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Sample records for alberta university slowpoke reactor

  1. SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Evans, D.J.R.; Downs, W.E.

    1974-01-01

    The SLOWPOKE reactor is described, which is a small pool type with thermal neutron fluxes ranging from 10 11 -10 12 n cm -2 sec -1 . It differs in many ways from conventional pool type, namely small critical mass, beryllium reflector and a closed reactor container. The reactor is designed as small and simply as possible, and consistently with safety and good operating practice. Access to the present model is via pneumatic irradiation tubes only, which limits the use of the facility to activation analysis, tracer production and training. (Mori, K.)

  2. SLOWPOKE

    International Nuclear Information System (INIS)

    Law, Charles.

    1979-01-01

    The SLOWPOKE (Safe Low Power Critical Experiment) reactor was developed by AECL at Whiteshell and Chalk River between 1968 and 1970. It is a neutron-producing reactor of low power with minimal fuel, shielding, and cooling requirements and intrinsic safety. Four Canadian universities and one German one have acquired SLOWPOKE reactors for neutron activation analyses and for student research in nuclear engineering and reactor physics. (LL)

  3. Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada); Hilborn, J.W. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Carlin, G.E. [Ontario Power Generation, Toronto, Ontario (Canada); Gagnon, R.; Busatta, P. [Canadian Forces (Canada)

    2014-07-01

    Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as {sup 99}Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as {sup 99}Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO{sub 2}SO{sub 4}) with 994.2 g of {sup 235}U (enrichment at 20%) providing an excess reactivity at operating temperature (40 {sup o}C) of 3.8 mk for a molality determined as 1.46 mol kg{sup -1} for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 {sup o}C. Peak temperature and power were determined as 83 {sup o}C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the

  4. Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

    International Nuclear Information System (INIS)

    Bonin, H.W.; Hilborn, J.W.; Carlin, G.E.; Gagnon, R.; Busatta, P.

    2014-01-01

    Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as 99 Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as 99 Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO 2 SO 4 ) with 994.2 g of 235 U (enrichment at 20%) providing an excess reactivity at operating temperature (40 o C) of 3.8 mk for a molality determined as 1.46 mol kg -1 for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 o C. Peak temperature and power were determined as 83 o C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the temperature and void coefficients are

  5. Utilization of the SLOWPOKE-2 research reactor

    International Nuclear Information System (INIS)

    Lalor, G.C.

    2001-01-01

    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)

  6. First critical: the original SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Hilborn, J.W.; Stevens-Guille, P.D.

    2011-01-01

    The first approach to critical of the SLOWPOKE reactor is described together with many as yet unpublished photographs of the event. The development of the reactor and the overpower testing are discussed.

  7. Longer life cores for SLOWPOKE-2 reactors

    International Nuclear Information System (INIS)

    Irish, J.D.; Hilborn, J.W.

    1985-06-01

    A method has been devised to increase the lifetime of SLOWPOKE-2 cores by increasing the initial fuel loading by about 7 percent. The method was implemented during the commissioning of the SLOWPOKE-2 (Kanata) reactor. Calculations indicate that the core lifetime will be doubled

  8. Dalhousie SLOWPOKE-2 reactor: A nuclear analytical chemistry facility

    International Nuclear Information System (INIS)

    Chatt, A.; Holzbecher, J.

    1990-01-01

    SLOWPOKE is an acronym for Safe Low POwer Kritical Experiment. The SOWPOKE-2 is a compact, inherently safe, swimming-pool-type reactor designed by the Atomic Energy of Canada Limited for neutron activation analysis (NAA) and isotope production. The Dalhousie University SLOWPOKE-2 reactor (DUSR) has been operating since 1976; a large beryllium reflector was added in 1986 to extend its lifetime by another 8 to 10 yr. The DUSR is generally operated at half-power with a maximum thermal flux of 1.1 x 10 12 n/cm 2 ·s in the inner pneumatic sites and that of 5.4 x 10 11 n/cm 2 ·s in the outer sites. Despite this comparatively low flux, SLOWPOKE-2 reactors have many beneficial features that are continuously being exploited at the DUSR facility for developing nuclear analytical methods for fundamental as well as applied studies. Although NAA is a well-established analytical technique, much of the activation analysis being performed in most facilities has been limited to methods using fairly long-lived nuclides. The approach at the DUSR facility has been to utilize the highly homogeneous, stable, and reproducible neutron flux to develop NAA methods based on short-lived nuclides. SLOWPOKE reactors have a fairly high epithermal neutron flux, which is being advantageously used for determining several trace elements in complex matrices. Radiochemical NAA (RNAA) methods using coprecipitation, distillation, and ion-exchange separations have been used for the determination of very low levels of several elements in biological materials

  9. Little reactor that can, the bigger reactor that may be. [SLOWPOKE-2; 2 MW SLOWPOKE

    Energy Technology Data Exchange (ETDEWEB)

    Duffy, J.Q.

    1981-01-01

    The Slowpoke-2 research reactor and its marketing are featured, with an account of an interview with Dr. John Hilborn, designer. Also discussed is a scaled-up 2 MW version for space heating or small-scale district heating. The new version will rely on natural convection and inherent safety like Slowpoke, but will differ from it in many ways. The core will contain 200 kg of fuel elements with 5 percent enrichment. The new reactor lacks an upper beryllium reflector. Control will be by moving an annular beryllium reflector up and down. Inherent safety will be achieved through diminution of reactivity resulting from the onset of boiling. The article also mentions projected or actual use of small reactors for heating in the U.S.S.R. and France.

  10. SLOWPOKE: heating reactors in the urban environment

    International Nuclear Information System (INIS)

    Hilborn, J.W.; Lynch, G.F.

    1988-06-01

    Since global energy requirements are expected to double over the next 40 years, nuclear heating could become as important as nuclear electricity generation. To fill that need, AECL has designed a 10 MW nuclear heating plant for large buildings. Producing hot water at temperatures below 100 degrees Celsius, it incorporates a small pool-type reactor based on the successful SLOWPOKE Research Reactor. A 2 MW prototype is now being tested at the Whiteshell Nuclear Research Establishment in Manitoba, and the design of a 10 MW commercial unit is well advanced. With capital costs in the range $5 million to $7 million, unit energy costs could be as low as $0.02 per kWh, for a unit operating at 50% load factor over a 25-year period. By keeping the reactor power low and the water temperature below 100 degrees Celsius, much of the complexity of the large nuclear power plants can be avoided, thus allowing these small, safe, nuclear heating systems to be economically viable

  11. Development Directions For CANDU and Slowpoke Reactors

    International Nuclear Information System (INIS)

    Brooks, Gordon L.

    1990-01-01

    This paper provides a broader-based discussion of overall development directions foreseen for CANDU reactors, particularly those which have further evolved sine the earlier paper. The paper then discusses development directions for the Slowpokes Energy System which is a small nuclear heat source intended to meet local heating needs for building complexes and municipal heating systems. In evolving a sound development direction, it is necessary, firstly, to address the question of requirements, viz., what are the requirements which future nuclear power plants must satisfy if they are to be successful? Today, some in the nuclear industry believe that the most important of such requirements relates to the need for 'safer' reactors. Indeed, some proponents of this view would seem to suggest that if only we could develop such 'safer' reactors, suddenly all of our problem s with public acceptance would disappear and utilities would form long lines waiting to purchase such marvellous machines. I do not share such a simplistic view nor, indeed, do many of my colleagues in the international nuclear power industry

  12. The SLOWPOKE-2 reactor with low enrichment uranium oxide fuel

    International Nuclear Information System (INIS)

    Townes, B.M.; Hilborn, J.W.

    1985-06-01

    A SLOWPOKE-2 reactor core contains less than 1 kg of highly enriched uranium (HEU) and the proliferation risk is very low. However, to overcome proliferation concerns a new low enrichment uranium (LEU) fuelled reactor core has been designed. This core contains approximately 180 fuel elements based on the Zircaloy-4 clad UOsub(2) CANDU fuel element, but with a smaller outside diameter. The physics characteristics of this new reactor core ensure the inherent safety of the reactor under all conceivable conditions and thus the basic SLOWPOKE safety philosophy which permits unattended operation is not affected

  13. An experimental investigation of fission product release in SLOWPOKE-2 reactors - Data report

    International Nuclear Information System (INIS)

    Harnden, A.M.C.

    1995-09-01

    The results of an investigation into the release of fission products from SLOWPOKE-2 reactors fuelled with a highly-enriched uranium alloy core are detailed in Volume 1. This data report (Volume 2) contains plots of the activity concentrations of the fission products observed in the reactor container at the University of Toronto, Ecole Polytechnique and the Kanata Isotope Production Facility. Release rates from the reactor container water to the gas headspace are also included. (author)

  14. Diffusion calculation's for the SLOWPOKE-2 reactor using DONJON

    International Nuclear Information System (INIS)

    Noceir, S.; El Hajjaji, O.; Varin, E.

    1997-01-01

    The SLOWPOKE reactor at Ecole Polytechnique will be refueled with a Low Enriched Uranium (LEU) fuel in place of a High Enriched Uranium (HEU) fuel used until now. The purpose of this study is to provide various models, using the reactor physics chain of codes DRAGON/DONJON, in order to predict the behavior of the new LEU Slowpoke. In particle, we will present some numerical results concerning the separate temperature effects of the main components of the core, the effect of a partial void appearing near the fuel pins and the axial and radial flux distributions. Finally the difference between the present HEU and the future LEU fuel power will be given. (author)

  15. Comparative neutronic analysis between MNSR and Slowpoke-II reactors

    International Nuclear Information System (INIS)

    Khamis, I.; Khattab, K.

    1998-12-01

    It was found possible to lower the fuel enrichment of the Miniature Neutron Source Reactor (MNSR) to 20% using Uo 2 as fuel instead of UAl 4 . The number of fuel elements required for the new core is 199. The use of double thickness of the bottom reflector in Slowpoke reactor made it possible to load the reactor with lower enriched fuel compared to MNSR. A neutronic model, dedicated mainly for the MNSR, has been developed to perform neutronic calculations for both reactors. values of reactivity flooding effects for single or combination of inner irradiation sites were obtained accurately. Results show good agreement with reported data for MNSR. (author)

  16. Keeping research reactors relevant: A pro-active approach for SLOWPOKE-2

    International Nuclear Information System (INIS)

    Cosby, L.R.; Bennett, L.G.I.; Nielsen, K.; Weir, R.

    2010-01-01

    The SLOWPOKE is a small, inherently safe, pool-type research reactor that was engineered and marketed by Atomic Energy of Canada Limited (AECL) in the 1970s and 80s. The original reactor, SLOWPOKE-1, was moved from Chalk River to the University of Toronto in 1970 and was operated until upgraded to the SLOWPOKE-2 reactor in 1973. In all, eight reactors in the two versions were produced and five are still in operation today, three having been decommissioned. All of the remaining reactors are designated as SLOWPOKE-2 reactors. These research reactors are prone to two major issues: aging components and lack of relevance to a younger audience. In order to combat these problems, one SLOWPOKE -2 facility has embraced a strategy that involves modernizing their reactor in order to keep the reactor up to date and relevant. In 2001, this facility replaced its aging analogue reactor control system with a digital control system. The system was successfully commissioned and has provided a renewed platform for student learning and research. The digital control system provides a better interface and allows flexibility in data storage and retrieval that was never possible with the analogue control system. This facility has started work on another upgrade to the digital control and instrumentation system that will be installed in 2010. The upgrade includes new computer hardware, updated software and a web-based simulation and training system that will allow licensed operators, students and researchers to use an online simulation tool for training, education and research. The tool consists of: 1) A dynamic simulation for reactor kinetics (e.g., core flux, power, core temperatures, etc). This tool is useful for operator training and student education; 2) Dynamic mapping of the reactor and pool container gamma and neutron fluxes as well as the vertical neutron beam tube flux. This research planning tool is used for various researchers who wish to do irradiations (e.g., neutron

  17. Operation of the SLOWPOKE-2 reactor in Jamaica

    Energy Technology Data Exchange (ETDEWEB)

    Grant, C.N.; Lalor, G.C.; Vuchkov, M.K. [University of the West Indies, Kingston (Jamaica)

    2001-07-01

    Over the past sixteen years lCENS has operated a SLOWPOKE 2 nuclear reactor almost exclusively for the purpose of neutron activation analysis. During this period we have adopted a strategy of minimum irradiation times while optimizing our output in an effort to increase the lifetime of the reactor core and to maintaining fuel integrity. An inter-comparison study with results obtained with a much larger reactor at IPEN has validated this approach. The parameters routinely monitored at ICENS are also discussed and the method used to predict the next shim adjustment. (author)

  18. Operation of the SLOWPOKE-2 reactor in Jamaica

    International Nuclear Information System (INIS)

    Grant, C.N.; Lalor, G.C.; Vuchkov, M.K.

    2001-01-01

    Over the past sixteen years lCENS has operated a SLOWPOKE 2 nuclear reactor almost exclusively for the purpose of neutron activation analysis. During this period we have adopted a strategy of minimum irradiation times while optimizing our output in an effort to increase the lifetime of the reactor core and to maintaining fuel integrity. An inter-comparison study with results obtained with a much larger reactor at IPEN has validated this approach. The parameters routinely monitored at ICENS are also discussed and the method used to predict the next shim adjustment. (author)

  19. Safety analysis of a homogeneous SLOWPOKE reactor (part 2)

    International Nuclear Information System (INIS)

    Gagnon, R.L.

    2007-01-01

    An opportunity is presented with the approaching end of some of the SLOWPOKE-2 research reactors' design life, which consists of replacing the current heterogeneous core with a homogeneous assembly that would allow the extraction of radioisotopes (such as 99 Mo) for nuclear medicine and other applications. Preliminary investigation has demonstrated the feasibility of this concept and produced an initial design of a Homogeneous SLOWPOKE reactor that demonstrates the potential for inherent safety based on calculations of a strong negative reactivity coefficient due to temperature. The present research aims at continuing the safety analysis of the proposed homogeneous assembly, most notably in assessing its inherent safety characteristics with respect to factors such as void fraction of the moderator and additional thermalhydraulic effects. Modelling of the reactor is accomplished using both the deterministic WIMS-AECL and the probabilistic MCNP 5 for the determination of the reactor's reactivity and flux shape, while COMSOL Multiphysics is used for thermalhydraulics modelling. In pursuing the safety analysis, the design of the reactor is improved. One example of the improvements is the proposed substitution of the required additional reflector material in the initial design with graphite instead of beryllium. Another improvement is the replacement of the unique control rod in the core centre with a cluster of control rods within the radial reflector. This would not only simplify the construction of the reactor vessel, but increase the core volume for added radioisotope production capacity. The latest results of reactor simulations and the safety analysis will be presented. (author)

  20. A new safety principle for the SLOWPOKE-2 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yue, S., E-mail: yues@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Polugari, S. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Ryerson Univ., Toronto, Ontario (Canada); Anghel, V. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Hilborn, J. [Deep River, Ontario (Canada); Sur, B. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2013-06-15

    SLOWPOKE-2 (LEU core) is a pool-type nuclear reactor with a maximum nominal thermal power of 20 kW. It uses a pelletized uranium oxide fuel (19.9% enrichment) and provides a useful high neutron flux in the order of 10{sup 12} n{center_dot}cm{sup 2}s{sup -1}. The key safety features built into the reactor design are the strictly limited amount of excess reactivity and the negative reactivity feedback characteristics, which provide a demonstrably safe self-limiting power excursion response to large reactivity insertions. However, the limited amount of excess reactivity also limits continuous prolonged reactor operation at full power. With a 4 mk excess reactivity, the reactor can operate for about one day at full power, 20 kW, before criticality is lost due to temperature effects and xenon poisoning. A new safety concept is proposed in this paper that enables the continuous operation to a few months by increasing the excess reactivity from 4 mk to 8 mk. A Matlab/simulink model of SLOWPOKE-2 has demonstrated that core operation life can be extended to several months without adding a beryllium shim. (author)

  1. A new safety principle for the SLOWPOKE-2 reactor

    International Nuclear Information System (INIS)

    Yue, S.; Polugari, S.; Anghel, V.; Hilborn, J.; Sur, B.

    2013-01-01

    SLOWPOKE-2 (LEU core) is a pool-type nuclear reactor with a maximum nominal thermal power of 20 kW. It uses a pelletized uranium oxide fuel (19.9% enrichment) and provides a useful high neutron flux in the order of 10 12 n·cm 2 s -1 . The key safety features built into the reactor design are the strictly limited amount of excess reactivity and the negative reactivity feedback characteristics, which provide a demonstrably safe self-limiting power excursion response to large reactivity insertions. However, the limited amount of excess reactivity also limits continuous prolonged reactor operation at full power. With a 4 mk excess reactivity, the reactor can operate for about one day at full power, 20 kW, before criticality is lost due to temperature effects and xenon poisoning. A new safety concept is proposed in this paper that enables the continuous operation to a few months by increasing the excess reactivity from 4 mk to 8 mk. A Matlab/simulink model of SLOWPOKE-2 has demonstrated that core operation life can be extended to several months without adding a beryllium shim. (author)

  2. Dynamic simulation of the 2 MWt slowpoke heating reactor

    International Nuclear Information System (INIS)

    Tseng, C.M.; Lepp, R.M.

    1982-04-01

    A 2 MWt SLOWPOKE reactor, intended for commercial space heating, is being developed at the Chalk River Nuclear Laboratories. A small-signal dynamic simulation of this reactor, without closed-loop control, was developed. Basic equations were used to describe the physical phenomena in each kf the eight reactor subsystems. These equations were then linearized about the normal operation conditions and rearranged in a dimensionless form for implementation. The overall simulation is non-linear. Slow transient responses (minutes to days) of the simulation to both reactivity and temperature perturbations were measured at full power. In all cases the system reached a new steady state in times varying from 12 h to 250 h. These results illustrate the benefits of the inherent negative reactivity feedback of this reactor concept. The addition of closed-loop control using core outlet temperature as the controlled variable to move a beryllium reflector is also examined

  3. Safety analysis of a homogeneous SLOWPOKE reactor (part 2)

    Energy Technology Data Exchange (ETDEWEB)

    Gagnon, R.L. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

    2007-07-01

    An opportunity is presented with the approaching end of some of the SLOWPOKE-2 research reactors' design life, which consists of replacing the current heterogeneous core with a homogeneous assembly that would allow the extraction of radioisotopes (such as {sup 99}Mo) for nuclear medicine and other applications. Preliminary investigation has demonstrated the feasibility of this concept and produced an initial design of a Homogeneous SLOWPOKE reactor that demonstrates the potential for inherent safety based on calculations of a strong negative reactivity coefficient due to temperature. The present research aims at continuing the safety analysis of the proposed homogeneous assembly, most notably in assessing its inherent safety characteristics with respect to factors such as void fraction of the moderator and additional thermalhydraulic effects. Modelling of the reactor is accomplished using both the deterministic WIMS-AECL and the probabilistic MCNP 5 for the determination of the reactor's reactivity and flux shape, while COMSOL Multiphysics is used for thermalhydraulics modelling. In pursuing the safety analysis, the design of the reactor is improved. One example of the improvements is the proposed substitution of the required additional reflector material in the initial design with graphite instead of beryllium. Another improvement is the replacement of the unique control rod in the core centre with a cluster of control rods within the radial reflector. This would not only simplify the construction of the reactor vessel, but increase the core volume for added radioisotope production capacity. The latest results of reactor simulations and the safety analysis will be presented. (author)

  4. Analysis of the Jamaican Slowpoke-2 Research Reactor for the Conversion from HEU to LEU Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Puig, F.; Dennis, Haile T.

    2014-01-01

    The Jamaican SLOWPOKE-2 (JM-1) is a 20 kW research reactor manufactured by Atomic Energy of Canada Limited that has been operating for 30 years at the University of the West Indies, Mona Campus in Kingston, Jamaica. The University, with IAEA assistance under the GTRI/RERTR program, is currently in the process of converting from HEU to LEU. Full-reactor neutronic and thermal hydraulic analyses were performed, using MCNP5 and PLTEMP/ANL v4.1 respectively, on both the existing HEU and proposed LEU core configurations. Although conversion will result in the full nominal reactor power increasing from 20 kW to approximately 22 kW, in order to maintain the 1012 n·cm-2 s-1 flux in the inner irradiation channels, and maximum fuel temperature to increase from ~82°C to ~113°C, the analysis illustrates that increased safety margins will be obtained. No significant reactor behavior changes are expected and the characteristic SLOWPOKE-2 reactor inherent safety features will be preserved.

  5. DRAGON modelling of the SLOWPOKE-2 reactor at Ecole Polytechnique

    International Nuclear Information System (INIS)

    Marleau, G.; Noceir, S.; Roy, R.; Rozon, D.

    1997-01-01

    Predicting the behaviour of the SLOWPOKE-2 reactor at Ecole Polytechnique de Montreal poses a major challenge from the point of view of transport calculations since it has properties which forbid the use of such simple schemes as those considered for power reactor analysis. For example, the use of a totally reflected 2-D cell containing a single fuel pin with its associated coolant is not good enough to generate the fuel averaged properties required in a full core diffusion calculation. Here we present the DRAGON cell model which was used to generate the fewgroup macroscopic cross sections needed for full core diffusion calculations. We also discuss how DRAGON can be used to evaluate and explain the effect on reactivity of temperature and local voiding perturbations. (author)

  6. LEU-fuelled SLOWPOKE-2 research reactors: Operational experience and utilisation

    International Nuclear Information System (INIS)

    Kennedy, G.; St Pierre, J.; Bennett, L.G.I.; Nielsen, K.S.

    2002-01-01

    Atomic Energy of Canada Limited designed the SLOWPOKE-2 research reactor [1] based on experience with the SLOWPOKE-1 prototype, which operated for four years at the University of Toronto. Between 1976 and 1984, seven SLOWPOKE-2 reactors with HEU fuel were commissioned in six Canadian cities and in Kingston, Jamaica. They use 93% enriched uranium in the form of 28% uranium-aluminum alloy with aluminum cladding. The core is an assembly of about 300 fuel pins, only 22 cm diameter and 23 cm high, surrounded by a fixed beryllium annulus and a bottom beryllium slab. Criticality is maintained by adding beryllium plates in a tray on top of the core. The newer LEU fuel is constructed in the same manner as CANDU fuel, Zircaloy-clad, but with 20% enrichment instead of natural uranium oxide. The pool, reactor water container, light water moderator, beryllium reflector, cadmium control rod and irradiation sites are the same as for the HEU-fuelled reactors. A very important feature of the SLOWPOKE-2 reactor is its inherent safety due to its limited excess reactivity and large negative temperature coefficient of reactivity. With both the HEU and the LEU cores, power excursions were carried out during commissioning up to the maximum credible reactivity insertion of 4.3 mk. For both types of cores, the power reached about 80 kW after about 2 minutes before levelling off. At lower powers (lower temperatures), the negative feedback with temperature increase is greater with the HEU core and, for reactivity insertions less than 4.3 mk, lower powers are reached with the HEU core. Both cores are highly undermoderated but the HEU core even more so because there is less water in the volume of the core. At 80 kW some boiling may take place with both cores, causing rapid negative feedback, and the LEU core has additional negative feedback due to the U-238. Considering all the reactivity feedback effects, the HEU and LEU cores are roughly equivalent from a safety standpoint, since neither can

  7. SLOWKIN: a simplified model for the simulation of reactor transients in SLOWPOKE-2

    International Nuclear Information System (INIS)

    Rozon, D.; Kavih, S.

    1997-01-01

    This paper will describe the model used to analyse reactor transients in the SLOWPOKE-2 reactor at Polytechnique. The model is intended to simulate reactor transients which will be induced by control rod displacements during commissioning of the new LEU core to be installed in the SLOWPOKE-2 reactor in 1997, in replacement of the original HEU core. A simplified treatment is justified since our objective is mainly to provide a physical interpretation for any difference observed in the transient behaviour of the new core, as opposed to the current HEU core. The SLOWKIN model used point kinetics to predict neutron power with time. The reactor physics codes DRAGON/DONJON were used to provide some reactor physics insight on the strong neutronic/thermalhydraulic coupling in the reactor and to generate the necessary reactivity coefficients to be used in SLOWKIN. (DM)

  8. A novel approach to the production of medical radioisotopes: the homogeneous SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Bonin, H.W.; Hilborn, J.W.; Carlin, G.E.; Gagnon, R.; Busatta, P.

    2015-01-01

    In 2009, the unexpected 15-month outage of the Canadian NRU nuclear reactor resulted in a sudden 30% world shortage, with higher shortages experienced in North America than in Europe. Commercial radioisotope production is from just eight nuclear reactors, most being aging systems near the end of their service life. This paper proposes a more efficient production and distribution model. Tc-99m unit doses would be distributed to regional hospitals from ten integrated 'industrial radiopharmacies', located at existing licensed nuclear reactor sites in North America. At each site, one or more 20 kW Homogeneous SLOWPOKE nuclear reactors would deliver 15 litres of irradiated aqueous uranyl sulfate fuel solution daily to industrial-scale hot cells, for extraction of Mo-99; and the low-enriched uranium would be recycled. Purified Mo-99 would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily for road delivery to all of the nuclear medicine hospitals within a 3-hour range. At the current price of $20 per unit dose, the annual gross income from 10 sites would be approximately $360 million. The Homogeneous SLOWPOKE reactor evolved from the inherently safe SLOWPOKE-2 research reactor, with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors at the end-of-core life, enabling them to continue their primary missions of research and education, together with full time commercial radioisotope production. The Homogeneous SLOWPOKE reactor was modelled using both deterministic and probabilistic reactor simulation codes. The homogeneous fuel mixture is a dilute aqueous solution of low-enriched uranyl sulfate containing approximately 1 kg of U-235. The reactor is controlled by mechanical absorber rods in the beryllium reflector. Safety analysis was carried out for both normal operation and transient conditions. The most severe

  9. A novel approach to the production of medical radioisotopes: the homogeneous SLOWPOKE reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada); Hilborn, J.W. [retired, Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Carlin, G.E. [Ontario Power Generation, Toronto, Ontario (Canada); Gagnon, R.; Busatta, P. [Royal Canadian Navy, Ottawa, Ontario (Canada)

    2015-03-15

    In 2009, the unexpected 15-month outage of the Canadian NRU nuclear reactor resulted in a sudden 30% world shortage, with higher shortages experienced in North America than in Europe. Commercial radioisotope production is from just eight nuclear reactors, most being aging systems near the end of their service life. This paper proposes a more efficient production and distribution model. Tc-99m unit doses would be distributed to regional hospitals from ten integrated 'industrial radiopharmacies', located at existing licensed nuclear reactor sites in North America. At each site, one or more 20 kW Homogeneous SLOWPOKE nuclear reactors would deliver 15 litres of irradiated aqueous uranyl sulfate fuel solution daily to industrial-scale hot cells, for extraction of Mo-99; and the low-enriched uranium would be recycled. Purified Mo-99 would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily for road delivery to all of the nuclear medicine hospitals within a 3-hour range. At the current price of $20 per unit dose, the annual gross income from 10 sites would be approximately $360 million. The Homogeneous SLOWPOKE reactor evolved from the inherently safe SLOWPOKE-2 research reactor, with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors at the end-of-core life, enabling them to continue their primary missions of research and education, together with full time commercial radioisotope production. The Homogeneous SLOWPOKE reactor was modelled using both deterministic and probabilistic reactor simulation codes. The homogeneous fuel mixture is a dilute aqueous solution of low-enriched uranyl sulfate containing approximately 1 kg of U-235. The reactor is controlled by mechanical absorber rods in the beryllium reflector. Safety analysis was carried out for both normal operation and transient conditions. The most severe

  10. An experimental investigation of fission product release in SLOWPOKE-2 reactors

    International Nuclear Information System (INIS)

    Harnden, A.M.C.

