obsolescence, current codes, and hazards vulnerability (especially, seismic) were emphasized during the analyses. This initial assessment concluded that the overall condition of NRU was good and there was no undue risk to the public or environment with the present operation. In addition, seven major upgrades were identified to enhance reactor safety to satisfy modern standards. In 1992, the AECL executive approved the Upgrades Project. Implementation of the seven upgrades were then included in the Facility Authorization document that defines the limiting conditions for safe operation with the Chalk River site license. The Atomic Energy Control Board would approve and license the upgrades under the change control provisions of the FA. Each upgrade and/or assessment recommendation (minor modification) had to be implemented without adversely affecting the current

  1. Proceedings of the European Research Reactor Conference - RRFM 2012 Transactions

    International Nuclear Information System (INIS)

    In 2012 RRFM, the European Research Reactor Conference will be jointly organised with IGORR, the International Group Operating Research Reactors. This will allow offering engineers and specialised nuclear researchers the chance to focus on the latest technological developments in the field of nuclear research reactors. The conference programme will revolve around a series of Plenary Sessions dedicated to the latest global developments with regards to research reactor technology and management systems, parallel sessions that focused on specific research projects and initiatives. (authors)

  2. MAPLE research reactor safety uncertainty assessment methodology

    International Nuclear Information System (INIS)

    The MAPLE (multipurpose Applied Physics Lattice Experiment) reactor is a low pressure, low temperature, open-tank-in pool type research reactor that operates at a power level of 5 to 35 MW. MAPLE is designed for ease of operation, maintenance, and to meet today's most demanding requirements for safety and licensing. The emphasis is on the use of passive safety systems and environmentally qualified components. Key safety features include two independent and diverse shutdown systems, two parallel and independent cooling loops, fail safe operation, and a building design that incorporates the concepts of primary containment supported by secondary confinement

  3. Using deterministic methods for research reactor studies

    International Nuclear Information System (INIS)

    As an alternative to prohibitive Monte Carlo simulations, deterministic methods can be used to simulate research reactors. Using various microscopic cross section libraries currently available in Canada, flux distributions were obtained from DRAGON cell and supercell transport calculations. Then, homogenization/condensation is done to produce few-group nuclear properties, and diffusion calculations were performed using DONJON core models. In this paper, the multigroup modular environment of the code DONJON is presented, and the various steps required in the modelling of SLOWPOKE hexagonal cores are described. Numerical simulations are also compared with experimental data available for the EPM Slowpoke reactor. (author)

  4. The Australian centre for RF bioeffects research (ACRBR) - an NHMRC centre of research excellence

    International Nuclear Information System (INIS)

    Full text: The Australian Centre for Radiofrequency Bioeffects Research (ACRBR) is a newly established multi-institutional research centre which seeks to research questions pertaining to possible health effects of exposure to radiofrequency devices, such as mobile phones and which is funded under the Australian National Health and Medical Research Council (NHMRC) Centres of Research Excellence funding program. The Centre of Research Excellence in Electromagnetic Energy is combining the efforts of engineers, epidemiologists, physicists, psychophysiologists and veterinary pathologists from RMIT University, the Institute of Medical and Veterinary Science in South Australia (IMVS), Monash University, Swinburne University of Technology and Telstra Research Laboratories (TRL). The centre is funded at $2.5 M over five years and will undertake a program of research to address the issue of exposure to radiofrequency (RF) devices and health. It will also train new scientists, keep the community informed of ongoing developments and help the development of government policies in this area of considerable public concern. The 5-year program has the following components: Neurobiology: One important area where there is a perceived research gap is in the area of potential neurological effects, which will hence be a major focus of this Centre. The proposed studies range from in vitro and in vivo research studies of RF effects on neuron and neural system functioning in rodents, to that of RF effects on simple neural function, cognition and subjective report in humans. The latter series of studies have been developed to account for the consensus view that more emphasis needs to be placed on possible differences in RF population sensitivity (e.g. youth versus aged, and ' electromagnetic hypersensitives'). Epidemiological studies are an important tool in studying the impact on public health from exposure of whole populations to modern radio technologies. Cancer outcomes in this area of

  5. Review of Operation and Maintenance Support Systems for Research Reactors

    International Nuclear Information System (INIS)

    Operation support systems do not directly control the plant but it can aid decision making itself by obtaining and analyzing large amounts of data. Recently, the demand of research reactor is growing and the need for operation support systems is increasing, but it has not been applied for research reactors. This study analyzes operation and maintenance support systems of NPPs and suggests appropriate systems for research reactors based on analysis. In this paper, operation support systems for research reactors are suggested by comparing with those of power reactors. Currently, research reactors do not cover special systems in order to improve safety and operability in comparison with power reactors. Therefore we expect to improve worth to use by introducing appropriate systems for research reactors. In further research, we will develop an appropriate system such as applications or tools that can be applied to the research reactor

  6. RA Research reactor, Annual report 1972

    International Nuclear Information System (INIS)

    During 1972, the total production was 31151 MWh which is 3.8% higher than planned. The reactor was used for irradiation and experiments according to the demand of 381 users, of which 340 from the Institute and 41 external users. This report contains detailed data about reactor power and experiments performed in 1972. Discrepancies from the action plan, meaning higher production was achieved due to special demands of the users. Total number of interruptions was lower than during all the previous years, and were caused mainly due to announced power cuts. There was only on scram shutdown during this year caused by a false signal of the reactor control instrumentation. There were no longer interruptions. One shorter interruption (shorter than 24 hours) caused by removal of a UO2 capsule from the core, placed there for measuring heat transfer. Total personnel exposure dose was lower than during previous years. One accident caused contamination with gases and aerosols containing mainly shot-living isotopes. Decontamination od surfaces was less than during previous years. Practically there was no surface contamination that would demand action of the decontamination team, except for the regular decontamination after refueling. It was concluded that the successful operation in 1972 has a special significance having taking in account the financial crisis caused by the unresolved status of the reactor. It is emphasised, in the plan for the next year that there is an urgent need of making a long-term plan of rector application. It is indispensable to finish preparatory tasks for replacing the fuel with the highly enriched fuel elements by 1974, and building the core emergency cooling system

  7. Radio Nuclides Release in Research Reactors

    International Nuclear Information System (INIS)

    One of the major topic in nuclear safety is the quantitative evaluation of the radionuclides source term in nuclear reactors under routine and accidental conditions. The present study considers the release paths from fuel to coolant during normal and accidental situations of research reactors. Equivalent full power days approach, has been adopted for implementing reactor operating history in the calculations. Origin II code , recoil and Knock out phenomena, experimental correlations, and mathematical models have been employed in determining source term in fuel, releases to fuel clad interface, release from clad to coolant, and concentration in coolant. Different volatile fission products have been manipulated as: Br-83, Kr-85, I-129, I-131, I-133, Xe-133, Xe-135, Cs-137, Te-127, Te-131 m, Tc-99, Tc 99 m, Mo-99, Sr-90, Ru-106. Normal operation and accidental situation have been studied. The results have been verified against published data during normal operating conditions, it showed a good agreement

  8. Pakistan research reactor-1 and its upgradation

    International Nuclear Information System (INIS)

    In this article the author describes the procedure of renovation and upgradation of a swimming pool type Pakistan Research Reactor-1 (PARR-1) installed at PINSTECH. The reactor originally designed for a thermal power of 5 MW using highly enriched uranium as has been upgraded 10 MW with low enriched uranium as fuel. All the required safety precaution has been also modified with the new requirements. The cooling system of PARR-1 was modified to meet the requirements of upgraded power of 10 MW. In order to ensure safety for upgraded PARR-1 and to bring the reactor the current safety standards, some additional safety systems have been provided. An emergency core cooling system ECCS has been installed to remove core decay heat in case of loss of coolant accident (LOCA). (A.B.)

  9. Transnational Capacity Building: An Australian-Danish Partnership Model for Higher Education and Research in Nursing

    DEFF Research Database (Denmark)

    Rasmussen, Bodil; Kolbæk, Raymond; Lorentzen, Vibeke;

    2013-01-01

    Aim: The article describes how a three level nursing partnership program between Australia and Denmark evolved and how barriers can be diminished when built on guiding principles of: professional trust, mutual understanding and respect for each other’s social, educational and cultural conditions...... knowledge and expertise across international borders as an important vehicle for developing nursing practice and research. Conclusion: The Australian-Danish education and research partnership program demonstrates that exchanging experiences can create opportunities for nurses’ professional growth, to...

  10. Operation and utilizations of Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    The reconstructed Dalat nuclear research reactor was commissioned in March 1984 and up to September 1988 more than 6200 hours of operation at nominal power have been recorded. The major utilizations of the reactor include radioisotope production, activation analysis, nuclear data research and training. A brief review of the utilizations of the reactor is presented. Some aspects of reactor safety are also discussed. (author)

  11. Japan Atomic Energy Research Institute, Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in the Division of Reactor Engineering in fiscal 1980 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

  12. Nuclear reactors for research and radioisotope production in Argentina

    International Nuclear Information System (INIS)

    In Argentina, the construction, operation, and use of research and radioisotope production reactors is and has been an important method of personnel preparation for the nuclear power program. Moreover, it is a very suitable means for technology transfer to countries developing their own nuclear programs. At present, the following research reactors are in operation in Argentina: Argentine Reactor 0 (RA-0); Argentine Reactor 1 (RA-1); Argentine Reactor 2 (RA-2); Argentine Reactor 3 (RA-3); Argentine Reactor 4 (RA-4). The Argentine Reactor 6 (RA-6), under construction, should reach criticality in 1981

  13. Low-enriched research reactor fuel: Post-Irradiation Examinations at SCK-CEN

    International Nuclear Information System (INIS)

    Generally, research and test reactors are fuelled with fuel plates instead of pins. In most cases in the past, these plates consisted of high enriched (higher than 95 percent 235U) UAl3 powder mixed with a pure Al matrix (called the meat) in between two aluminium alloy plates (the cladding). These plates are then assembled in fuel elements of different designs to fit the needs of the various reactors. Since the 1970's, efforts have been going on to replace the high-enriched, low-density UAl3 fuel with high-density, low enriched (235U) replacements. This search is driven by the attempt to reduce the civil use of high-enriched materials because of proliferation risks and terrorist threats. American initiatives, such as the Global Threat Reduction Initiative and the Reduced Enrichment for Research and Test Reactors program have triggered the development of reliable low-enriched fuel types for these reactors, which can replace the high enriched ones without loss of performance. Most success has been obtained with U3Si2 fuel, which is currently used in many research reactors in the world. However, efforts to search for a better replacement have continued and are currently directed towards the U-Mo alloy fuel (7-10 weight percent Mo)

  14. Complex degradation and ageing phenomena of research reactor core structural materials - experience at 14 MW TRIGA reactor from INR Pitesti

    International Nuclear Information System (INIS)

    The 14 MW TRIGA Research Reactor designed in the early '70s is a relative new research reactor with an operational experience of 30 years. The specific design of reactor core objectives, were to manufacture, build and operate a flexible structure which incorporate previous experience of pool type research reactors. Aluminum alloy 6061 and stainless steel are only materials used for core structural components, which are all easily remotely removable and replaceable by simple hand tools. Properties of those categories of materials were well characterized / known for many other reactors predecessors, and no special criteria or preliminary tests were performed. The mechanical core structure is presented in the paper and designed procedure for periodic testing and inspection is also described. In spite of well known materials properties, the behavior uncertainties of those materials in each reactor case may have special aspects related to design of components, manufacturing technologies, surface finishing and processing, quality control methods, price of specific components, complex conditions in core and vicinity, history of operation, inspection and verification of components, radioactive waste characterization at the end of life of components. Limited assessment of materials properties and suitability for certain application without considering the each individual component load, exposure and life time, may produce limited information on material itself, in fact the issue is the selection criteria for a standard material suitable for a certain application and consequent failure of components. The degradation and ageing are specific to components starting from design, manufacturing technology and expected life when the component should be replaced. The paper presents the practical experience on maintenance requirements specific to TRIGA core components and some techniques of material investigations available at Institute for Nuclear Research Pitesti Post Irradiation

  15. Ageing investigation and upgrading of components/systems of Kartini research reactor

    International Nuclear Information System (INIS)

    Kartini research reactor has been operated in good condition and has demonstrated successful operation for the past 18 years, utilized for: reactor kinetic and control studies, instrumentation tests, neutronic and thermohydraulic studies, routine neutron activation analysis, reactor safety studies, training for research reactor operators and supervisors, and reactor physics experiments. Several components of Kartini reactor use components from the abandoned IRT-2000 Project at Serpong and from Bandung Reactor Centre such as: reactor tank, reactor core, heat exchanger, motor blower for ventilation system, fuel elements, etc. To maintain a good operating performance and also for aging investigation purposes, the component failure data collection has been done. The method used is based on the Manual on Reliability Data Collection For Research Reactor PSAs, IAEA TECDOC 636, and analyzed by using Data Entry System (DES) computer code. Analysis result shows that the components/systems failure rate of Kartini reactor is around 1,5.10-4 up to 2,8.10-4 per hour, these values are within the ranges of the values indicated in IAEA TECDOC 478. Whereas from the analysis of irradiation history shows that the neutron fluence of fuel element with highest burn-up (2,05 gram U-235 in average) is around 1.04.1016 n Cm-2 and this value is still far below its limiting value. Some reactor components/systems have been replaced and upgraded such as heat exchanger, instrumentation and control system (ICS), etc. The new reactor ICS was installed in 1994 which is designed as a distributed structure by using microprocessor based systems and bus system technology. The characteristic and operating performance of the new reactor ICS, as well as the operation history and improvement of the Kartini research reactor is presented. (J.P.N.)

  16. Ageing investigation and upgrading of components/systems of Kartini research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Syarip; Widi Setiawan [Yogyakarta Nuclear Research Centre, Yogyakarta (Indonesia)

    1998-10-01

    Kartini research reactor has been operated in good condition and has demonstrated successful operation for the past 18 years, utilized for: reactor kinetic and control studies, instrumentation tests, neutronic and thermohydraulic studies, routine neutron activation analysis, reactor safety studies, training for research reactor operators and supervisors, and reactor physics experiments. Several components of Kartini reactor use components from the abandoned IRT-2000 Project at Serpong and from Bandung Reactor Centre such as: reactor tank, reactor core, heat exchanger, motor blower for ventilation system, fuel elements, etc. To maintain a good operating performance and also for aging investigation purposes, the component failure data collection has been done. The method used is based on the Manual on Reliability Data Collection For Research Reactor PSAs, IAEA TECDOC 636, and analyzed by using Data Entry System (DES) computer code. Analysis result shows that the components/systems failure rate of Kartini reactor is around 1,5.10{sup -4} up to 2,8.10{sup -4} per hour, these values are within the ranges of the values indicated in IAEA TECDOC 478. Whereas from the analysis of irradiation history shows that the neutron fluence of fuel element with highest burn-up (2,05 gram U-235 in average) is around 1.04.10{sup 16} n Cm{sup -2} and this value is still far below its limiting value. Some reactor components/systems have been replaced and upgraded such as heat exchanger, instrumentation and control system (ICS), etc. The new reactor ICS was installed in 1994 which is designed as a distributed structure by using microprocessor based systems and bus system technology. The characteristic and operating performance of the new reactor ICS, as well as the operation history and improvement of the Kartini research reactor is presented. (J.P.N.)