    1995-09-01

    Increasing radiation fields due to a release of fission products in the reactor container of several SLOWPOKE-2 reactors fuelled with a highly-enriched uranium (HEU) alloy core have been observed. It is believed that these increases are associated with the fuel fabrication where a small amount of uranium-bearing material is exposed to the coolant at the end-welds of the fuel element. To investigate this phenomenon samples of reactor water and gas from the headspace above the water have been obtained and examined by gamma spectrometry methods for reactors of various burnups at the University of Toronto, Ecole Polytechnique and Kanata Isotope Production Facility. An underwater visual examination of the fuel core at Ecole Polytechnique has also provided information on the condition of the core. This report (Volume 1) summarizes the equipment, analysis techniques and results of tests conducted at the various reactor sites. The data report is published as Volume 2. (author). 30 refs., 9 tabs., 20 figs

  11. The Development of Neutron Radiography and Tomography on a SLOWPOKE-2 Reactor

    Science.gov (United States)

    Bennett, L. G. I.; Lewis, W. J.; Hungler, P. C.

    Development of neutron radiography at the Royal Military College of Canada (RMC) started by trying to interest the Royal Canadian Air Force (RCAF) in this new non-destructive testing (NDT) technique. A Californium-252 based device was ordered and then installed at RMC for development of applicable techniques for aircraft by the first author. A second and transportable device was then designed, modified and used in trials at RCAF Bases and other locations for one year. This activity was the only foreign loan of the U.S. Californium Loan Program. Around this time, SLOWPOKE-2 reactors were being installed at four Canadian universities, while a new science and engineering building was being built at RMC. A reactor pool was incorporated and efforts to procure a reactor succeeded a decade later with a SLOWPOKE-2 reactor being installed at RMC. The only modification by the vendor for RMC was a thermal column replacing an irradiation site inside the reactor container for a later installation of a neutron beam tube (NBT). Development of a working NBT took several years, starting with the second author. A demonstration of the actual worth of neutron radiography took place with a CF-18 Hornet aircraft being neutron and X-radiographed at McClellan Air Force Base, Sacramento, CA. This inspection was followed by one of the rudders that had indications of water ingress being radiographed successfully at RMC just after the NBT became functional. The next step was to develop a neutron radioscopy system (NRS), initially employing film and then digital imaging, and is in use today for all flight control surfaces (FCS). With the third author, a technique capable of removing water from affected FCS was developed at RMC. Heating equipment and a vacuum system were utilized to carefully remove the water. This technique was proven using a sequence of near real time neutron images obtained during the drying process. The results of the drying process were correlated with a relative humidity

  12. Flux measurements in the LEU refueled Slowpoke-2 reactor of Ecole Polytechnique de Montreal

    Energy Technology Data Exchange (ETDEWEB)

    EL Hajjaji, O.; Kennedy, G.; Rozon, D. [Ecole Polytechnique de Montreal, Quebec (Canada). Institut de Genie Nucleaire]. E-mail: elhajj@meca.polymtl.ca

    1998-07-01

    The HEU (93%) SLOWPOKE-2 reactor of Ecole Polytechnique de Montreal was refueled in September 1997 with (20%) LEU fuel after twenty years of operation. Upon completion of refueling the thermal and epithermal neutron fluxes were measured at four radii in the new core by irradiating gold and copper wire at 20 W for 10 minutes. These flux profiles were normalized to the values measured in an irradiation site in the beryllium reflector. We have also used the DRAGON/DONJON chain of codes and a detailed SLOWPOKE reactor model to calculate the flux distribution in the core and in the irradiation site. The calculated flux profiles along the four vertical lines are in agreement with the experimental values. This work also enable us to validate our codes, normally used for power reactors, for a low power research reactor. (author)

  13. Flux measurements in the LEU refueled Slowpoke-2 reactor of Ecole Polytechnique de Montreal

    International Nuclear Information System (INIS)

    EL Hajjaji, O.; Kennedy, G.; Rozon, D.

    1998-01-01

    The HEU (93%) SLOWPOKE-2 reactor of Ecole Polytechnique de Montreal was refueled in September 1997 with (20%) LEU fuel after twenty years of operation. Upon completion of refueling the thermal and epithermal neutron fluxes were measured at four radii in the new core by irradiating gold and copper wire at 20 W for 10 minutes. These flux profiles were normalized to the values measured in an irradiation site in the beryllium reflector. We have also used the DRAGON/DONJON chain of codes and a detailed SLOWPOKE reactor model to calculate the flux distribution in the core and in the irradiation site. The calculated flux profiles along the four vertical lines are in agreement with the experimental values. This work also enable us to validate our codes, normally used for power reactors, for a low power research reactor. (author)

  14. Large-signal, dynamic simulation of the slowpoke-3 nuclear heating reactor

    International Nuclear Information System (INIS)

    Tseng, C.M.; Lepp, R.M.

    1983-07-01

    A 2 MWt nuclear reactor, called SLOWPOKE-3, is being developed at the Chalk River Nuclear Laboratories (CRNL). This reactor, which is cooled by natural circulation, is designed to produce hot water for commercial space heating and perhaps generate some electricity in remote locations where the costs of alternate forms of energy are high. A large-signal, dynamic simulation of this reactor, without closed-loop control, was developed and implemented on a hybrid computer, using the basic equations of conservation of mass, energy and momentum. The natural circulation of downcomer flow in the pool was simulated using a special filter, capable of modelling various flow conditions. The simulation was then used to study the intermediate and long-term transient response of SLOWPOKE-3 to large disturbances, such as loss of heat sink, loss of regulation, daily load following, and overcooling of the reactor coolant. Results of the simulation show that none of these disturbances produce hazardous transients

  15. Refuelling the SLOWPOKE-2 reactor at Ecole Polytechnique: procedure and proposed experiments

    International Nuclear Information System (INIS)

    Kennedy, G.; Marleau, G.

    1997-01-01

    As the expected lifetime of the present fuel in the SLOWPOKE-2 reactor at Ecole Polytechnique de Montreal was seen to approach, a project was initiated which will lead to the refueling of the reactor in 1997. Two aspects of this project require major development work: the defueling and fuel loading procedures need to be revised since this is the first time a SLOWPOKE reactor will be refueled; work is also required to bring safety analysis and documentation in line with recent regulatory requirements. Here, we present the proposed overall refueling strategy and discuss the changes in the operation of the core resulting from the use of low-enriched fuel. Additional experiments, which should be carried out during commissioning, are also analyzed. (author)

  16. Biomedical and health studies with the new Canadian SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Jervis, R.E.; Hancock, R.G.V.; Isles, K.; Hill, D.E.

    1977-01-01

    Results are reported from studies on clinical patients who had malnutrition, cystic fibrosis and other related electrolyte disorders. A stable activable tracer technique has been developed to determine the extracellular fluid volume (ECV) of infants. A regulated dose of sodium bromide is injected into the patient and, following short-term equilibration and dilution of this sample, a small blood sample is taken, yielding 50 μl of plasma. The plasma bromide concentration is determined by 80 Br (T=18 m) activation. Some samples were cross-checked by a microdiffusion method. The technique has been applied to 230 patients and controls, and has proved to be simple, rapid, accurate and sensitive for determining ECV to +-6%. Patients with cystic fibrosis (C.F.) were studied with respect to their growth and their sodium and electrolyte balance. In related clinical studies, hair and nail clippings from 50 C.F. patients and control children of the same age groups were activated at SLOWPOKE and Cu, Ca, Br, Cl, K, Na and I determined for use in differentiating C.F., along with a number of other elements including Zn, Mn, Al, Ti and Ni which showed little difference. A fairly good correlation of hair and nail concentrations was found for a number of the elements determined, suggesting that either tissue may be used in future studies. (T.G.)

  17. An overview of thermalhydraulics R and D for SLOWPOKE heating reactors

    International Nuclear Information System (INIS)

    Dimmick, G.R.

    1988-09-01

    AECL is currently demonstrating the use of pool-type reactors of up to 10 MW output to produce hot water at about 90 degrees Celsius. The initial focus for the development is the provision of a source of hot water for institutional and municipal heating networks. Ongoing developments are designed to broaden the applications to electricity generation and industrial processes such as desalination and agricultural needs. The reactor concept is based on the Slowpoke-2 research reactor, eight of which are successfully operating in Canada and abroad. The primary-circuit flow is driven by natural convection, with the heated water, produced by the reactor core near the bottom of the pool, being ducted to low-pressure-drop heat exchangers in the upper part of the pool. As the pool volume is relatively large, the fluid transit time around the circuit is long, ensuring that the reactor response to all normal transients is extremely slow. To investigate thermalhydraulics aspects of the reactor design, including its behaviour underextreme conditions, an electrically heated, natural-convection loop was designed and constructed. The core of the loop consists of a rod bundle that is a precise reproduction of one quarter of the core of the 2-MW SLOWPOKE Demonstration Reactor presently being tested at the Whiteshell Nuclear Research Establishment. With this loop, measurements of the distribution of pressure, temperature, velocity and subcooled void have been made in the simulated core, via a variety of intrusive and non-intrusive techniques. In addition, both the single- and two-phase behaviour of the system have been studied. This paper gives examples of the various in-core measurements made and also makes comparisons between the measured system behaviour and that predicted by the various steady-state and transient computer codes

  18. Simulation of startup transients of the SLOWPOKE-3 nuclear heating reactor

    International Nuclear Information System (INIS)

    Tseng, C.M.; Frketich, G.

    1984-07-01

    A natural circulation, pool-type nuclear reactor, called SLOWPOKE-3, is being developed at the Chalk River Nuclear Laboratories. It is intended for producing 2 MW of hot water at atmospheric pressure for space heating and perhaps for generating some electricity. A simulation has been developed to investigate the rate-of-rise of reactor power and consequences of loss-of-regulation accidents during startup. The effects of fuel temperature and of coolant density on the rate-of-rise of reactor power were examined individually and in combination. The influence of different initial pool temperatures and input reactivity rates on startup transients was also investigated. The simulation is based on the point kinetic equations for neutrons and the conservation of mass, energy and momentum for the thermal-hydraulic circuit. The equations were solved digitally on CDC CYBER 175/6600 computers via the FORSIM computer program, developed at Chalk River Nuclear Laboratories

  19. An Integrated Management System (IMS) for JM-1 SLOWPOKE-2 research reactor in Jamaica: experiences in documentation

    Energy Technology Data Exchange (ETDEWEB)

    Warner, T., E-mail: traceyann.warner02@uwimona.edu.jm [Univ. of West Indies, Mona (Jamaica)

    2014-07-01

    Since the first criticality in March 1984, the Jamaica SLOWPOKE-2 research reactor at the University of the West Indies, Mona located in the department of the International Centre for Environmental and Nuclear Sciences (ICENS) has operated for approximately 52% of the lifetime of the existing core configuration. The 20kW pool type research reactor has been primarily used for neutron activation analysis in environmental, agricultural, geochemical, health-related studies and mineral exploration in Jamaica. The involvement of the JM-1 reactor for research and teaching activities has segued into commercial applications which, coupled with the current core conversion programme from HEU to LEU, has demanded the implementation of management systems to satisfy regulatory requirements and assure compliance with internationally defined quality standards. At ICENS, documentation related to the Quality Management System aspect of an Integrated Management System (IMS) is well underway. The quality system will incorporate operational and nuclear safety, training, maintenance, design, utilization, occupational health and safety, quality service, and environmental management for its Nuclear Analytical Laboratory, NAL. The IMS is being designed to meet the requirements of the IAEA GS-R-3 with additional controls from international standards including: ISO/IEC 17025:2005, ISO 9001:2008, ISO 14001:2004 and OHSAS 18001:2007. This paper reports on the experiences of the documentation process in a low power reactor facility characterized by limited human resource, where innovative mechanisms of system automation and modeling are included to increase productivity and efficiency. (author)

  20. An Integrated Management System (IMS) for JM-1 SLOWPOKE-2 research reactor in Jamaica: experiences in documentation

    International Nuclear Information System (INIS)

    Warner, T.

    2014-01-01

    Since the first criticality in March 1984, the Jamaica SLOWPOKE-2 research reactor at the University of the West Indies, Mona located in the department of the International Centre for Environmental and Nuclear Sciences (ICENS) has operated for approximately 52% of the lifetime of the existing core configuration. The 20kW pool type research reactor has been primarily used for neutron activation analysis in environmental, agricultural, geochemical, health-related studies and mineral exploration in Jamaica. The involvement of the JM-1 reactor for research and teaching activities has segued into commercial applications which, coupled with the current core conversion programme from HEU to LEU, has demanded the implementation of management systems to satisfy regulatory requirements and assure compliance with internationally defined quality standards. At ICENS, documentation related to the Quality Management System aspect of an Integrated Management System (IMS) is well underway. The quality system will incorporate operational and nuclear safety, training, maintenance, design, utilization, occupational health and safety, quality service, and environmental management for its Nuclear Analytical Laboratory, NAL. The IMS is being designed to meet the requirements of the IAEA GS-R-3 with additional controls from international standards including: ISO/IEC 17025:2005, ISO 9001:2008, ISO 14001:2004 and OHSAS 18001:2007. This paper reports on the experiences of the documentation process in a low power reactor facility characterized by limited human resource, where innovative mechanisms of system automation and modeling are included to increase productivity and efficiency. (author)

  1. The SLOWPOKE-2 nuclear reactor at the Royal Military College of Canada: applications for the Canadian Armed Forces

    Energy Technology Data Exchange (ETDEWEB)

    Hungler, P.C.; Andrews, M.T.; Kelly, D.G.; Nielsen, K.S. [Royal Military College of Canada, Kingston, Ontario (Canada)

    2014-03-15

    The Royal Military College of Canada (RMCC) has a 20 kW SLOWPOKE-2 nuclear research reactor which is used for teaching and research. Since its commissioning, the reactor facility and instruments have been continuously upgraded to develop and enhance nuclear capabilities for the Canadian Armed Forces (CAF). Specific applications of neutron activation analysis (NAA), delayed neutron counting (DNC) and neutron imaging relevant to the CAF are discussed. (author)

  2. The SLOWPOKE-2 nuclear reactor at the Royal Military College of Canada: applications for the Canadian Armed Forces

    International Nuclear Information System (INIS)

    Hungler, P.C.; Andrews, M.T.; Kelly, D.G.; Nielsen, K.S.

    2014-01-01

    The Royal Military College of Canada (RMCC) has a 20 kW SLOWPOKE-2 nuclear research reactor which is used for teaching and research. Since its commissioning, the reactor facility and instruments have been continuously upgraded to develop and enhance nuclear capabilities for the Canadian Armed Forces (CAF). Specific applications of neutron activation analysis (NAA), delayed neutron counting (DNC) and neutron imaging relevant to the CAF are discussed. (author)

  3. The SLOWPOKE-2 nuclear reactor at the Royal Military College of Canada: applications for the Canadian Armed Forces

    Energy Technology Data Exchange (ETDEWEB)

    Hungler, P.C.; Andrews, M.T.; Kelly, D.G.; Nielson, K.S., E-mail: paul.hungler@rmc.ca [Royal Military College of Canada, Kington, Ontario (Canada)

    2013-07-01

    The Royal Military College of Canada (RMCC) has a 20 kW SLOWPOKE-2 nuclear research reactor which is used for teaching and research.Since its commissioning, the reactor facility and instruments have been continuously upgraded to develop and enhance nuclear capabilities for the Canadian Armed Forces (CAF). Specific applications of neutron activation analysis (NAA), delayed neutron counting (DNC) and neutron imaging relevant to the CAF are discussed. (author)

  4. The SLOWPOKE-2 nuclear reactor at the Royal Military College of Canada: applications for the Canadian Armed Forces

    International Nuclear Information System (INIS)

    Hungler, P.C.; Andrews, M.T.; Kelly, D.G.; Nielson, K.S.

    2013-01-01

    The Royal Military College of Canada (RMCC) has a 20 kW SLOWPOKE-2 nuclear research reactor which is used for teaching and research.Since its commissioning, the reactor facility and instruments have been continuously upgraded to develop and enhance nuclear capabilities for the Canadian Armed Forces (CAF). Specific applications of neutron activation analysis (NAA), delayed neutron counting (DNC) and neutron imaging relevant to the CAF are discussed. (author)

  5. The self-limiting power excursion behaviour of the SLOWPOKE reactor: results of experiments and qualitative explanation

    International Nuclear Information System (INIS)

    Kay, R.E.; Hilborn, J.W.; Poulsen, N.B.

    1976-01-01

    This report describes all the transient experiments performed on both the SLOWPOKE-1 (CRNL) and the SLOWPOKE-2 (Ottawa) reactors between 1970 and 1973. Data is presented in terms of the measured parameters, reactor power and coolant temperatures, and the derived system reactivity, during self-limiting power excursions following rapid reactivity insertions of up to 6.48 mk. During a typical excursion the reactor power exhibits several distinct peaks which increase in number and magnitude as the size of the reactivity excursion increases. A maximum peak power of 186 kW was observed. This report discusses qualitatively the many phenomena influencing transient behaviour, and presents a limited analysis of the experimental results. (author)

  6. A program for the a priori evaluation of detection limits in instrumental neutron activation analysis using a SLOWPOKE II reactor

    International Nuclear Information System (INIS)

    Galinier, J.L.; Zikovsky, L.

    1982-01-01

    A program that permits the a priori calculation of detection limits in monoelemental matrices, adapted to instrumental neutron activation analysis using a SLOWPOKE II reactor, is described. A simplified model of the gamma spectra is proposed. Products of (n,p) and (n,α) reactions induced by the fast components of the neutron flux that accompanies the thermal flux at the level of internal irradiation sites in the reactor have been included in the list of interfering radionuclides. The program calculates in a systematic way the detection limits of 66 elements in an equal number of matrices using 153 intermediary radionuclides. Experimental checks carried out with silicon (for short lifetimes) and aluminum and magnesium (for intermediate lifetimes) show satisfactory agreement with the calculations. These results show in particular the importance of the contribution of the (n,p) and (n,α) reactions in the a priori evaluation of detection limits with a SLOWPOKE type reactor [fr

  7. On the use and usefulness of SLOWPOKE-Toronto

    International Nuclear Information System (INIS)

    Aufreiter, S.; Hancock, R.G.V.

    1994-01-01

    After 21 years of operation at the University of Toronto, the SLOWPOKE Reactor Facility is still used predominantly for the neutron activation analysis of a wide range of samples in both research and undergraduate teaching laboratories. A large number of researchers and students continue to take advantage of the five on-site gamma-ray spectrometers available for general use. The usage patterns of the low flux SLOWPOKE-2 reactor are addressed and an assessment is made of the relative continuing usefulness of the reactor facility to a range of research areas and teaching groups, with specific examples to illustrate the broad cross-section of use. (author) 31 refs.; 6 tabs

  8. Inertial fusion energy - research at the University of Alberta and a proposed Alberta/Canada Program

    International Nuclear Information System (INIS)

    Fedosejevs, R.; Offenberger, A.A.; Singh, S.; Tsui, Y.Y.

    2011-01-01

    Fusion Energy is being pursued internationally using a number of different approaches from magnetic confinement energy to inertial confinement fusion (ICF). Recently there has been significant advancement in inertial confinement fusion using laser drivers with the expectation of the demonstration of large fusion yield within the next year or two opening the path to engineering of fusion reactors based on high energy laser drivers. The Laser Plasma Research group at the University of Alberta has been involved in inertial fusion energy (IFE) research for the past few decades. The current status of IFE and the activities of the University of Alberta Research group in this area is reviewed. Funding of IFE related research in Canada has been very limited and Canada has fallen behind in this area. Given the major developments occurring internationally it is time to increase activities in Canada. A plan for an expanded Alberta/Canadian program in IFE in the near future is discussed. (author)

  9. R and D of proton conducting SOFC reactors to co-generate electricity and ethylene at University of Alberta

    International Nuclear Information System (INIS)

    Fu, X.Z.; Zhou, G.H.; Luo, J.L.; Chuang, K.T.; Sanger, A.R.

    2010-01-01

    Ethane exists in many natural gas deposits and is also a by-product of petroleum refining. Ethane's primary use is as a petrochemical feedstock to produce ethylene, a major intermediate in the manufacture of polymers and petrochemicals. Steam cracking is the principal method for conversion of ethane to ethylene. However, in this process, over 10 per cent of ethane is oxidized to carbon dioxide (CO 2 ), generating a nitrogen oxide pollutant. A large amount of ethane is deeply oxidized to CO 2 using common oxidative dehydrogenation of ethane to ethylene, and the chemical energy is not easily recovered as high grade energy. In addition, oxidative methods also produce acetylene, which is very detrimental to the manufacture of polymers because it poisons the catalysts and must therefore be removed to form high purity ethylene feed, which is a costly process. Ethane has the potential to be used as a fuel for hydrocarbon solid oxide fuel cells (SOFCs) to generate electrical energy with high efficiency and low impact on the environment, in which it is completely oxidized to CO 2 and water. However, consumption of ethane generates greenhouse gas (CO 2 ) emissions in conventional SOFCs using oxygen ion electrolyte, and consumption of these non-renewable resources is less desirable than their use for manufacture of petrochemicals. This paper discussed the development of ethane proton conducting solid oxide fuel cell reactors and related materials in order to more efficiently use ethane resources in an environmentally friendly process. The advantages of these fuel cell reactors were presented. 5 refs.

  10. Low Enrichment Uranium (LEU)-fueled SLOWPOKE-2 nuclear reactor simulation with the Monte-Carlo based MCNP 4A code

    International Nuclear Information System (INIS)

    Pierre, J.R.M.

    1996-01-01

    Following the commissioning of the Low Enrichment Uranium (LEU) Fuelled SLOWPOKE-2 research reactor at the Royal Military College-College Militaire Royal (RMC-CMR), excess reactivity measurements were conducted over a range of temperature and power. The results showed a maximum excess reactivity of 3.37 mk at 33 o C. Several deterministic models using computer codes like WIMS-CRNL, CITATION, TRIVAC and DRAGON have been used to try to reproduce the excess reactivity and temperature trend of both the LEU and HEU SLOWPOKE-2 reactors. The best simulations had been obtained at Ecole Polytechnique de Montreal. They were able to reproduce the temperature trend of their HEU-fuelled reactor using TRIVAC calculations, but this model over-estimated the absolute value of the excess reactivity by 119 mk. Although calculations using DRAGON did not reproduce the temperature trend as well as TRIVAC, these calculations represented a significant improvement on the absolute value at 20 o C reducing the discrepancy to 13 mk. Given the advance in computer technology, a probabilistic approach was tried in this work, using the Monte-Carlo N-Particle Transport Code System MCNP 4A, to model the RMC-CMR SLOWPOKE-2 reactor.

  11. The SLOWPOKE licensing model

    International Nuclear Information System (INIS)

    Snell, V.G.

    1992-01-01

    The SLOWPOKE Energy System (SES-10) is a 10 MW heating reactor that has been developed in Canada. It will be capable of running without a licensed operator in continuous attendance, and will be sited in urban areas. It has forgiving safety characteristics, including transient time-scales of the order of hours. A process called 'up-front' licensing has been evolved in Canada to identify, and resolve, regulatory concerns early in the process. Because of the potential market in Hungary for nuclear district heating, a licensing plan has been developed that incorporates Canadian licensing experience, identifies specific Hungarian requirements, and reduces the risk of licensing delays by seeking agreement of all parties at an early stage in the program. (orig.)

  12. The SLOWPOKE licensing model

    International Nuclear Information System (INIS)

    Snell, V.G.; Takats, F.; Szivos, K.

    1989-08-01

    The SLOWPOKE Energy System (SES-10) is a 10 MW heating reactor that has been developed in Canada. It will be capable of running without a licensed operator in continuous attendance, and will be sited in urban areas. It has forgiving safety characteristics, including transient time-scales of the order of hours. A process called 'up-front' licensing has been evolved in Canada to identify, and resolve, regulatory concerns early in the process. Because of the potential market in Hungary for nuclear district heating, a licensing plan has been developed that incorporates Canadian licensing experience, identifies specific Hungarian requirements, and reduces the risk of licensing delays by seeking agreement of all parties at an early stage in the program

  13. Slowpoke: the first decade and beyond

    International Nuclear Information System (INIS)

    Hilborn, J.W.; Burbidge, G.A.

    1983-10-01

    Since the startup of the first SLOWPOKE reactor at Chalk River Nuclear Laboratories in 1970, six SLOWPOKE-2 research reactors have been installed at other locations in Canada and a seventh is nearing completion in Jamaica. Designed mainly for neutron activation analysis, the 20 KW SLOWPOKE produces a thermal neutron flux of 10 12 n.cm -2 s -1 at five sample sites in a beryllium reflector surrounding the core. There are an additional five sites in the water reflector outside the beryllium. It has a high degree of inherent safety, arising from the negative temperature and void coefficients of the core, limited maximum excess reactivity, and restricted access to the core by users. As a result the reactor does not require an automatic shutdown system, neutron ionization chambers or low power startup instruments. Automatic control is exercised by a single motor-driven absorber rod responding to a self-powered neutron detector. Once operating, the reactor is licensed to be left unattended, but remotely monitored, for periods up to 24 hours. Because the reactor is so simple and safe, users of the facility can be licensed as operators without formal training in reactor technology. They must, of course, be fully qualified in radiation protection procedures. Reactor users do not have access to the core and are not permitted to store enriched uranium fuel at the reactor site. Present work at the Chalk River Nuclear Laboratories is directed toward the conversion of future SLOWPOKE reactors to low-enriched fuel, in support of an international effort to prevent the possible diversion and misuse of highly-enriched uranium. The feasibility of uprating SLOWPOKE to 2 MWt for heating buildings is also being studied

  14. Production of 165 Dy for radiation synovectomy, in a low-power (slowpoke) nuclear reactor

    International Nuclear Information System (INIS)

    Bridges, C.; Duke, M.J.M.; McQuarrie, S.A.; Wiebe, L.I.