  17. Experience in using a research reactor for the training of power reactor operators

    International Nuclear Information System (INIS)

    A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

  18. New developments in transportation for research reactors

    International Nuclear Information System (INIS)

    For more than 30 years, Transnucleaire has been performing safely a large number of national and international transports of radioactive material. Transnucleaire has also designed and supplied numerous packagings for all types of nuclear fuel cycle radioactive materials: for front-end and back-end products and for power and research reactors. Since the last meeting held in Bruges, Transnucleaire has been continuously involved in transportation activities for fresh and irradiated materials for research reactors. We are pleased to take the opportunity in this meeting to share with reactor operators, official bodies and other partners, the on-going developments in transportation and associated services. Special attention will be paid to the starting of transports of MTR spent fuel elements to the La Hague reprocessing plant where COGEMA offers reprocessing services on a long-term basis to reactors operators. Detailed information is provided on regulatory issues, which may affect transport activities: evolution of the regulations, real experiences of recent transportation and development of new packaging designs. Options and solutions will be proposed by Transnucleaire to improve the situation for continuation of national and international transports at an acceptable price whilst maintaining an ultimate level of safety (author)

  19. The current status of Kartini research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Tri Wulan Tjiptono; Syarip

    1998-10-01

    The Kartini reactor reached the first criticality on January 25, 1979. In the first three years, the reactor power is limited up to 50 kW thermal power and on July 1, 1982 has been increased to 100 kW. It has been used as experiments facility by researcher of Atomic Energy National Agency and students of the Universities. Three beam tubes used as experiments facilities, the first, is used as a neutron source for H{sub 2}O-Natural Uranium Subcritical Assembly, the second, is developed for neutron radiography facility and the third, is used for gamma radiography facility. The other facilities are rotary rack and two pneumatic transfer systems, one for delayed neutron counting system and the other for the new Neutron Activation Analysis (NAA) facility. The rotary rack used for isotope production for NAA purpose (for long time irradiation), the delayed neutron counting system used for analysis the Uranium contents of the ores and the new NAA is provided for short live elements analysis. In the last three years the Reactor Division has a joint use program with the Nuclear Component and Engineering Center in research reactor instrumentation and control development. (author)

  20. Radionuclide release from research reactor spent fuel

    International Nuclear Information System (INIS)

    Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions were performed. The results obtained indicate slow corrosion rates for the UO2 fuel matrix. Special fuel-types (mostly dispersed fuels, high enriched in 235U, cladded with aluminium) are used in German research reactors, whereas in German nuclear power plants, UO2-fuel (LWR fuel, enrichment in 235U up to 5%, zircaloy as cladding) is used. Irradiated research reactor fuels contribute less than 1% to the total waste volume. In Germany, the state is responsible for fuel operation and for fuel back-end options. The institute for energy research (IEF-6) at the Research Center Juelich performs investigation with irradiated research reactor spent fuels under repository relevant conditions. In the study, the corrosion of research reactor spent fuel has been investigated in MgCl2-rich salt brine and the radionuclide release fractions have been determined. Leaching experiments in brine with two different research reactor fuel-types were performed in a hot cell facility in order to determine the corrosion behaviour and the radionuclide release fractions. The corrosion of two dispersed research reactor fuel-types (UAlx-Al and U3Si2-Al) was studied in 400 mL MgCl2-rich salt brine in the presence of Fe2+ under static and initially anoxic conditions. Within these experimental parameters, both fuel types corroded in the experimental time period of 3.5 years completely, and secondary alteration phases were formed. After complete corrosion of the used research reactor fuel samples, the inventories of Cs and Sr were quantitatively detected in solution. Solution concentrations of Am and Eu were lower than the solubility of Am(OH)3(s) and Eu(OH)3(s) solid phases respectively, and may be controlled by sorption processes. Pu concentrations may be controlled by Pu(IV) polymer species, but the presence of Pu(V) and Pu(IV) oxyhydroxides species due to radiolytic effects cannot completely be

  1. The utility of different reactor types for the research

    International Nuclear Information System (INIS)

    The report presents a general view of the use of the different belgian research reactor i.e. venus reactor, BR-1 reactor, BR-2 reactor and BR-3 reactor. Particular attention is given to the programmes which is in the interest of international collaboration. In order to reach an efficient utilization of such reactors they require a specialized personnel groups to deal with the irradiation devices and radioactive materials and post irradiation examinations, creating a complete material testing station. (A.J.)

  2. Research reactor fuel management in the Czech Republic

    International Nuclear Information System (INIS)

    Fuel management of the Czech research reactors is described. There are three research reactors in the Czech Republic: LVR-15 and LR-0 operated by the Nuclear Research Institute Rez plc, VR-1 operated by the Czech Technical University, Faculty of Nuclear Sciences and Physical Engineering in Prague, and SR-0 reactor of SKODA JS plc which is under decommissioning now. The paper describes the major features of the Czech research reactors, types of fuels used in them, and the spent fuel management principles. The participation of the LVR-15 and VR-1 reactors in the RERTR international programme (Reduced Enrichment for Research and Test Reactors) is also highlighted. (author)

  3. EURATOM Research Framework Programme on Reactor Systems

    International Nuclear Information System (INIS)

    The activities of the European Commission (EC) in the field of nuclear energy are governed by the Treaty establishing the European Atomic Energy Community (EURATOM). The research activities of the European Union (EU) are designed as multi-annual Framework Programmes (FP). The EURATOM 6. Framework Programme (EURATOM FP -6), covering the period 2002-2006, is funded with a budget of 1, 230 million Euros and managed by the European Commission. Beyond the general strategic goal of the EURATOM Framework Programmes to help exploit the potential of nuclear energy, in a safe and sustainable manner, FP -6 is designed to contribute also to the development of the 'European Research Area' (ERA), a concept described in the Commission's Communication COM(2000)6, of January 2000. Moreover EURATOM FP-6 contributes to the creation of the conditions for sharing the same nuclear safety culture throughout the EU-25 and the Candidate Countries, fostering the acceptance of nuclear power as an element of the energy mix. This paper gives an overview of the research activities undertaken through EURATOM FP-6 in the area of Reactor Systems, covering the safety of present reactors, the development of future safe reactors, and the needs in terms of research infrastructures and education and training. The actions under FP-6 are presented in their continuity of actions under FP-5. The perspectives under FP -7 are also provided. Other parts of the EURATOM FP, covering Waste Handling and Radiation Protection, as well as Fusion Energy, are not detailed in this paper. (authors)

  4. Decision-making process to shut down, refurbish/modify, or decommission research reactors

    International Nuclear Information System (INIS)

    Most US research reactors were built more than 20 years ago and some more than 40 years ago. Many have undergone refurbishments and modifications to update their safety systems and experimental capabilities. But changing safety bases, social concerns, and budget constraints have required research reactor operators to continually make decisions to shut down or refurbish/modify their facilities. These decisions involve potential replacement of reactor equipment that has reached its lifetime limits. Changes in philosophy and operation of the reactors are also factors to be considered. In this paper, each of the four factors involved in the decision-making process are discussed in detail. Then, several examples from DOE research reactors in the United States are discussed. Finally, some general conclusions are given to aid in the decision-making process

  5. Agonist Replacement for Stimulant Dependence: A Review of Clinical Research

    OpenAIRE

    Stoops, William W.; Rush, Craig R.

    2013-01-01

    Stimulant use disorders are an unrelenting public health concern worldwide. Agonist replacement therapy is among the most effective strategies for managing substance use disorders including nicotine and opioid dependence. The present paper reviewed clinical data from human laboratory self-administration studies and clinical trials to determine whether agonist replacement therapy is a viable strategy for managing cocaine and/or amphetamine use disorders. The extant literature suggests that ago...

  6. Basic CFD investigation of decay heat removal in a pool type research reactor

    International Nuclear Information System (INIS)

    Safety is one of the most important and desirable characteristic in a nuclear plant. Natural circulation cooling systems are noted for providing passive safety. These systems can be used as mechanism for removing the residual heat from the reactor, or even as the main cooling system for heated sections, such as the core. In this work, a computational fluid-dynamics (CFD) code is used to simulate the process of natural circulation in an open pool research reactor after its shutdown. The physical model studied is similar to the Open Pool Australian Light water reactor (OPAL), and contains the core, cooling pool, reflecting tank, circulation pipes and chimney. For best computing performance, the core region was modeled as a porous media, where the parameters were obtained from a separately detailed CFD analysis. (author)

  7. A Delphi study on research priorities in radiation therapy: The Australian perspective

    International Nuclear Information System (INIS)

    Radiation therapists (RTs) need to engage more in research to establish an evidence base for their daily practice. However, RTs world-wide conduct little research themselves, although positive moves have been made in some countries. This project is the second stage of a Delphi process aimed at prioritising RT areas of research interest. A questionnaire was constructed using responses to a previous questionnaire which identified the research interests of Australian RTs. Fifty-three Research Areas were identified from these responses and grouped into 12 categories such as 'imaging in radiation therapy', 'symptom management', 'accuracy of patient positioning' and 'techniques/equipment'. The survey was sent to all Australian departments of radiation oncology, and RTs were asked to form interest groups to discuss and prioritise the Research Areas. There was a 50% response rate (18 of 36 departments surveyed). The highest ranked research Category was 'imaging in radiation therapy'. Six of the top 10 ranked Research Areas were within Central RT practice ('imaging in radiation therapy'; 'symptom management'; 'accuracy of patient positioning' and 'techniques/equipment') and the other four were within broader RT practice ('diversification, recognition and other professional issues'; and 'management and staff issues'). Patient Care was also considered to be an area requiring more research. This prioritization of Research Areas and categories provides a useful list of future research for RTs, which will enable them to decide whether their research ideas are a high priority, and spend less time deciding on a relevant research topic that needs investigation in their own workplaces.

  8. Research Reactors: Decommissioning of a Small Reactor (BR3 Reactor, Belgium). Appendix III

    International Nuclear Information System (INIS)

    Research reactors are nuclear reactors that serve primarily as source of neutrons. They are less complex than power reactors and operate at lower temperatures. Research reactors need far less fuel, and far less fission products build up as the fuel is used. On the other hand, their fuel requires more highly enriched uranium, typically up to 20% 235U. More than 650 research reactors worldwide have been built or are under construction or in a planning phase; of which more than 350 have been shut down and partly or wholly decommissioned. Experience has shown that decommissioning can be undertaken in line with safety standards aimed at protecting human beings or the environment from harm, provided that decommissioning activities are undertaken in accordance with a properly formulated plan. The potential or actual radiological hazards associated with reactors may require the application of special techniques and procedures during decommissioning. The decommissioning of the BR3 reactor in Mol, Belgium, Belgian nuclear research centre SCK•CEN, provides an example of current good practice in decommissioning research reactors.13 Since 1991, the organization’s statutory mission gives priority to research on problems of societal concern such as the safety of nuclear installations, radiation protection, safe treatment and disposal of radioactive waste, fighting against uncontrolled proliferation of fissile materials, and education and training. BR3 was the first European pressurized water reactor (PWR) power plant and was put into service in 1962. It was in that industrial context that the BR3 has played its role as a demonstration unit for the development and improvement of decommissioning related techniques. While the BR3 power level was low (40 MW(th), 10.5 MW(e) net), it contains all the features of commercial PWR power plants. The reactor was used at the beginning of its lifetime as a training facility for future nuclear power plant operators. Later, it was also used

  9. A New Generation of Research Reactors Fuelled with LEU

    International Nuclear Information System (INIS)

    A number of countries have recently shown interest in new research reactors. In response to such willingness to develop nuclear technologies, we have prepared technical proposals on typical research reactors (RR) which will be built as part of nuclear research centres (NRC) according to base design principles. The requirements for such research reactors are defined to represent their competitive service parameters, including capabilities to support a wide spectrum of studies in various areas of theoretical and applied researches. Analysis of the current and projected uses of research reactors and assessment of the external market demands have prompted two design options of a pool-type reactor at a nuclear research centre, namely, a small (up to 0.5 MW) reactor with natural coolant circulation through its core and a reactor with forced coolant circulation scaled up to 10-15 MW. The research reactors under development will run with commercially available and well-proven fuel of low enrichment. (author)

  10. The current status of utilization of research reactors in China

    International Nuclear Information System (INIS)

    Seminars on utilization of research reactors were held to enhance experience exchanging among institutes and universities in China. The status of CARR (China Advanced Research Reactor) project is briefly described. The progress in BNCT program in China is introduced. (author)

  11. Decommissioning Experience: Apsara Research Reactor, India

    International Nuclear Information System (INIS)

    Full text: In India, at the Bhabha Atomic Research Centre, a 1 MW(th) pool type research reactor called Apsara was built in 1956 and shut down in 2009. The reactor fuel and internals were removed, leaving the pool available for draining and decontamination. The pool was drained progressively while monitoring for hot spots. Additional material and debris at the bottom were removed. The lining was cleaned by water jetting using detergents. In summary, the defuelling and partial decommissioning were successfully completed in around six months, with a total dose consumption of 23.5 man mSv (approximately 10% of budget). The generation of waste amounted to a solid waste volume of around 20 m3 (low level) and a liquid waste volume of 280 m3 (low level). A detailed description of achievements and plans for the Apsara decommissioning is given. (author)

  12. Pakistan research reactor and its utilization

    International Nuclear Information System (INIS)

    The 5 MW enriched uranium fuelled, light water moderated and cooled Pakistan Research reactor became critical on 21st December, 1965 and was taken to full power on 22nd June, 1966. Since then is has been operated for about 23000 hours till 30th June, 1983 without any major break down. It has been used for the studies of neutron cross-sections, nuclear structure, fission physics, structure of material, radiation damage in crystals and semiconductors, studies of geological, biological and environmental samples by neutron activation techniques, radioisotope production, neutron radiography and for training of scientists, engineers and technicians. In the paper we have described briefly the facility of Pakistan Research Reactor and the major work carried around it during the last decade. (author)

  13. Developing the fuel for research reactors

    International Nuclear Information System (INIS)

    A review of papers dealing with the possibility of research reactor adaptation to moderately and slightly enriched fuel with the 235U content of 45 and 20%, respectively, is presented. The main peculiarities and results of investigations carried out in two main directions, are under consideration: the increase of specific uranium content in traditional fuels (UAlsub(x)-Al, U3O8-Al, U,ZrHsub(x)) by means of improvements in technology and production (USA, FRG and France); the development of new highly dense kinds of fuel, such as U3Si, U3Si-Al, UO2 (USA, France). A conclusion is drawn that the research reactor fuel enrichment may be decreased

  14. The role of the safety analysis organization in steam generators replacement and reactor vessel head replacement evaluations

    International Nuclear Information System (INIS)

    When a major component in a nuclear power plant is replaced, especially the steam generators, the plant operator is presented a rare opportunity to learn from operating experience and significantly improve the performance, reliability and robustness of the plant. In addition to the use of improved materials, improved design margins can be built into the component specification that can later be used to provide meaningful operating margins. A Safety Analysis organization that is well-integrated with other plant organizations and possesses a detailed knowledge of the plant design and licensing bases can effectively balance the wants and needs of each organization to optimize the benefits realized by the plant as a whole. Knowledge of the assumptions, limitations, and available margins, both analytical and operating, can be used to specify a replacement steam generator design that optimizes costs and operating improvements. The work scope required to support the new design can be controlled through carefully selected and evaluated restrictions in operations, development of alternate operating strategies, and imposition of appropriate limitations. The important point is that the effective Safety Analysis organization must possess both the breadth and depth of knowledge of the plant design and operations and proactively use this information to support the replacement steam generator project. (author)

  15. Chemistry research and chemical techniques based on research reactors

    International Nuclear Information System (INIS)