    1998-01-01

    Full text: Severe, debilitating pain accompanies inflammation of the synovial membrane in rheumatoid arthritis. Under certain conditions, radiation synovectomy is an effective alternative to surgery for relief of these symptoms. Radionuclides which decay by the emission of beta particles, or beta plus low yields of gamma/x-rays are indicated for this medical application. Of the radionuclides with appropriate decay emissions, half-life and physical/chemical properties, 165 Dy is a suitable candidate for production in a low-power reactor. Literature methods for production of this radiopharmaceutical usually involve irradiating solid Dy(OH) 3 , which is dissolved in HCl to form DyCl 3 and then re-precipitated under controlled conditions using NaOH, to produce the desired particle size for medical use. A procedure in which most or all of this post-irradiation processing can be eliminated is particularly important when using low neutron flux reactors, in order to avoid reductions in the amount of deliverable radiopharmaceutical. Radiological safety considerations may also necessitate avoiding post-irradiation processing, since low-power reactor facilities usually have no appropriate hot cells for extensive manipulation of highly active samples. Appropriately-sized, pre-formed Dy(OH) 3 particles were produced under a variety of conditions in attempts to produce a stable, sodium-free product that would be suitable for irradiation and use without further processing. Sodium content could be reduced to about 165 Dy production yields and particle characteristics will be presented in support of this concept

  15. Quality Assurance of University Education in Alberta and Kenya ...

    African Journals Online (AJOL)

    Since the introduction of degree granting institutions, Alberta and Kenya have persistently made efforts to manage and improve the quality of university education. While contexts, stakeholders, and quality assurance regimes have changed over time, debate on academic quality in both jurisdictions has continued bringing to ...

  16. Experimental and computational determination of radiation dose rates in the SLOWPOKE-2 research reactor at the Royal Military College of Canada

    Energy Technology Data Exchange (ETDEWEB)

    Lamarre, G.B.; Bonin, H.W. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

    1999-07-01

    The first SLOWPOKE-2 research reactor designed to use Low Enriched Uranium (LEU) dioxide fuel was commissioned at the Royal Military College of Canada/College militaire royal du Canada in September 1985. The enrichment is 19.89% in {sup 235}U . The reactor is a pool-type design, moderated and cooled by light water with the core located at the bottom of a 5.87 m pool, ensuring a 4.42 m layer of water above the core to provide the necessary radiation shielding. Cooling is by means of natural convection, the reactor power being limited to 20 kW{sub th}. The design allows free access to the reactor pool: in addition to the pneumatic irradiation system permitting the positioning of small samples within the beryllium reflector and close to the core, larger samples can be positioned in the pool against the reactor vessel using an 'elevator'-type positioning device. Several research projects have taken and are taking advantage of this equipment, most notably investigations of intense radiation effects on advanced polymers such as epoxies and poly-ether-ether-ketones (PEEKs). These research activities however require sound knowledge of the dose rates at the various irradiation sites within the reactor vessel, as well as at incremental positions within the pool. Accurate measurements of the particle fluxes were attempted before, but unfortunately yielded limited information due to the complexity of the composite radiation field and the capabilities of the instrumentation at that time. The present work aims at yet another attempt to gather sound dose rate data, using improved radiation detectors on one hand, and better computational resources (both hardware and software) on the other hand. All research on particle dose rates was performed with the reactor at steady-state half power (10 kW{sub th}) and at the reactor core mid-height. (author)

  17. Experimental and computational determination of radiation dose rates in the SLOWPOKE-2 research reactor at the Royal Military College of Canada

    International Nuclear Information System (INIS)

    Lamarre, G.B.; Bonin, H.W.

    1999-01-01

    The first SLOWPOKE-2 research reactor designed to use Low Enriched Uranium (LEU) dioxide fuel was commissioned at the Royal Military College of Canada/College militaire royal du Canada in September 1985. The enrichment is 19.89% in 235 U . The reactor is a pool-type design, moderated and cooled by light water with the core located at the bottom of a 5.87 m pool, ensuring a 4.42 m layer of water above the core to provide the necessary radiation shielding. Cooling is by means of natural convection, the reactor power being limited to 20 kW th . The design allows free access to the reactor pool: in addition to the pneumatic irradiation system permitting the positioning of small samples within the beryllium reflector and close to the core, larger samples can be positioned in the pool against the reactor vessel using an 'elevator'-type positioning device. Several research projects have taken and are taking advantage of this equipment, most notably investigations of intense radiation effects on advanced polymers such as epoxies and poly-ether-ether-ketones (PEEKs). These research activities however require sound knowledge of the dose rates at the various irradiation sites within the reactor vessel, as well as at incremental positions within the pool. Accurate measurements of the particle fluxes were attempted before, but unfortunately yielded limited information due to the complexity of the composite radiation field and the capabilities of the instrumentation at that time. The present work aims at yet another attempt to gather sound dose rate data, using improved radiation detectors on one hand, and better computational resources (both hardware and software) on the other hand. All research on particle dose rates was performed with the reactor at steady-state half power (10 kW th ) and at the reactor core mid-height. (author)

  18. International Conference held at the University of Alberta

    CERN Document Server

    Strobeck, Curtis

    1983-01-01

    This volume contains the Proceedings of the International Conference in Population Biology held at The University of Alberta, Edmonton, Canada from June 22 to June 30, 1982. The Conference was sponsored by The University of Alberta and The Canadian Applied Mathematics Society, and overlapped with the summer meeting of CAMS. The main objectives of this Conference were: to bring mathematicians and biologists together so that they may interact for their mutual benefit; to bring those researchers interested in modelling in ecology and those interested in modelling in genetics together; to bring in keynote speakers in the delineated areas; to have sessions of contributed papers; and to present the opportunity for researchers to conduct workshops. With the exception of the last one, the objec­ tives were carried out. In order to lend some focus to the Conference, the following themes were adopted: models of species growth, predator-prey, competition, mutualism, food webs, dispersion, age structure, stability, evol...

  19. The use of teleglaucoma at the University of Alberta.

    Science.gov (United States)

    Kassam, Faazil; Amin, Samreen; Sogbesan, Enitan; Damji, Karim F

    2012-10-01

    The aim of the teleglaucoma service at the University of Alberta is to improve access for people in northern Alberta who have early-stage glaucoma or who are at risk for glaucoma. Two types of teleglaucoma service are offered: remote and in-house. A standardized approach is used to capture patient information (structured histories, examinations and fundus photographs) which is then sent to a tertiary care centre for grading and recommendations. Only one grader reads and makes management recommendations for each case. Reports are sent electronically. A total of 195 cases have been graded through the remote service since 2008. A total of 62 cases have been graded through the in-house service since 2011. The average reporting time for consultations in the in-house service was 7 days, and it was also 7 days for the remote service. We believe that the use of teleglaucoma can improve the way that patients are diagnosed and managed, both in industrialized and developing countries. Teleglaucoma is currently being used as a screening tool at the Aga Khan University Hospital in Nairobi with mobile units equipped with a fundus camera and a visual field machine.

  20. University Reactor Instrumentation Program

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1992-11-01

    Recognizing that the University Reactor Instrumentation Program was developed in response to widespread needs in the academic community for modernization and improvement of research and training reactors at institutions such as the University of Florida, the items proposed to be supported by this grant over its two year period have been selected as those most likely to reduce foreed outages, to meet regulatory concerns that had been expressed in recent years by Nuclear Regulatory Commission inspectors or to correct other facility problems and limitations. Department of Energy Grant Number DE-FG07-90ER129969 was provided to the University of Florida Training Reactor(UFTR) facility through the US Department of Energy's University Reactor Instrumentation Program. The original proposal submitted in February, 1990 requested support for UFTR facility instrumentation and equipment upgrades for seven items in the amount of $107,530 with $13,800 of this amount to be the subject of cost sharing by the University of Florida and $93,730 requested as support from the Department of Energy. A breakdown of the items requested and total cost for the proposed UFTR facility instrumentation and equipment improvements is presented

  1. The University of Alberta High Altitude Balloon Program

    Science.gov (United States)

    Johnson, W.; Buttenschoen, A.; Farr, Q.; Hodgson, C.; Mann, I. R.; Mazzino, L.; Rae, J.; University of Alberta High Altitude Balloon Team

    2011-12-01

    The University of Alberta High Altitude Balloon (UA-HAB) program is a one and half year program sponsored by the Canadian Space Agency (CSA) that offers hands on experience for undergraduate and graduate students in the design, build, test and flight of an experimental payload on a high altitude balloon platform. Utilising low cost weather balloon platforms, and through utilisation of the CSA David Florida Laboratory for thermal-vacuum tests , in advance of the final flight of the payload on a NASA high altitude balloon platform. Collectively the program provided unique opportunities for students to experience mission phases which parallel those of a space satellite mission. The program has facilitated several weather balloon missions, which additionally provide educational opportunities for university students and staff, as well as outreach opportunities among junior and senior high school students. Weather balloon missions provide a cheap and quick alternative to suborbital missions; they can be used to test components for more expensive missions, as well as to host student based projects from different disciplines such as Earth and Atmospheric Sciences (EAS), Physics, and Engineering. In addition to extensive skills development, the program aims to promote recruitment of graduate and undergraduate students into careers in space science and engineering. Results from the UA-HAB program and the flight of the UA-HAB shielded Gieger counter payload for cosmic ray and space radiation studies will be presented. Lessons learned from developing and maintaining a weather balloon program will also be discussed. This project is undertaken in partnership with the High Altitude Student Platform, organized by Louisiana State University and the Louisiana Space Consortium (LaSpace), and sponsored by NASA, with the financial support of the Canadian Space Agency.

  2. University Reactor Sharing Program

    International Nuclear Information System (INIS)

    Reese, W.D.

    2004-01-01

    Research projects supported by the program include items such as dating geological material and producing high current super conducting magnets. The funding continues to give small colleges and universities the valuable opportunity to use the NSC for teaching courses in nuclear processes; specifically neutron activation analysis and gamma spectroscopy. The Reactor Sharing Program has supported the construction of a Fast Neutron Flux Irradiator for users at New Mexico Institute of Mining and Technology and the University of Houston. This device has been characterized and has been found to have near optimum neutron fluxes for A39/Ar 40 dating. Institution final reports and publications resulting from the use of these funds are on file at the Nuclear Science Center

  3. Various applications using the SLOWPOKE-2 facility at RMC

    International Nuclear Information System (INIS)

    Bennett, L.G.I.; Nielsen, K.S.

    2011-01-01

    History will record that the reactor pool at the SLOWPOKE-2 Facility at RMC was one of the first SLOWPOKE pools to be constructed (mid 1970s), even though the reactor itself was the last SLOWPOKE reactor to be installed and commissioned (1985). The unique and very useful feature of the reactor pool is that it is uncovered, allowing for applications in addition to the NAA and radioisotope production applications initially advertised. Because the installation of a tangential neutron beam tube (NBT) had been planned from the beginning, an outer irradiation site inside the reactor container was replaced by a thermal column. Next, a positioning system was added to accept large objects such as flight control surfaces from DND's CF-18 fighter aircraft. Imaging of these surfaces using film is being phased out with the introduction of digital imaging. Very recently a tomography stage was designed and built and is now integrated into the neutron imaging system. Also in the open pool are three pulley and rope 'elevators', two of which allow for large samples to be exposed to various kinds of radiation directly outside of the reactor container. The third elevator is located against the west pool wall, which allows for sample exposure to radiation without any neutron contribution. At the time of negotiating the purchase of the reactor, a teaching package consisting of an in-pool borated ion chamber and an outlet thermocouple was ordered. Automatic irradiation and counting systems in the form of cyclic, pseudo-cyclic, and long counting options were added to the original manual irradiation option. This past summer (2010), a delayed neutron counting system (DNCS) was built and installed in the SLOWPOKE-2 Facility at RMC. Examples will be given for the above-mentioned applications.

  4. Calgary, Edmonton and the University of Alberta: the extraordinary medical mobilization by Canada's newest province.

    Science.gov (United States)

    Da Cambra, Mark P; McAlister, Vivian C

    2017-09-01

    The Canadian contribution of medical services to the British Empire during the First World War was a national endeavour. Physicians from across the country enlisted in local regiments to join. No other region provided more physicians per capita than the newly formed province of Alberta. Largely organized through the Medical School of the University of Alberta, the No. 11 Canadian Field Ambulance out of Edmonton and the No. 8 Canadian Field Ambulance out of Calgary ultimately enlisted between one-third and half of the province's doctors to the war campaign. Many individuals from this region distinguished themselves, including LCol J.N. Gunn from Calgary, who commanded the No. 8 Canadian Field Ambulance; Maj Heber Moshier, one of the founders of the School of Pharmacy at the University of Alberta; and Dr. A.C. Rankin, who would go on to be the first Dean of Medicine at the University of Alberta. These Canadian heroes, and the many others like them who served with the No. 8 and 11 Field Ambulances, personify the sacrifice, strength and resilience of the medical community in Alberta and should not be forgotten.

  5. University Reactor Conversion Lessons Learned Workshop for Purdue University Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Eric C. Woolstenhulme; Dana M. Hewit

    2008-09-01

    The Department of Energy’s Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at Purdue University Reactor. With this work completed and in anticipation of other impending conversion projects, the INL convened and engaged the project participants in a structured discussion to capture the lessons learned. The lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project team’s experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.

  6. DOE/university reactor sharing

    International Nuclear Information System (INIS)

    Young, H.H.

    1985-01-01

    The objective of the US Department of Energy's program of reactor sharing is to strengthen nuclear science and engineering instruction and nuclear research opportunities in non-reactor-owning colleges and universities. The benefits of the program and need for the continuation of the program in the future are discussed

  7. Status of Japanese university reactors

    International Nuclear Information System (INIS)

    Fujita, Yoshiaki

    1999-01-01

    Status of Japanese university reactors, their role and value in research and education, and the spent fuel problem are presented. Some of the reactors are now faced by severe difficulties in continuing their operation services. The point of measures to solve the difficulties is suggested. (author)

  8. Slowpoke - its application to district heating

    International Nuclear Information System (INIS)

    Lynch, G.F.

    1987-07-01

    Over 25% of the primary energy consumption in most of the countries of the northern Pacific Basin is used to heat buildings. This represents an important opportunity for nuclear energy to significantly reduce the dependence on fossil fuels in an end-use application that is readily amenable to substitution. In a major departure from traditional nuclear power technology, Atomic Energy of Canada Limited has developed the SLOWPOKE Energy System - a 10 MWt nuclear heat source specially designed to satisfy the needs of local heating systems used by buildings and institutions. A prototype reactor has been constructed to verify in a very demonstrative way that the technical, economic and safety criteria for nuclear district heating systems can in fact be met

  9. SLOWPOKE-its application to district heating

    International Nuclear Information System (INIS)

    Lynch, G.F.

    1987-01-01

    Over 25% of the primary energy consumption in most of the countries of the northern Pacific Basin is used to heat buildings. This represents an important opportunity for nuclear energy to significantly reduce the dependence on fossil fuels in an end-use application that is readily amenable to substitution. In a major departure from traditional nuclear power technology, Atomic Energy of Canada Limited has developed the SLOWPOKE Energy System-a 10 MWt nuclear heat source specially designed to satisfy the needs of local heating systems used by buildings andinstitutions. A prototype reactor has been constructed to verify in a very demonstrative way that the technical, economic and safety criteria for nuclear district heating systems can in fact be met. (author)

  10. LEU-fueled SLOWPOKE-2 modelling with MCNP4A

    International Nuclear Information System (INIS)

    Pierre, J.R.M.; Bonin, H.W.J.

    1996-01-01

    Following the commissioning of the Low Enrichment Uranium (LEU) Fueled SLOWPOKE-2 research reactor at Royal Military College,excess reactivity measurements were conducted over a range of temperature and power. Given the advance in computer technology, the use of Monte Carlo N-Particle Transport Code System MCNP 4A appeared possible for the simulation of the LEU-fueled SLOWPOKE-2 reactor core, and this work demonstrates that this is indeed the case. MCNP 4A is a full three dimensional program allowing the user to enter a large amount of complexity. The limit on the geometry complexity is the computing time required to achieve a reasonable standard deviation. To this point several models of the SLOWPOKE-2 have been developed giving some insight on the sensitivity of the code. MCNP4A can use various cross section libraries. The aim of this work is to calculate accurately the reactivity of the core and reproduce The temperature trend of the reactivity. The model preserved as much as possible the details of the core and facility in order to allow further study in the flux mapping

  11. Royal Military College of Canada SLOWPOKE-2 facility. Integrated regulating and instrumentation system (SIRCIS) upgrade project

    International Nuclear Information System (INIS)

    Corcoran, W.P.; Nielsen, K.S.; Kelly, D.G.; Weir, R.D.

    2013-01-01

    The SLOWPOKE-2 Facility at the Royal Military College of Canada has operated the only digitally controlled SLOWPOKE reactor since 2001 (Version 1.0). The present work describes ongoing project development to provide a robust digital reactor control system that is consistent with Aging Management as summarized in the Facility's Life Cycle Management and Maintenance Plan. The project has transitioned from a post-graduate research activity to a comprehensively managed project supported by a team of RMCC professional and technical staff who have delivered an update of the V1.1 system software and hardware implementation that is consistent with best Canadian nuclear industry practice. The challenges associated with the implementation of Version 2.0 in February 2012, the lessons learned from this implementation, and the applications of these lessons to a redesign and rewrite of the RMCC SLOWPOKE-2 digital instrumentation and regulating system (Version 3) are discussed. (author)

  12. Arkansas Tech University reactor project

    Energy Technology Data Exchange (ETDEWEB)

    Sankoorikal, J.T.; Culp, R.R.; Hamm, J.R. (Arkansas Tech. Univ., Russellville (United States))

    1991-11-01

    The purpose of this paper is to describe the nuclear reactor project at Arkansas Tech University (ATU). The reactor will be a part of the Center for Energy Studies (CES) located on the ATU campus in Russellville, Arkansas. It will be used for education, training, and research. The Arkansas Tech University TRIGA Reactor (ATUTR) is a TRIGA Mark I that will be operated in two basic modes: steady state and pulsing. The maximum power level for steady-state operation is 250 kW(thermal), and the maximum step reactivity insertion will be 2.0$. The inherent safety of this reactor comes from the large negative temperature coefficient of the uranium-zirconium-hydride fuel-moderator elements. Principal design parameters for the reactor are summarized. The application for reactor construction and operating license was submitted to the US Nuclear Regulatory Commission in November 1989. The review process is continuing. ATU plans to continue to work with local industry and the public to provide a wide variety of services related to nuclear science and engineering.

  13. Calgary, Edmonton and the University of Alberta: the extraordinary medical mobilization by Canada’s newest province

    Science.gov (United States)

    Da Cambra, Mark P.; McAlister, Vivian C.

    2017-01-01

    Summary The Canadian contribution of medical services to the British Empire during the First World War was a national endeavour. Physicians from across the country enlisted in local regiments to join. No other region provided more physicians per capita than the newly formed province of Alberta. Largely organized through the Medical School of the University of Alberta, the No. 11 Canadian Field Ambulance out of Edmonton and the No. 8 Canadian Field Ambulance out of Calgary ultimately enlisted between one-third and half of the province’s doctors to the war campaign. Many individuals from this region distinguished themselves, including LCol J.N. Gunn from Calgary, who commanded the No. 8 Canadian Field Ambulance; Maj Heber Moshier, one of the founders of the School of Pharmacy at the University of Alberta; and Dr. A.C. Rankin, who would go on to be the first Dean of Medicine at the University of Alberta. These Canadian heroes, and the many others like them who served with the No. 8 and 11 Field Ambulances, personify the sacrifice, strength and resilience of the medical community in Alberta and should not be forgotten. PMID:28930035

  14. Oregon State University TRIGA Reactor annual report

    International Nuclear Information System (INIS)

    Anderson, T.V.; Johnson, A.G.; Bennett, S.L.; Ringle, J.C.

    1979-01-01

    The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included

  15. Measurements in support of a neutron radiography facility for the SLOWPOKE-2 at RMC

    Science.gov (United States)

    Lewis, W. J.; Andrews, W. S.; Bennett, L. G. I.; Beeley, P. A.

    1990-12-01

    The feasibility of using the small (20 kWh) SLOWPOKE-2 research reactor for neutron radiography has been investigated. Although designed primarily for neutron activation analysis (NAA) and radioisotope production, the SLOWPOKE-2 at RMC was installed with a thermal column of heavy water in a sector of the water gap between the beryllium reflector and the reactor container. The thermal-neutron flux in the reactor pool, just beyond the reactor container, has been measured to be a factor of 2.7 higher than in similar locations remote from the thermal column. Placed in this location was a prototype neutron radiography facility, consisting of a beam tube (or collimator), vertically tangential to the reactor core, and a beam stop. Once the feasibility of using a SLOWPOKE-2 for neutron radiography was demonstrated, subsequent investigations were carried out to optimize the quality of the obtainable radiographs. Both neutron radiographic and thermal-neutron flux measurements were undertaken to determine the optimum placement and arrangement of the beam tube. A Category III (as defined by the ASTM Standard E545-86) neutron radiography facility was obtained, although Category I or II were indicated as feasible. Based on this prototype design and experimentation, a permanent neutron radiography facility will be installed. The design calculations have been finalized, construction blueprints have been prepared, and work is proceeding with the construction, installation and commissioning of the facility.

  16. Measurements in support of a neutron radiography facility for the SLOWPOKE-2 at RMC

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, W.J.; Andrews, W.S.; Bennett, L.G.I.; Beeley, P.A. (Royal Military Coll. of Canada, Kingston, ON (Canada). SLOWPOKE-2 Facility Royal Military Coll. of Canada, Kingston, ON (Canada). Dept. of Chemistry and Chemical Engineering)

    1990-12-20

    The feasibility of using the small (20 kWh) SLOWPOKE-2 research reactor for neutron radiography has been investigated. Although designed primarily for neutron activation analysis (NAA) and radioisotope production, the SLOWPOKE-2 at RMC was installed with a thermal column of heavy water in a sector of the water gap between the beryllium reflector and the reactor container. The thermal-neutron flux in the reactor pool, just beyond the reactor container, has been measured to be a factor of 2.7 higher than in similar locations remote from the thermal column. Placed in this location was a prototype neutron radiography facility, consisting of a beam tube (or collimator), vertically tangential to the reactor core, and a beam stop. Once the feasibility of using a SLOWPOKE-2 for neutron radiography was demonstrated, subsequent investigations were carried out to optimize the quality of the obtainable radiographs. Both neutron radiographic and thermal-neutron flux measurements were undertaken to determine the optimum placement and arrangement of the beam tube. A Category III (as defined by the ASTM Standard E545-86) neutron radiography facility was obtained, although Category I or II were indicated as feasible. Based on this prototype design and experimentation, a permanent neutron radiography facility will be installed. The design calculations have been finalized, construction blueprints have been prepared, and work is proceeding with the construction, installation and commissioning of the facility. (orig.).

  17. Measurements in support of a neutron radiography facility for the SLOWPOKE-2 at RMC

    International Nuclear Information System (INIS)

    Lewis, W.J.; Andrews, W.S.; Bennett, L.G.I.; Beeley, P.A.; Royal Military Coll. of Canada, Kingston, ON

    1990-01-01

    The feasibility of using the small (20 kWh) SLOWPOKE-2 research reactor for neutron radiography has been investigated. Although designed primarily for neutron activation analysis (NAA) and radioisotope production, the SLOWPOKE-2 at RMC was installed with a thermal column of heavy water in a sector of the water gap between the beryllium reflector and the reactor container. The thermal-neutron flux in the reactor pool, just beyond the reactor container, has been measured to be a factor of 2.7 higher than in similar locations remote from the thermal column. Placed in this location was a prototype neutron radiography facility, consisting of a beam tube (or collimator), vertically tangential to the reactor core, and a beam stop. Once the feasibility of using a SLOWPOKE-2 for neutron radiography was demonstrated, subsequent investigations were carried out to optimize the quality of the obtainable radiographs. Both neutron radiographic and thermal-neutron flux measurements were undertaken to determine the optimum placement and arrangement of the beam tube. A Category III (as defined by the ASTM Standard E545-86) neutron radiography facility was obtained, although Category I or II were indicated as feasible. Based on this prototype design and experimentation, a permanent neutron radiography facility will be installed. The design calculations have been finalized, construction blueprints have been prepared, and work is proceeding with the construction, installation and commissioning of the facility. (orig.)

  18. District heating with SLOWPOKE energy systems

    International Nuclear Information System (INIS)

    Lynch, G.F.

    1988-03-01

    The SLOWPOKE Energy System, a benign nuclear heat source designed to supply 10 thermal megawatts in the form of hot water for local heating systems in buildings and institutions, is at the forefront of these developments. A demonstration unit has been constructed in Canada and is currently undergoing an extensive test program. Because the nuclear heat source is small, operates at atmospheric pressure, and produces hot water below 100 degrees Celcius, intrinsic safety features will permit minimum operator attention and allow the heat source to be located close to the load and hence to people. In this way, a SLOWPOKE Energy System can be considered much like the oil- or coal-fired furnace it is designed to replace. The low capital investment requirements, coupled with a high degree of localization, even for the first unit, are seen as attractive features for the implementation of SLOWPOKE Energy Systems in many countries

  19. Arkansas Tech University TRIGA nuclear reactor

    International Nuclear Information System (INIS)

    Sankoorikal, J.; Culp, R.; Hamm, J.; Elliott, D.; Hodgson, L.; Apple, S.

    1990-01-01

    This paper describes the TRIGA nuclear reactor (ATUTR) proposed for construction on the campus of Arkansas Tech University in Russellville, Arkansas. The reactor will be part of the Center for Energy Studies located at Arkansas Tech University. The reactor has a steady state power level of 250 kW and can be pulsed with a maximum reactivity insertion of $2.0. Experience gained in dismantling and transporting some of the components from Michigan State University, and the storage of these components will be presented. The reactor will be used for education, training, and research. (author)

  20. Slowpoke - a new Canadian heat source

    International Nuclear Information System (INIS)

    Bancroft, A.R.; Lynch, G.F.; Ohta, M.M.