    Chemistry has occupied an important position historically in the sciences associated with nuclear reactors and it continues to play a prominent role in reactor-based research investigations. This Panel of prominent scientists in the field was convened by the International Atomic Energy Agency (IAEA) to assess the present state of such chemistry research for the information of its Member States and others interested in the subject. There are two ways in which chemistry is associated with nuclear reactors: (a) general applications to many scientific fields in which chemical techniques are involved as essential service functions; and (b) specific applications of reactor facilities to the solution of chemical problems themselves. Twenty years of basic research with nuclear reactors have demonstrated a very widespread, and still increasing, demand for radioisotopes and isotopically-labelled molecules in all fields of the physical and biological sciences. Similarly, the determination of the elemental composition of a material through the analytical technique of activation analysis can be applied throughout experimental science. Refs, figs and tabs

  16. The BR2-material testing reactor and its major contribution to the reactor material, fuel and safety research

    International Nuclear Information System (INIS)

    The BR2 was shutdown at the end of June 1995 for a programme of extensive refurbishment after more than 30 years utilization. The beryllium matrix was replaced and the aluminum vessel inspected and requalified for the envisaged 15 years life extension. Other aspects of the refurbishment programme were aimed at reliability and availability of the installations, safety of operation and compliance with modem safety standards. The reactor was restarted in April 1997. This paper deals with aspects of this refurbishment in general as well as the ongoing experimental projects in the areas of reactor material, fuel behaviour and safety research. (author)

  17. Thermal calculations for water cooled research reactors

    International Nuclear Information System (INIS)

    The formulae and the more important numerical data necessary for thermic calculations on the core of a research reactor, cooled with low pressure water, are presented. Most of the problems met by the designer and the operator are dealt with (calculations margins, cooling after shut-down). Particular cases are considered (gas release, rough walls, asymmetric cooling slabs etc.), which are not generally envisaged in works on general thermics

  18. Decommissioning of a 5 MW research reactor

    International Nuclear Information System (INIS)

    The complete decommissioning of a research reactor is described. Planning and execution of all activities, including schedules, budgets, waste management, health physics and subcontracted operations are presented. Flexibility in operations was obtained by using the operating staff as the decommissioning progressed. Totals for waste shipments and costs are given. Final site conditions are presented along with a description of the subsequent use of the facility. (author)

  19. Hydrogen problems in reactor safety research

    International Nuclear Information System (INIS)

    The BMFT and BMI have initiated a workshop 'Hydrogen Problems in Reactor Safety Research' that took place October 3./4., 1983. The objective of this workshop was to present the state of the art in the main areas - Hydrogen-Production - Hydrogen-Distribution - Hydrogen-Ignition - Hydrogen-Burning and Containment Behaviour - Mitigation Measures. The lectures on the different areas are compiled. The most important results of the final discussion are summarized as well. (orig.)

  20. Defuelling of the UTR-300 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Scott, R.D.; Banford, H.M.; East, B.W. [Scottish Universities Research and Reactor Centre, Glasgow (United Kingdom); Ord, M.A.; Gaffka, A.P. [AEA Technology, Harwell, Didcot, Oxfordshire OX11 0RA (United Kingdom)

    1997-12-01

    A description is given of the movement of fuel elements from the core of the UTR-300 research reactor to the UNIFETCH flask, which is normally loaded under water, through a specially designed shielding arrangement which permits a dry transfer. The regulatory requirements and the safety case are summarised along with the predicted and measured doses to operators. The task was successfully completed to a tight time schedule with recorded doses which were well within the allocated dose budget. (orig.) 3 refs.

  1. Safety review, assessment and inspection on research reactors, experimental reactors and nuclear heating reactors

    International Nuclear Information System (INIS)

    The NNSA and its regional office step further strengthened the regulation on the safety of in-service research reactors in 1996. A lot of work has been done on the supervision of safe in rectifying the review and assessment of modified items, the review of operational documents, the treatment of accidents, the establishment of the system for operational experience feedback, daily and routine inspection on nuclear safety. The internal management of the operating organization on nuclear safety was further strengthened, nuclear safety culture was further enhanced, the promotion in nuclear safety and the safety situation for in-service research reactors were improved

  2. Organization and management of operation of the research reactor MARIA

    International Nuclear Information System (INIS)

    The MARIA research reactor belongs to the Institute of Atomic Energy. The MARIA research reactor operation provides basing on the Atomic Law code and requirements of the State Nuclear Safety. Main task of the operation Department is the current MARIA reactor operation and relevant technological systems. The Head of the Reactor bears the direct responsibility for nuclear safety and radiological protection of the reactor plant. Service of reactor operation is accomplished by the Shift Groups. The cooperation with the reactor users is based on the principles defined by the Regulations of MARIA Reactor Operation. In the abnormal and emergency states the procedure is determined by 'Schedule of emergency procedure for the MARIA reactor plant'. Reactor has got valid and actual documents which are compulsory to all the persons being involved in operation and usage of reactor. (author)

  3. The WWR-SM-20 research reactor

    International Nuclear Information System (INIS)

    In this paper the design features and experimental capabilities of the WWR-SM-20 research reactor are described. The reactor uses fuel assemblies consisting of six coaxial fuel tubes with a square cross-section. IRT-3M fuel assemblies can be used with both 90% enriched and 36% enriched uranium. The main characteristics of the IRT-3M fuel assemblies are given, as are the technical and physical parameters of the WWR-SM-20 reactor. The core can hold up to ten ampoule-type channels with a diameter of up to 68 mm. For irradiation purposes, up to 22 26-mm-diameter channels in the fuel assemblies, and up to 48 42-mm-diameter channels in the beryllium blocks of the reflector can be used. In the graphite blanket between the horizontal channels, channels with a diameter of up to 130 mm can be used. The thermal neutron flux density has a maximum value of 1.5 X 1018 m-2 · s-1 in the core and 2.3 X 1018 m-2 · s-1 in the reflector, and the fast neutron flux density (cE > 0.821 MeV) a maximum of 1.9 X 1018 m-2 · s-1. A number of design features have been incorporated in the WWR-SM-20 reactor to make it effectively safe

  4. Japan Atomic Energy Research Institute, Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in the Division of Reactor Engineering in fiscal 1978 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committees on Reactor Physics and in Decommissioning of Nuclear Facilities. (author)

  5. Materials research with neutron beams from a research reactor

    International Nuclear Information System (INIS)

    Because of the unique ways that neutrons interact with matter, neutron beams from a research reactor can reveal knowledge about materials that cannot be obtained as easily with other scientific methods. Neutron beams are suitable for imaging methods (radiography or tomography), for scattering methods (diffraction, spectroscopy, and reflectometry) and for other possibilities. Neutron-beam methods are applied by students and researchers from academia, industry and government to support their materials research programs in several disciplines: physics, chemistry, materials science and life science. The arising knowledge about materials has been applied to advance technologies that appear in everyday life: transportation, communication, energy, environment and health. This paper illustrates the broad spectrum of materials research with neutron beams, by presenting examples from the Canadian Neutron Beam Centre at the NRU research reactor in Chalk River. (author)

  6. Materials research with neutron beams from a research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Root, J.; Banks, D. [Canadian Neutron Beam Centre, Chalk River Laboratories, Chalk River, Ontario (Canada)

    2015-03-15

    Because of the unique ways that neutrons interact with matter, neutron beams from a research reactor can reveal knowledge about materials that cannot be obtained as easily with other scientific methods. Neutron beams are suitable for imaging methods (radiography or tomography), for scattering methods (diffraction, spectroscopy, and reflectometry) and for other possibilities. Neutron-beam methods are applied by students and researchers from academia, industry and government to support their materials research programs in several disciplines: physics, chemistry, materials science and life science. The arising knowledge about materials has been applied to advance technologies that appear in everyday life: transportation, communication, energy, environment and health. This paper illustrates the broad spectrum of materials research with neutron beams, by presenting examples from the Canadian Neutron Beam Centre at the NRU research reactor in Chalk River. (author)

  7. Has the Return on Australian Public Investment in Agricultural Research Changed?

    OpenAIRE

    Binenbaum, Eran; Mullen, John D.; Wang, Chang Tao

    2008-01-01

    We examine whether there has been a decline in the returns from Australian public investment in research on broadacre agriculture. Complementing a forthcoming paper by Mullen, we use alternative specifications for the regression equation, which employs the log of total factor productivity (TFP) as the dependent variable. The rate of return is computed on an annual basis rather than by using multi-year averages. In contrast to Mullen’s earlier preliminary analysis, we have now found some evide...

  8. Size and Distribution of Research Benefits in the Australian Dairy Industry

    OpenAIRE

    Liu, Esther; Tarrant, Katherine A.; Ho, Christie K.M.; Malcolm, Bill; Griffith, Garry R.

    2012-01-01

    An equilibrium displacement model of the Australian dairy industry is being developed for estimating the net benefits from dairy research undertaken by DPI Victoria. In this initial version, the dairy industry is represented by a system of aggregate demand and supply relationships for two input sectors, raw milk and milk processing inputs, and three output sectors, export and domestic manufactured milk and domestic fluid milk. Quantities and prices are calibrated in terms of milk equivalents....

  9. 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)

    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

  10. 78 FR 58575 - Review of Experiments for Research Reactors

    Science.gov (United States)

    2013-09-24

    ... COMMISSION Review of Experiments for Research Reactors AGENCY: Nuclear Regulatory Commission. ACTION... Guide (RG) 2.4, ``Review of Experiments for Research Reactors.'' The guide is being withdrawn because... Experiments for Research Reactors,'' (ADAMS Accession No. ML003740131) because its guidance no longer...

  11. Progress activity of Thai Research Reactor in 2002

    International Nuclear Information System (INIS)

    Thai Research Reactor-1/Modification 1 (TRR-1/M1) is a multipurpose research reactor with nominal power of 2 MW. The reactor is a swimming pool type, cooled and moderate with light water, using the LEU-fuel. TRR-1/M1 has been operated and utilized for various applications such as neutron activation analysis, radioisotope production, gem irradiation, neutron radiography and research works. To expand and promote the utilization of research reactor, the new 10 MW Research Reactor will be established in the Ongkarak Nuclear Research Center (ONRC) project and the project will be finished in the near future. (author)

  12. Research reactor status for future nuclear research in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Raymond, Patrick; Bignan, Gilles; Guidez, Joel [Commissariat a l' Energie Atomique - CEA (France)

    2010-07-01

    During the 1950's and 60's, the European countries built several research reactors, partially to support their emerging nuclear-powered electricity programs. Now, over forty years later, the use and operation of these reactors have both widened and grown more specialized. The irradiation reactors test materials and fuels for power reactors, produce radio-isotopes for medicine, neutro-graphies, doping silicon, and other materials. The neutron beam reactors are crucial to science of matter and provide vital support to the development of nano-technologies. Other reactors are used for other specialized services such as teaching, safety tests, neutron physics measurements... The modifications to the operating uses and the ageing of the nuclear facilities have led to increasing closures year after year. Since last ENC, for example, we have seen, only in France, the closure of the training reactor Ulysse in 2007, the closure of the safety test dedicated reactor Phebus in 2008 and recently the Phenix reactor, last fast breeder in operation in the European Community, has been shut down after a set of 'end of life' technological and physical tests. For other research reactors, safety re-evaluations have had to take place, to enable extension of reactor life. However, in the current context of streamlining and reorganization, new European tools have emerged to optimally meet the changing demands for research. However the operation market of these reactors seems now increasing in all fields. For the neutron beams reactors (FRMII, ORPHEE, ILL, ISIS,..) the experimental needs are increasing years after years, especially for nano sciences and bio sciences new needs. The measurement of residual stress on manufactured materials is also more and more utilised. All these reactors have increasing utilizations, and their future seems promising. A new project project based on a neutron spallation is under definition in Sweden (ESSS: European Spallation Source

  13. The korea multi-purpose research reactor

    International Nuclear Information System (INIS)

    This paper presents and discusses background and status of the design of the 30MW Korea Multi-purpose Research Reactor(KMRR) which is planed to achieve its first criticality in December, 19992, at Daeduk site of the Korea Advanced Energy Research Institute (KAERI). KAERI playing the leading role in Korea's nuclear technology development takes the total responsibility for its design, construction and operation. Number of Korean nuclear industries are, also, actively participating in the project while making the most of their expertise in relevant areas. (Author)

  14. Decommissioning activities for Salaspils research reactor - 59055

    International Nuclear Information System (INIS)

    In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor (SRR). The reactor is out of operation since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und Umwelttechnik GmbH at 1998-1999. The Latvian government decided to start the direct dismantling to 'green field' in October 26, 1999. The upgrade of decommissioning and dismantling plan was performed in 2003-2004 years, which change the main goal of decommissioning to the 'brown field'. The paper deals with the SRR decommissioning experience during 1999-2010. The main decommissioning stages are discussed including spent fuel and radioactive wastes management. The legal aspects and procedures for decommissioning of SRR are described in the paper. It was found, that the involvement of stakeholders at the early stages significantly promotes the decommissioning of nuclear facility. Radioactive waste management's main efforts were devoted to collecting and conditioning of 'historical' radioactive wastes from different storages outside and inside of reactor hall. All radioactive materials (more than 96 tons) were conditioned in concrete containers for disposal in the radioactive wastes repository 'Radons' at Baldone site. The dismantling of contaminated and activated components of SRR systems is discussed in paper. The cementation of dismantled radioactive wastes in concrete containers is discussed. Infrastructure of SRR, including personal protective and radiation measurement equipment, for decommissioning purposes was upgraded significantly. Additional attention was devoted to the free release measurement's technique. The certified laboratory was installed for supporting of all decommissioning activities. All non-radioactive equipments and materials outside of reactor buildings were released for clearance and dismantled for reusing or conventional disposing. Weakly contaminated materials from reactor hall were collected

  15. Second trip system for NRU research reactor

    International Nuclear Information System (INIS)

    For the past four decades, the NRU research reactor has played an important role at the Chalk River Laboratories, Atomic Energy of Canada Limited, serving as one of its major research and isotope production facilities. To ensure that it continues as an effective facility, compliant with the current safety standards, a comprehensive upgrade program is underway. Adding a second trip system (STS) is part of this upgrade program, aiming at improving the effectiveness and reliability of the overall shutdown function. This document describes the main features and basic principles of the STS.The STS is an independent, seismically qualified trip system, that guarantees reactor shutdown even if the existing trip system fails. It is designed based on 2 out of 3 general coincidence logic, with minimal interferences and changes to the existing system. In addition to the manual trip in the main control room, a remote manual trip is provided in the new Qualified Emergency Response Centre, which is also seismically qualified and always accessible. Thus, for any reason, if the main control room becomes uninhabitable, the reactor still can be manually shut down from this centre. ((orig.))

  16. Refueling strategy at the Budapest research reactor

    International Nuclear Information System (INIS)

    Refueling strategy is very important for nuclear power plants and for highly utilized research reactors with power level in the megawatt range. New core design shall fulfill several demands and needs which can contradict each other sometimes. The loaded uranium quantity should assure the scheduled operation time (energy generation) and the maneuvering capability even at the end of the campaign. On the other hand the built in excess reactivity cannot be too high, because otherwise it would jeopardize the shutdown margin and reactor safety. Moreover the core arrangement should be optimum for in-core irradiation purposes and for the beam port experiments too. Sometimes this demand can be in contradiction with the desired burnup level. The achieved burnup level is very important from the fresh fuel consumption point of view, which has direct economic significance, however the generated spent fuel quantity is an important issue too. The refueling technique presented here allowed us at the Budapest Research Reactor to reach average burnup levels superseding 60%. (author)

  17. New Research Reactor Project in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Sangik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-07-01

    New research reactor project in Korea aims to increase self-sufficiency in terms of medical and industrial radioisotope supply, to enlarge the supply of NTD silicon doping and to make up the advanced technology related to research reactor. As a major national project for nuclear science and engineering in Korea, this project has been officially started on Apr. 2012 funded by the Government and Local Governments, Kijang-Gun and Busan City, that accommodate this facility in their land. It has five years project schedule from design to commissioning just before starting the normal operation in 2017. KAERI, who is the owner contracted with the Government, is doing the design by itself based on our own knowledge and experiences from the KRR-1, KRR-2 and HANARO. The reactor is be composed of 8.0 g/cc U-Mo fuel, which is the First-of-a-kind application in world, and will be enable of operating over 300 days per year and 60% high burn-up pertinently to produce the required neutron flux. It is expected that the construction permit application will be submitted to regulatory body by the first half of 2014 and the first criticality by 2017.