    1987-07-01

    Atomic Energy of Canada Limited now has a new product, the SLOWPOKE Energy System, that provides low temperature heat suitable for building and process heating. The SLOWPOKE Energy System is sized to deliver up to 10 megawatts of hot water at up to 90 degrees C, appropriate for large buildings and industrial processes. It is designed for operation without the full-time attendance of dedicated staff and, because of its inherent safety, for siting close to users. At less than 2 cents/kWh, the heat is competitive with oil, gas and electricity in most regions of Canada and the world

  1. The first university research reactor in India

    International Nuclear Information System (INIS)

    Murthy, G.S.

    1999-01-01

    At low power research reactor is being set up in Andhra University to cater to the needs of researchers and isotope users by the Department of Atomic Energy in collaboration with Andhra University. This reactor is expected to be commissioned by 2001-02. Departments like Chemistry, Earth Sciences, Physics, Life Sciences, Pharmacy, Medicine and Engineering would be the beneficiaries of the availability of this reactor. In this paper, details of the envisaged research programme and training activities are discussed. (author)

  2. University of Alberta Flare Research Project : interim report November 1996-Jun 2000

    International Nuclear Information System (INIS)

    Kostiuk, L.; Johnson, M.

    2000-01-01

    The Flare Research Project at the University of Alberta is an ongoing multi year study into the emissions, combustion process and fluid mechanics related to flaring, which is commonly used in the energy and petrochemical industries to dispose of unwanted combustible gases by burning them in an open flame. This report focused on the emissions and efficiency of flares under operating conditions typical of solution gas flares. While most solution gas produced in Alberta is conserved, it is estimated that 6 per cent of these gases are flared with significant changes in the volumes flared from site to site. The median volume of flared or vented gas was approximately 60,300 m 3 /year and 95 per cent of battery sites flare and vent less than 1,000,000 m 3 /year. The goal of this project is to experimentally study the scaled-down generic pipe flares under well-controlled conditions to better understand the performance of flares. Research was conducted in a closed-loop wind tunnel to determine the effects of wind on flaring. Other objectives of the research are to develop methods for measuring the overall combustion efficiency of flares with either gaseous flare streams or those containing liquid droplets. Models for the scaling of plumes that disperse the products of combustion from flares as a function of wind speed, exit velocity and flare stack diameter were also examined. And finally, this research project measured the emissions of selected toxic compounds in both their vapor and soot phases. 38 refs., 10 tabs., 56 figs

  3. University Reactor Matching Grants Program

    International Nuclear Information System (INIS)

    John Valentine; Farzad Rahnema; Said Abdel-Khalik

    2003-01-01

    During the 2002 Fiscal year, funds from the DOE matching grant program, along with matching funds from the industrial sponsors, have been used to support research in the area of thermal-hydraulics. Both experimental and numerical research projects have been performed. Experimental research focused on two areas: (1) Identification of the root cause mechanism for axial offset anomaly in pressurized water reactors under prototypical reactor conditions, and (2) Fluid dynamic aspects of thin liquid film protection schemes for inertial fusion reactor chambers. Numerical research focused on two areas: (1) Multi-fluid modeling of both two-phase and two-component flows for steam conditioning and mist cooling applications, and (2) Modeling of bounded Rayleigh-Taylor instability with interfacial mass transfer and fluid injection through a porous wall simulating the ''wetted wall'' protection scheme in inertial fusion reactor chambers. Details of activities in these areas are given

  4. Neutron fluence effects on SLOWPOKE-2 beryllium reflector composition and reactivity

    Energy Technology Data Exchange (ETDEWEB)

    Puig, Francesc, E-mail: fpuig@anl.gov [Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (United States); Dennis, Haile, E-mail: haile.dennis02@uwimona.edu.jm [International Centre for Environmental and Nuclear Sciences, 2 Anguilla Close, University of the West Indies, Mona, Kingston 7 (Jamaica)

    2016-08-15

    Highlights: • SLOWPOKE-2 reflector composition evolution estimated using two different methods. • Reactivity effects of reflector composition changes calculated using MCNP5. • Impurities depletion dominates over poisons buildup, increasing reactivity. • Results contradict previously published behavior estimates for MNSR reactors. • Identified main factors explaining the observed prediction discrepancies. - Abstract: Within the scope of the conversion process from HEU to LEU of the Jamaican SLOWPOKE-2 reactor (JM-1), the effects of the neutron fluence on the beryllium reflector composition, and the corresponding effect on reactivity throughout the life of the reactor core, have been studied. Two different methods have been used and compared involving MCNP5, ORIGEN2.2, ORIGEN-S and COUPLE codes, reaching excellent agreement between them. The neutron flux profile and energy spectrum specific to the beryllium reflectors of this reactor design have been taken into account to analyze several scenarios, comprising both real and hypothetical conditions and involving different initial reflector compositions and reactor burnups. The analysis has been extended to provide estimates for the similar MNSR reactor design and compared with previously published predictions for the Syrian MNSR. The results show small overall reactivity effects in most cases, being dominated by impurity depletion as opposed to poison buildup, contrarily to what generally occurs in beryllium reflected reactors of far higher power and to MNSR predictions. The resulting reactivity increases are typically of less than 0.4 mk for usual impurity levels and maximum HEU core burnup achievable.

  5. Neutron fluence effects on SLOWPOKE-2 beryllium reflector composition and reactivity

    International Nuclear Information System (INIS)

    Puig, Francesc; Dennis, Haile

    2016-01-01

    Highlights: • SLOWPOKE-2 reflector composition evolution estimated using two different methods. • Reactivity effects of reflector composition changes calculated using MCNP5. • Impurities depletion dominates over poisons buildup, increasing reactivity. • Results contradict previously published behavior estimates for MNSR reactors. • Identified main factors explaining the observed prediction discrepancies. - Abstract: Within the scope of the conversion process from HEU to LEU of the Jamaican SLOWPOKE-2 reactor (JM-1), the effects of the neutron fluence on the beryllium reflector composition, and the corresponding effect on reactivity throughout the life of the reactor core, have been studied. Two different methods have been used and compared involving MCNP5, ORIGEN2.2, ORIGEN-S and COUPLE codes, reaching excellent agreement between them. The neutron flux profile and energy spectrum specific to the beryllium reflectors of this reactor design have been taken into account to analyze several scenarios, comprising both real and hypothetical conditions and involving different initial reflector compositions and reactor burnups. The analysis has been extended to provide estimates for the similar MNSR reactor design and compared with previously published predictions for the Syrian MNSR. The results show small overall reactivity effects in most cases, being dominated by impurity depletion as opposed to poison buildup, contrarily to what generally occurs in beryllium reflected reactors of far higher power and to MNSR predictions. The resulting reactivity increases are typically of less than 0.4 mk for usual impurity levels and maximum HEU core burnup achievable.

  6. The first university research reactor in India

    International Nuclear Information System (INIS)

    Murty, G.S.

    1999-01-01

    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)

  7. University Research Reactors: Issues and Challenges

    International Nuclear Information System (INIS)

    Bernard, John A.; Hu Linwen

    2000-01-01

    University research reactors are underutilized and, as a result, are being decommissioned. The reason for the lack of utilization is shown to be a chronic inability to generate sufficient funds to procure and maintain state-of-the-art instrumentation for prospective researchers. The role of these reactors in nuclear science/engineering education is explored and the rationale for their continued operation is presented. It is argued that base financial support for both reactor operations and the technical support staff needed to interface with experimenters is necessary if these research facilities are not to be irretrievably lost from the educational infrastructure of the United States

  8. Operational safety and reactor life improvements of Kyoto University Reactor

    International Nuclear Information System (INIS)

    Utsuro, M.; Fujita, Y.; Nishihara, H.

    1990-01-01

    Recent important experience in improving the operational safety and life of a reactor are described. The Kyoto University Reactor (KUR) is a 25-year-old 5 MW light water reactor provided with two thermal columns of graphite and heavy water as well as other kinds of experimental facilities. In the graphite thermal column, noticeable amounts of neutron irradiation effects had accumulated in the graphite blocks near the core. Before the possible release of the stored energy, all the graphite blocks in the column were successfully replaced with new blocks using the opportunity provided by the installation of a liquid deuterium cold neutron source in the column. At the same time, special seal mechanisms were provided for essential improvements to the problem of radioactive argon production in the column. In the heavy-water thermal column we have accomplished the successful repair of a slow leak of heavy water through a thin instrumentation tube failure. The repair work included the removal and reconstructions of the lead and graphite shielding layers and welding of the instrumentation tube under radiation fields. Several mechanical components in the reactor cooling system were also exchanged for new components with improved designs and materials. On-line data logging of almost all instrumentation signals is continuously performed with a high speed data analysis system to diagnose operational conditions of the reactor. Furthermore, through detailed investigations on critical components, operational safety during further extended reactor life will be supported by well scheduled maintenance programs

  9. New training reactor at Dresden Technical University

    International Nuclear Information System (INIS)

    Hansen, W.; Knorr, J.; Wolf, T.

    2006-01-01

    A total of 14 low-power (up to 10 W) training reactors have been operated at German universities, 9 of them officially classified as being operational in 2004, though for very different uses. This number is expected to drop sharply. The only comprehensive upgrading of a training reactor took place at Dresden Technical University: AKR-2, the most modern facility in Germany, started routine operation in April 2005, under a newly granted license pursuant to Sec. 7, Subsec. 1 of the German Atomic Energy Act, for training students in nuclear technology, for suitable research projects, and a a center of information about reactor technology and nuclear technology for the interested public. One special aspect of this refurbishment was the installation of digital safety I and C systems of the TELEPERM XS line, which are used also in other modern plants. This fact, plus the easy possibility to use the plant for many basic experiments in reactor physics and radiation protection, make the AKR-2 attractive also to other users (e.g. for training reactor personnel or other persons working in nuclear technology). (orig.)

  10. University Reactor Conversion Lessons Learned Workshop for Texas A&M University Nuclear Science Center Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Eric C. Woolstenhulme; Dana M. Meyer

    2007-04-01

    The objectives of this meeting were to capture the observations, insights, issues, concerns, and ideas of those involved in the Texas A&M University Nuclear Science Center (TAMU NSC) TRIGA Reactor Conversion so that future efforts can be conducted with greater effectiveness, efficiency, and with fewer challenges. This workshop was held in conjunction with a similar workshop for the University of Florida Reactor Conversion. Some of the generic lessons from that workshop are included in this report for completeness.

  11. A case study in Gantt charts as historiophoty: A century of psychology at the University of Alberta.

    Science.gov (United States)

    Dawson, Michael R W

    2013-05-01

    History is typically presented as historiography, where historians communicate via the written word. However, some historians have suggested alternative formats for communicating and thinking about historical information. One such format is known as historiophoty, which involves using a variety of visual images to represent history. The current article proposes that a particular type of graph, known as a Gantt chart, is well suited for conducting historiophoty. When used to represent history, Gantt charts provide a tremendous amount of information. Furthermore, the spatial nature of Gantt charts permits other kinds of spatial operations to be performed on them. This is illustrated with a case study of the history of a particular psychology department. The academic year 2009-2010 marked the centennial of psychology at the University of Alberta. This centennial was marked by compiling a list of its full-time faculty members for each year of its history. This historiography was converted into historiophoty by using it as the source for the creation of a Gantt chart. The current article shows how the history of psychology at the University of Alberta is revealed by examining this Gantt chart in a variety of different ways. This includes computing simple descriptive statistics from the chart, creating smaller versions of the Gantt to explore departmental demographics, and using image processing methods to provide measures of departmental stability throughout its history. (PsycINFO Database Record (c) 2013 APA, all rights reserved).

  12. Teaching chemistry with neutron activation analysis at Dalhousie University

    International Nuclear Information System (INIS)

    Holzbecher, J.; Chatt, A.

    1991-01-01

    The Dalhousie University SLOWPOKE-2 Reactor (DUSR) has been operating since July 1976 and has proven to be an invaluable tool in many teaching programs. These reactors are inherently safe and are designed to serve teaching and research needs of the universities, research centers, hospitals, etc. Since the DUSR has been, from its inception, associated with the Trace Analysis Research Centre, which is the Analytical Chemistry Division of the Department of Chemistry, the main thrust of its use continues to be in the field of nuclear analytical chemistry. Both teaching and research programs involve trace element analysis by neutron activation

  13. Measuring the productivity of university research reactors

    International Nuclear Information System (INIS)

    Voth, M.H.

    1989-01-01

    University Research Reactors (URRs) on 33 campuses in the United States provide valuable contributions to academic instruction and research programs. In most cases, there are no alternative diagnostic techniques to supplant the need for a reactor and associated facilities. Since URRs constitute a major financial commitment, it is important that they be operated in a productive manner. Productivity may be defined as the sum of new knowledge generated, existing knowledge transferred to others, and analytical services provided to assist in the generation of new knowledge; another definition of productivity is this sum expressed as a function of the cost incurred. In either case, a consistent measurement is difficult and more qualitative than quantitative. A uniform reporting system has been proposed that defines simplified categories through which meaningful comparisons can be performed

  14. Nuclear Training Reactor of the Technical University Budapest

    International Nuclear Information System (INIS)

    Csom, Gy.

    1982-01-01

    The history, operation, technical parameters and applications of the Training Reactor of Technical University, Budapest are described. The laboratories built around the five experimental channels of the reactor, their instrumentation and tasks are briefly outlined. The educational (including university training courses and international postgraduate courses organized by IAEA) and research activity performed at the Training Reactor are summarized. (D.Gy.)

  15. Education for university students, high school teachers and the general public using the Kinki University Reactor

    International Nuclear Information System (INIS)

    Tsuruta, T.

    2007-01-01

    Atomic Energy Research Institute of Kinki University is equipped with a nuclear reactor which is called UTR-KINKI. UTR is the abbreviation for University Teaching and Research Reactor. The reactor is the first one installed in Japanese universities. Though the reactor is owned and operated by Kinki University, its use is widely open to scientists and students from other universities and research institutions. The reactor is made the best of teaching instrument for the training of high school teachers. In addition, the reactor is utilized for general public education concerning atomic energy. (author)

  16. Is Universal Screening Necessary? Incidence of Tuberculosis among Tibetan Refugees Arriving in Calgary, Alberta.

    Science.gov (United States)

    Lim, Rachel; Jarand, Julie; Field, Stephen K; Fisher, Dina

    2016-01-01

    Background . Canadian policy requires refugees with a history of tuberculosis (TB) or abnormal chest radiograph to be screened after arrival for TB. However, Tibetan refugees are indiscriminately screened, regardless of preimmigration assessment. We sought to determine the incidence of latent (LTBI) and active TB, as well as treatment-related outcomes and associations between preimmigration factors and TB infection among Tibetan refugees arriving in Calgary, Alberta. Design . Retrospective cohort study including Tibetan refugees arriving between 2014 and 2016. Associations between preimmigration factors and incidence of latent and active TB were determined using Chi-square tests. Results . Out of 180 subjects, 49 percent had LTBI. LTBI was more common in migrants 30 years of age or older ( P = 0.009). Treatment initiation and completion rates were high at 90 percent and 76 percent, respectively. No associations between preimmigration factors and treatment completion were found. A case of active TB was detected and treated. Conclusion . Within this cohort, the case of active TB would have been detected through the usual postsurveillance process due to a history of TB and abnormal chest radiograph. Forty-nine percent had LTBI, compared to previously quoted rates of 97 percent. Tibetan refugees should be screened for TB in a similar manner to other refugees resettling in Canada.

  17. Reactor console replacement at Washington State University

    International Nuclear Information System (INIS)

    Lovas, Thomas A.

    1978-01-01

    A replacement reactor console was installed in 1977 at the W.S.U. 1 MW TRIGA-fueled reactor as the final step in an instrumentation upgrade program. The program was begun circa 1972 with the design, construction and installation of various systems and equipment. Major instruments were installed in the existing console and tested in the course of reactor operation. The culmination of the program was the installation of a cubicle designed and constructed to house the updated instrumentation. (author)

  18. Developing an integrated evidence-based medicine curriculum for family medicine residency at the University of Alberta.

    Science.gov (United States)

    Allan, G Michael; Korownyk, Christina; Tan, Amy; Hindle, Hugh; Kung, Lina; Manca, Donna

    2008-06-01

    There is general consensus in the academic community that evidence-based medicine (EBM) teaching is essential. Unfortunately, many postgraduate programs have significant weakness in their EBM programs. The Family Medicine Residency committee at the University of Alberta felt their EBM curriculum would benefit from critical review and revision. An EBM Curriculum Committee was created to evaluate previous components and develop new strategies as needed. Input from stakeholders including faculty and residents was sought, and evidence regarding the teaching and practical application of EBM was gathered. The committee drafted goals and objectives, the primary of which were to assist residents to (1) become competent self-directed, lifelong learners with skills to effectively and efficiently keep up to date, and 2) develop EBM skills to solve problems encountered in daily practice. New curriculum components, each evidence based, were introduced in 2005 and include a family medicine EBM workshop to establish basic EBM knowledge; a Web-based Family Medicine Desktop promoting easier access to evidence-based Internet resources; a brief evidence-based assessment of the research project enhancing integration of EBM into daily practice; and a journal club to support peer learning and growth of rapid appraisal skills. Issues including time use, costs, and change management are discussed. Ongoing evaluation of the curriculum and its components is a principal factor of the design, allowing critical review and adaptation of the curriculum. The first two years of the curriculum have yielded positive feedback from faculty and statistically significant improvement in multiple areas of residents' opinions of the curriculum and comfort with evidence-based practice.

  19. RELAP/SCDAPSIM Reactor System Simulator Development and Training for University and Reactor Applications

    International Nuclear Information System (INIS)

    Hohorst, J.K.; Allison, C.M.

    2010-01-01

    The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during normal and accident conditions, is being developed as part of an international nuclear technology development program called SDTP (SCDAP Development and Training Program). SDTP involves more than 60 organizations in 28 countries. One of the important applications of the code is for simulator training of university faculty and students, reactor analysts, and reactor operations and technical support staff. Examples of RELAP/SCDAPSIM-based system thermal hydraulic and severe accident simulator packages include the SAFSIM simulator developed by NECSA for the SAFARI research reactor in South Africa, university-developed simulators at the University of Mexico and Shanghai Jiao Tong University in China, and commercial VISA and RELSIM packages used for analyst and reactor operations staff training. This paper will briefly describe the different packages/facilities. (authors)

  20. Future plans on the Kyoto University Research Reactor (KUR)

    International Nuclear Information System (INIS)

    Shibata, Seiichi

    2000-01-01

    The Research Reactor Institute (RRI), Kyoto University, for aiming at performing the 'Experiments using a reactor and its related research', was established in Showa 38 (1963) as a cooperative research institute for universities and so on in allover Japan. Operation using KUR of one of main facilities in RRI was started by 1 MW of its rated output in 1964, and converted to 5 MW in 1968, after which through development , addition and modification of various research apparatus it has been proposed to the cooperative application researches with universities and so on in allover Japan, hitherto. Among these periods, its research organization is improved to six departments containing twenty divisions and two attached research facilities to progress some investigations on future plans at RRI for response to new researching trends. Here were described on present state of research on use of low concentrated uranium fuels at research reactor, and future plans on neutron factory and hybrid reactor. The former aims at establishment of a new research facility capable of alternating to KUR for future academic research on research reactor containing high quality and high degree application of neutron field and safety management and feature upgrading of nuclear energy. And, the latter aims at development on an accelerator drive uncritical reactor combined an accelerator neutron source and an uncritical reactor. (G.K.)

  1. Universal Fast Breeder Reactor Subassembly Counter manual

    Energy Technology Data Exchange (ETDEWEB)

    Menlove, H.O.; Eccleston, G.W.; Swansen, J.E.; Goris, P.; Abedin-Zadeh, R.; Ramalho, A.

    1984-08-01

    A neutron coincidence counter has been designed for the measurement of fast breeder reactor fuel assemblies. This assay system can accommodate the full range of geometries and masses found in fast breeder subassemblies under IAEA safeguards. The system's high-performance capability accommodates high plutonium loadings of up to 16 kg. This manual describes the system and its operation and gives performance and calibration parameters for typical applications.

  2. Universal Fast Breeder Reactor Subassembly Counter manual

    International Nuclear Information System (INIS)

    Menlove, H.O.; Eccleston, G.W.; Swansen, J.E.; Goris, P.; Abedin-Zadeh, R.; Ramalho, A.

    1984-08-01

    A neutron coincidence counter has been designed for the measurement of fast breeder reactor fuel assemblies. This assay system can accommodate the full range of geometries and masses found in fast breeder subassemblies under IAEA safeguards. The system's high-performance capability accommodates high plutonium loadings of up to 16 kg. This manual describes the system and its operation and gives performance and calibration parameters for typical applications

  3. Nuclear science and engineering education at a university research reactor

    International Nuclear Information System (INIS)

    Loveland, W.

    1990-01-01

    The research and teaching operations of the Nuclear Chemistry Division of the Dept. of Chemistry and the Dept. of Nuclear Engineering are housed at the Oregon State University Radiation Center. This facility which includes a 1.1 MW TRIGA reactor was used for 53 classes from a number of different academic departments last year. About one-half of these classes used the reactor and ∼25% of the reactor's 45 hour week was devoted to teaching. Descriptions will be given of reactor-oriented instructional programs in nuclear engineering, radiation health and nuclear chemistry. In nuclear chemistry, classes in (a) nuclear chemistry for nuclear engineers, (b) radiotracer methods, (c) elementary and advanced activation analysis, and (d) advanced nuclear instrumentation will be described in detail. The use of the facility to promote general nuclear literacy among college students, high school and grade school students and the general population will also be covered

  4. Slowpoke: a role for nuclear technology in district heating

    International Nuclear Information System (INIS)

    Lynch, G.F.

    1987-08-01

    The successful application of the SLOWPOKE concept to satisfy the heating needs of institutions and building complexes is described. Although the load factor for heating in Japan may not be as high as those experienced in other countries of the northern hemipshere, this particular application clearly demonstrates that small, special purpose, ultra-safe nuclear energy sources are technically and economically viable. They can be designed for easy operation and maintenance, to be located in urban areas and remote communities, thereby satsifying a broad spectrum of energy needs that cannot be served by central nuclear electrical generators

  5. Utilization of research reactors in universities and their medical applications

    International Nuclear Information System (INIS)

    Kanda, Keiji.

    1983-01-01

    In Japan, five research reactors and a critical assembly are operated by the universities. They are opened to all university researchers, the system of which is financially supported by the Ministry of Education, Culture and Science of the Japanese government. Usually KUR is operated eight cycles per year. One cycle consists of the following four week operation: 1. Mainly for researchers from other universities; 2. Mainly for researchers in the institute; 3. Mainly for beam experiment; 4. Sort time experiment. In the weeks of 1 ∼ 3 the KUR is operated continously from Tuesday morning to Friday evening. The experiment include studies on physics, chemistry, biology, medicine, engineering etc. Recently the medical application of research reactors has become popular in Japan. The new technique of the boron neutron capture thereby has been successfully applied to brain tumors and will be to melanoma (skin cancer) in near future. (author)

  6. Use of university research reactors to teach control engineering

    International Nuclear Information System (INIS)

    Bernard, J.A.

    1991-01-01

    University research reactors (URRs) have provided generations of students with the opportunity to receive instruction and do hands-on work in reactor dynamics, neutron scattering, health physics, and neutron activation analysis. Given that many URRs are currently converting to programmable control systems, the opportunity now exists to provide a similar learning experience to those studying systems control engineering. That possibility is examined here with emphasis on the need for the inclusion of experiment in control engineering curricula, the type of activities that could be performed, and safety considerations

  7. 75 FR 56597 - University of Wisconsin; University of Wisconsin Nuclear Reactor Environmental Assessment and...

    Science.gov (United States)

    2010-09-16

    ... when solid waste is generated from use of the UWNR, it is transferred to the University of Wisconsin.... In the years that solid waste was generated, less than 400 milliCuries of solid waste was transferred...; University of Wisconsin Nuclear Reactor Environmental Assessment and Finding of No Significant Impact The U.S...

  8. University Reactor Conversion Lessons Learned Workshop for the University of Florida

    Energy Technology Data Exchange (ETDEWEB)

    Eric C. Woolstenhulme; Dana M. Meyer

    2007-04-01

    The Department of Energy’s (DOE) Idaho National Laboratory (INL), under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at the University of Florida. This project was successfully completed through an integrated and collaborative effort involving the INL, Argonne National Laboratory (ANL), DOE (Headquarters and Field Office), the Nuclear Regulatory Commission, the Universities, and contractors involved in analyses, fuel design and fabrication, and SNF shipping and disposition. With the work completed with these two universities, and in anticipation of other impending conversion projects, INL convened and engaged the project participants in a structured discussion to capture lessons learned. The objectives of this meeting were to capture the observations, insights, issues, concerns, and ideas of those involved in the reactor conversions so that future efforts can be conducted with greater effectiveness, efficiency, and with fewer challenges.

  9. The value and cost of university research reactors

    International Nuclear Information System (INIS)

    Harling, O.K.; Bernard, J.A.

    1989-01-01

    In this paper the authors provide a brief overview of the value and costs of U.S. university research reactors (URRs). More than three dozen URRs are currently operating in an approximately equal number of states. These URRs are an important part of the U.S. capabilities in nuclear science and technology. These multipurpose research facilities are located on the campuses of universities and colleges and therefore are easily accessible to university staff and students as well as to the high-technology industries, which often are located near universities. The close proximity, i.e., convenient location, to a diverse user base is a major reason for the multifaceted applications of URRs, including basic and applied science, technology, education, and industrial applications. The URRs have an extraordinarily broad range of applicability, including medicine and the life sciences, materials science, environmental sciences, earth and planetary sciences, and nuclear energy

  10. Major Refurbishment of the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    Joradn, Kelly; Berglund, Matthew; Shea, Brian

    2013-01-01

    The research reactor fleet is aging with few replacements being built. At the same time the technology for refurbishment of the older reactors has advanced well beyond that of currently installed equipment. The disparity between new and old technology results in an inability to find simple replacements for the older, highly integrated components. The lack of comprehensive guidance for digital equipment adds to the technical problems of installing individual replacement parts. Up to this point, no U. S. facilities have attempted a complete modernization effort because of the time commitment, financial burden, and licensing required for a total upgrade. The University of Florida Training Reactor is tackling this problem with a replacement of nearly all of the major facility sub-systems, including electrical distribution, reactor controls, nuclear instrumentation, security, building management, and environmental controls. This approach offers increased flexibility over the piece-by-piece replacement method by leveraging modern control systems based on global standards and capable of good data interchange with higher levels of redundancy. The UFTR reviewed numerous technologies to arrive at the final system architecture and this 'clean-slate' installation methodology. It is this concept of total system replacement and strict use of modular, open-standards technology that has allowed for a facility design that will be easy to install, maintain, and build upon over time

  11. 76 FR 69296 - University of Utah, University of Utah TRIGA Nuclear Reactor, Notice of Issuance of Renewed...

    Science.gov (United States)

    2011-11-08

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION University of Utah, University of Utah TRIGA Nuclear Reactor, Notice of Issuance of Renewed... University of Utah (UU, the licensee), which authorizes continued operation of the UU TRIGA Nuclear Reactor...

  12. Radiopharmaceuticals developed at the University of Missouri research reactor

    International Nuclear Information System (INIS)

    Ketring, A.R.; Ehrhardt, G.J.; Day, D.E.

    1997-01-01

    The University of Missouri Research Reactor (MURR) has put a great deal of effort in the last two decades into development of radiotherapeutic beta emitters as nuclear medicine radiotherapeutics for malignancies. This paper describes the development of two of these drugs, 153 Sm ethylenediaminetetra-methylene phosphonic acid (EDTMP) (Quadramet trademark) and 90 Y glass microspheres (TheraSphere trademark). Samarium-153 EDTMP is a palliative used to treat the pain of metastatic bone cancer without the side effects of narcotic pain killers. Yttrium-90 glass microspheres are delivered via hepatic artery catheter to embolize the capillaries of liver tumors and deliver a large radiation dose for symptom palliation and life prolonging purposes

  13. Utilization of a university reactor for public acceptance

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myung Hyun [Kyung Hee Univ., Gyeonggi-do (Korea, Republic of). Reactor Research and Education Center

    2015-06-15

    AGN-201K is a university reactor in Kyung Hee University (KHU) mainly used for student education as training short course as well as academic course for senior-level. After the Fukushima accident, public concern on radiation hazard has been increased beyond rational level at a neighboring country. It was found that AGN-201K be the perfect tool for interaction with general public. It is very safe to operate with general participants because it is adapted to the very low power. However, radiation level is reasonably high to detect and shield for practice. KHU has a Regional Radiation Monitoring Post where environmental radiation level at Suwon city is continuously measured. In this facility, radiation level at soil, rain, and local agricultural products were measured and reported to the national monitoring headquarter. A new mission of reactor research and education center of KHU has been tried from last summer. Facilities were opened for high school students and teachers for their science camps during summer and winter. A special public acceptance program named as experience camp for understanding the nuclear power and radiation was held 6 times for the last one-year period. Even though number of attendee was limited and small, feedback from participants was hot and positive enough to make professors be ready to sacrifice their personal time.

  14. Reactor-produced radionuclides at the University of Missouri Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ketring, A.R.; Evans-Blumer, M.S.; Ehrhardt, G.J. [University of Missouri Research Reactor, Colombia (United States). Departments of Radiology, Chemistry and Nuclear Engineering

    1997-10-01

    Nuclear medicine has primarily been a diagnostic science for many years, but today is facing considerable challenges from other modalities in this area. However, these competing techniques (magnetic resonance imaging, ultrasound, and computer-assisted tomography) in general are not therapeutic. Although early nuclear medicine therapy was of limited efficacy, in recent years a revolution in radiotherapy has been developing base don more sophisticated targeting methods, including radioactive intra-arterial microspheres, chemically-guided bone agents, labelled monoclonal antibodies, and isotopically-tagged polypeptide receptor-binding agents. Although primarily used for malignancies, therapeutic nuclear medicine is also applicable to the treatment of rheumatoid arthritis and possibly coronary artery re closure following angioplasty. The isotopes of choice for these applications are reactor-produced beta emitters such as Sm-153, Re-186, Re-188, Ho-166, Lu-177, and Rh-105. Although alpha emitters possess greater cell toxicity due to their high LET, the greater range of beta emitters and the typically inhomogeneous deposition of radiotherapy agents in lesions leads to greater beta `crossfire` and better overall results. The University of Missouri Research Reactor (MURR) has been in the forefront of research into means of preparing, handling and supplying these high-specific-activity isotopes in quantities appropriate not only for research, but also for patient trials in the US and around the world. Researchers at MURR in collaboration with others at the University of Missouri (MU) developed Sm-153 Quadramet{sup TM}, a drug recently approved in the US for palliation of bone tumor pain. In conjunction with researchers at the University of Missouri-Rolla, MURR also developed Y-90 TheraSphere{sup TM}, an agent for the treatment of liver cancer now approved in Canada. Considerable effort has been expended to develop techniques for irradiation, handling, and shipping isotopes

  15. Reactor-produced radionuclides at the University of Missouri Research Reactor

    International Nuclear Information System (INIS)

    Ketring, A.R.; Evans-Blumer, M.S.; Ehrhardt, G.J.

    1997-01-01

    Nuclear medicine has primarily been a diagnostic science for many years, but today is facing considerable challenges from other modalities in this area. However, these competing techniques (magnetic resonance imaging, ultrasound, and computer-assisted tomography) in general are not therapeutic. Although early nuclear medicine therapy was of limited efficacy, in recent years a revolution in radiotherapy has been developing base don more sophisticated targeting methods, including radioactive intra-arterial microspheres, chemically-guided bone agents, labelled monoclonal antibodies, and isotopically-tagged polypeptide receptor-binding agents. Although primarily used for malignancies, therapeutic nuclear medicine is also applicable to the treatment of rheumatoid arthritis and possibly coronary artery re closure following angioplasty. The isotopes of choice for these applications are reactor-produced beta emitters such as Sm-153, Re-186, Re-188, Ho-166, Lu-177, and Rh-105. Although alpha emitters possess greater cell toxicity due to their high LET, the greater range of beta emitters and the typically inhomogeneous deposition of radiotherapy agents in lesions leads to greater beta 'crossfire' and better overall results. The University of Missouri Research Reactor (MURR) has been in the forefront of research into means of preparing, handling and supplying these high-specific-activity isotopes in quantities appropriate not only for research, but also for patient trials in the US and around the world. Researchers at MURR in collaboration with others at the University of Missouri (MU) developed Sm-153 Quadramet TM , a drug recently approved in the US for palliation of bone tumor pain. In conjunction with researchers at the University of Missouri-Rolla, MURR also developed Y-90 TheraSphere TM , an agent for the treatment of liver cancer now approved in Canada. Considerable effort has been expended to develop techniques for irradiation, handling, and shipping isotopes

  16. University Reactor Sharing Program. Final report, September 30, 1992--September 29, 1994

    International Nuclear Information System (INIS)

    Wehring, B.W.

    1995-01-01

    Over the past 20 years, the number of nuclear reactors on university campuses in the US declined from more than 70 to less than 40. Contrary to this trend, The University of Texas at Austin constructed a new reactor facility at a cost of $5.8 million. The new reactor facility houses a new TRIGA Mark II reactor which replaces an in-ground TRIGA Mark I reactor located in a 50-year old building. The new reactor facility was constructed to strengthen the instruction and research opportunities in nuclear science and engineering for both undergraduate and graduate students at The University of Texas. On January 17, 1992, The University of Texas at Austin received a license for operation of the new reactor. Initial criticality was achieved on March 12, 1992, and full power operation, on March 25, 1992. The UT-TRIGA research reactor provides hands-on education, multidisciplinary research and unique service activities for academic, medical, industrial, and government groups. Support by the University Reactor Sharing Programs increases the availability of The University of Texas reactor facility for use by other educational institutions which do not have nuclear reactors

  17. Universities research reactor annual report 1977-78

    International Nuclear Information System (INIS)

    1978-01-01

    The report contains the following information: summaries of projects (reactor and neutron physics, radiochemistry and application of radioisotopes, activation analysis service, teaching programme, site utilisation, reactor safety committee and site documentation, URR site health and safety committee); composition of policy and technical committees, lists of users and projects, teaching and courses, publications; reports by reactor manager and reactor engineer. ((U.K.)

  18. Systems for aiding operators at university-owned research reactors in Japan

    International Nuclear Information System (INIS)

    Nishihara, H.; Kimura, Y.; Shibata, T.

    1984-01-01

    University-owned research reactors are operated for various purposes, and small disturbances may arise from various experimental facilities. Also not uniform are the technical levels of operators who range from supervised-students to reactor physicists. Considerable efforts are therefore devoted to the preventive maintainance. With these boundary conditions imposed, systems for aiding operators are designed at these research reactor facilities. (author)

  19. A new materials irradiation facility at the Kyoto university reactor

    International Nuclear Information System (INIS)

    Yoshiie, T.; Hayashi, Y.; Yanagita, S.; Xu, Q.; Satoh, Y.; Tsujimoto, H.; Kozuka, T.; Kamae, K.; Mishima, K.; Shiroya, S.; Kobayashi, K.; Utsuro, M.; Fujita, Y.

    2003-01-01

    A new materials irradiation facility with improved control capabilities has been installed at the Kyoto University Reactor (KUR). Several deficiencies of conventional fission neutron material irradiation systems have been corrected. The specimen temperature is controlled both by an electric heater and by the helium pressure in the irradiation tube without exposure to neutrons at temperatures different from the design test conditions. The neutron spectrum is varied by the irradiation position. Irradiation dose is changed by pulling the irradiation capsule up and down during irradiation. Several characteristics of the irradiation field were measured. The typical irradiation intensity is 9.4x10 12 n/cm 2 s (>0.1 MeV) and the irradiation temperature of specimens is controllable from 363 to 773 K with a precision of ±2 K

  20. Radiopharmaceuticals developed at the University of Missouri research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ketring, A.R.; Ehrhardt, G.J. [Univ. of Missouri, Columbia, MO (United States); Day, D.E. [Univ. of Missouri, Rolla, MO (United States)

    1997-12-01

    The University of Missouri Research Reactor (MURR) has put a great deal of effort in the last two decades into development of radiotherapeutic beta emitters as nuclear medicine radiotherapeutics for malignancies. This paper describes the development of two of these drugs, {sup 153}Sm ethylenediaminetetra-methylene phosphonic acid (EDTMP) (Quadramet{trademark}) and {sup 90}Y glass microspheres (TheraSphere{trademark}). Samarium-153 EDTMP is a palliative used to treat the pain of metastatic bone cancer without the side effects of narcotic pain killers. Yttrium-90 glass microspheres are delivered via hepatic artery catheter to embolize the capillaries of liver tumors and deliver a large radiation dose for symptom palliation and life prolonging purposes.

  1. Gas-cooled reactor application for a university campus

    International Nuclear Information System (INIS)

    Colak, Ue.; Kadiroghlu, O.K.; Soekmen, C.N.; Schmitt, H.

    1991-01-01

    Large urban areas with unfavourable topographic and meteorological conditions suffer severe air pollution during the winter months. Use of low grade lignites, imported higher quality coal or imported fuel oil are the sources of air pollution in the form of sulphur dioxide, fly ash and soot. Large housing complexes or old and historical locations within the city are in need of pollution free centralized district heating systems. Natural gas imported from the Soviet Union is a solution for this problem. Lack of gas distribution network for high pressure gas within the city is the main bottle-neck for the heating systems utilizing natural gas. Concern of the safety of flammable high pressure gas circulating within the city is another drawback for the natural gas heating systems. Nuclear district heating is an environmentally viable option worth looking into it. Localized urban nuclear heating is an interesting solution for large urban areas with old and historical character. The results of a feasibility study on the HGR application for the Hacettepe University presented here, summarizes the concept of gas-cooled heating reactors specially designed for urban centers. The inherently safe characteristics of the pebble bed heating reactor makes localized urban nuclear heating a viable alternative to other heat sources. An economical analysis of various heat sources with equal power levels is done for the Beytepe campus of Hacettepe University in Ankara. Under special boundary conditions, the price for heat generation can be much lower for nuclear heating with GHR 20 than for hard coal or fuel oil. It is also possible that if the price escalation rate for natural gas exceeds 3%, then nuclear heating with GHR can be more competitive. It is concluded that the nuclear heating of Beytepe campus with a GHR 20 is feasible and economical. (author) 3 figs., 5 refs

  2. DOE University Reactor Sharing Program. Final technical report for 1996--1997

    International Nuclear Information System (INIS)

    Chappas, W.J.; Adams, V.G.

    1998-01-01

    The Department of Energy University Reactor Sharing Program at University of Maryland, College Park (UMCP) has, once again, stimulated a broad use of the reactor and radiation facilities by undergraduate and graduate students, visitors, and professionals. Participants are exposed to topics such as nuclear engineering, radiation safety, and nuclear reactor operations. This information is presented through various means including tours, slide presentations, experiments, and discussions. Student research using the MUTR is also encouraged. In addition, the Reactor Sharing Program here at the University of Maryland does not limit itself to the confines of the TRIGA reactor facility. Incorporated in the program are the Maryland University Radiation Effects Laboratory, and the UMCP 2 x 4 Thermal Hydraulic Loop. These facilities enhance and give an added dimension to the tours and experiments. The Maryland University Training Reactor (MUTR) and the associated laboratories are made available to any interested institution six days a week on a scheduled basis. Most institutions are scheduled at the time of their first request--a reflection of their commitment to the Reactor Sharing Program. The success of the past years by no means guarantees future success. Therefore, the reactor staff is more aggressively pursuing its outreach program, especially with junior colleges and universities without reactor or radiation facilities; more aggressively developing demonstration and training programs for students interested in careers in nuclear power and radiation technology; and more aggressively up-grading the reactor facilities--not only to provide a better training facility but to prepare for relicensing in the year 2000

  3. Teaching and training applications of the Oregon State University Triga Reactor

    International Nuclear Information System (INIS)

    Dodd, B.

    1990-01-01

    This paper summarizes the recent use of the Oregon State University TRIGA Reactor (OSTR) for teaching and training. In particular, data spanning the last five years are presented which cover teaching through formal university classes, theses, public information, and school programs. Training is covered by presenting data on domestic and foreign reactor operator training, health physics training, and neutron activation analysis training

  4. Requalification of SPERT [Special Power Excursion Reactor Test] pins for use in university reactors

    International Nuclear Information System (INIS)

    Snelgrove, J.L.; Domagala, R.F.; Dates, L.R.

    1986-12-01

    A series of nondestructive and destructive examinations have been performed on a representative sample of stainless steel-clad UO 2 fuel pins procured in the early-to-mid 1960s for the SPERT program. These examinations were undertaken in order to requalify the SPERT pins for use in converting university research reactors from the use of highly enriched uranium to the use of low-enriched uranium. The requalification program included visual and dimensional inspections of fuel pins and fuel pellets, radiographic inspections of welds, fill gas analyses, and chemical and spectrographic analyses of fuel and cladding materials. In general all attributes tested were within or very close to specified values, although some weld defects not covered by the original specifications were found. 1 ref., 4 figs., 11 tabs

  5. University of Michigan workscope for 1991 DOE University program in robotics for advanced reactors

    International Nuclear Information System (INIS)

    Wehe, D.K.

    1990-01-01

    The University of Michigan (UM) is a member of a team of researchers, including the universities of Florida, Texas, and Tennessee, along with Oak Ridge National Laboratory, developing robotic for hazardous environments. The goal of this research is to develop the intelligent and capable robots which can perform useful functions in the new generation of nuclear reactors currently under development. By augmenting human capabilities through remote robotics, increased safety, functionality, and reliability can be achieved. In accordance with the established lines of research responsibilities, our primary efforts during 1991 will continue to focus on the following areas: radiation imaging; mobile robot navigation; three-dimensional vision capabilities for navigation; and machine-intelligence. This report discuss work that has been and will be done in these areas

  6. Some experiences of upgrading research reactor performance for effective utilization in Kyoto University

    International Nuclear Information System (INIS)

    Shiroya, Seiji

    2006-01-01

    In Kyoto University Research Reactor Institute (KURRI), the heavy water facility of the Kyoto University research Reactor (KUR) was remodeled in order to upgrade the performance of Neutron Capture Therapy (NCT) in the fiscal year 1995. A new materials irradiation facility was installed in the KUR during fiscal year 1996-1998. These facilities have been used effectively to promote the joint use program among Japanese universities. (author)

  7. Conversion and standardization of US university reactor fuels using LEU, status 1989

    International Nuclear Information System (INIS)

    Brown, K.R.; Matos, J.E.

    1989-01-01

    In 1986, the US Department of Energy initiated a program to change the fuel used in most of the US university research reactors using HEU (93%) to LEU(<20%) in order to minimize the risk of theft or diversion of this weapons-useable material. An important consideration in the LEU conversion planning process has been the desire to standardize the fuels that are used and to enhance the performance and utilization of the reactors. This paper describes the current status of this conversion process and the plans and schedules to complete an orderly transition from HEU to LEU fuel in most of these reactors. To date, three university reactors have been converted to LEU fuel, completed safety documentation for three reactors is being evaluated by the USNRC, and work on the safety documentation for six reactors is in progress. 13 refs., 9 tabs

  8. Transmission issues in Alberta

    International Nuclear Information System (INIS)

    Levson, D.

    2002-01-01

    This paper outlined the major issues and concerns facing users of the transmission system in Alberta. They include congestion management issues that make investors uncertain about power generation. It is necessary to know the difference between which transmission price signals will be faced by low cost cogeneration at Fort McMurray and Cold Lake coal-fired generation near Edmonton compared to combined cycle gas generation near Calgary. Import and export policy tariffs are another concern. Most new generation opportunities in Alberta require access to export markets, but transmission facilities for export need policy support and appropriate tariffs. It was noted that the past actions of Alberta's Transmission Administrator and balancing pool may be distorting market signals for ancillary service markets, and that loss studies and calculations need upgrading

  9. Final report. U.S. Department of Energy University Reactor Sharing Program

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, John A

    2003-01-21

    Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants.

  10. University of Wisconsin, Nuclear Reactor Laboratory. Annual report, 1985-1986

    International Nuclear Information System (INIS)

    Cashwell, R.J.

    1986-01-01

    Operational activities for the reactor are described concerning nuclear engineering classes from the University of Wisconsin; reactor sharing program; utility personnel training; sample irradiations and neutron activation analysis; and changes in personnel, facility, and procedures. Results of surveillance tests are presented for operating statistics and fuel exposure; emergency shutdowns and inadvertent scrams; maintenance; radioactive waste disposal; radiation exposures; environmental surveys; and publications and presentations on work based on reactor use

  11. The little reactor that can, the bigger reactor that may be

    International Nuclear Information System (INIS)

    Duffy, J.Q.

    1981-01-01

    The Slowpoke-2 research reactor and its marketing are featured, with an account of an interview with Dr. John Hilborn, designer. Also discussed is a scaled-up 2 MW version for space heating or small-scale district heating. The new version will rely on natural convection and inherent safety like Slowpoke, but will differ from it in many ways. The core will contain 200 kg of fuel elements with 5 percent enrichment. The new reactor lacks an upper beryllium reflector. Control will be by moving an annular beryllium reflector up and down. Inherent safety will be achieved through diminution of reactivity resulting from the onset of boiling. The article also mentions projected or actual use of small reactors for heating in the U.S.S.R. and France

  12. Survey of research reactors

    International Nuclear Information System (INIS)

    Boek, H.; Villa, M.

    2004-06-01

    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)

  13. Pennsylvania State University Breazeale Nuclear Reactor. Thirtieth annual progress report, July 1, 1984-June 30, 1985

    International Nuclear Information System (INIS)

    Levine, S.H.; Totenbier, R.E.

    1985-08-01

    This report is the thirtieth annual progress report of the Pennsylvania State University Breazeale Nuclear Reactor and covers such topics as: personnel; reactor facility; cobalt-60 facility; education and training; Radionuclear Application Laboratory; Low Level Radiation Monitoring Laboratory; and facility research utilization

  14. Management of radioactive liquid and solid wastes at the Research Reactor Institute, Kyoto University, (3)

    International Nuclear Information System (INIS)

    Tsutsui, Tenson; Shimoura, K.; Koyama, A.

    1977-11-01

    In this report, the management of radioactive liquid and solid wastes at the Research Reactor Institute, Kyoto University during past 6 years, from April in 1971 to March in 1977 are reviewed. (auth.)

  15. Alberta Essay Scales: Models.

    Science.gov (United States)

    Nyberg, Verner R.; Nyberg, Adell M.

    The Alberta Essay Scales were developed to assist teachers in the grading of essays. They represent a standard based on written compositions at the 12th grade level in 1964 to be compared with current composition writing achievement. A scale for mechanics in English and one for writing style and content are defined through model essays and…

  16. Conversion and standardization of university reactor fuels using low-enrichment uranium: Plans and schedules

    International Nuclear Information System (INIS)

    Young, H.H.; Brown, K.R.; Matos, J.E.

    1986-01-01

    The highly-enriched uranium (HEU) fuel used in twenty United States university reactors can be viewed as contributing to the risk of theft or diversion of weapons-useable material. To minimize this risk, the US Nuclear Regulatory Commission issued its final rule on ''Limiting the Use of Highly Enriched Uranium in Domestically Licensed Research and Test Reactors,'' in February 1986. This paper describes the plans and schedules developed by the US Department of Energy to coordinate an orderly transition from HEU to LEU fuel in most of these reactors. An important element in the planning process has been the desire to standardize the LEU fuels used in US university reactors and to enhance the performance and utilization of a number of these reactors. The program is estimated to cost about $10 million and to last about five years

  17. Final report for U.S. Department of Energy Grant DE-FG02-95NE38118-5 University Reactor Sharing Program [Purdue University

    Energy Technology Data Exchange (ETDEWEB)

    Bean, R.S.

    2001-06-01

    Under the Reactor Sharing Program, a total of 350 high school students participated in the neutron activation experiment and 484 high school and university students and members of the general public participated in reactor tours.

  18. Research reactor usage at the Idaho National Engineering Laboratory in support of university research and education

    International Nuclear Information System (INIS)

    Woodall, D.M.; Dolan, T.J.; Stephens, A.G.

    1990-01-01

    The Idaho National Engineering Laboratory is a US Department of Energy laboratory which has a substantial history of research and development in nuclear reactor technologies. There are a number of available nuclear reactor facilities which have been incorporated into the research and training needs of university nuclear engineering programs. This paper addresses the utilization of the Advanced Reactivity Measurement Facility (ARMF) and the Coupled Fast Reactivity Measurement Facility (CFRMF) for thesis and dissertation research in the PhD program in Nuclear Science and Engineering by the University of Idaho and Idaho State University. Other reactors at the INEL are also being used by various members of the academic community for thesis and dissertation research, as well as for research to advance the state of knowledge in innovative nuclear technologies, with the EBR-II facility playing an essential role in liquid metal breeder reactor research. 3 refs

  19. Small reactor operating mode

    International Nuclear Information System (INIS)

    Snell, V.G.

    1997-01-01

    There is a potential need for small reactors in the future for applications such as district heating, electricity production at remote sites, and desalination. Nuclear power can provide these at low cost and with insignificant pollution. The economies required by the small scale application, and/or the remote location, require a review of the size and location of the operating staff. Current concepts range all the way from reactors which are fully automatic, and need no local attention for days or weeks, to those with reduced local staff. In general the less dependent a reactor is on local human intervention, the greater its dependence on intrinsic safety features such as passive decay heat removal, low-stored energy and limited reactivity speed and depth in the control systems. A case study of the design and licensing of the SLOWPOKE Energy System heating reactor is presented. (author)

  20. Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia

    International Nuclear Information System (INIS)

    Chiesa, Davide; Clemenza, Massimiliano; Pozzi, Stefano; Previtali, Ezio; Sisti, Monica; Alloni, Daniele; Magrotti, Giovanni; Manera, Sergio; Prata, Michele; Salvini, Andrea; Cammi, Antonio; Zanetti, Matteo; Sartori, Alberto

    2016-01-01

    Highlights: • A fuel evolution model for a TRIGA Mark II reactor has been developed. • Reproduction of nearly 50 years of reactor operation. • The model was used to predict the best reactor reconfiguration. • Reactor life was extended without adding fresh fuel elements. - Abstract: A time evolution model was developed to study fuel burnup for the TRIGA Mark II reactor at the University of Pavia. The results were used to predict the effects of a complete core reconfiguration and the accuracy of this prediction was tested experimentally. We used the Monte Carlo code MCNP5 to reproduce system neutronics in different operating conditions and to analyze neutron fluxes in the reactor core. The software that took care of time evolution, completely designed in-house, used the neutron fluxes obtained by MCNP5 to evaluate fuel consumption. This software was developed specifically to keep into account some features that differentiate low power experimental reactors from those used for power production, such as the daily ON/OFF cycle and the long fuel lifetime. These effects can not be neglected to properly account for neutron poison accumulation. We evaluated the effect of 48 years of reactor operation and predicted a possible new configuration for the reactor core: the objective was to remove some of the fuel elements from the core and to obtain a substantial increase in the Core Excess reactivity value. The evaluation of fuel burnup and the reconfiguration results are presented in this paper.

  1. Whither Alberta's oil production?

    International Nuclear Information System (INIS)

    Purvis, R.A.; Dick, A.B.