  18. Improving nuclear safety at international research reactors: The Integrated Research Reactor Safety Enhancement Program (IRRSEP)

    International Nuclear Information System (INIS)

    Nuclear energy continues to play a major role in the world's energy economy. Research and test reactors are an important component of a nation's nuclear power infrastructure as they provide training, experiments and operating experience vital to developing and sustaining the industry. Indeed, nations with aspirations for nuclear power development usually begin their programs with a research reactor program. Research reactors also are vital to international science and technology development. It is important to keep them safe from both accident and sabotage, not only because of our obligation to prevent human and environmental consequence but also to prevent corresponding damage to science and industry. For example, an incident at a research reactor could cause a political and public backlash that would do irreparable harm to national nuclear programs. Following the accidents at Three Mile Island and Chernobyl, considerable efforts and resources were committed to improving the safety posture of the world's nuclear power plants. Unsafe operation of research reactors will have an amplifying effect throughout a country or region's entire nuclear programs due to political, economic and nuclear infrastructure consequences. (author)

  19. IAEA's Cross Cutting Activities on Research Reactors

    International Nuclear Information System (INIS)

    Full text: For nuclear research and technology development to continue to advance, research reactors (RRs) must be safely and reliably operated, adequately utilized, refurbished when necessary, provided with adequate proliferation-resistant fuel cycle services and safely decommissioned at the end of life. The IAEA has established its competence in the area of RRs with a long history of assistance to Member States in improving their utilization, by taking the lead in the development of safety standards, norms and dissemination of information on good practices for all aspects of the nuclear fuel cycle and in the planning and implementation of decommissioning. IAEA activities on RRs are formulated to cover a broad range of RR issues and to promote the continued development of scientific research and technological development using RRs. Member States look to the IAEA for coordination of the worldwide effort in this area and for help in solving specific problems. Today RR operating organizations need to overcome challenges such as the on-going management of ageing facilities, pressures for increased vigilance with respect to non-proliferation, and shrinking resources (financial as well as human) while fulfilling an expanding role in support of nuclear technology development. The IAEA coordinates and implements an array of activities that together provide broad support for RRs. As with other aspects of nuclear technology, RR activities within the IAEA are spread through diverse groups in different Departments. To ensure harmonized approaches a Cross-cutting coordination Group on Research Reactors (CCCGRR) has been established, with representatives from all IAEA Departments actively supporting RR activities. Utilization and application activities are generally lead from within the Department of Nuclear Sciences and Applications (NA). With respect to RRs, NA is primarily carrying out IAEA activities to assist and advise Member States in assessing their needs for research

  20. A Citation Analysis of Australian Information Systems Researchers: Towards a New ERA?

    Directory of Open Access Journals (Sweden)

    Roger Clarke

    2008-05-01

    Full Text Available Citation analysis is a potentially valuable means of assessing the contributions of researchers, in Information Systems (IS as in other disciplines. In particular, a combination of raw counts and deeper analysis of citation data can deliver insights into the impact of a researcher's publications on other researchers. Despite this potential, the limited literature in the IS discipline has paid very little attention to the use of citation analysis for this purpose. Meanwhile, the federal department responsible for education funding has convinced successive federal governments to develop research quality measures that can be used as a basis for differential funding. The Howard Government's proposed Research Quality Framework (RQF has been abandoned, but a number of aspects of it survive within the Rudd Government's Excellence in Research for Australia (ERA initiative. The ERA also appears likely to involve a highly formalised process whereby 'research groupings' within individual universities will be evaluated, with (as yet unclear impacts on the distribution of research funding. Funding agencies have an interest in score-keeping, whether or not their enthusiasm is shared by Australian researchers. It is therefore highly advisable that Australian disciplines, and especially less well-established and powerful disciplines like Information Systems, achieve a clear understanding of their performance as indicated by the available measurement techniques applied to the available data. This paper reports on citation analysis using data from both the longstanding Thomson/ISI collection and the more recently developed Google Scholar service. Few Australian IS researchers have achieved scores of any great significance in the Thomson/ISI collection, whereas the greater depth available in Google Scholar provides a more realistic picture. Quality assessment of the Thomson/ISI collection shows it to be seriously inappropriate for relatively new disciplines

  1. TRIGA research reactors with higher power density

    International Nuclear Information System (INIS)

    The recent trend in new or upgraded research reactors is to higher power densities (hence higher neutron flux levels) but not necessarily to higher power levels. The TRIGA LEU fuel with burnable poison is available in small diameter fuel rods capable of high power per rod (∼48 kW/rod) with acceptable peak fuel temperatures. The performance of a 10-MW research reactor with a compact core of hexagonal TRIGA fuel clusters has been calculated in detail. With its light water coolant, beryllium and D2O reflector regions, this reactor can provide in-core experiments with thermal fluxes in excess of 3 x 1014 n/cm2·s and fast fluxes (> 0.1 MeV) of 2 x 1014 n/cm2·s. The core centerline thermal neutron flux in the D2O reflector is about 2 x 1014 n/cm2·s and the average core power density is about 230 kW/liter. Using other TRIGA fuel developed for 25-MW test reactors but arranged in hexagonal arrays, power densities in excess of 300 kW/liter are readily available. A core with TRIGA fuel operating at 15-MW and generating such a power density is capable of producing thermal neutron fluxes in a D2O reflector of 3 x 1014 n/cm2·s. A beryllium-filled central region of the core can further enhance the core leakage and hence the neutron flux in the reflector. (author)

  2. Shielding design for research and education reactor

    International Nuclear Information System (INIS)

    For the purpose of education and research at the University, 20-KW powered SLOWPOKE-2 research reactor has been chosen as a prototype reactor. In order to study the safety characteristics of the reactor, exposure rate has been estimated at the pool boundary. Reactor core as a radiation source is assumed to be cylindrical volume source. Thus point kernel integration method can be applied to determine the exposure rate. For the sake of simplicity, calculation was done only for the prompt fission gamma rays and fission product gamma rays. As a result, the maximum exposure rate at the pool boundary was estimated to be 18R/min at the same height of the center of the core. In order to examine the accuracy for the point kernel integration method, two shielding experiments were carried out: one for the water tank only and the other for with concrete blocks outside the water tank. Water tank was made of wood pieces which is 13.4cm wide, 1.5cm thick and 2.15m long. Thus the water tank has the total dimension of 1 m radius and 2.1 m height. The experiment was carried out for the radiation source of 0.968 mCi Co-60 at the center of the water tank and the penetrated gamma rays were measured at 5 different detector positions. For the measurement and analysis of the responses, NaI(T1) 3''x3'' detector and 256 channel multichannel analyzer was utilized. To convert pulse height distribution to the exposure rate, Moriuchi conversion factor was adopted. Data from the calculations by point kernel method were well agreed within 10% band with the data from the the experiments. (Author)

  3. Vocational Trajectories within the Australian Labour Market. Research Report

    Science.gov (United States)

    Yu, Serena; Bretherton, Tanya; Schutz, Hanna

    2012-01-01

    This is a report of the first year of a three-year project entitled "Vocations: the link between post-compulsory education and the labour market." The project's aim is to research how pathways can be improved within education, within work, and between education and work. There are three strands in the project; the first strand is researching…

  4. Research Productivity and Social Capital in Australian Higher Education

    Science.gov (United States)

    Salaran, Mohammad

    2010-01-01

    This study investigates the role of social capital in raising research productivity in academic institutions. Social capital as a strategic resource embedded in social relationships can be utilised towards decreasing pressures from external environmental conditions, such as the global financial crisis. A survey was sent to academic staff in five…

  5. Procedures for the medical application of research reactors (Appendix)

    International Nuclear Information System (INIS)

    The Kyoto University Reactor (KUR) is one of the four research reactors in Japan that are currently licensed for medical application, in addition to other research purposes. Taking the KUR as an example, legal and other procedures for using research reactors for boron neutron capture therapy (BNCT) are described, which are practiced in accordance with the 'Provisional Guideline Pertaining to Medical Irradiation by Accelerators and/or Reactors, other than defined by the Medical Service Act' of the Science Council of Japan

  6. Safety Design Strategy for the Advanced Test Reactor Primary Coolant Pump and Motor Replacement Project

    Energy Technology Data Exchange (ETDEWEB)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  7. Safety Design Strategy for the Advanced Test Reactor Diesel Bus (E-3) and Switchgear Replacement Project

    Energy Technology Data Exchange (ETDEWEB)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  8. Remote mechanized equipment for the repair and replacement of boiling water reactor recirculation loop piping

    International Nuclear Information System (INIS)

    Equipment has been assembled for the remote repair or replacement of boiling water reactor nuclear plant piping in the diameter range of 4 to 28 inches (10-71 cm). The objectives of this program were to produce high-quality pipe welds, reduce plant downtime, and reduce man-rem exposure. The repair strategy was to permit repair personnel to install and check out the repair subsystems and then leave the radiation zone allowing the operations to be conducted at a distance of up to 300 feet (91 m) from the operator. The complete repair system comprises subsystems for pipe severing, dimensional gaging, joint preparation, counterboring, welding, postweld nondestructive inspection (conceptual design), and audio, electronic, and visual monitoring of all operations. Components for all subsystems, excluding those for postweld nondestructive inspection, were purchased and modified as needed for integration into the repair system. Subsystems were designed for two sizes of Type 304 stainless steelpipe. For smaller, 12-inch-diameter (30.5 cm) pipe, severing is accomplished by a power hack saw and joint preparation and counterboring by an internally mounted lathe. The 22-inch-diameter (56 cm) pipe is severed, prepared, and counterbored using an externally mounted, single-point machining device. Dimensional gaging is performed to characterize the pipe geometry relative to a fixed external reference surface, allowing the placement of the joint preparation and the counterbore to be optimized. For both pipe sizes, a track-mounted gas tungsten-arc welding head with filler wire feed is used

  9. Proceedings of the European Research Reactor Conference - RRFM 2013 Transactions

    International Nuclear Information System (INIS)

    In 2013 RRFM, the European Research Reactor Conference is jointly organised by ENS and Atomexpo LLC. This time the Research Reactor community meet in St. Petersburg, Russia. The conference programme will revolve around a series of Plenary Sessions dedicated to the latest global developments with regards to research reactor technology and management. Parallel sessions will focus on all areas of the Fuel Cycle of Research Reactors, their Utilisation, Operation and Management as well as specific research projects and innovative methods in research reactor analysis and design. In 2013 the European Research Reactor Conference will for the first time give special attention to complementary safety assessments of Research Reactors, following the Fukushima-Dai-Ichi NPP's Accident. (authors)

  10. Research reactor utilization in the Philippines

    International Nuclear Information System (INIS)

    The Philippine Research Reactor (PRR-1) has been used since 1963 for a wide spectrum of scientific activities ranging from fundamental research in nuclear physics, nuclear chemistry, and radiobiology to radioisotope production, neutron activation analysis, materials testing, and manpower development. The paper gives a brief history of the establishment of PRR-1 and its utilization. The current research programme of the Philippine Nuclear Research Institute (PNRI) using the PRR-1 is then presented. The main objective of the programme is to accelerate the application of nuclear energy for the industrialization of the country through the utilization of the PRR-1. The paper also presents the PNRI's regulatory protocol which ensures the safe operation of the PRR-1. (author)

  11. Experience and prospects for developing research reactors of different types

    International Nuclear Information System (INIS)

    NIKIET has a 60-year experience in the development of research reactors. Altogether, there have been more than 25 NIKIET-designed plants of different types built in Russia and 20 more in other countries, including pool-type water-cooled and water moderated research reactors, tank-type and pressure-tube research reactors, pressurized high-flux, heavy-water, pulsed and other research reactors. Most of the research reactors were designed as multipurpose plants for operation at research centers in a broad range of applications. Besides, unique research reactors were developed for specific application fields. Apart from the experience in the development of research reactor designs and the participation in the reactor construction, a unique amount of knowledge has been gained on the operation of research reactors. This makes it possible to use highly reliable technical solutions in the designs of new research reactors to ensure increased safety, greater economic efficiency and maintainability of the reactor systems. A multipurpose pool-type research reactor of a new generation is planned to be built at the Center for Nuclear Energy Science & Technology (CNEST) in the Socialist Republic of Vietnam to be used to support a spectrum of research activities, training of skilled personnel for Vietnam nuclear industry and efficient production of isotopes. It is exactly the applications a research reactor is designed for that defines the reactor type, design and capacity, and the selection of fuel and components subject to all requirements of industry regulations. The design of the new research reactor has a great potential in terms of upgrading and installation of extra experimental devices. (author)

  12. Current activities at the MIT research reactor

    International Nuclear Information System (INIS)

    The MIT Research Reactor (MITR) is a 5 MW nuclear research reactor that is owned and operated by the Massachusetts Institute of Technology to further its educational and research goals at both the undergraduate and graduate level. The facility (MITR-II) uses finned, aluminum-clad, plate-type fuel that is cooled and moderated by light water and reflected by heavy water. This paper provides an overview of current activities at the MITR including: (1) The current operating license will expire in August 1999. A decision has been made to pursue a power upgrade to the maximum level (6-7 MW) that can be safely supported by the existing heat removal equipment. Preparation of relicensing documents and results of thermal hydraulic studies are reviewed. (2) The status of an on-going phase-I clinical trial of BNCT for both glioblastoma multiform and metastatic melanoma will be reported. (3) A fission converter facility has been designed for advanced BNCT clinical trials and for routine therapy. This facility will provide a high quality epithermal neutron beam which is capable of treating a patient in a few minutes. Construction of the facility is currently in progress. The facility's design is summarized. (4) A recent study that was completed at the MIT-II using NAA is reported. This study entailed evaluation of the air quality in Upstate New York from October 1991 through September 1993. (5) A number of unique experimental water loop facilities for the study of light water power reactor coolant chemistry have been installed and operated in the MITR-II. The capabilities and the research objectives addressed by these facilities are summarized. (author)

  13. Current activities at the MIT research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Lin Wen; Bernard, John A.; Harling, Otto K.; Kohse, Gordon E.; Olmez, Ilhan [MIT, Cambridge (United States)

    1998-07-01

    The MIT Research Reactor (MITR) is a 5 MW nuclear research reactor that is owned and operated by the Massachusetts Institute of Technology to further its educational and research goals at both the undergraduate and graduate level. The facility (MITR-II) uses finned, aluminum-clad, plate-type fuel that is cooled and moderated by light water and reflected by heavy water. This paper provides an overview of current activities at the MITR including: (1) The current operating license will expire in August 1999. A decision has been made to pursue a power upgrade to the maximum level (6-7 MW) that can be safely supported by the existing heat removal equipment. Preparation of relicensing documents and results of thermal hydraulic studies are reviewed. (2) The status of an on-going phase-I clinical trial of BNCT for both glioblastoma multiform and metastatic melanoma will be reported. (3) A fission converter facility has been designed for advanced BNCT clinical trials and for routine therapy. This facility will provide a high quality epithermal neutron beam which is capable of treating a patient in a few minutes. Construction of the facility is currently in progress. The facility's design is summarized. (4) A recent study that was completed at the MIT-II using NAA is reported. This study entailed evaluation of the air quality in Upstate New York from October 1991 through September 1993. (5) A number of unique experimental water loop facilities for the study of light water power reactor coolant chemistry have been installed and operated in the MITR-II. The capabilities and the research objectives addressed by these facilities are summarized. (author)