    1991-01-01

    It is demonstrated how a combination of old theory (decline methods and statistics) and new technology (computer graphics) can enhance decline-curve forecasts for multi-well groupings. Production and well-count forecasts are presented for four different sized groups of aggregate production. The four examples are: the small Manville pool; the Pembina Cardium, Alberta's largest oil pool; an aggregate of all reef pools of Keg River age; and an aggregate of all wells reporting conventional oil production in the province of Alberta. In each case graphical results show the historical and forecast trends for the statistical distribution of well rates, the median well rate, the aggregated rate, and the number of producing wells. It is concluded that well rate distributions for groups ranging from 15 wells in a single pool to thousands of wells in hundreds of pools are all approximately lognormal. Lognormal well rate distributions and Lorenz graphs provide qualitative and quantitative assessments of a resource base. Decline curves for the median well rate can reveal trends masked in the aggregated rate by changing well count, operating practice and degradation of the resource base. The number of producing wells in Alberta has grown from ca 9000 in 1970 to ca 24,000 in 1988, has remained constant from 1988-1990, and will start to decline as the number of suspended or abandoned wells exceeds the number of new completions. 3 refs., 13 figs., 4 figs

  2. Alberta propylene upgrading prospects

    International Nuclear Information System (INIS)

    2000-03-01

    A very significant byproduct recovery and purification scheme is at present being prepared by TransCanada Midstream (TCMS). Alberta Economic Development commissioned an independent study to identify propylene supply options while proceeding with the evaluation of various propylene derivatives with regard to their fit with the Alberta context. Identification of chemical companies with derivative interests was also accomplished. By 2005, it is estimated that 280 kilo-tonnes of propylene will be available on an annual basis from byproduct sources. Those sources are oil sands upgraders, ethylene plants and refineries. The ranges of impurities and supply costs vary between the different sources. An option being considered involves pipeline and rail receipt with a major central treating and distillation facility for the production of polymer grade (PG) propylene with propane and other smaller byproducts. Special consideration was given to three chemicals in this study, namely: polypropylene (PP), acrylonitrile (ACN), and acrylic acid (AA). Above average growth rates were identified for these chemicals: demand is growing at 6 to 7 per cent a year for both PP and ACN, while demand for AA grows at 8 per cent annually. Two other possibilities were identified, propylene oxide (PO) and phenol. The study led to the conclusion that low capital and operating costs and shipping costs to the Pacific Rim represent advantages to the development of propylene derivatives in the future in Alberta. 4 refs., 87 tabs., 7 figs

  3. Monte Carlo Analysis of the Accelerator-Driven System at Kyoto University Research Reactor Institute

    Directory of Open Access Journals (Sweden)

    Wonkyeong Kim

    2016-04-01

    Full Text Available An accelerator-driven system consists of a subcritical reactor and a controllable external neutron source. The reactor in an accelerator-driven system can sustain fission reactions in a subcritical state using an external neutron source, which is an intrinsic safety feature of the system. The system can provide efficient transmutations of nuclear wastes such as minor actinides and long-lived fission products and generate electricity. Recently at Kyoto University Research Reactor Institute (KURRI; Kyoto, Japan, a series of reactor physics experiments was conducted with the Kyoto University Critical Assembly and a Cockcroft–Walton type accelerator, which generates the external neutron source by deuterium–tritium reactions. In this paper, neutronic analyses of a series of experiments have been re-estimated by using the latest Monte Carlo code and nuclear data libraries. This feasibility study is presented through the comparison of Monte Carlo simulation results with measurements.

  4. A human reliability analysis of the University of New Mexico's AGN- 201M nuclear research reactor

    International Nuclear Information System (INIS)

    Brumburgh, G.P.; Heger, A.S.

    1992-01-01

    During 1990--1991, a probabilistic risk assessment was conducted on the University of New Mexico's AGN-201M nuclear research reactor to address the risk and consequence of a maximum hypothetical release accident. The assessment indicated a potential for consequential human error to precipitate Chis scenario. Subsequently, a human reliability analysis was performed to evaluate the significance of human interaction on the reactor's safety systems. This paper presents the results of that investigation

  5. Education and training activities at North Carolina State University's PULSTAR reactor

    International Nuclear Information System (INIS)

    Mayo, C.W.

    1992-01-01

    Research reactor utilization has been an integral part of the North Carolina State University's (NCSU's) nuclear engineering program since its inception. The undergraduate curriculum has a strong teaching laboratory component. Graduate classes use the reactor for selected demonstrations, experiments, and projects. The reactor is also used for commercial power reactor operator training programs, neutron radiography, neutron activation analysis (NAA), and sample and tracer activation for industrial short courses and services as part of the university's land grant mission. The PULSTAR reactor is a 1-MW pool-type reactor that uses 4% enriched UO 2 pellet fuel in Zircaloy II cladding. Standard irradiation facilities include wet exposure ports, a graphite thermal column, and a pneumatic transfer system. In the near term, general facility upgrades include the installation of signal isolation and computer data acquisition and display functions to improve the teaching and research interface with the reactor. In the longer term, the authors foresee studies of new core designs and the development of beam experiment design tools. These would be used to study modifications that may be desired at the end of the current core life and to undertake the development of new research instruments

  6. University Reactor Instrumentation Program. Final report, September 30, 1993--March 31, 1996

    International Nuclear Information System (INIS)

    1997-01-01

    The University of Massachusetts Lowell Research Reactor has received a total of $115,723.00 from the Department of Energy (DOE) Instrumentation Program (DOE Grant No. DE-FG02-91ID13083) and $40,000 in matching funds from the University of Massachusetts Lowell administration. The University of Massachusetts Lowell Research Reactor has been serving the University and surrounding communities since it first achieved criticality in May 1974. The principle purpose of the facility is to provide a multidisciplinary research and training center for the University of Massachusetts Lowell and other New England academic institutions. The facility promotes student and industrial research, in addition to providing education and training for nuclear scientists, technicians, and engineers. The 1 MW thermal reactor contains a variety of experimental facilities which, along with a 0.4 megacurie cobalt source, effectively supports the research and educational programs of many university departments including Biology, Chemistry, Nuclear and Plastics Engineering, Radiological Sciences, Physics, and other campuses of the University of Massachusetts system. Although the main focus of the facility is on intra-university research, use by those outside the university is fully welcomed and highly encouraged

  7. Decommissioning Small Research and Training Reactors; Experience on Three Recent University Projects - 12455

    Energy Technology Data Exchange (ETDEWEB)

    Gilmore, Thomas [LVI Services Inc. (United States); DeWitt, Corey; Miller, Dustin; Colborn, Kurt [Enercon Services, Inc. (United States)

    2012-07-01

    Decommissioning small reactors within the confines of an active University environment presents unique challenges. These range from the radiological protection of the nearby University population and grounds, to the logistical challenges of working in limited space without benefit of the established controlled, protected, and vital areas common to commercial facilities. These challenges, and others, are discussed in brief project histories of three recent (calendar year 2011) decommissioning activities at three University training and research reactors. These facilities include three separate Universities in three states. The work at each of the facilities addresses multiple phases of the decommissioning process, from initial characterization and pre-decommissioning waste removal, to core component removal and safe storage, through to complete structural dismantlement and site release. The results of the efforts at each University are presented, along with the challenges that were either anticipated or discovered during the decommissioning efforts, and results and lessons learned from each of the projects. (authors)

  8. Broad scope educational role of a midsize university reactor NAA laboratory

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    2000-01-01

    Broad scope educational activities at the Neutron Activation Analysis Laboratory (NAAL) associated with the 100 kW University of Florida Training Reactor (UFTR) have been implemented to serve a deserve and multidisciplinary academic clientele to meet a wide spectrum of educational needs for students at all academic levels. Educational usage of the complementary laboratory facilities is described and the importance of such academic experimental experience is emphasized for developing and maintaining a cadre of professionals in the analytical applications of nuclear energy. The synergistic operation of the NAAL and the reactor at the University of Florida to serve as a model worthy of emulation for other similar facilities is emphasized. (author)

  9. Utilization of the Cornell University research reactors in support of the Nuclear Power Industry

    International Nuclear Information System (INIS)

    Aderhold, A.C.

    1993-01-01

    Cornell University is licensed to operate two research reactor facilities on its main campus in Ithaca, New York: a 500-kW pulsing TRIGA and a 100-W zero-power reactor (ZPR). The initial criticality of both reactors took place in 1962, and the utilization of each has been, and continues to be, dedicated to the teaching and research programs of Cornell's many academic departments. As the nation's nuclear power industry grew, the demand for services at research and test reactors increased. As a result, and in large part because of special design features of the TRIGA, Cornell responded to a few requests for reactor testing services while maintaining the policy that these services would not interfere with teaching and research programs. The frequency of service requests suddenly mushroomed in November of 1989, when the nation's major testing reactor was shut down for repairs. In spite of a small staff of two full-time reactor operators, a decision was made to support the nuclear industry to the fullest extent possible without jeopardizing Cornell's teaching and research programs. This turned into a monumental task of tight scheduling and meeting precise deadlines. It could only be accomplished by working late evenings and weekends and, on a number of occasions, staying at the facility for up to 5 days continuously

  10. New research facilities at the University of Missouri research reactor

    International Nuclear Information System (INIS)

    McKibben, J.C.; Rhyne, J.J.

    1992-01-01

    The University of Missouri-Columbia is investing its resources for a significant expansion of the research capabilities and utilization of MURR to provide it the opportunity to deliver on its obligation to become the nation's premier educational institution in nuclear-related fields and so that it can provide scientific personnel and a state-of-the-art research test bed to support the national need for highly trained graduates in nuclear science and engineering

  11. DOE/NE University Program in robotics for advanced reactors

    International Nuclear Information System (INIS)

    Sweeney, F.J.; Gonzalez, R.C.; Trivedi, M.M.; Wehe, D.K.

    1990-05-01

    The US Department of Energy has provided support to four universities and the Oak Ridge National Laboratory in order to pursue research leading to the development and deployment of advanced robotic systems capable of performing tasks that are hazardous to humans, that generate significant occupational radiation exposure, and/or whose execution times can be reduced if performed by an automated system. The goal is to develop a generation of advanced robotic systems capable of economically performing surveillance, maintenance, and repair tasks in nuclear facilities and other hazardous environments. The approach to achieving the program objective is a transition from teleoperation to the capability of autonomous operation within three successive generations of robotic systems. The strategy adopted in order to achieve the program goals in an efficient and timely manner consists in utilizing, and advancing where required, state-of-the-art robotics technology through close interaction between the universities and the manufacturers and operators of nuclear power plants. There is a potentially broad range of applications for the robotic systems developed in the course of this project. Therefore, it is expected that efforts to obtain additional support from other agencies, e.g., DOD and NASA, will be successful. Areas of cooperation with other nations (e.g., Japan, France, Germany) are being explored. This Program features a unique teaming arrangement among the Universities of Florida, Michigan, Tennessee, Texas, and the Oak Ridge National Laboratory, and their industrial partners, Odetics, Gulf State Utilities, Florida Power and Light Company, Remotec, and Telerobotics International

  12. An ultracold neutron source at the NC State University PULSTAR reactor

    Science.gov (United States)

    Korobkina, E.; Wehring, B. W.; Hawari, A. I.; Young, A. R.; Huffman, P. R.; Golub, R.; Xu, Y.; Palmquist, G.

    2007-08-01

    Research and development is being completed for an ultracold neutron (UCN) source to be installed at the PULSTAR reactor on the campus of North Carolina State University (NCSU). The objective is to establish a university-based UCN facility with sufficient UCN intensity to allow world-class fundamental and applied research with UCN. To maximize the UCN yield, a solid ortho-D 2 converter will be implemented coupled to two moderators, D 2O at room temperature, to thermalize reactor neutrons, and solid CH 4, to moderate the thermal neutrons to cold-neutron energies. The source assembly will be located in a tank of D 2O in the space previously occupied by the thermal column of the PULSTAR reactor. Neutrons leaving a bare face of the reactor core enter the D 2O tank through a 45×45 cm cross-sectional area void between the reactor core and the D 2O tank. Liquid He will cool the disk-shaped UCN converter to below 5 K. Independently, He gas will cool the cup-shaped CH 4 cold-neutron moderator to an optimum temperature between 20 and 40 K. The UCN will be transported from the converter to experiments by a guide with an inside diameter of 16 cm. Research areas being considered for the PULSTAR UCN source include time-reversal violation in neutron beta decay, neutron lifetime determination, support measurements for a neutron electric-dipole-moment search, and nanoscience applications.

  13. Radioisotope research, production, and processing at the University of Missouri Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ehrhardt, G.J.; Ketring, A.R.; Ja, Wei; Ma, D.; Zinn, K.; Lanigan, J.

    1995-12-31

    The University of Missouri Research Reactor (MURR) is a 10 MW, light-water-cooled and moderated research reactor which first achieved criticality in 1996 and is currently the highest powered university-owned research reactor in the U.S. For many years a major supplier of reactor-produced isotopes for research and commercial purposes, in the last 15 years MURR has concentrated on development of reactor-produced beta-particle emitters for experimental use in nuclear medicine therapy of cancer and rheumatoid arthritis. MURR has played a major role in the development of bone cancer pain palliation with the agents {sup 153}Sm EDTMP and {sup 186}Re/{sup 188}Re HEDP, as well as in the use of {sup 186}Re, {sup 177}Lu, {sup 166}Ho, and {sup 105}Rh for radioimmunotherapy and receptor-agent-guided radiotherapy. MURR is also responsible for the development of therapeutic, {sup 90}Y-labeled glass microspheres for the treatment of liver tumors, a product ({sup 90}Y Therasphere{trademark}) which is currently an approved drug in Canada. MURR has also pioneered the development of {sup 188}W/{sup 188}Re and {sup 99}Mo/{sup 99m}Tc gel generators, which make the use of low specific activity {sup 188}W and {sup 99}Mo practical for such isotope generators.

  14. Radioisotope research, production, and processing at the University of Missouri Research Reactor

    International Nuclear Information System (INIS)

    Ehrhardt, G.J.; Ketring, A.R.; Ja, Wei; Ma, D.; Zinn, K.; Lanigan, J.

    1995-01-01

    The University of Missouri Research Reactor (MURR) is a 10 MW, light-water-cooled and moderated research reactor which first achieved criticality in 1996 and is currently the highest powered university-owned research reactor in the U.S. For many years a major supplier of reactor-produced isotopes for research and commercial purposes, in the last 15 years MURR has concentrated on development of reactor-produced beta-particle emitters for experimental use in nuclear medicine therapy of cancer and rheumatoid arthritis. MURR has played a major role in the development of bone cancer pain palliation with the agents 153 Sm EDTMP and 186 Re/ 188 Re HEDP, as well as in the use of 186 Re, 177 Lu, 166 Ho, and 105 Rh for radioimmunotherapy and receptor-agent-guided radiotherapy. MURR is also responsible for the development of therapeutic, 90 Y-labeled glass microspheres for the treatment of liver tumors, a product ( 90 Y Therasphere trademark) which is currently an approved drug in Canada. MURR has also pioneered the development of 188 W/ 188 Re and 99 Mo/ 99m Tc gel generators, which make the use of low specific activity 188 W and 99 Mo practical for such isotope generators

  15. Operational experience with the TRIGA reactor of the University of Pavia

    International Nuclear Information System (INIS)

    Borio di Tigliole, A.; Alloni, D.; Cagnazzo, M.; Coniglio, M.; Lana, F.; Losi, A.; Magrotti, G.; Manera, S.; Marchetti, F.; Pappalardo, P.; Prata, M.; Salvini, A.; Scian, G.; Vinciguerra, G.

    2008-01-01

    The TRIGA Mark II research reactor of the University of Pavia is in operation since 1965. The annual operational time at nominal power (250 kW) is in the range of 300 - 400 hours depending upon the time schedule of some experiments and research activities. The reactor is mainly used for NAA activities and BNCT research. Few tens of hours per year are dedicated also to electronic devices irradiation and student training courses. Few homemade upgrading of the reactor were realized in the past two years: components of the secondary/tertiary cooling circuit were substituted and a new radiation area monitoring system was installed. Also the Instrumentation and Control (I and C) system was almost completely refurbished. The presentation describes the major extraordinary maintenance activities implemented and the status of main reactor systems: - The I and C System: complete substitution, channel-by-channel without changing the operating and safety logics; - Tertiary and secondary water-cooling circuits: complete substitution of the tertiary water-cooling circuit and partial substitution of the components of the secondary water-cooling circuit; - Reactor Building Air Filtering and Ventilation System: installation of a computerized air filtering and ventilation system; - Radiation Area Monitoring System: new system based on a commercial micro-computer and an home-made software developed on Lab-View platform. The system is made of a network of different instruments coupled, trough a serial bus line RS232, with a data acquisition station; - Fuel Elements: at the moment, the core is made of 48 Aluminium clad and 34 SST clad TRIGA fuel elements controlled periodically for their elongation and/or bowing. All components and systems undergo ordinary maintenance according to the Technical Prescriptions and to the 'Good Practice Procedures'. In summary, the TRIGA reactor of the University of Pavia shows a very good technical state and, at the moment, there are no political or

  16. Modern design and safety analysis of the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    Jordan, K.A.; Springfels, D.; Schubring, D.

    2015-01-01

    Highlights: • A new safety analysis of the University of Florida Training Reactor is presented. • This analysis uses modern codes and replaces the NRC approved analysis from 1982. • Reduction in engineering margin confirms that the UFTR is a negligible risk reactor. • Safety systems are not required to ensure that safety limits are not breached. • Negligible risk reactors are ideal for testing digital I&C equipment. - Abstract: A comprehensive series of neutronics and thermal hydraulics analyses were conducted to demonstrate the University of Florida Training Reactor (UFTR), an ARGONAUT type research reactor, as a negligible risk reactor that does not require safety-related systems or components to prevent breach of a safety limit. These analyses show that there is no credible UFTR accident that would result in major fuel damage or risk to public health and safety. The analysis was based on two limiting scenarios, whose extremity bound all other accidents of consequence: (1) the large step insertion of positive reactivity and (2) the release of fission products due to mechanical damage to a spent fuel plate. The maximum step insertion of positive reactivity was modeled using PARET/ANL software and shows a maximum peak fuel temperature of 283.2 °C, which is significantly below the failure limit of 530 °C. The exposure to the staff and general public was calculated for the worst-case fission product release scenario using the ORIGEN-S and COMPLY codes and was shown to be 6.5% of the annual limit. Impacts on reactor operations and an Instrumentation & Control System (I&C) upgrade are discussed

  17. Research Reactor Utilization at the University of Utah for Nuclear Education, Training and Services

    International Nuclear Information System (INIS)

    Jevremovic, T.; Choe, D.O.

    2013-01-01

    In the years of nuclear renaissance we all recognize a need for modernizing the approaches in fostering nuclear engineering and science knowledge, in strengthening disciplinary depth in students’ education for their preparation for workforce, and in helping them learn how to extend range of skills, develop habits of mind and subject matter knowledge. The education infrastructure at the University of Utah has been recently revised to incorporate the experiential learning using our research reactor as integral part of curriculum, helping therefore that all of our students build sufficient level of nuclear engineering literacy in order to be able to contribute productively to nuclear engineering work force or continue their education toward doctoral degrees. The University of Utah TRIGA Reactor built 35 years ago represents a university wide facility to promote research, education and training, as well as is used for various applications of nuclear engineering, radiation science and health physics. Our curriculum includes two consecutive classes for preparation of our students for research reactor operating license. Every year the US Nuclear Regulatory Commission’s representatives hold the final exam for our students. Our activities serve the academic community of the University of Utah, commercial and government entities, other universities and national laboratories as well. (author)

  18. Innovations and Enhancements for a Consortium of Big-10 University Research and Training Reactors. Final Report

    International Nuclear Information System (INIS)

    Brenizer, Jack

    2011-01-01

    The Consortium of Big-10 University Research and Training Reactors was by design a strategic partnership of seven leading institutions. We received the support of both our industry and DOE laboratory partners. Investments in reactor, laboratory and program infrastructure, allowed us to lead the national effort to expand and improve the education of engineers in nuclear science and engineering, to provide outreach and education to pre-college educators and students and to become a key resource of ideas and trained personnel for our U.S. industrial and DOE laboratory collaborators.

  19. Safety Evaluation Report related to the renewal of the operating license for the research reactor at Pennsylvania State University

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Evaluation Report for the application filed by the Pennsylvania State University for a renewal of Operating License R-2 to continue to operate the Pennsylvania State University Breazeale Reactor (PSBR) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the campus in University Park, Pennsylvania. On the basis of its technical review, the staff concludes that the reactor facility can continue to be operated by the university without endangering the health and safety of the public or the environment

  20. Small reactors for low-temperature heating

    International Nuclear Information System (INIS)

    Hilborn, J.W.; Glen, J.S.

    For regions which do not have abundant long term supplies of oil, gas, or electricity, small nuclear reactors for heating large buildings are a future energy option. In Canada, the first installations might be in remote arctic communities where heating costs are highest. Atomic Energy of Canada Limited is studying the feasibility of small units in the range 2 to 20 MWt. Based on the inherently safe SLOWPOKE research reactor, the proposed heating reactor would produce hot water at temperatures less than 100 0 C. It would be unattended most of the time, responding automatically to daily variations in load demand. The reactor core would contain enough uranium fuel to last two heating seasons. Thermohydraulic tests have been carried out on an electrically heated tube simulating a single fuel element, and a 31-element test rig simulating the core and primary coolant circuit is under construction. Preliminary cost estimates indicate that heat from a 2MWt SLOWPOKE-type reactor compares favourably in cost with heat from electricity and imported oil, but is significantly more expensive than the corresponding energy from natural gas. If the current studies at the Chalk River Nuclear Laboratories confirm technical and economic feasibility, a 2 MWt prototype reactor will be built at Chalk River in 1984/85

  1. Self-sustainability of a research reactor facility with neutron activation analysis

    International Nuclear Information System (INIS)

    Chilian, C.; Kennedy, G.

    2010-01-01

    Long-term self-sustainability of a small reactor facility is possible because there is a large demand for non-destructive chemical analysis of bulk materials that can only be achieved with neutron activation analysis (NAA). The Ecole Polytechnique Montreal SLOWPOKE Reactor Facility has achieved self-sustainability for over twenty years, benefiting from the extreme reliability, ease of use and stable neutron flux of the SLOWPOKE reactor. The industrial clientele developed slowly over the years, mainly because of research users of the facility. A reliable NAA service with flexibility, high accuracy and fast turn-around time was achieved by developing an efficient NAA system, using a combination of the relative and k0 standardisation methods. The techniques were optimized to meet the specific needs of the client, such as low detection limit or high accuracy at high concentration. New marketing strategies are presented, which aim at a more rapid expansion. (author)

  2. University of Florida--US Department of Energy 1994-1995 reactor sharing program

    Energy Technology Data Exchange (ETDEWEB)

    Vernetson, W.G.

    1996-06-01

    The grant support of $24,250 (1994-95?) was well used by the University of Florida as host institution to support various educational institutions in the use of UFTR Reactor. All users and uses were screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research was not funded by grants for contract funding from outside sources. Over 12 years, the program has been a key catalyst for renewing utilization of UFTR both by external users around the State of Florida and the Southeast and by various faculty members within the University of Florida. Tables provide basic information about the 1994-95 program and utilization of UFTR.

  3. Ten-year utilization of the Oregon State University TRIGA Reactor (OSTR)

    International Nuclear Information System (INIS)

    Ringle, John C.; Anderson, Terrance V.; Johnson, Arthur G.

    1978-01-01

    The Oregon State University TRIGA Reactor (OSTR) has been used heavily throughout the past ten years to accommodate exclusively university research, teaching, and training efforts. Averages for the past nine years show that the OSTR use time has been as follows: 14% for academic and special training courses; 44% for OSU research projects; 6% for non-OSU research projects; 2% for demonstrations for tours; and 34% for reactor maintenance, calibrations, inspections, etc. The OSTR has operated an average of 25.4 hours per week during this nine-year period. Each year, about 20 academic courses and 30 different research projects use the OSTR. Visitors to the facility average about 1,500 per year. No commercial radiations or services have been performed at the OSTR during this period. Special operator training courses are given at the OSTR at the rate of at least one per year. (author)

  4. University of Virginia open-quotes virtualclose quotes reactor facility tours

    International Nuclear Information System (INIS)

    Krause, D.R.; Mulder, R.U.

    1995-01-01

    An electronic information and tour book has been constructed for the University of Virginia reactor (UVAR) facility. Utilizing the global Internet, the document resides on the University of Virginia World Wide Web (WWW or W) server within the UVAR Homepage at http://www.virginia. edu/∼reactor/. It is quickly accessible wherever an Internet connection exists. The UVAR Homepage files are accessed with the hypertext transfer protocol (http) prefix. The files are written in hypertext markup language (HTML), a very simple method of preparing ASCII text for W3 presentation. The HTML allows use of various hierarchies of headers, indentation, fonts, and the linking of words and/or pictures to other addresses-uniform resource locators. The linking of texts, pictures, sounds, and server addresses is known as hypermedia

  5. University of Florida--US Department of Energy 1994-1995 reactor sharing program

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1996-06-01

    The grant support of $24,250 (1994-95?) was well used by the University of Florida as host institution to support various educational institutions in the use of UFTR Reactor. All users and uses were screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research was not funded by grants for contract funding from outside sources. Over 12 years, the program has been a key catalyst for renewing utilization of UFTR both by external users around the State of Florida and the Southeast and by various faculty members within the University of Florida. Tables provide basic information about the 1994-95 program and utilization of UFTR

  6. Present status of operation and utilization of Kyoto University Reactor, KUR

    International Nuclear Information System (INIS)

    Kimura, Itsuro

    1988-01-01

    The Research Reactor Institute was established as an inter-university research institute in 1963. The main installation of the Institute is the KUR, a light water moderated, tank type reactor of 5,000 kW. In addition, a 46 MeV electron linear accelerator and a gamma ray irradiation facility with 10,000 Ci Co-60 are actively used for research. In 1974, Kyoto University Critical Assembly (KUCA) was constructed, and it has been used for research and education. The Reactor Utilization Center and the Fundamental Research Laboratory for Neutron Therapy were established in 1975 and 1976, respectively. Approximately 200 people work there, of them, some 80 do research and education, including 13 professors and 12 associate professors. All the experimental facilities of the Institute are available for the cooperative research projects of other universities and public research institutions in the fields of natural science and engineering, medical science, agriculture and forestry, fishery and stock-raising, environment science, cultural science and others. As a rule, the KUR is operated for about 70 hours from Tuesday morning to Friday evening every week. The annual examination by the government is carried out in spring. The total operation time was about 45,000 hours as of the end of 1987. The recent topics are reported. (Kako, I.)

  7. Alberta Chamber of Resources : 1997 resources guide and directory

    International Nuclear Information System (INIS)

    1997-01-01

    The Alberta Chamber of Resources (ACR) is composed of 140 member companies from the oil and gas industry, forestry, pulp and paper, mining, oil sands, utilities, contractors, suppliers, consultants, banking and other service groups, as well as representatives from universities and governments. ACR's activities during 1996 were reviewed. These included supporting or sponsoring a careers forum, and various other networking and information sharing opportunities, a study of the potential for Alberta's minerals industry, and exploring opportunities for research in the forestry sector and the further development of Alberta's oil sands. Studies of the transportation and infrastructures strategies for Alberta's resources, royalty regimes, tenure and compensation issues associated with oil sands reservoirs that are 'capped' by natural gas reservoirs, taxation issues related to oil sands development, mineral rights tenure, and toll design and royalty issues affecting Alberta's natural gas sector rounded out the Chamber's activities. The annual review also profiled a number of ACR member companies, among them Koch Oil Company Ltd., Pardee Equipment Ltd., Interprovincial Pipe Line Inc., Clearwater Welding and Fabricating Ltd., and Weldwood of Canada. A listing of all ACR members was also provided

  8. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

    Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

  9. Reactor

    International Nuclear Information System (INIS)

    Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

    1979-01-01

    Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

  10. University of Florida Training Reactor: Annual progress report, September 1, 1986-August 31, 1987

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1987-11-01

    The University of Florida Training Reactor's overall utilization for the past reporting year (September 1986 through August 1987) has returned to the increased levels of quality usage characteristic of the two years prior to the last reporting year when the maintenance outage to repair sticking control blades reduced availability for the year to near 50%. Indeed, the 91.5% availability factor for this reporting year is the highest in the last five years and probably in the 27 year history of the facility. As a final statement on the effectiveness of the corrective maintenance last year, the overall availability factor has been over 94% since returning to normal operations. The UFTR continues to experience a high rate of utilization in a broad spectrum of areas with total utilization continuing near the highest levels recorded in the early 1970's. This increase has been supported by a variety of usages ranging from research and educational utilization by users within the University of Florida as well as other researchers and educators around the state of Florida through the support of the DOE Reactor Sharing Program and several externally supported usages. Significant usage has also been devoted to facility enhancement where a key ingredient for this usage has been a stable management staff. Uses, reactor operation, maintenance, technical specifications, radioactive releases, and research programs are described in this report

  11. Insight conference proceedings : Alberta power

    International Nuclear Information System (INIS)

    2004-01-01

    This conference addressed issues dealing with Alberta's restructured electric power industry and new policies from the perspective of Alberta's independent power industry. It covered lessons learned from electric industry restructuring, transmission strategies, transmission frameworks, competitive markets, power costs, energy prices, and power outages. Interconnected power systems between Alberta and British Columbia were also reviewed along with grid reinforcement requirements. Markets and restructuring efforts in other jurisdictions such as Quebec and Maritime Canada were briefly reviewed. The move to deregulate the industry has played an important role in restructuring a vertically integrated industry into power generation, transmission and distribution. High electricity prices eventually resulted in re regulation of the industry and a synergy between wholesale and retail markets. Five of the 17 papers were indexed separately for inclusion in the database. refs., tabs., figs

  12. China joins Alberta oilsands research

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This paper reports that China's state oil company has bought a stake in an in situ oilsands research project in northern Alberta. China National Petroleum Corp. (CNPC) will invest $6.5 million in the Underground Test Facility (UTF) operated by Alberta Oilsands Technology and Research Authority (Aostra) near Fort McMurray. It is the first foreign research investment for CNPC. The UTF is a joint venture by provincial agency Aostria, the Canadian federal government, and commercial partners in underground mining techniques to extract crude oil from bitumen. Alberta opened a trade office in Beijing in 1991 and now sells several hundred million dollars a year in petroleum equipment and services to China. A horizontal well in situ steam injection process is approaching the production stage at the UTF. It is to begin producing at a rate of 2,000 b/d this fall. The current project is a followup to a pilot project

  13. Status of University of Cincinnati reactor-site nuclear engineering graduate programs

    International Nuclear Information System (INIS)

    Anno, J.N.; Christenson, J.M.; Eckart, L.E.

    1993-01-01

    The University of Cincinnati (UC) nuclear engineering program faculty has now had 12 yr of experience in delivering reactor-site educational programs to nuclear power plant technical personnel. Currently, with the sponsorship of the Toledo-Edison Company (TED), we are conducting a multiyear on-site graduate program with more than 30 participants at the Davis-Besse nuclear power plant. The program enables TED employees with the proper academic background to earn a master of science (MS) degree in nuclear engineering (mechanical engineering option). This paper presents a brief history of tile evolution of UC reactor-site educational programs together with a description of the progress of the current program

  14. Annual progress report of the University of Florida Training Reactor, September 1, 1981-August 31, 1982

    International Nuclear Information System (INIS)

    Diaz, N.J.; Vernetson, W.G.

    1982-11-01

    The University of Florida Training Reactor's overall utilization for the past reporting year has decreased by about 50% compared to the previous year, approaching the low levels of utilization characteristic of the previous two reporting years ending in August 1979 and August 1980 respectively. The energy generation also continues to be far below average historical levels and represents a drop of nearly 50% from the improved level of the previous year. The UFTR continues to operate with an outstanding safety record and in full compliance with regulatory requirements. The reactor and associated facilities continue to maintain a high in-state visibility and strong industry relationship. It is hoped that more indirect industry training will be accomplished in the upcoming year

  15. Improving the beam quality of the neutron radiography facility using the SLOWPOKE-2 at the Royal Military College of Canada

    International Nuclear Information System (INIS)

    Lewis, W.J.; Bennett, L.G.I.; Teshima, P.

    1996-01-01

    At the SLOWPOKE-2 Facility at the Royal Military College of Canada, a neutron radiography facility has been designed and installed, and the beam quality has been improved by performing a series of radiographs using American standard for testing and materials (ASTM) E 545 indicators. Other means of determining the progress such as bubble detectors and activation foils were used. Modifications to the nosepiece of the beam tube including shielding and linings for fast neutron and gamma radiation were made. (orig.)

  16. Transmutation research and fuel cycle (report on discussion at Research Reactor Institute, Kyoto University)

    International Nuclear Information System (INIS)

    Yamana, Hajimu

    1999-01-01

    A symposium was held on a topic of 'Transmutation Research' on Dec. 21 and 22, 1999 at Research Reactor Institute, Kyoto University. This meeting was held as a joint-meeting of KUR's specialist meeting and Tokyo University's activity supported by the Grant-in-Aid for Scientific Research of Ministry of Education, Sport and Culture of Japan. This paper describes the overview of the discussions of this joint-meeting, and interprets their significance. Major themes discussed are, needed discussions on the transmutation research, policy and concepts of the organizations doing transmutation researches, a view from university side, transmutation researches in the oversea countries, opinions from various standpoints of the nuclear fuel cycle, conclusive discussions. 'the meanings of the transmutation research should be discussed together with the geological disposal and fast reactor system', 'transmutation may be a cooperative option for the disposal, thus, they should not be in a independent relation', and Balance evaluation will be needed' are the examples of the conclusive remarks of this meeting. (author)

  17. Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin [University of Illinois, Urbana (United States)

    2014-08-15

    Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor.

  18. Educational Change in Alberta, Canada

    Directory of Open Access Journals (Sweden)

    Charles F. Webber

    1995-07-01

    Full Text Available Alberta, Canada, is the site of large-scale educational change initiatives legislated by the provincial government. The mandates have sparked heated public debate over the appropriateness, wisdom, and utility of the reforms. This article summarizes the views of representatives of several educational interest groups and offers suggestions for making change more meaningful and successful.

  19. Neutronics modeling of TRIGA reactor at the University of Utah using agent, KENO6 and MCNP5 codes

    International Nuclear Information System (INIS)

    Yang, X.; Xiao, S.; Choe, D.; Jevremovic, T.

    2010-01-01

    The TRIGA reactor at the University of Utah is modelled in 2D using the AGENT state-of-the-art methodology based on the Method of Characteristics (MOC) and R-function theory supporting detailed reactor analysis of reactor geometries of any type. The TRIGA reactor is also modelled using KENO6 and MCNP5 for comparison. The spatial flux and reaction rates distribution are visualized by AGENT graphics support. All methodologies are in use in to study the effect of different fuel configurations in developing practical educational exercises for students studying reactor physics. At the University of Utah we train graduate and undergraduate students in obtaining the Nuclear Regulatory Commission license in operating the TRIGA reactor. The computational models as developed are in support of these extensive training classes and in helping students visualize the reactor core characteristics in regard to neutron transport under various operational conditions. Additionally, the TRIGA reactor is under the consideration for power uprate; this fleet of computational tools once benchmarked against real measurements will provide us with validated 3D simulation models for simulating operating conditions of TRIGA. (author)

  20. The Intense Slow Positron Beam Facility at the NC State University PULSTAR Reactor

    International Nuclear Information System (INIS)

    Hawari, Ayman I.; Moxom, Jeremy; Hathaway, Alfred G.; Brown, Benjamin; Gidley, David W.; Vallery, Richard; Xu, Jun

    2009-01-01

    An intense slow positron beam is in its early stages of operation at the 1-MW open-pool PULSTAR research reactor at North Carolina State University. The positron beam line is installed in a beam port that has a 30-cmx30-cm cross sectional view of the core. The positrons are created in a tungsten converter/moderator by pair-production using gamma rays produced in the reactor core and by neutron capture reactions in cadmium cladding surrounding the tungsten. Upon moderation, slow (∼3 eV) positrons that are emitted from the moderator are electrostatically extracted, focused and magnetically guided until they exit the reactor biological shield with 1-keV energy, approximately 3-cm beam diameter and an intensity exceeding 6x10 8 positrons per second. A magnetic beam switch and transport system has been installed and tested that directs the beam into one of two spectrometers. The spectrometers are designed to implement state-of-the-art PALS and DBS techniques to perform positron and positronium annihilation studies of nanophases in matter.

  1. Reactivity worth measurement of the control blades of the University of Florida training reactor

    International Nuclear Information System (INIS)

    Quintero-Leyva, Barbaro

    1997-01-01

    A series of experiments were carried out in order to measure the reactivity worth of the safety and regulating blades of the University of Florida Training Reactor (UFTR) using the Inverse Kinetics, the Inverse Kinetics-Rod Drop method and the Power Ratio. The reactor's own instrumentation (compensated ion chamber) and an independent counting system (fission chamber) were used. A very smooth exponential decay of the flux was observed after 6s of the beginning of the transients using the reading of the reactor detector. The results of the measurements of the reactivity using both detectors were consistent and in good agreement. The compensated ion chamber showed a very smooth exponential behavior; this suggests that if we could record the power for a small sample time, say 0.1 s from the beginning of the transient, several additional research projects could be accomplished. First, precise intercomparison of the methods could be achieved if the statistics level is acceptable. Second, a precise description of the bouncing of the blades and its effects on the reactivity could be achieved. Finally, the design of a reactivity-meter could be based on such study. (author)

  2. Twenty-ninth annual progress report of the Pennsylvania State University Breazeale Nuclear Reactor, July 1, 1983-June 30, 1984

    International Nuclear Information System (INIS)

    Levine, S.H.; Totenbier, R.E.

    1984-07-01

    The twenty-ninth annual progress report of the operation of the Pennsylvania State University Breazeale Reactor is submitted in accordance with the requirements of Contract DE-AC02-76ER03409 with the United States Department of Energy. This report also provides the University administration with a summary of the operation of the facility for the past year

  3. 77 FR 13376 - Notice of License Termination for the University of Arizona Research Reactor, License No. R-52

    Science.gov (United States)

    2012-03-06

    ... the University of Arizona Research Reactor, License No. R-52 The U.S. Nuclear Regulatory Commission (NRC) is noticing the termination of Facility Operating License No. R-52, for the University of Arizona... Operating License No. R-52 is terminated. For further details with respect to the proposed action, see the...

  4. 78 FR 5840 - Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115

    Science.gov (United States)

    2013-01-28

    ... University of Illinois Advanced TRIGA Reactor, License No. R-115 The U.S. Nuclear Regulatory Commission (NRC) is noticing the termination of Facility Operating License No. R-115, for the University of Illinois... Operating License No. R-115 is terminated. The above referenced documents may be examined, and/or copied for...

  5. Scottish Universities Research and Reactor Centre annual report 1987-1988

    International Nuclear Information System (INIS)

    Whitley, J.E.

    1988-01-01

    The Scottish Universities Research and Reactor Centre (SURRC) provides facilities for research in isotopic, nuclear and earth sciences and collaborates with Scottish University departments on a wide range of research topics. One of its main areas of work is the Isotope Geology Unit. This has worked with the Nuclear Medicine Unit on the application of enriched stable isotope tracers in the biological and clinical sciences. The measurement of radioactive isomers is applied to quaternary geology, archaeology, nuclear medicine, health physics, oceanography, atomospheric sciences, environmental chemistry, nuclear waste disposal and mathematical modelling of the environment. There are also radiocarbon dating facilities. The facilities and the research undertaken at the Centre in the year 1987-1988, the Centre's twenty-fifth year are summarized in this report. (U.K.)

  6. Systems dynamics (SD) strategy for Small Modular Reactor (SMR) marketing - Conquest at the MIT Energy Laboratory (Pres. MIT Energy Initiative)

    International Nuclear Information System (INIS)

    Woo, T. H.

    2016-01-01

    This reactor has the specification as the power is 330 MWt pressurized water reactor (PWR) with integral steam generators and advanced safety features. In the plant design, it is planned for electricity generation of 100 MWe and thermal applications of seawater desalination where the life span is a 60-year operation design and three-year refueling cycle. Regarding of the licensing, the standard design was approved from the Korean regulator in mid-2012 and the Korea Atomic Energy Research Institute (KAERI) has a plan to build a demonstration plant to operate from 2017. According to the previous study of the marketing strategy of the Canadian small reactor, Safe LOW-POwer Kritical Experiment (SLOWPOKE) reactor had been investigated in 1988. Therefore, it is interesting to compare SMART and SLOWPOKE. In this work, it is to find out the strategy of the successful marketing of SMART and suggest continuous marketing prospects. There are specifications and parameters of SMART in Tables 1 and 2. The public acceptance (PA) had been studies as safety-public interpretation, SLOWPOKE safety-experience and process, and economics in the previous paper of the SLOWPOKE, which was about the marketing strategy for the commercial nuclear reactor. The highly cognitive networking based dynamical modeling was discussed where the system is treated by a complex and non-linear way. The linear networking of the interested issue was changed by the SD algorithm where the feedback and multiple connections are added to the original networking theory. The non-linear method has shown the complexity of the marketing strategy, especially for the NPP which is the very expensive and safety focused facility

  7. Systems dynamics (SD) strategy for Small Modular Reactor (SMR) marketing - Conquest at the MIT Energy Laboratory (Pres. MIT Energy Initiative)

    Energy Technology Data Exchange (ETDEWEB)

    Woo, T. H. [Yonsei University, Wonju (Korea, Republic of)

    2016-10-15

    This reactor has the specification as the power is 330 MWt pressurized water reactor (PWR) with integral steam generators and advanced safety features. In the plant design, it is planned for electricity generation of 100 MWe and thermal applications of seawater desalination where the life span is a 60-year operation design and three-year refueling cycle. Regarding of the licensing, the standard design was approved from the Korean regulator in mid-2012 and the Korea Atomic Energy Research Institute (KAERI) has a plan to build a demonstration plant to operate from 2017. According to the previous study of the marketing strategy of the Canadian small reactor, Safe LOW-POwer Kritical Experiment (SLOWPOKE) reactor had been investigated in 1988. Therefore, it is interesting to compare SMART and SLOWPOKE. In this work, it is to find out the strategy of the successful marketing of SMART and suggest continuous marketing prospects. There are specifications and parameters of SMART in Tables 1 and 2. The public acceptance (PA) had been studies as safety-public interpretation, SLOWPOKE safety-experience and process, and economics in the previous paper of the SLOWPOKE, which was about the marketing strategy for the commercial nuclear reactor. The highly cognitive networking based dynamical modeling was discussed where the system is treated by a complex and non-linear way. The linear networking of the interested issue was changed by the SD algorithm where the feedback and multiple connections are added to the original networking theory. The non-linear method has shown the complexity of the marketing strategy, especially for the NPP which is the very expensive and safety focused facility.

  8. Reactor Physics Experiments by Korean Under-Graduate Students in Kyoto University Critical Assembly Program (KUGSiKUCA Program)

    International Nuclear Information System (INIS)

    Pyeon, Cheol Ho; Misawa, Tsuyoshi; Unesaki, Hironobu; Ichihara, Chihiro; Shiroya, Seiji; Whang, Joo Ho; Kim, Myung Hyun

    2006-01-01

    The Reactor Laboratory Course for Korean Under-Graduate Students in Kyoto University Critical Assembly (KUGSiKUCA) program has been launched from 2003, as one of international collaboration programs of Kyoto University Research Reactor Institute (KURRI). This program was suggested by Department of Nuclear Engineering, College of Advanced Technology, Kyunghee University (KHU), and was adopted by Ministry of Science and Technology of Korean Government as one of among Nuclear Human Resources Education and Training Programs. On the basis of her suggestion for KURRI, memorandum for academic corporation and exchange between KHU and KURRI was concluded on July 2003. The program has been based on the background that it is extremely difficult for any single university in Korea to have her own research or training reactor. Up to this 2006, total number of 61 Korean under-graduate school students, who have majored in nuclear engineering of Kyunghee University, Hanyang University, Seoul National University, Korea Advanced Institute of Science and Technology, Chosun University and Cheju National University in all over the Korea, has taken part in this program. In all the period, two professors and one teaching assistant on the Korean side led the students and helped their successful experiments, reports and discussions. Due to their effort, the program has succeeded in giving an effective and unique course, taking advantage of their collaboration

  9. IDRC and the University of Alberta

    International Development Research Centre (IDRC) Digital Library (Canada)

    . The kit's use spread through China, Bangladesh, India, Indo- nesia, Malaysia, Pakistan, and Taiwan. A British Columbia company, Syndel, went on to commercialize the technol- ogy in the form of Ovaprim, now used around the world. N . K. U.

  10. U.S. Department of Energy University Reactor Sharing Program at the University of Florida. Final report for period August 15, 2000 - May 31, 2001

    Energy Technology Data Exchange (ETDEWEB)

    Vernetson, William G.

    2002-01-01

    Department of Energy Grant Number DE-FG02-96NE38152 was supplied to the University of Florida Training Reactor (UFTR) facility through the U.S. Department of Energy's University Reactor Sharing Program. The renewal proposal submitted in January 2000 originally requested over $73,000 to support various external educational institutions using the UFTR facilities in academic year 2000-01. The actual Reactor Sharing Grant was only in the amount of $40,000, all of which has been well used by the University of Florida as host institution to support various educational institutions in the use of our reactor and associated facilities as indicated in the proposal. These various educational institutions are located primarily within the State of Florida. However, when the 600-mile distance from Pensacola to Miami is considered, it is obvious that this Grant provides access to reactor utilization for a broad geographical region and a diverse set of user institutions serving over fourteen million inhabitants throughout the State of Florida and still others throughout the Southeast.

  11. Preparation of mandatory documentation before the start up of the RA-0 'zero power' nuclear reactor at Cordoba National University

    International Nuclear Information System (INIS)

    Martin, H.R.; Keil, W.M.; Pezzi, N.

    1991-01-01

    Before the start up of the RA-0 'zero power' nuclear reactor installed at Cordoba National University, it was necessary to send to the Regulatory Authority the mandatory documentation which is required in the licensing process. With the previous papers existing for the operation in the first years of the '70, a work program for the future operational training personnel was elaborated. Based on the Authority's applicable rules and the recommendations and with particular criteria originated in the working university conditions, the SAFETY report of RA-0 nuclear reactor was prepared. This paper describes the principal contents, items and documents involved in the safety report. (Author) [es

  12. Qualitative assessment of the value of the Ohio State University TRIGA reactor

    International Nuclear Information System (INIS)

    Binney, S.E.; Johnson, A.G.

    1989-01-01

    The Oregon State University (OSU) TRIGA Reactor (OSTR) is a major regional research, training, and service facility. The OSTR supports a wide variety of organizations at the local, state, regional, national, and international levels. Examples of usage of the OSTR are given in this paper to serve as a basis for assessing the value of the OSTR to its user organizations. It is difficult to assess the value of a facility such as the OSTR quantitatively, primarily because a dollar value cannot be assigned to many of the services that the OSTR performs, e.g., forensic analysis to assist police agencies in criminal cases. Significant qualitative statements can be made, however, to demonstrate the fact that the value of a research reactor facility such as the OSTR substantially outweighs the capital and operating costs of such a facility. Analysis of the data presented above clearly indicates that the value of the OSTR facility is overwhelmingly positive, i.e., the benefits associated with the services provided by the OSTR facility outweigh the cost of providing such services by perhaps as much as an order of magnitude

  13. LOSS-OF-COOLANT ACIDENT SIMULATIONS IN THE NATIONAL RESEARCH UNIVERSAL REACTOR

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, W D; Goodman, R L; Heaberlin, S W; Hesson, G M; Nealley, C; Kirg, L L; Marshall, R K; McNair, G W; Meitzler, W D; Neally, G W; Parchen, L J; Pilger, J P; Rausch, W N; Russcher, G E; Schreiber, R E; Wildung, N J

    1981-02-01

    Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a series of experiments in the U-2 loop of the National Research Universal Reactor at Chalk River, Ontario, Canada. The first of these experiments includes up to 45 parametric thermal-hydraulic tests to establish the relationship among the reflood delay time of emergency coolant, the reflooding rate, and the resultant fuel rod cladding peak temperature. Subsequent experiments establish the fuel rod failure characteristics at selected peak cladding temperatures. Fuel rod cladding pressurization simulates high burnup fission gas pressure levels of modern PWRs. This document contains both an experiment overview of the LOCA simulation program and a review of the safety analyses performed by Pacific Northwest Laboratory (PNL) to define the expected operating conditions as well as to evaluate the worst case operating conditions. The primary intent of this document is to supply safety information required by the Chalk River Nuclear Laboratories (CRNL), to establish readiness to proceed from one test phase to the next and to establish the overall safety of the experiment. A hazards review summarizes safety issues, normal operation and three worst case accidents that have been addressed during the development of the experiment plan.

  14. DOE/NE University Program in robotics for advanced reactors research

    International Nuclear Information System (INIS)

    Trivedi, M.M.

    1990-01-01

    The document presents the bimonthly progress reports published during 1990 regarding the US Department of Energy/NE-sponsored research at the University of Tennessee Knoxville under the DOE Robitics for Advanced Reactors Research Grant. Significant accomplishments are noted in the following areas: development of edge-segment based stereo matching algorithm; vision system integration in the CESAR laboratory; evaluation of algorithms for surface characterization from range data; comparative study of data fusion techniques; development of architectural framework, software, and graphics environment for sensor-based robots; algorithms for acquiring tactile images from planer surfaces; investigations in geometric model-based robotic manipulation; investigations of non-deterministic approaches to sensor fusion; and evaluation of sensor calibration techniques. (MB)

  15. URI Program Final Report FY 2001 Grant for the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    2004-01-01

    The purpose of the URI program is to upgrade and improve university nuclear research and training reactors and to contribute to strengthening the academic community's nuclear engineering infrastructure. It should be noted that the proposed UFTR facility instrumentation and equipment can generally be subdivided into three categories: (1) to improve reactor operations, (2) to improve existing facility/NAA Laboratory operations, and (3) to expand facility capability. All of these items were selected recognizing the objectives of the University Reactor Instrumentation Program to respond to the widespread needs in the academic reactor community for modernization and improvement of research and training reactor facilities, especially at large and diverse institutions such as the University of Florida. These needs have been particularly pressing at the UFTR which is the only such research and training reactor in the State of Florida which is undergoing rapid growth in a variety of technical areas. As indicated in Table 2, the first item is a security system control panel with associated wiring and detectors. The existing system is over 30 years old and has been the subject of repeated maintenance over the past 5 years. Some of its detection devices are no longer replaceable from stock. Modifications made many years ago make troubleshooting some parts of the system such as the backup battery charging subsystem essentially impossible, further increasing maintenance frequency to replace batteries. Currently, various parts of the system cable trays remain open for maintenance access further degrading facility appearance. In light of relicensing plans, this item is also a key consideration for housekeeping appearance considerations. The cost of a replacement ADEMCO Vista 20 security system including turnkey installation by a certified vendor was to be $2,206. Replacement of this system was expected to save up to 5 days of maintenance per year, decrease security alarm response

  16. Documentation Experiences for Jamaican SLOWPOKE-2 Conversion from HEU to LEU

    International Nuclear Information System (INIS)

    Warner, T.-A.; Dennis, H.; Antoine, J.

    2015-01-01

    The Jamaican SLOWPOKE–2 (JM–1) is a 20 kW research reactor manufactured by Atomic Energy of Canada Limited and has been operating since March 1984, in the department of the International Centre for Environmental and Nuclear Sciences (ICENS), at the University of the West Indies, Mona Campus in Kingston, Jamaica. The pool type reactor has been primarily used for Neutron Activation Analysis in environmental, agricultural, geochemical, health-related studies and mineral exploration. The University, assisted by the IAEA under the GTRI/RERTR program, is currently in the process of converting from HEU to LEU. Extensive documentation on policies, general requirements, elements of the conversion quality assurance (QA) system and conversion QA administrative procedures is required for the conversion. The core conversion activities are being carried out in accordance with current international standards and regulatory guidelines of the newly established Jamaican Radiation Safety Authority (RSA) with agreement between the RSA and IAEA or DOE related to Nuclear Safety and Control. The documentation structure has taken into consideration nuclear safety and licensing, LEU fuel design and conversion analysis, LEU fuel procurement and fabrication, removal of HEU fuel and reactor maintenance and conversion and commissioning, with the conversion QA manual at the apex of the structure. To a large extent, the documentation format will adhere to that of the IAEA applicable regulatory standards and guidance documents. The major challenge of the conversion activities, it is envisioned, will come from the absence of any previous regulatory framework in Jamaica; however, a timeline for the process, which includes training and equipping of regulators, will guide operation. (author)

  17. Digital Preservation of the Quon Sang Lung Laundry Building, Fort Macleod, Alberta

    Science.gov (United States)

    Dawson, P.; Baradaran, F.; Jahraus, A.; Rubalcava, E.; Farrokhi, A.; Robinson, C.

    2017-08-01

    This paper describes the results of an emergency recording and archiving of a historic structure in Southern Alberta and explores the lessons learned. Digital recording of the Quon Sang Lung Laundry building in Fort Macleod, Alberta, was a joint initiative between Alberta Culture and Tourism and the University of Calgary. The Quon Sang Lung Laundry was a boomtown-style wood structure situated in the Fort Macleod Provincial Historic Area, Alberta. Built in the mid-1800s, the structure was one of the four buildings comprising Fort Macleod's Chinatown. Its association with Chinese immigration, settlement, and emergence of Chinese-owned businesses in early twentieth-century Alberta, made the Quon Sang Lung Laundry a unique and very significant historic resource. In recent years, a condition assessment of the structure indicated that the building was not safe and that the extent of the instability could lead to a sudden collapse. In response, Alberta Culture and Tourism engaged the Departments of Anthropology and Archaeology and Geomatics Engineering from the University of Calgary, to digitally preserve the laundry building. A complete survey including the laser scanning of all the remaining elements of the original structure, was undertaken. Through digital modeling, the work guarantees that a three-dimensional representation of the building is available for future use. This includes accurate 3D renders of the exterior and interior spaces and a collection of architectural drawings comprising floor plans, sections, and elevations.