  14. Innovative cost-effective technologies for Research Reactor operation safety increasing. Robotic complexes for diagnostic, recovery and repair of Research Reactors

    International Nuclear Information System (INIS)

    Today the question for operation safety providing of Research Reactors is actual worldwide. The same actual is the question of extension of operation time of the Research Reactors and Spent Fuel Storages. Early and trustworthiness diagnostics and analysis are the key procedures for safety operation of Research Reactors. To solve the question of extension of operation time and repair-recovery operations planning there review required based on complex technical diagnostics of reactor metal constructions and other equipment also. Often, diagnostic works are sufficiently complicated by specific design of the Reactor, necessity to provide diagnostic works under high radiation influence in hardly reachable areas. There application of non-traditional methods required in these cases as a result. After diagnostic works and estimation of current technical condition we could say about necessity to do recovery works. Usually, these methods are required replacement of worst case constructions and installation of new ones to provide prolongation of Research Reactor's operation time. These methods are required significant time spending and extra money for recovery and additional expenses caused by Reactor outage. DIAKONT company by order of ROSATOM has created alternative technology for efficient diagnostic and recovery to minimize operation expenses caused by Reactor outage. DIAKONT based on long-term designing and installation experience of special-purpose equipment for safety increasing on Energy and Research Nuclear Objects has developed the Remote Operated diagnostic and welding complex, which could accurately estimate current technical condition of metal constructions, provide repair and recovery works and sufficiently decrease expenses for repair and outage. The complex is efficiently solving the following tasks: Remote-operated diagnostic of reactor and spent fuel storages metal constructions (especially in hardly reachable areas) including: Measurement of metal

  15. Inspection and repair techniques in the reactor vessel of the experimental fast reactor Joyo. Development of repair techniques for UCS replacement of Joyo

    International Nuclear Information System (INIS)

    Development of repair techniques in the reactor vessel of sodium cooled fast reactors is important to secure its safety and integrity. With the incident as an opportunity, repair techniques for Upper Core Structure (UCS) replacement was developed in Joyo. Since the UCS of Joyo was designed as an eternal structure and it has high dose rate due to the irradiation for over 30 years, the following subjects were mainly discussed in this study as critical tasks. (1) Prevention of deformation during jack-up and retrieval of the UCS, (2) Reducing UCS cask weight In order to resolve above (1), the allowable load to prevent the deformation of the UCS and guide sleeve were evaluated using finite element method analysis code with 3-D model. Furthermore, the general design of the equipment were established based on the requirement of monitoring and control of the factors (load, flatness, inclination and pull-up speed etc.) and gap observation to achieve UCS jack-up and retrieval. Concerning with above (2), multistage cask without crane and door valve was suggested in this study. As a result of this study, total weight of cask (including UCS) was reduced to be less than 100ton, which is the maximum load of the crane in the reactor containment vessel of Joyo. The UCS replacement is scheduled in 2014. Achievement of the UCS replacement and accumulated experience will be able to provide valuable insights for further improving and verifying repair techniques in sodium cooled fast reactors. (author)

  16. Grey Component Replacement Research, Modelling Tone And Color Reproduction

    Science.gov (United States)

    Fisch, Richard S.

    1990-06-01

    Four different scanning Color Electronic Pagination System (CEPS) devices were tested to study their conventional and Grey Component Replacement/Undercolor Addition (GCR/UCA) tone and color response in the 4 color Positive Acting Offset Lithographic printing process. A common transparency input and ganged printing output was used. Inter and intra machine differences are disclosed. A new depiction of the full tone reproduction characteristics is presented for several different levels of GCR/UCA and conventional printing.

  17. Operation experience of the research reactor HANARO

    International Nuclear Information System (INIS)

    Operation experiences and the status of utilization facilities are presented in this paper. Problems in the reactor regulating system, diesel generator, cooling fan, and fuel handling are described, along with their causes and the actions taken. Most of the problems were caused by instrument error but the problem in the cooling fan could be classified as a human error. Such problems are minor but give a lesson in reactor operation and maintenance. More kinds of radioisotopes are being produced every year in parallel with improvements in production technology. The number of neutron activation analyses and neutron radiography tasks done for customers is increasing. In the Hanaro reactor five beam tubes are reserved for neutron beam research and in three of them the beam facilities are already installed or are in installation. Non-fissile material testing using a capsule was performed and fissile material tests are planned for the beginning of 1999. The fuel test loop is expected to hold its first fuel test in the year 2000. Fission molybdenum, cold neutron source, and neutron capture therapy are in the stage of conceptual or basic design. The use of HANARO will be more and more in demand as installation of utilization facilities increases year by year. (author)

  18. Status and some safety philosophies of the China advanced research reactor CARR

    International Nuclear Information System (INIS)

    The existing two research reactors, HWRR (heavy water research reactor) and SPR (swimming pool reactor), have been operated by China Institute of Atomic Energy (CIAE) since, respectively, 1958 and 1964, and are both in extending service and facing the aging problem. It is expected that they will be out of service successively in the beginning decade of the 21st century. A new, high performance and multipurpose research reactor called China advanced research reactor (CARR) will replace these two reactors. This new reactor adopts the concept of inverse neutron trap compact core structure with light water as coolant and heavy water as the outer reflector. Its design goal is as follows: under the nuclear power of 60MW, the maximum unperturbed thermal neutron flux in peripheral D2O reflector not less than 8 x 1014 n/cm2. s while in central experimental channel, if the central cell to be replaced by an experimental channel, the corresponding value not less than 1 x 1015 n/cm2. s. The main applications for this research reactor will cover RI production, neutron scattering experiments, NAA and its applications, neutron photography, NTD for monocrystaline silicon and applications on reactor engineering technology. By the end of 1999, the preliminary design of CARR was completed, then the draft of preliminary safety analysis report (PSAR) was submitted to the relevant authority at the end of 2000 for being reviewed. Now, the CARR project has entered the detail design phase and safety reviewing procedure for obtaining the construction permit from the relevant licensing authority. This paper will only briefly introduce some aspects of safety philosophy of CARR design and PSAR. (orig.)

  19. Monte Carlo modelling of TRIGA research reactor

    Energy Technology Data Exchange (ETDEWEB)

    El Bakkari, B., E-mail: bakkari@gmail.co [Reactor Operating Unit (UCR), National Centre of Sciences, Energy and Nuclear Techniques (CNESTEN/CENM), POB 1382, Rabat (Morocco); ERSN-LMR, Department of Physics, Faculty of Sciences, POB 2121, Tetuan (Morocco); Nacir, B. [Reactor Operating Unit (UCR), National Centre of Sciences, Energy and Nuclear Techniques (CNESTEN/CENM), POB 1382, Rabat (Morocco); El Bardouni, T. [ERSN-LMR, Department of Physics, Faculty of Sciences, POB 2121, Tetuan (Morocco); El Younoussi, C. [Reactor Operating Unit (UCR), National Centre of Sciences, Energy and Nuclear Techniques (CNESTEN/CENM), POB 1382, Rabat (Morocco); ERSN-LMR, Department of Physics, Faculty of Sciences, POB 2121, Tetuan (Morocco); Merroun, O. [ERSN-LMR, Department of Physics, Faculty of Sciences, POB 2121, Tetuan (Morocco); Htet, A. [Reactor Technology Unit (UTR), National Centre of Sciences, Energy and Nuclear Techniques (CNESTEN/CENM), POB 1382, Rabat (Morocco); Boulaich, Y. [Reactor Operating Unit (UCR), National Centre of Sciences, Energy and Nuclear Techniques (CNESTEN/CENM), POB 1382, Rabat (Morocco); ERSN-LMR, Department of Physics, Faculty of Sciences, POB 2121, Tetuan (Morocco); Zoubair, M.; Boukhal, H. [ERSN-LMR, Department of Physics, Faculty of Sciences, POB 2121, Tetuan (Morocco); Chakir, M. [EPTN-LPMR, Faculty of Sciences, Kenitra (Morocco)

    2010-10-15

    The Moroccan 2 MW TRIGA MARK II research reactor at Centre des Etudes Nucleaires de la Maamora (CENM) achieved initial criticality on May 2, 2007. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes for their use in agriculture, industry, and medicine. This study deals with the neutronic analysis of the 2-MW TRIGA MARK II research reactor at CENM and validation of the results by comparisons with the experimental, operational, and available final safety analysis report (FSAR) values. The study was prepared in collaboration between the Laboratory of Radiation and Nuclear Systems (ERSN-LMR) from Faculty of Sciences of Tetuan (Morocco) and CENM. The 3-D continuous energy Monte Carlo code MCNP (version 5) was used to develop a versatile and accurate full model of the TRIGA core. The model represents in detailed all components of the core with literally no physical approximation. Continuous energy cross-section data from the more recent nuclear data evaluations (ENDF/B-VI.8, ENDF/B-VII.0, JEFF-3.1, and JENDL-3.3) as well as S({alpha}, {beta}) thermal neutron scattering functions distributed with the MCNP code were used. The cross-section libraries were generated by using the NJOY99 system updated to its more recent patch file 'up259'. The consistency and accuracy of both the Monte Carlo simulation and neutron transport physics were established by benchmarking the TRIGA experiments. Core excess reactivity, total and integral control rods worth as well as power peaking factors were used in the validation process. Results of calculations are analysed and discussed.

  20. Monte Carlo modelling of TRIGA research reactor

    International Nuclear Information System (INIS)

    The Moroccan 2 MW TRIGA MARK II research reactor at Centre des Etudes Nucleaires de la Maamora (CENM) achieved initial criticality on May 2, 2007. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes for their use in agriculture, industry, and medicine. This study deals with the neutronic analysis of the 2-MW TRIGA MARK II research reactor at CENM and validation of the results by comparisons with the experimental, operational, and available final safety analysis report (FSAR) values. The study was prepared in collaboration between the Laboratory of Radiation and Nuclear Systems (ERSN-LMR) from Faculty of Sciences of Tetuan (Morocco) and CENM. The 3-D continuous energy Monte Carlo code MCNP (version 5) was used to develop a versatile and accurate full model of the TRIGA core. The model represents in detailed all components of the core with literally no physical approximation. Continuous energy cross-section data from the more recent nuclear data evaluations (ENDF/B-VI.8, ENDF/B-VII.0, JEFF-3.1, and JENDL-3.3) as well as S(α, β) thermal neutron scattering functions distributed with the MCNP code were used. The cross-section libraries were generated by using the NJOY99 system updated to its more recent patch file 'up259'. The consistency and accuracy of both the Monte Carlo simulation and neutron transport physics were established by benchmarking the TRIGA experiments. Core excess reactivity, total and integral control rods worth as well as power peaking factors were used in the validation process. Results of calculations are analysed and discussed.

  1. Monte Carlo modelling of TRIGA research reactor

    Science.gov (United States)

    El Bakkari, B.; Nacir, B.; El Bardouni, T.; El Younoussi, C.; Merroun, O.; Htet, A.; Boulaich, Y.; Zoubair, M.; Boukhal, H.; Chakir, M.

    2010-10-01

    The Moroccan 2 MW TRIGA MARK II research reactor at Centre des Etudes Nucléaires de la Maâmora (CENM) achieved initial criticality on May 2, 2007. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes for their use in agriculture, industry, and medicine. This study deals with the neutronic analysis of the 2-MW TRIGA MARK II research reactor at CENM and validation of the results by comparisons with the experimental, operational, and available final safety analysis report (FSAR) values. The study was prepared in collaboration between the Laboratory of Radiation and Nuclear Systems (ERSN-LMR) from Faculty of Sciences of Tetuan (Morocco) and CENM. The 3-D continuous energy Monte Carlo code MCNP (version 5) was used to develop a versatile and accurate full model of the TRIGA core. The model represents in detailed all components of the core with literally no physical approximation. Continuous energy cross-section data from the more recent nuclear data evaluations (ENDF/B-VI.8, ENDF/B-VII.0, JEFF-3.1, and JENDL-3.3) as well as S( α, β) thermal neutron scattering functions distributed with the MCNP code were used. The cross-section libraries were generated by using the NJOY99 system updated to its more recent patch file "up259". The consistency and accuracy of both the Monte Carlo simulation and neutron transport physics were established by benchmarking the TRIGA experiments. Core excess reactivity, total and integral control rods worth as well as power peaking factors were used in the validation process. Results of calculations are analysed and discussed.

  2. Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program

    Energy Technology Data Exchange (ETDEWEB)

    1987-05-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions.

  3. Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program

    International Nuclear Information System (INIS)

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions

  4. "They should come out here ...": research findings on lack of local palliative care services for Australian aboriginal people.

    Science.gov (United States)

    McGrath, Pam; Holewa, Hamish; Kail-Buckley, Stasia

    2007-01-01

    Although Aboriginal Australians experience morbidity and mortality rates far greater than that of the wider Australian population, to date, their access to culturally appropriate palliative care services has remained unexplored. This article provides findings from an Australian National Health and Medical Research funded study that documents the availability of palliative care services to Aboriginal peoples of the Northern Territory, Australia. The data were collected through a series of open-ended, qualitative interviews with a cross section of Aboriginal peoples and health professionals conducted during a 2-year period. The findings provide an overview of the palliative care services that are presently available and reflect a serious lack of local, culturally appropriate palliative care services. This research shows the similarities in the struggles and difficulties faced by Australian Aboriginals and Indigenous peoples worldwide. The hope is that the suggestions put forward for improvement will one day be useful for the world's Indigenous peoples. PMID:17502434

  5. TRIGA research reactor activities around the world

    International Nuclear Information System (INIS)

    Recent activities at several overseas TRIGA installations are discussed in this paper, including reactor performance, research programs under way, and plans for future upgrades. The following installations are included: (1) 14,000-kW TRIGA at the Institute for Nuclear Research, Pitesti, Romania; (2) 2,000-kW TRIGA Mark II at the Institute of Nuclear Technology, Dhaka, Bangladesh; (3) 3,000-kW TRIGA conversion, Philippine Nuclear Research Institute, Quezon City, Philippines; and (4) other ongoing installations, including a 1,500-kW TRIGA Mark II at Rabat, Morocco, and a 1,000-kW conversion/upgrade at the Institute Asunto Nucleares, Bogota, Columbia

  6. TRIGA research reactor activities around the world

    Energy Technology Data Exchange (ETDEWEB)

    Chesworth, R.H.; Razvi, J.; Whittemore, W.L. (General Atomics, San Diego, CA (United States))

    1991-11-01

    Recent activities at several overseas TRIGA installations are discussed in this paper, including reactor performance, research programs under way, and plans for future upgrades. The following installations are included: (1) 14,000-kW TRIGA at the Institute for Nuclear Research, Pitesti, Romania; (2) 2,000-kW TRIGA Mark II at the Institute of Nuclear Technology, Dhaka, Bangladesh; (3) 3,000-kW TRIGA conversion, Philippine Nuclear Research Institute, Quezon City, Philippines; and (4) other ongoing installations, including a 1,500-kW TRIGA Mark II at Rabat, Morocco, and a 1,000-kW conversion/upgrade at the Institute Asunto Nucleares, Bogota, Columbia.

  7. Simulation of the TR-1 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dayday, N.; Alsan, S.; Erk, S.

    1978-01-01

    TR-1 is a 1 MW pool-type research reactor. A simulation of TR-1 was attempted in order to predict the values and the variations of principal parameters during the normal and accident conditions. A model based on point kinetics was developed and the variations of neutronics and thermal parameters were studied. A computer program was prepared and successfully run on a desktop calculator HP 9821. Thus it has been shown that a digital computer may be used in a simulation problem in contrast to an analog or hybrid type which are commonly used.

  8. Experimental facilities for Generation IV reactors research

    International Nuclear Information System (INIS)

    Centrum Vyzkumu Rez (CVR) is research and development Company situated in Czech Republic and member of the UJV group. One of its major fields is material research for Generation IV reactor concepts, especially supercritical water-cooled reactor (SCWR), very high temperature/gas-cooled fast reactor (VHTR/GFR) and lead-cooled fast reactor (LFR). The CVR is equipped by and is building unique experimental facilities which simulate the environment in the active zones of these reactor concepts and enable to pre-qualify and to select proper constructional materials for the most stressed components of the facility (cladding, vessel, piping). New infrastructure is founded within the Sustainable Energy project focused on implementation the Generation IV and fusion experimental facilities. The research of SCWR concept is divided to research and development of the constructional materials ensured by SuperCritical Water Loop (SCWL) and fuel components research on Fuel Qualification Test loop (SCWL-FQT). SCWL provides environment of the primary circuits of European SCWR, pressure 25 MPa, temperature 600 deg. C and its major purpose is to simulate behavior of the primary medium and candidate constructional materials. On-line monitoring system is included to collect the operational data relevant to experiment and its evaluation (pH, conductivity, chemical species concentration). SCWL-FQT is facility focused on the behavior of cladding material and fuel at the conditions of so-called preheater, the first pass of the medium through the fuel (in case of European SCWR concept). The conditions are 450 deg. C and 25 MPa. SCWL-FQT is unique facility enabling research of the shortened fuel rods. VHTR/GFR research covers material testing and also cleaning methods of the medium in primary circuit. The High Temperature Helium Loop (HTHL) enables exposure of materials and simulates the VHTR/GFR core environment to analyze the behavior of medium, especially in presence of organic compounds and

  9. Project Experiences in Research Reactor Ageing Management, Modernization and Refurbishment. Report of a Technical Meeting on Research Reactor Ageing Management, Modernization and Refurbishment

    International Nuclear Information System (INIS)

    Research reactors have played an important role in several scientific fields for around 60 years: in the development of nuclear science and technology; in the valuable generation of radioisotopes for various applications; and in the development of human resources and skills. Moreover, research reactors have been effectively utilized to support sustainable development in more than 60 countries worldwide. More than half of all operating research reactors are now over 40 years old, with many exceeding their originally conceived design life. The majority of operating research reactors face challenges due to the negative impacts of component and system ageing, which manifest in a number of forms. This situation was highlighted by a serious medical isotope supply crisis which peaked in mid-2010, when several major producing reactors underwent prolonged shutdowns due to extensive necessary overhauls of various systems. Several facilities have established a proactive systematic approach to managing ageing or mitigating its impact on safety and availability of isotopes. Others have tried to prevent or remedy the drawbacks of ageing on a case by case basis. Overall, a large body of knowledge related to ageing issues exists in many Member States. Collecting and sharing this information within the research reactor community can provide a solid foundation to develop a more systematic approach — that is, an ageing management programme to prevent negative consequences of ageing on the safety, and the operability and lifetime of operating, or even future, reactors. It may also help organizations to manage research reactors that have been in an extended shutdown state by ensuring that any required systems are operated and maintained in a safe manner prior to final decommissioning and disposal of fuel to safe storage facilities. Sharing experiences from projects undertaken to refurbish or replace equipment and systems, satisfy safety and regulatory requirements, improve

  10. INVAP Experience in the Design and Construction of Research Reactors. (Research Reactors in and from Argentina)

    International Nuclear Information System (INIS)

    Full Text: Argentina has a long tradition in the design and construction of Research Reactors. The first research reactor in Argentina, RA-1, was built by CNEA (Argentina Atomic Energy Commission) in 1958, using drawings lent by USA. RA-2, RA-3, RA-4 and RA-0 followed through. In 1976, a career degree in Nuclear Engineering was started by CNEA and the University of Cuyo in Bariloche. It was decided that there would be a university type reactor to assist with the training of the students. INVAP, a recently created company, was assigned the task of building the reactor in accordance with the engineering developed by CNEA. The RA-6 was a very successful project, which allowed INVAP to build the knowledge for participating in RR projects abroad. Since 1982, INVAP has built research reactors in Algeria, Egypt, Argentina and Australia and had a large participation in the RRs CNEA built in Peru. INVAP has also designed several other RR for different clients, which were not subsequently built. This paper explores this history, giving details of the RR projects in which INVAP has been involved through the years. (author)

  11. The AFR. An approved network of research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, Gabriele [Mainz Univ. (Germany). Arbeitsgemeinschaft fuer Betriebs- und Sicherheitsfragen an Forschungsreaktoren (AFR)

    2012-10-15

    AFR (Arbeitsgemeinschaft fuer Betriebs- und Sicherheitsfragen an Forschungsreaktoren) is the German acronym for 'Association for Research Reactor Operation and Safety Issues' which was founded in 1959. Reactor managers of European research reactors mainly from the German linguistic area meet regularly for their mutual benefit to exchange experience and knowledge in all areas of operating, managing and utilization of research reactors. In the last 2 years joint meetings were held together with the French association of research reactors CER (Club d'Exploitants des Reacteurs). In this contribution the AFR, its members, work and aims as well as the French partner CER are presented. (orig.)

  12. Present status of BNCT at Kyoto University Research Reactor Institute

    International Nuclear Information System (INIS)

    At Kyoto University Research Reactor Institute, we have two facilities for BNCT such as a reactor-based and an accelerator-based neutron source. In this article, we will present the characteristics overview of both facilities. (author)

  13. Taking into account a reactivity accident in research reactors design

    International Nuclear Information System (INIS)

    The particular studies realized in France for research reactors design at a Borax accident type are described. The cases of ORPHEE and RHF reactors are particularly developed. The evolution of the studies and the conservatism used are given

  14. Refurbishment of IRT-2000 research reactor in Sofia

    International Nuclear Information System (INIS)

    The decommissioning strategy of IRT-2000 research reactor, Sofia is subjected to a refurbishment into low-power reactor. Some pre-decommissioning activities of this complicated decommissioning-refurbishment process have been carried out. (author)

  15. Development of the HANARO research reactor simulator for operator training

    International Nuclear Information System (INIS)

    HANARO (High flux Advanced Neutron Application ReactOr) is multi purpose research reactor in Korea Atomic Energy research Institute, and is operating since 1995. It is needed that training and retraining programs for the operating staff, including: reactor manager, shift supervisors, reactor operators, and others working at the research reactor facility. Recently, we developed HANARO research reactor real time simulator for operating staff training to satisfy these programs. The development of computer based training simulator have provided an easy understanding of reactor physics, operation, and control. Real time simulator is recognized as the ultimate training tool because they allow experiencing, in a dynamic mode, every type of operational condition which can be encountered including: start up, variation of power, shut down, operation during accidents, etc. Also, the simulator will be used as a dynamic test-bed for the reactor regulating system control algorithm

  16. Development of the HANARO research reactor simulator for operator training

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee Choon; Kim, Jang Yeol; Park, Jae Chang; Lee, Seung Wook; Hwang, In Ah; Lee, Dong Young [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    HANARO (High flux Advanced Neutron Application ReactOr) is multi purpose research reactor in Korea Atomic Energy research Institute, and is operating since 1995. It is needed that training and retraining programs for the operating staff, including: reactor manager, shift supervisors, reactor operators, and others working at the research reactor facility. Recently, we developed HANARO research reactor real time simulator for operating staff training to satisfy these programs. The development of computer based training simulator have provided an easy understanding of reactor physics, operation, and control. Real time simulator is recognized as the ultimate training tool because they allow experiencing, in a dynamic mode, every type of operational condition which can be encountered including: start up, variation of power, shut down, operation during accidents, etc. Also, the simulator will be used as a dynamic test-bed for the reactor regulating system control algorithm.

  17. A Study on the demands of research reactors and considerations for an export

    Energy Technology Data Exchange (ETDEWEB)

    Park, Cheol; Lee, Young Jun

    2008-11-15

    Among around 240 research reactors in operation over the world, around 80% have been operated for more than 20 years and 65% for more than 30 years. Hence the number of operable reactors is expected, between 2010 and 2020, to be reduced to 1/3 of the present situation if the lifetime of a research reactor is assumed to be 40 years. However, considering the recent re-highlighting of nuclear energy as a practical mass energy source and the contributions to the overall areas of science and technology, the demands for constructing a new research reactor and replacing the existing research reactors will be increased in the near future. On the other hand, vendors which participate in providing research reactors are not few, and AREVA in France and INVAP in Argentina are example of them in a positive position. Japan and Russia are regarded as potential competitors, but they do not actively appear in the market so far. Comparing those competitors with Korea, we have weak points regarding experiences on exports and the organizational systems as an integrated vendor. But we may have a competitiveness by grafting our experiences on the development of nuclear power technology and the construction and operation of the HANARO. In this report, the future potential demands for research reactors and the related considerations for exports have been surveyed and described, particularly, centering around the Netherlands, Vietnam and Thailand that are countries which may construct research reactors in the near future. Considerations for exporting a research reactor have been categorized into two groups of technical and nontechnical items. From a technical point of view, the issues on fuel and reactor type, design data and design ability, design codes, and technology property rights have been reviewed. For the non-technical items, an integrated project system, reasonable estimate of demands, social and economic conditions for potential demand countries, MOU status, nuclear non

  18. Operation and Utilizations of Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    The reconstructed Dalat nuclear research reactor was commissioned in March 1984 and up to September 1988 more than 6200 hours of operation at nominal power have been recorded. The major utilizations of the reactor include radioisotope production, activation analysis, nuclear data research and training. A brief review of the utilization of the reactor is presented. Some aspects of reactor safety are also discussed. (author) 2 figs.; 5 refs.; 1 tab

  19. Progress in Promoting Research Reactor Coalitions

    International Nuclear Information System (INIS)

    This presentation treats of the IAEA's role in Promoting Research Reactor (RR) coalitions, presents the strategic view, the types of coalitions, the 2007-2008 activities and Results, and the upcoming activities. The RR Coalitions Progress is presented first (Initial discussions, project design, approval of NTI grant request, informal consultations and development of 'national' proposals, Number of 'models' identified, exploratory missions/meetings, initial implementation of several coalitions, IAEA coordination, ideas/proposals/ventures, initial support. Some countries, institutes, or users want access to reactor capabilities without, or in advance of, building a domestic facility. Some countries, institutes, or users need access to alternative capabilities to permit the closure/consolidation of marginal facilities. Cooperative arrangements will result in increased utilization for each participant. The results from the reactor view are as follows: cover increases in order levels or scientific research; cover facility outages (planned or un-planned); delegate 'less profitable' products and services; access capacity for new products and services; reduce transport needs by geographical optimization; reduce investment needs by contracting for complementary capabilities; reduce costs of medical radio-isotope for R and D; share best practices in operations and safety. The results from the stakeholder View are: Better information on what reactors can offer/provide; greater range of services; more proactive product and service support; greater reliability in supplies of products and services. The types of coalitions are of different forms to meet needs, capabilities, objectives of members. In general they start small, evolve, change form, expand as confidence grows. The role of the Scientific consortium is to: distribute excess demand, test new concepts for implementation at high-flux reactors, direct requests for access to most appropriate RR, share best practices

  20. A Delphi study on research priorities in radiation therapy: The Australian perspective

    Energy Technology Data Exchange (ETDEWEB)

    Cox, Jennifer [Faculty of Health Sciences, University of Sydney, P.O. Box 170, Lidcombe, NSW 1825 (Australia)], E-mail: jenny.cox@usyd.edu.au; Halkett, Georgia [Western Australia Centre for Cancer and Palliative Care, Curtin University of Technology, Health Research Campus, GPO Box U1987, Perth, WA 6845 (Australia)], E-mail: g.halkett@curtin.edu.au; Anderson, Claudia [Faculty of Health Sciences, University of Sydney, P.O. Box 170, Lidcombe, NSW 1825 (Australia)], E-mail: claudia.anderson@usyd.edu.au; Heard, Robert [Faculty of Health Sciences, University of Sydney, P.O. Box 170, Lidcombe, NSW 1825 (Australia)], E-mail: r.heard@staff.usyd.edu.au

    2010-02-15

    Radiation therapists (RTs) need to engage more in research to establish an evidence base for their daily practice. However, RTs world-wide conduct little research themselves, although positive moves have been made in some countries. This project is the second stage of a Delphi process aimed at prioritising RT areas of research interest. A questionnaire was constructed using responses to a previous questionnaire which identified the research interests of Australian RTs. Fifty-three Research Areas were identified from these responses and grouped into 12 categories such as 'imaging in radiation therapy', 'symptom management', 'accuracy of patient positioning' and 'techniques/equipment'. The survey was sent to all Australian departments of radiation oncology, and RTs were asked to form interest groups to discuss and prioritise the Research Areas. There was a 50% response rate (18 of 36 departments surveyed). The highest ranked research Category was 'imaging in radiation therapy'. Six of the top 10 ranked Research Areas were within Central RT practice ('imaging in radiation therapy'; 'symptom management'; 'accuracy of patient positioning' and 'techniques/equipment') and the other four were within broader RT practice ('diversification, recognition and other professional issues'; and 'management and staff issues'). Patient Care was also considered to be an area requiring more research. This prioritization of Research Areas and categories provides a useful list of future research for RTs, which will enable them to decide whether their research ideas are a high priority, and spend less time deciding on a relevant research topic that needs investigation in their own workplaces.

  1. Radiological consequence analysis of research reactors

    International Nuclear Information System (INIS)

    The objective of the project is to study the environmental effects of research reactors having low enriched uranium as fuel in case of accident by using standard computer code KORIGEN. The study includes fission product inventory in core, atmospheric dispersion of radioactive effluents and dose rates at different receptor locations in order to determine the boundaries of extension and low population zones. Computer code KORIGEN has been employed to calculate the core inventory. Mathematical models were used to calculate the activity behavior and dose rates. Pakistan research reactor-1 (PARR-1) has been considered for the analysis. A continuous run for 123 days was assumed to achieve the target burn up of core. For a cooling time of 90 days the decay of total activity and decay heat was also studied. During this time activity and decay heat were reduced to 2.63% and 0.847% of their shut down values. The code may also be used to calculate fuel burn up and multiplication factor. (author)

  2. Refurbishing - A cost effective option for long term operation of research reactors

    International Nuclear Information System (INIS)

    In recent times it has been observed that the life time of research reactors can be significantly extended through implementation of appropriate refurbishing actions. This is feasible since the initially proclaimed design life of such facilities in most cases, is an arbitrary number. This aspect is applicable to research reactors, nuclear power plants and many nuclear fuel cycle facilities. In India extensive refurbishing of the 40 MWt research reactor CIRUS was done during 1997-2002. Cirus is a vertical tank type reactor using natural uranium as fuel, light water as coolant, heavy water as moderator and graphite as reflector and became operational in 1960. Detailed ageing assessment of its systems, structures and components was done during 1992-1997 after the reactor had been in operation for about 30 years. The assessment included inspections, operating experience review, review of the Safety Analysis Report, seismic re-evaluation of structures and assessment of stored energy in the graphite reflector. A refurbishing plan was then drawn-up and preparatory work undertaken that included development of procedures, procurement of replacement items etc. The reactor was then shutdown, core unloaded and reactor systems were prepared for preservation during refurbishing. Extensive refurbishing was then carried out and the reactor brought back into operation successfully. During refurbishing, a low temperature vacuum evaporation based desalination unit was also coupled to the reactor to serve as demonstration of using waste heat from a research reactor for sea water desalination. The scope of refurbishing of Cirus got considerably expanded as a result of identification of additional jobs during further inspections undertaken after reactor shut-down and core unloading. Consequently the refurbishing took about 5 years against the initially planned period of about 3 years. In spite of this, the facility could be refurbished at a cost which is less than 10% of the cost of

  3. The present status and the prospect of China research reactors

    International Nuclear Information System (INIS)

    A total of 100 reactor operation years' experience of research reactors has now been obtained in China. The type and principal parameters of China research reactors and their operating status are briefly introduced in this paper. Chinese research reactors have been playing an important role in nuclear power and nuclear weapon development, industrial and agricultural production, medicine, basic and applied science research and environmental protection, etc. The utilization scale, benefits and achievements will be given. There is a good safety record in the operation of these reactors. A general safety review is discussed. The important incidents and accidents happening during a hundred reactor operating years are described and analyzed. China has the capability of developing any type of research reactor. The prospective projects are briefly introduced

  4. Molten salt reactor related research in Switzerland

    International Nuclear Information System (INIS)

    Switzerland represented by the Paul Scherrer Institute (PSI) is a member of the Generation IV International Forum (GIF). In the past, the research at PSI focused mainly on HTR, SFR, and GFR. Currently, a research program was established also for Molten Salt Reactors (MSR). Safety is the key point and main interest of the MSR research at the Nuclear Energy and Safety (NES) department of PSI. However, it cannot be evaluated without knowing the system design, fuel chemistry, salt thermal-hydraulics features, safety and fuel cycle approach, and the relevant material and chemical limits. Accordingly, sufficient knowledge should be acquired in the other individual fields before the safety can be evaluated. The MSR research at NES may be divided into four working packages (WP): WP1: MSR core design and fuel cycle, WP2: MSR fuel behavior at nominal and accidental conditions, WP3: MSR thermal-hydraulics and decay heat removal system, WP4: MSR safety, fuel stream, and relevant limits. The WPs are proposed so that there are research topics which can be independently studied within each of them. The work plan of the four WPs is based on several ongoing or past national and international projects relevant to MSR, where NES/PSI participates. At the current stage, the program focuses on several specific and design independent studies. The safety is the key point and main long-term interest of the MSR research at NES. (author)

  5. Research reactor de-fueling and fuel shipment

    International Nuclear Information System (INIS)

    Planning for the Georgia Institute of Technology Research Reactor operations during the 1996 Summer Olympic Games began in early 1995. Before any details could be outlined, several preliminary administrative decisions had to be agreed upon by state, city, and university officials. The two major administrative decisions involving the reactor were (1) the security level and requirements and (2) the fuel status of the reactor. The Georgia Tech Research Reactor (GTRR) was a heavy-water moderated and cooled reactor, fueled with high-enriched uranium. The reactor was first licensed in 1964 with an engineered lifetime of thirty years. The reactor was intended for use in research applications and as a teaching facility for nuclear engineering students and reactor operators. Approximately one year prior to the olympics, the Georgia Tech administration decided that the GTRR fuel would be removed. In addition, a heightened, beyond regulatory requirements, security system was to be implemented. This report describes the scheduling, operations, and procedures

  6. The current status and future plan of nuclear research reactor in Thailand

    International Nuclear Information System (INIS)

    Thailand has involved in the field of Nuclear Research Reactor for about 30 years since the first Research Reactor TRR-1 was established in 1962. In 1975 the TRR-1 was shutdown for the first modification (TRR-1/M1) mainly with the Reactor Core by replacing the Core with TRIGA Mark III. Also the modifications were performed with the associated system i.e. Cooling, I and C and Irradiation facilities. Major utilizations of the TRR-1/M1 are NAA basic research, Radioisotope production for medical uses, and personnel training. Currently, the TRR-1/M1 is being shutdown for the second modification principally with the reactor pool and beam tubes. The shutdown has been started early this year and is expected to last by the end of 1991. Upon the Thai's cabinet, agreement on December 27, 1989 the decision was made to relocate the reactor TRR-1/M1. The OAEP responds to this decision by considering to purchase a new reactor with about 5 MW thermal power capacity for the new center. In the meantime, the TRR-1/M1 will continue further operation for about 8-10 years until the complete establishment of the New Research Reactor in the New Nuclear Research Center by the next decade. Decommissioning of the TRR-1/M1 after then is also being planned by the OAEP staff. (author)

  7. Present status of research reactor decommissioning programme in Indonesia

    International Nuclear Information System (INIS)

    At present Indonesia has 3 research reactors, namely the 30 MW MTR-type multipurpose reactor at Serpong Site, two TRIGA-type research reactors, the first one being 1 MW located at Bandung Site and the second one a small reactor of 100 kW at Yogyakarta Site. The TRIGA Reactor at the Bandung Site reached its first criticality at 250 kW in 1964, and then was operated at 1000 kW since 1971. In October 2000 the reactor power was successfully upgraded to 2 MW. This reactor has already been operated for 38 years. There is not yet any decision for the decommissioning of this reactor. However it will surely be an object for the near future decommissioning programme and hence anticipation for the above situation becomes necessary. The regulation on decommissioning of research reactor is already issued by the independent regulatory body (BAPETEN) according to which the decommissioning permit has to be applied by the BATAN. For Indonesia, an early decommissioning strategy for research reactor dictates a restricted re-use of the site for other nuclear installation. This is based on high land price, limited availability of radwaste repository site, and other cost analysis. Spent graphite reflector from the Bandung TRIGA reactor is recommended for a direct disposal after conditioning, without any volume reduction treatment. Development of human resources, technological capability as well as information flow from and exchange with advanced countries are important factors for the future development of research reactor decommissioning programme in Indonesia. (author)

  8. Global estimation of potential unreported plutonium in thermal research reactors

    International Nuclear Information System (INIS)

    As of November, 1993, 303 research reactors (research, test, training, prototype, and electricity producing) were operational worldwide; 155 of these were in non-nuclear weapon states. Of these 155 research reactors, 80 are thermal reactors that have a power rating of 1 MW(th) or greater and could be utilized to produce plutonium. A previously published study on the unreported plutonium production of six research reactors indicates that a minimum reactor power of 40 MW (th) is required to make a significant quantity (SQ), 8 kg, of fissile plutonium per year by unreported irradiations. As part of the Global Nuclear Material Control Model effort, we determined an upper bound on the maximum possible quantity of plutonium that could be produced by the 80 thermal research reactors in the non-nuclear weapon states (NNWS). We estimate that in one year a maximum of roughly one quarter of a metric ton (250 kg) of plutonium could be produced in these 80 NNWS thermal research reactors based on their reported power output. We have calculated the quantity of plutonium and the number of years that would be required to produce an SQ of plutonium in the 80 thermal research reactors and aggregated by NNWS. A safeguards approach for multiple thermal research reactors that can produce less than 1 SQ per year should be conducted in association with further developing a safeguards and design information reverification approach for states that have multiple research reactors

  9. Replacement of the reactor control and protection system in Unit 1 and 2 of the Beznau Nuclear Power Plant

    International Nuclear Information System (INIS)

    The Beznau Nuclear Power Plant (KKB) consists of two identical units and is located in the lower Aare River valley. The plant has an electrical capacity of 760 MW and is operated by Nordostschweizerische Kraftwerke (NOK). Both units are pressurized-water reactors, each with two steam generators and two turbine sets. Unit 1 came on-line in 1969, and Unit 2 followed in 1971. A programme of retrofitting and upgrading aimed at keeping the power plant up to date in terms of safety has been carried on with the replacement of the reactor control and protection system by a state-of-the-art computer-based system. The old safety control system, which had operated without malfunctions, had to be changed because the system supplier no longer provided technical support and thus no spare were available. Project PRESSURE (the name is a German acronym meaning 'reactor control and protection system replacement') went through several intensive phases, dating back to 1990. They included a number of feasibility studies and bid invitations to suppliers all over the world. The management of the project lies with a team of our own in-house engineers, who have not only special knowledge of control systems but also good knowledge of the processes in the existing plant. The replacement was successful. Since then both plants are in undisturbed operation. (author)

  10. Reactor Design Strategy for Martian Research Base

    International Nuclear Information System (INIS)

    With the discovery of nuclear energy, the manned exploration of the Solar system became technologically feasible. Nuclear powered propulsion systems can provide high propellant utilization efficiency and short transfer times to other planets, while long-life and compact nuclear reactors can provide power-rich environment for the research activities on the planet surface. For example, Reference Mission of the Mars Exploration. developed at NASA relies on the Nuclear Thermal Rocket concept for the men and equipment transfers from Earth to Mars. According to the same mission plan, the nuclear powered In-situ Resource Utilization unit should be set up on the Mars surface and produce methane fuel from the Martian atmosphere for the crew return trip. The members of Mars Homestead Project team are taking the challenge of space exploration one step further and aiming ultimately at establishing a permanent colony on Mars. The success of such enterprise would depend to a large extent on the availability of abundant and reliable energy source capable to satisfy the colony power needs. Considering the solar energy density at the Mars surface and the availability of other local resources, a nuclear power system is, clearly, the only technologically mature option for the near term deployment. The first estimate of the Mars colony energy needs has been recently reported by the Mars Homestead Project team at the 8 International Mars Society Conference(2). The main bulk of the energy is assumed to be supplied by three nuclear reactors 2 M Wth each. This paper outlines the fundamental considerations of such nuclear reactor design

  11. Repair or replacement of defective restorations by dentists in The Dental Practice-Based Research Network

    DEFF Research Database (Denmark)

    Gordan, Valeria V; Riley, Joseph L; Geraldeli, Saulo;

    2012-01-01

    The authors aimed to determine whether dentists in practices belonging to The Dental Practice-Based Research Network (DPBRN) were more likely to repair or to replace a restoration that they diagnosed as defective; to quantify dentists' specific reasons for repairing or replacing restorations......; and to test the hypothesis that certain dentist-, patient- and restoration-related variables are associated with the decision between repairing and replacing restorations....

  12. Contributions of research reactors in science and technology

    Energy Technology Data Exchange (ETDEWEB)

    Butt, N.M.; Bashir, J.

    1994-01-01

    In the present paper, after defining a research reactor, its basic constituents, types of reactors, and their distribution in the world, some typical examples of their uses are given. Particular emphasis is placed on the contribution of PARR-1 (Pakistan Research Reactor-1), the 5MW Swimming Pool Research reactor which first became critical at the Pakistan Institute of Nuclear Science and Technology (PINSTECH) in Dec. 1965 and attained its full power in June 1966. This was and still is the major research facility at PINSTECH for research and development.

  13. Contributions of research Reactors in science and technology

    International Nuclear Information System (INIS)

    In the present paper, after defining a research reactor, its basic constituents, types of reactors, their distribution in the world, some typical examples of their uses are given. Particular emphasis in placed on the contribution of PARR-I (Pakistan Research Reactor-I), the 5 MW Swimming Pool Research reactor which first became critical at the Pakistan Institute of Nuclear Science and Technology (PINSTECH) in Dec. 1965 and attained its full power in June 1966. This is still the major research facility at PINSTECH for research and development. (author)

  14. Spherical tokamak research for fusion reactor

    International Nuclear Information System (INIS)

    Between ITER and the commercial fusion reactor, there are many technological problems to be solved such as cost, neutron and steady-state operation. In the conceptual design of VECTOR and Slim CS reactors it was shown that the key is 'low aspect ratio'. The spherical tokamak (ST) has been expected as the base for fusion reactors. In US, ST is considered as a non-superconducting reactor for use in the neutron irradiation facility. Conceptual design of the superconducting ST reactor is conducted in Japan and Korea independently. In the present article, the prospect of the ST reactor design is discussed. (author)

  15. Post reactor researches of fuel pins, tested under alternating NEMF reactor functioning modes

    International Nuclear Information System (INIS)

    Changing of rod ceramic fuel pins state under their exploitation conditions changing influence at alternating of three-mode nuclear energy-moving facility reactor functioning has been examined. There are presented the results of researches of fuel pins, tested in the reactor IRGIT and RA, firstly under moving mode, then - under energy mode of minor power of NEMF reactor. (author)

  16. Current status and future of utilization in research reactors

    International Nuclear Information System (INIS)

    In research reactors of Japan Atomic Energy Research Institute (JAERI), JRR-3 was upgraded (so called JRR-3M) with irradiation facilities and neutron beam experimental facilities. Particularly the new supply of cold neutrons brings to a great increase of fields of utilization in research reactors of JAERI. In JRR-4, it is planned to reduce the fuel enrichment and to renew several utilization facilities in several years. JRR-2 will be shut down also in several years because of its superannuation. On the other hand most research reactors of other institutes in Japan have faced with their superannuation and the difficulties of refurbishment or upgrading as well as new construction because of the changes of environmental condition such as urbanization of their surroundings. The research reactors in JAERI will play more important role for research and development using neutrons in future than past and present. Therefore the investigation was made in order to catch the needs for utilization of research reactors. The results of this investigation show that there are many research institutes which hope to utilize research reactors in accordance with the increase of available fields such as research of high polymer, biology, industrial materials and components, and contribution to environmental investigation by using neutron scattering, neutron radiography and activation analysis. This means that the research reactor utilization will be able to contribute to general scientific fields as well as utilization for research and development of nuclear energy which have been popular as utilization of research reactors. In this presentation, the current status of utilization of research reactors in JAERI and utilization fields of research reactors expected in future based on the investigation are described. It is also discussed what is important for the utilization to use effectively the research reactors in JAERI. (author)

  17. Research activities on fast reactors in Switzerland

    International Nuclear Information System (INIS)

    The current domestic Swiss electricity supply is primarily based on hydro power (approximately 61%) and nuclear power (about 37%). The contribution of fossil systems is, consequently, minimal (the remaining 2%). In addition, long-term (but limited in time) contracts exist, securing imports of electricity of nuclear origin from France. During the last two years, the electricity consumption has been almost stagnant, although the 80s recorded an average annual increase rate of 2.7%. The future development of the electricity demand is a complex function of several factors with possibly competing effects, like increased efficiency of applications, changes in the industrial structure of the country, increase of population, further automation of industrial processes and services. Due to decommissioning of the currently operating nuclear power plants and expiration of long-term electricity import contracts there will eventually open a gap between the postulated electricity demand and the base supply. The assumed projected demand cases, high and low, as well as the secured yearly electric energy supply are shown. The physics aspects of plutonium burning fast reactor configurations are described including first results of the CIRANO experimental program. Swiss research related to residual heat removal in fast breeder reactors is presented. It consists of experimental ana analytic investigations on the mixing between two horizontal fluid layers of different velocities and temperatures. Development of suitable computer codes for mixing layer calculation are aimed to accurately predict the flow and temperature distribution in the pools. A satisfactory codes validation based on experimental data should be done

  18. Innovation and research in reactor safety

    International Nuclear Information System (INIS)

    In line with the engineered safeguards principle of in-depth safety, the survey article deals with innovation and research in the field of reactor safety, improvements in plant operation, innovation in accident management, and reduction of the consequences of severe accidents. The survey reveals that the development and application of innovative and efficient technologies is aimed primarily at the management of aging and of the operating life, and at simplifying and improving operations processes. Another area of innovation is accident management. In this respect, some of the main areas under development are the expansion of the multi-level safety concept, the introduction of further accident control measures so as to complete the spectrum of accidents covered, the quantification of safety margins by means of the application of modern methods of computation, and the introduction of passive elements reducing the need for fast countermeasures to be initiated by the plant operating personnel. The authors conclude that, on the whole, light water reactors attain a level of safety which, in combination with corresponding efforts in the economic sector, is a precondition for the renaissance of nuclear technology in the century just begun. The second part of the article, which is to be published in July, will deal mainly with the reduction of consequences of severe accidents. (orig.)

  19. Defuelling of the UTR-300 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Scott, R.D.; Banford, H.M.; East, B.W. [Scottish Universities Research and Reactor Centre, Glasgow (United Kingdom)

    1997-07-01

    The UTR-300 reactor at the Scottish Universities Research and Reactor Centre was based on the original Argonaut design with two aluminium core tanks set in a graphite reflector each containing six fuel elements cooled and moderated by water flowing up through the tanks in a closed primary circuit. The fuel plates in the original 13-plate elements were uranium oxide-aluminium with a 22g loading of 90% {sup 235}U. After 7 years of operation at 100 kW (10 kW average), the maximum power was increased to 300 kW (30 kW average) and, in order to maintain the operational excess reactivity, it was necessary to add another plate to each element progressively over the years until they all contained 14 plates. These extra plates were uranium metal-aluminium with 24.5 g of 90% {sup 235}U. No further modification of the elements was possible and so, with reactivity steadily decreasing, and for a variety of other reasons, a decision was taken to cease operation in September 1995. This paper describes the procedures whereby the fuel was unloaded from the core into a UNIFETCH flask equipped with a specially designed rotating gamma ray shield and then transported on two separate loads to Dounreay for reprocessing. (author)

  20. Defuelling of the UTR-300 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Scott, R.D.; Banford, H.M.; East, B.W. [Scottish Universities Research and Reactor Centre, Glasgow (United Kingdom)

    1997-07-01

    The UTR-300 reactor at the Scottish Universities Research and Reactor Centre was based on the original Argonaut design with two aluminium core tanks set in a graphite reflector each containing six fuel elements cooled and moderated by water flowing up through the tanks in a closed primary circuit. The fuel plates in the original 13-plate elements were uranium oxide-aluminium with a 22g loading of 90% {sup 235}U. After 7 years of operation at 100 kW (10 kW average), the maximum power was increased to 300 kW (30 kW average) and, in order to maintain the operational excess reactivity, it was necessary to add another plate to each element progressively over the years until they all contained 14 plates. These extra plates were uranium metal-aluminium with 24.5 g of 90% {sup 235}U. No further modification of the elements was possible and so, with reactivity steadily decreasing, and for a variety of other reasons, a decision was taken to cease operation in September 1995. This paper describes the procedures whereby the fuel was unloaded from the core into a UNIFETCH flask equipped with a specially designed rotating gamma ray shield and then transported on two separate loads to Dounreay for reprocessing. (author) 2 figs., 2 tabs., refs.

  1. Optimum burnup of BAEC TRIGA research reactor

    International Nuclear Information System (INIS)

    Highlights: ► Optimum loading scheme for BAEC TRIGA core is out-to-in loading with 10 fuels/cycle starting with 5 for the first reload. ► The discharge burnup ranges from 17% to 24% of U235 per fuel element for full power (3 MW) operation. ► Optimum extension of operating core life is 100 MWD per reload cycle. - Abstract: The TRIGA Mark II research reactor of BAEC (Bangladesh Atomic Energy Commission) has been operating since 1986 without any reshuffling or reloading yet. Optimum fuel burnup strategy has been investigated for the present BAEC TRIGA core, where three out-to-in loading schemes have been inspected in terms of core life extension, burnup economy and safety. In considering different schemes of fuel loading, optimization has been searched by only varying the number of fuels discharged and loaded. A cost function has been defined and evaluated based on the calculated core life and fuel load and discharge. The optimum loading scheme has been identified for the TRIGA core, the outside-to-inside fuel loading with ten fuels for each cycle starting with five fuels for the first reload. The discharge burnup has been found ranging from 17% to 24% of U235 per fuel element and optimum extension of core operating life is 100 MWD for each loading cycle. This study will contribute to the in-core fuel management of TRIGA reactor

  2. Cost Estimation for Research Reactor Decommissioning

    International Nuclear Information System (INIS)

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world'. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The purpose of this publication is to develop a costing methodology and a software tool in order to support cost estimation for research reactor decommissioning. The costing methodology is intended for the preliminary cost estimation stages for research reactor decommissioning with limited inventory data and other input data available. Existing experience in decommissioning costing is considered. As the basis for the cost calculation structure, the costing model uses the International Structure for Decommissioning Costing (ISDC) that is recommended by the IAEA, the Organisation for

  3. Enhancement of research reactor utilization in the developing countries

    International Nuclear Information System (INIS)

    As the research reactor represents a significant capital investment on the part of any institution and in addition there are recurring annual operating costs, therefore, the subject of its effective utilization has always been of interest. World wide there are about three hundred research reactors. Of these, 92 are located in the developing countries. Together, these reactors represent quite significant research potential. In the present paper, reasons of under utilization, procedures necessary to measure the productivity, ways and means of enhancing the utilization of research reactors are described. In the end, use of two research reactors at PINSTECH are described to illustrate some of the ways in which a successful utilization of a research reactor can made in the developing country. (author) 9 figs

  4. Research reactors for the social safety and prosperous neutron use

    International Nuclear Information System (INIS)

    The present status of nuclear reactors in Japan and the world was briefly described in this report. Aiming to construct a background of stable future society dependent on nuclear energy, the necessity to establish an organization for research reactors in Japan was pointed out. There are a total of 468 reactors in the world, but only 248 of them are running at present and most of them are superannuated. In Japan, 15 research reactors are running and 8 of them are under collaborative utilization, but not a few of them have various problems. In the education of atomic energy, a reactor is dispensable for understanding its working principle through practice learning. Furthermore, a research reactor has important roles for development of power reactor in addition to various basic studies such as activation analysis, fission track, biological irradiation, neutron scattering, etc. Application of a reactor has been also progressing in industrial and medical fields. However, operation of the reactors has become more and more difficult in Japan because of a large running cost and a lack of residential consensus for nuclear reactor. Here, the author proposed an establishment of organization of research reactor in order to promote utilization of a reactor in the field of education, rearing of professionals and science and engineering. (M.N.)

  5. Safety in the utilization and modification of research reactors

    International Nuclear Information System (INIS)

    This Safety Guide presents guidelines, approved by international consensus, for the safe utilization and modification of research reactors. While the Guide is most applicable to existing reactors, it is also recommended for use by organizations planning to put a new reactor into operation. 1 fig

  6. Modeling and kinetics research of IGR reactor

    International Nuclear Information System (INIS)

    The effort addresses issues related to modeling and studying of IGR reactor dynamic behavior; an example of IGR reactor kinetics model realization and study results in time and frequency domains are given. (author)

  7. Research Reactor: A Powerhouse of Nuclear Technology in Korea

    International Nuclear Information System (INIS)

    The nuclear era in Korea was opened with the 100 kW KRR-1 of which construction started in 1959. The second research reactor, 2 MW KRR-2, was finished in 1972, around when the first nuclear power plant project was launched. Then the next research reactor HANARO, a 30 MW multi-purpose reactor, started the operation in 1995 and has made the technologies for the research reactor development and utilization matured. The competitiveness of Korean research reactor technology was acknowledged by being selected as the supplier of 5 MW JRTR for Jordan. In addition, Korea is sharing its research reactor technologies with many other countries in the areas of training, engineering service, neutron beam instrument manufacturing, and supply of RI goods production equipment and of the advanced research reactor fuel material. KAERI, as a nuclear research institute, has a well-established R and D infrastructure together with the research reactor operation and utilization technology. It can contribute for the new comers to establish a research reactor facility as well as a research environment using the facility as a tool to build-up their nuclear technology and service capability for their public. (author)

  8. IAEA/CRP for decommissioning techniques for research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Zin; Won, H. J.; Kim, K. N.; Lee, K. W.; Jung, C. H

    2001-03-01

    The following were studied through the project entitled 'IAEA/CRP for decommissioning techniques for research reactors 1. Decontamination technology development for TRIGA radioactive soil waste - Electrokinetic soil decontamination experimental results and its mathematical simulation 2. The 2nd IAEA/CRP for decommissioning techniques for research reactors - Meeting results and program 3. Hosting the 2001 IAEA/RCA D and D training course for research reactors and small nuclear facilities.

  9. Initiatives Supporting Research Reactor in the Asia-Pacific Region

    International Nuclear Information System (INIS)

    The safe and effective operation and utilisation of research reactors in the Asia-Pacific will assist the region as it grows and develops into the world's powerhouse for economic development in the 21st century. This paper explores the drivers for developments in regional research reactor operation and high-level initiatives in safety for some nations. Detailed examples of safety initiatives for research reactors in some Asia-Pacific nations and challenges for the future in the region are given. (author)

  10. Progress in Korea Multi-purpose Research Reactor (KMRR)

    International Nuclear Information System (INIS)

    This paper gives the latest progress in Korea Multi-purpose Research Reactor (KMRR), a 30 MW open-tank-in-pool type reactor designed and being constructed by the Korea Atomic Energy Research Institute (KAERI), expected to take the central role of national nuclear R and D activities beyond the nineties. In this paper, background and necessity of this new research reactor are described. The progress in R and D, construction and commissioning of KMRR follow. (author)

  11. Research Reactor Benchmarking Database: Facility Specification and Experimental Data

    International Nuclear Information System (INIS)

    This web publication contains the facility specifications, experiment descriptions, and corresponding experimental data for nine different research reactors covering a wide range of research reactor types, power levels and experimental configurations. Each data set was prepared in order to serve as a stand-alone resource of well documented experimental data, which can subsequently be used in benchmarking and validation of the neutronic and thermal-hydraulic computational methods and tools employed for improved utilization, operation and safety analysis of research reactors

  12. Current status of the Thai Research Reactor (TRR-1/M1)

    International Nuclear Information System (INIS)

    The first Thai Research Reactor, TRR-1 went critical on 27 October 1962 at the maximum power of 1 MW. It was located at Office of Atoms for Peace (OAP) in Bangkok. Since then, TRR-1 was continuously operated and eventually shut down in 1975. Plate type, high-enriched uranium (HEU) and U3O8A1 cladding were used as the reactor fuel. Light water was used as moderator and coolant as well. In 1975, because of the problem from fuel supplier and also to supporting the Treaty of Non Proliferation of Nuclear Weapon or NPT, TRR-1 was shut down for modification. The reactor core and control system were disassembled and replaced by TRIGA Mark III. A new core was a hexagonal core shape designed by General Atomics (GA). Afterwards, TRR-1 was officially renamed to the Thai Research Reactor-1/Modification 1 (TRR-1/M1). TRR-1/M1 is a multipurpose swimming pool type reactor with nominal power of 2 MW. The TRR-1/M1 uses uranium enriched at 20% in U-235 (LEU) and ZrH alloy as fuel. Light water is also used as coolant and moderator. At present, the reactor is operating with core No.14. The reactor has been serving for various kinds of utilization namely, radioisotope production, neutron activation analysis, beam experiments and reactor physics experiments. (author)

  13. Optical inspections of research reactor tanks and tank components

    International Nuclear Information System (INIS)

    By the end of 1987 worldwide there were 326 research reactors in operation, 276 of them operating more than 10 years, and 195 of them operating more than 20 years. The majority of these reactors are swimming-pool type or tank type reactors using aluminium as structural material. Although aluminium has prooven its excellent properties for reactor application in primary system, it is however subjected to various types of corrosion if it gets into contact with other materials such as mild steel in the presence of destilled water. This paper describes various methods of research reactor tank inspections, maintenance and repair possibilities. 9 figs. (Author)

  14. Gas cooled fast reactor research and development program

    International Nuclear Information System (INIS)

    The research and development work in the field of core thermal-hydraulics, steam generator research and development, experimental and analytical physics and carbide fuel development carried out 1978 for the Gas Cooled Fast Breeder Reactor at the Swiss Federal Institute for Reactor Research is described. (Auth.)

  15. Reactor aging research. United States Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    The reactor ageing research activities in USA described, are focused on the research of reactor vessel integrity, including regulatory issues and technical aspects. Current emphasis are described for fracture analysis, embrittlement research, inspection capabilities, validation od annealing rule, revision of regulatory guide

  16. Gas cooled fast reactor research and development program

    International Nuclear Information System (INIS)

    The research and development work in the field of core thermal-hydraulics, steam generator research and development, experimental and analytical physics and carbide fuel development carried out 1979 for the Gas Cooled Fast Breeder Reactor at the Swiss Federal Institute for Reactor Research is described. (Auth.)

  17. Upgrading of the research reactors FRG-1 and FRG-2

    International Nuclear Information System (INIS)

    In 1972 for the research reactor FRG-2 we applied for a license to increase the power from 15 MW to 21 MW. During this procedure a public laying out of the safety report and an upgrading procedure for both research reactors - FRG-1 (5 MW) and FRG-2 - were required by the licensing authorities. After discussing the legal background for licensing procedures in the Federal Republic of Germany the upgrading for both research reactors is described. The present status and future licensing aspects for changes of our research reactors are discussed, too. (orig.)

  18. The current status of nuclear research reactor in Thailand

    Energy Technology Data Exchange (ETDEWEB)

    Sittichai, C.; Kanyukt, R.; Pongpat, P. [Office of Atomic Energy for Peace, Bangkok (Thailand)

    1998-10-01

    Since 1962, the Thai Research Reactor has been serving for various kinds of activities i.e. the production of radioisotopes for medical uses and research and development on nuclear science and technology, for more than three decades. The existing reactor site should be abandoned and relocated to the new suitable site, according to Thai cabinet`s resolution on the 27 December 1989. The decommissioning project for the present reactor as well as the establishment of new nuclear research center were planned. This paper discussed the OAEP concept for the decommissioning programme and the general description of the new research reactor and some related information were also reported. (author)

  19. Utilisation of the Research Reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    The TRIGA Mark II reactor of the University of Mainz can be operated in the steady state mode with thermal powers up to a maximum of 100 kW and in the pulse mode with a maximum peak power of 250 MW. So far, more than 17 000 pulses have been performed. For irradiations the TRIGA Mainz has a central experimental tube, three pneumatic transfer systems and a rotary specimen rack. In addition, the TRIGA Mainz includes four horizontal beam ports and a graphite thermal column which provides a source of well-thermalised neutrons. A broad spectrum of commercial applications, scientific research and training can be executed. For education and training various courses in nuclear and radiochemistry, radiation protection, reactor operation and physics are held for scientists, advanced students, teachers, engineers and technicians. Isotope production and Neutron Activation Analysis (NAA) are applied in in-core positions for different applications. NAA in Mainz is focused to determine trace elements in different materials such as in archaeometry, forensics, biology and technical materials including semiconductors for photovoltaics. The beam ports and the thermal column are used for commercial as well as for special basic and applied research in medicine, biology, chemistry and physics. Experiments are in preparation to determine the fundamental neutron properties with very high precision using ultra cold neutrons (UCN) produced at the tangential beam port. A second source is under development at the radial piercing beam port. Another experiment under development is the determination of ground-state properties of radioactive nuclei with very high precision using a penning trap and collinear laser spectroscopy. For many years fast chemical separation procedures combining a gas-jet transport system installed in one beam tube with either continuous or discontinuous chemical separation are carried out. In addition the thermal column of the reactor is also used for medical and

  20. An Overview of Ageing Management and Refurbishment of Research Reactors at Trombay

    International Nuclear Information System (INIS)

    preparatory work for decommissioning is at hand. Dhruva, a 100 MWth tank type research reactor using heavy water as primary coolant, moderator and reflector has been in operation since 1985. The reactor is being utilized for production of radioisotopes and neutron beam research applications. Modernization, safety upgrades and replacement of some important equipment in Dhruva have been planned to achieve smooth operation with better utilization and enhanced safety. The paper highlights the experience gained in refurbishment, re-commissioning and full power operation of Cirus, the plan for upgrading Apsara and ageing management of Dhruva. (author)