  18. Final report on the University of Florida U.S. Department of Energy 1995--96 Reactor Sharing Program

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1996-11-01

    Grant support has been well used by the University of Florida as host institution to support various educational institutions in the use of the reactor and associated facilities as indicated in the proposal. These various educational institutions are located primarily within Florida. However, when the 600-mile distance from Pensacola to Miami is considered, it is obvious that this Grant provides access to reactor utilization for a broad geographical region and a diverse set of user institutions serving over twelve million inhabitants throughout the State of Florida and still others throughout the nation. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research activities were not funded by grants for contract funding from outside sources. In some cases external grant funding is limited or is used up, in which case the Reactor Sharing Grant and frequent cost sharing by the UFTR facility and the University of Florida provide the necessary support to complete a project or to provide more results to make a complete project even better. In some cases this latter usage has aided renewal of external funding. The role of the Reactor Sharing Program, though relatively small in dollars, has been the single most important occurrence in assuring the rebirth and continued high utilization of the UFTR in a time when many better equipped and better placed facilities have ceased operations. Through dedicated and effective advertising efforts, the UFTR has seen nearly every four-year college and university in Florida make substantive use of the facility under the Reactor Sharing Program with many now regular users. Some have even been able to support usage from outside grants where the Reactor Sharing Grant has served as seed money; still others have been assisted when external grants were depleted

  19. Final report on the University of Florida U.S. Department of Energy 1995--96 Reactor Sharing Program

    Energy Technology Data Exchange (ETDEWEB)

    Vernetson, W.G.

    1996-11-01

    Grant support has been well used by the University of Florida as host institution to support various educational institutions in the use of the reactor and associated facilities as indicated in the proposal. These various educational institutions are located primarily within Florida. However, when the 600-mile distance from Pensacola to Miami is considered, it is obvious that this Grant provides access to reactor utilization for a broad geographical region and a diverse set of user institutions serving over twelve million inhabitants throughout the State of Florida and still others throughout the nation. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research activities were not funded by grants for contract funding from outside sources. In some cases external grant funding is limited or is used up, in which case the Reactor Sharing Grant and frequent cost sharing by the UFTR facility and the University of Florida provide the necessary support to complete a project or to provide more results to make a complete project even better. In some cases this latter usage has aided renewal of external funding. The role of the Reactor Sharing Program, though relatively small in dollars, has been the single most important occurrence in assuring the rebirth and continued high utilization of the UFTR in a time when many better equipped and better placed facilities have ceased operations. Through dedicated and effective advertising efforts, the UFTR has seen nearly every four-year college and university in Florida make substantive use of the facility under the Reactor Sharing Program with many now regular users. Some have even been able to support usage from outside grants where the Reactor Sharing Grant has served as seed money; still others have been assisted when external grants were depleted.

  20. Safety Evaluation Report related to the renewal of the operating license for the training and research reactor at the University of Michigan (Docket No. 50-2)

    International Nuclear Information System (INIS)

    1985-07-01

    This Safety Evaluation Report for the application filed by the University of Michigan (UM) for renewal of the Ford Nuclear Reactor (FNR) operating license number R-28 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the North Campus of the University of Michigan in Ann Arbor, Michigan. The staff concludes that the reactor can continue to be operated by the University of Michigan without endangering the health and safety of the public

  1. Critical experiment on natural uranium assembly in Kinki University Reactor UTR-KINKI, 1

    International Nuclear Information System (INIS)

    Ito, Tetsuo; Miki, Ryota; Tsuchihashi, Keiichiro; Kobayashi, Keiji; Ishihara, Shinji; Hayashi, Masatoshi; Shiroya, Seiji; Kanda, Keiji.

    1986-01-01

    Integral critical experiments on natural uranium assemblies (3 x 3 elements) which are set up in the central region of the enlarged central vertical stringer, 16.4 x 16.4 x 122 cm, located at the center of internal graphite refrector between two fuel tanks of Kinki University Research Reactor, UTR-KINKI, has been performed as a complement to the experiment in Kyoto University Critical Assembly, KUCA, to check and evaluate calculation methods of critical experiment and analysis on thorium assembly in UTR-KINKI. Enlarged natural uranium assemblies are composed of square natural uranium metal plates and square graphite plates. The experiments include the followings: (1) Measurement of reactivity of various enlarged natural uranium assemblies (2) Measurement of relative neutron flux distribution (Au foil reaction rate distribution) in various enlarged natural uranium assemblies. Experimental results on reactivity effect of natural uranium and thorium assemblies show different tendency, but the neutron flux distribution in various natural uranium and thorium assemblies have similar pattern. (author)

  2. Transmission infrastructure development in Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Stubbings, R.V. [EnVision Energy Consulting Ltd., Calgary, AB (Canada)

    2004-09-01

    Major power blackouts have resulted in greater attention to reliability. Changes in industry structure have placed unanticipated demands on transmission systems. Load growth has outstripped transmission investment, and there are major implications for infrastructure development due to the enactment of the new transmission regulation. This paper discusses several projects addressing new developments in the electric power industry, including details of an Edmonton-Calgary path upgrade in order to increase north-south transmission capacity. Proposed southwest Transmission upgrades were reviewed, including the construction of a double-circuit 240 kV line from Pincher Creek to Peigan or Mud Lake, in order to improve reliability and improve access to southern wind and hydro generation. Other possible projects include a High Voltage Direct Current (HVDC) from Fort McMurray to Calgary and a Northern Lights Transmission project between Fort McMurray and the Pacific Northwest. Various investment drivers were reviewed, with oil sands processing providing steam hosts for cogeneration at Fort McMurray and Cold Lake generation as well as Lake Wabamun. Plans concerning Southwest Alberta generation were presented, including wind-powered generation, and load growth in southern Alberta. Various investment limiters include absorption of existing capacity; improved facility utilization; and distributed generation. Competition for investment funds were discussed, in addition to uncertainties over generation siting as well as regulatory difficulties and power flow pattern irregularities due to increasing market integration. Uncertain access to markets, locational marginal pricing and various southern Alberta generation incentives were reviewed. Market implications include generation mix; lower price volatility; reduced potential for market power abuse by generators; and increased export levels. The implications for British Columbia were highlighted, with particular reference to an

  3. The American Imprint on Alberta Politics

    Science.gov (United States)

    Wiseman, Nelson

    2011-01-01

    Characteristics assigned to America's classical liberal ideology--rugged individualism, market capitalism, egalitarianism in the sense of equality of opportunity, and fierce hostility toward centralized federalism and socialism--are particularly appropriate for fathoming Alberta's political culture. The author contends that Alberta's early…

  4. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

    Object: To provide a boiling water reactor which can enhance a quake resisting strength and flatten power distribution. Structure: At least more than four fuel bundles, in which a plurality of fuel rods are arranged in lattice fashion which upper and lower portions are supported by tie-plates, are bundled and then covered by a square channel box. The control rod is movably arranged within a space formed by adjoining channel boxes. A spacer of trapezoidal section is disposed in the central portion on the side of the channel box over substantially full length in height direction, and a neutron instrumented tube is disposed in the central portion inside the channel box. Thus, where a horizontal load is exerted due to earthquake or the like, the spacers come into contact with each other to support the channel box and prevent it from abnormal vibrations. (Furukawa, Y.)

  5. Reactor

    International Nuclear Information System (INIS)

    Evans, R.M.

    1976-01-01

    Disclosed is a neutronic reactor having a moderator, coolant tubes traversing the moderator from an inlet end to an outlet end, bodies of material fissionable by neutrons of thermal energy disposed within the coolant tubes, and means for circulating water through said coolant tubes characterized by the improved construction wherein the coolant tubes are constructed of aluminum having an outer diameter of 1.729 inches and a wall thickness of 0.059 inch, and the means for circulating a liquid coolant through the tubes includes a source of water at a pressure of approximately 350 pounds per square inch connected to the inlet end of the tubes, and said construction including a pressure reducing orifice disposed at the inlet ends of the tubes reducing the pressure of the water by approximately 150 pounds per square inch. 1 claim, 16 figures

  6. SLOAN LOW-MASS WIDE PAIRS OF KINEMATICALLY EQUIVALENT STARS (SLoWPoKES): A CATALOG OF VERY WIDE, LOW-MASS PAIRS

    International Nuclear Information System (INIS)

    Dhital, Saurav; Stassun, Keivan G.; West, Andrew A.; Bochanski, John J.

    2010-01-01

    We present the Sloan Low-mass Wide Pairs of Kinematically Equivalent Stars (SLoWPoKES), a catalog of 1342 very-wide (projected separation ∼>500 AU), low-mass (at least one mid-K to mid-M dwarf component) common proper motion pairs identified from astrometry, photometry, and proper motions in the Sloan Digital Sky Survey. A Monte Carlo-based Galactic model is constructed to assess the probability of chance alignment for each pair; only pairs with a probability of chance alignment ≤0.05 are included in the catalog. The overall fidelity of the catalog is expected to be 98.35%. The selection algorithm is purposely exclusive to ensure that the resulting catalog is efficient for follow-up studies of low-mass pairs. The SLoWPoKES catalog is the largest sample of wide, low-mass pairs to date and is intended as an ongoing community resource for detailed study of bona fide systems. Here, we summarize the general characteristics of the SLoWPoKES sample and present preliminary results describing the properties of wide, low-mass pairs. While the majority of the identified pairs are disk dwarfs, there are 70 halo subdwarf (SD) pairs and 21 white dwarf-disk dwarf pairs, as well as four triples. Most SLoWPoKES pairs violate the previously defined empirical limits for maximum angular separation or binding energies. However, they are well within the theoretical limits and should prove very useful in putting firm constraints on the maximum size of binary systems and on different formation scenarios. We find a lower limit to the wide binary frequency (WBF) for the mid-K to mid-M spectral types that constitute our sample to be 1.1%. This frequency decreases as a function of Galactic height, indicating a time evolution of the WBF. In addition, the semi-major axes of the SLoWPoKES systems exhibit a distinctly bimodal distribution, with a break at separations around 0.1 pc that is also manifested in the system binding energy. Compared with theoretical predictions for the disruption of

  7. License renewal and power upgrade of the Cornell University TRIGA reactor

    International Nuclear Information System (INIS)

    Aderhold, Howard C.

    1984-01-01

    The Cornell Mark II TRIGA reactor has been a principal facility for instruction and research in nuclear science and engineering at Cornell, and it has been extensively used by other departments at Cornell and by nearby universities and industries. Initially the fuel was low hydride, 8.5w/o 19%-enriched, aluminum clad; in 1974 it was changed to high-hydride, stainless-steel-clad. The maximum power has been 100 kW, with pulses to $2, and operation has been on a one-shift demand basis. Annual energy generation of 50 MWH has been typical. Standard features include a 4-inch tangential port and our 6-inch radial ports, a thermal column with hohlraum and vertical access, a central thimble, a 'rabbit', and a set of dry irradiation tubes, replacing the 'Lazy Susan'. The license was renewed and amended in November 1983; the new limits are 500 kW and $3 pulses. Physical changes to the facility included addition of a water-to-water heat exchanger and of a diffuser at the water outlet ∼ 60 cm above the core. The flow rate is 300 liters per minute in the primary (reactor) side of the heat exchanger. The temperature of the chilled water entering the secondary of the exchanger is ∼ 12?C; its flow rate is adjusted by a servo-controlled by-pass valve to maintain the desired range of pool water temperature. Steps taken to go to higher power included rearrangement of fuel elements to increase excess reactivity, recalibration of control rods, and power vs ion chamber current calibrations at successively higher power by comparing the rate of rise of pool temperature with a known rate using electrical heating elements. Steady-state operation has been done up to 480 kW (nominal) but pulsing at the newly allowed higher levels has not been tested as yet

  8. Aspects of Reactor Physics Research at the Victoria University of Manchester

    International Nuclear Information System (INIS)

    Harris, M.J.; Walton, D.G.

    1964-01-01

    The Nuclear Engineering Department at Manchester University was established in 1959. Since that time post-graduate reactor physics studies have gradually enlarged and developed, starting virtually from scratch; experimental studies have concentrated on light-water systems and centred on the accelerator-driven, natural-uranium, light-water exponential. The paper contains a survey of the work to date, discussion of the results obtained, outlines of proposed future work, and, as they arise in the text, descriptions of various low-cost, labour-saving experimental techniques which have been adopted. The various divisions of the work are described below. The authors have studied neutron diffusion in light water using both pulsed source and steady source methods. In the former method they have particularly stressed full harmonic analysis to the extent of actually studying the higher modes as opposed to most former work which has tried only to eliminate them. In the study of steady source methods they have concentrated on eliminating all effects from finite source and detector size, resonance activation, flux perturbation and so on. The results of both are discussed and compared. A very careful measurement of absorption cross-sections by the pulsed technique, taking care to eliminate harmonic and other effects likely to lead to error is also in progress and is described. Thermal neutron spectra in ''poisoned'' light water are being measured as a means of investigating and developing integral detector techniques. This discussion includes some interesting time- and cost-saving examples. Large foil activation and counting techniques for measuring spatially averaged neutron densities, and hence a number of reactor parameters, have been studied. Some interesting points have arisen, particularly with regard to spectrum measurement. The method makes possible many reactor physics investigations with limited resources. A low-cost natural uranium, light-water exponential has been

  9. Section 1: Alberta Power Limited

    International Nuclear Information System (INIS)

    Kothari, R.; Quinn, D.

    1991-01-01

    A study was carried out to produce a compendium of electric and magnetic field levels that exist in Canada and to characterize and classify the sources of electric and magnetic fields. Alberta Power's contribution to this project was mainly to measure electric and magnetic fields produced by transmission lines in their service area in Alberta. Ten 240 kV transmission lines, ten 144 kV transmission lines, one 72 kV transmission line, two 25 kV distribution lines, two substations, and one residence were monitored for 60 Hz electric and magnetic field levels. For the 240 kV transmission lines, the electric field ranged from 0.4 kV/m to 1.9 kV/m and the magnetic field from 2.5 milligauss to 27 milligauss at the edge of the right-of-way. For 144 kV lines, the electric and magnetic fields ranged from 0.24-1.00 kV/m and 2.25-12.00 milligauss, respectively, at the edge of the right-of-way. 5 tabs

  10. Safety Evaluation Report related to the construction permit and operating license for the research reactor at the University of Texas (Docket No. 50-602)

    International Nuclear Information System (INIS)

    1985-05-01

    This Safety Evaluation Report for the application filed by the University of Texas for a construction permit and operating license to construct and operate a TRIGA research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Texas and is located at the university's Balcones Research Center, about 7 miles (11.6 km) north of the main campus in Austin, Texas. The staff concludes that the TRIGA reactor facility can be constructed and operated by the University of Texas without endangering the health and safety of the public

  11. Development and implementation of an automatic control algorithm for the University of Utah nuclear reactor

    International Nuclear Information System (INIS)

    Crawford, Kevan C.; Sandquist, Gary M.

    1990-01-01

    The emphasis of this work is the development and implementation of an automatic control philosophy which uses the classical operational philosophies as a foundation. Three control algorithms were derived based on various simplifying assumptions. Two of the algorithms were tested in computer simulations. After realizing the insensitivity of the system to the simplifications, the most reduced form of the algorithms was implemented on the computer control system at the University of Utah (UNEL). Since the operational philosophies have a higher priority than automatic control, they determine when automatic control may be utilized. Unlike the operational philosophies, automatic control is not concerned with component failures. The object of this philosophy is the movement of absorber rods to produce a requested power. When the current power level is compared to the requested power level, an error may be detected which will require the movement of a control rod to correct the error. The automatic control philosophy adds another dimension to the classical operational philosophies. Using this philosophy, normal operator interactions with the computer would be limited only to run parameters such as power, period, and run time. This eliminates subjective judgements, objective judgements under pressure, and distractions to the operator and insures the reactor will be operated in a safe and controlled manner as well as providing reproducible operations

  12. Preparation for shipment of spent TRIGA fuel elements from the research reactor of the Medical University of Hannover

    International Nuclear Information System (INIS)

    Hampel, Gabriele; Cordes, Harro; Ebbinghaus, Kurt; Haferkamp, Dirk

    1998-01-01

    In the early seventies a research reactor of type TRIGA Mark I was installed in the Department of Nuclear Medicine at the Medical University of Hannover (MHH) for the production of isotopes with short decay times for medical use. Since new production methods have been developed, the reactor has become obsolete and the MHH decided to decommission it. Probably in the second quarter of 1999 all 76 spent TRIGA fuel elements will be shipped to Idaho National Engineering and Environmental Laboratory (INEEL), USA, in one cask of type GNS 16. Due to technical reasons within the MHH a special Mobile Transfer System, which is being developed by the company Noell-KRC, will be used for reloading the fuel elements and transferring them from the reactor to the cask GNS 16. A description of the main components of this system as well as the process for transferring the fuel elements follows. (author)

  13. Our petroleum legacy: The Alberta story

    International Nuclear Information System (INIS)

    Bott, R.

    1992-11-01

    Background information is presented on the importance of the petroleum industry in Alberta. Alberta holds over 70% of Canada's coal and natural gas reserves and, if bitumen is included, over 90% of Canada's established oil reserves. Alberta's major exports are dominated by crude oil and related products ($9.6 billion in 1990) and the oil and gas sector had $15.7 billion in revenues in 1991, over 4 times as much as the next most important sector, agriculture. About 140,000 Albertans are directly or indirectly employed in the oil and gas industry, about 11% of employed persons. The industry's capital spending in Alberta was $5.3 billion in 1991, and its total expenditures were about $15 billion, and during the 1980s the industry paid about $42 billion to the Alberta government in the form of taxes, royalties, and other fees. Other benefits of the oil and gas industry's presence in Alberta include those related to its employment of a skilled workforce, its advanced research capabilities, and economic spinoff effects from employment and technological development. The influence of recent events on the industry is outlined, including the effects of international energy commodity markets, deregulation, and higher exploration and development costs. The declining financial viability of the Alberta petroleum industry is noted and its future is discussed in the light of such factors as oil prices, markets, new technologies, environmental constraints, and the volume of new discoveries. 9 refs., 5 figs., 1 tab

  14. Zap... Alberta is jolted by electric deregulation

    International Nuclear Information System (INIS)

    Howe, M.E.

    2001-01-01

    Of all Canadian provinces, Alberta has travelled the furthest along the electric deregulation road. On January 1, 2001, full retail competition came into effect. Wholesale electricity prices are set by the province through an auction process. The bids from purchasers are made through the Power Pool of Alberta against supply offers. Power prices increased from being amongst the lowest in the world to being amongst the highest in North America as a result of deregulation. Changes to the Electric Utilities Act were made recently by the Alberta government to try to mitigate the factors affecting power price increases. RBC Dominion Securities is of the opinion that the changes will not significantly impact the Alberta Pool Price. It is expected that the trend for power price increases to continue, despite some relief from relatively low-cost electricity being felt by other Canadian provinces as a result of the energy crisis in North America. Based on the Electric Competition Unfolds in Alberta report dated June 2, 2001 prepared by RBC Dominion Securities, this document examines the factors at play in electric price increases, assess the sustainability of current power prices in Alberta, and identify Canadian companies believed to be best positioned in the pipeline and gas and electric sectors to benefit from the high power prices in Alberta. Those companies were ATCO, Canadian Utilities, Westcoast Energy and TransCanada PipeLines, and TransAlta. 5 tabs., 5 figs

  15. Monitoring and Control Research Using a University Reactor and SBWR Test-Loop

    International Nuclear Information System (INIS)

    Edwards, Robert M.

    2003-01-01

    The existing hybrid simulation capability of the Penn State Breazeale nuclear reactor was expanded to conduct research for monitoring, operations and control. Hybrid simulation in this context refers to the use of the physical time response of the research reactor as an input signal to a real-time simulation of power-reactor thermal-hydraulics which in-turn provides a feedback signal to the reactor through positioning of an experimental changeable reactivity device. An ECRD is an aluminum tube containing an absorber material that is positioned in the central themble of the reactor kinetics were used to expand the hybrid reactor simulation (HRS) capability to include out-of-phase stability characteristics observed in operating BWRs

  16. Argon-41 production and evolution at the Oregon State University TRIGA Reactor (OSTR)

    International Nuclear Information System (INIS)

    Anellis, L.G.; Johnson, A.G.; Higginbotham, J.F.

    1988-01-01

    In this study, argon-41 concentrations were measured at various locations within the reactor facility to assess the accuracy of models used to predict argon-41 evolution from the reactor tank, and to determine the relationship between argon gas evolution from the tank and subsequent argon-41 concentrations throughout the reactor room. In particular, argon-41 was measured directly above the reactor tank with the reactor tank lids closed, at other accessible locations on the reactor top with the tank lids both closed and open, and at several locations on the first floor of the reactor room. These measured concentrations were then compared to values calculated using a modified argon-41 production and evolution model for TRIGA reactor tanks and ventilation values applicable to the OSTR facility. The modified model was based in part on earlier TRIGA models for argon-41 production and release, but added features which improved the agreement between predicted and measured values. The approximate dose equivalent rate due to the presence of argon-41 in reactor room air was calculated for several different locations inside the OSTR facility. These dose rates were determined using the argon-41 concentration measured at each specific location, and were subsequently converted to a predicted quarterly dose equivalent for each location based on the reactor's operating history. The predicted quarterly dose equivalent values were then compared to quarterly doses measured by film badges deployed as dose-integrating area radiation monitors at the locations of interest. The results indicate that the modified production and evolution model is able to predict argon-41 concentrations to within a factor of ten when compared to the measured data. Quarterly dose equivalents calculated from the measured argon-41 concentrations and the reactor's operating history seemed consistent with results obtained from the integrating area radiation monitors. Given the argon-41 concentrations measured

  17. Big and Little Feet Provincial Profiles: Alberta

    Directory of Open Access Journals (Sweden)

    Sarah Dobson

    2017-09-01

    Full Text Available This communiqué provides a summary of the production- and consumption-based greenhouse gas emissions accounts for Alberta, as well as their associated trade flows. It is part of a series of communiqués profiling the Canadian provinces and territories.1 In simplest terms, a production-based emissions account measures the quantity of greenhouse gas emissions produced in Alberta. In contrast, a consumption-based emissions account measures the quantity of greenhouse gas emissions generated during the production process for final goods and services that are consumed in Alberta through household purchases, investment by firms and government spending. Trade flows refer to the movement of emissions that are produced in Alberta but which support consumption in a different province, territory or country (and vice versa. For example, emissions associated with the production of Alberta crude oil that is exported to British Columbia for refining and sale as motor gasoline are recorded as a trade flow from Alberta to British Columbia. Moving in the opposite direction, emissions associated with the production of Saskatchewan crops that are exported to Alberta for processing and sale in Alberta grocery stores are recorded as a trade flow from Saskatchewan to Alberta. For further details on these results in a national context, the methodology for generating them and their policy implications, please see the companion papers to this communiqué series: (1 Fellows and Dobson (2017; and (2 Dobson and Fellows (2017. Additionally, the consumption emissions and trade flow data for each of the provinces and territories are available at: http://www.policyschool.ca/embodied-emissions-inputs-outputs-datatables-2004-2011/.

  18. Annual progress report of the University of Florida Training Reactor September 1, 1979-August 31, 1980

    International Nuclear Information System (INIS)

    Diaz, N.J.

    1980-11-01

    Reported are: reactor operation, modifications, maintenance and tests, changes to technical specifications and standard operating procedures, radioactive releases and environmental surveillance, and training utilization

  19. Outcrop - core correlation and seismic modeling of the Athabasca Oil Sands Deposit, Fort McMurray area, northeast Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Hein, F.J. [Alberta Geological Survey, Calgary, AB (Canada); Langenberg, C.W.; Cotterill, D.C.; Berhane, H. [Alberta Geological Survey, Edmonton, AB (Canada); Lawton, D.; Cunningham, J. [Calgary Univ., AB (Canada)

    1999-11-01

    A joint study between the Alberta Geological Survey and the University of Calgary was conducted which involved a detailed facies analysis of cores and outcrops from the Athabasca Oil Sands Deposit in Alberta`s Steepbank area. A unified facies classification for the deposit was developed. Larger scale facies associations were also determined, as well as proxy sonic logs for outcrops used in seismic modeling. The cores which were displayed exhibited detailed sedimentological and stratigraphic analysis of 10 outcrops in the area. 7 refs.

  20. Use of the TRIGA Reactor by the Radiochemistry Group of the Atominstitute of the Austrian Universities

    International Nuclear Information System (INIS)

    Bichler, M.; Buchtela, K.; Grass, F.; Ismail, S.

    1994-01-01

    The Radiochemistry Group of the Atominstitute of the Austrian Universities uses the TRIGA Mark II Reactor mainly for neutron activation analysis. Transport of samples to and from the irradiation positions in the reactor is performed by fast pneumatic transfer systems (transfer time 20 msec and 300 msec) and slow conventional transport facilities. Gamma-spectrometric instrumentation equipped with loss free counting systems is used to handle the high count rates up to 500 000 counts/sec. During the last years neutron activation analysis was applied to investigate environmental samples (soil, dust, incineration ash), geological samples (rocks, sediments, fossils, volcanic gases), biological materials (lichens, mushrooms and other plant materials, human diet, biological reference materials), raw materials (phosphate, coal) and archaeological materials (ancient glass). Lichen analysis was used for environmental monitoring. The content of some of the trace elements can be correlated with industrial activities, like manganese content with steel industry, the occurrence of vanadium and nickel with oil firing plants and stainless steel industry, selenium is found in lichen near coal firing plants. The amount of chlorine and sodium indicates the application of salt for road treatment during winter time, aluminum, scandium and hafnium content depends on the amount of dust in the environment. A further environmental application of neutron activation analysis is the determination of trace elements in volcanic gases. The halogens, arsenic, antimony, selenium, tellurium and mercury were determined and their daily output was calculated. The distribution of trace elements in fossils of known age gives us a geochemical key to condition and development of the paleo-environment. For this purpose we determined rare earth elements in 250 million years old microfossils (conodonts). Neutron activation analysis served also for some non scientific but nevertheless useful purposes: Organic

  1. Safety evaluation report related to the renewal of the operating license for the University of New Mexico Research Reactor (Docket No. 50-252)

    International Nuclear Information System (INIS)

    1987-03-01

    This Safety Evaluation Report for the application filed by the University of New Mexico (UNM) for renewal of Operating License No. R-102 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the campus of the University of New Mexico in Albuquerque, New Mexico. The staff concludes that the reactor can continue to be operated by the University of New Mexico without endangering the health and safety of the public. 7 refs., 7 figs., 2 tabs

  2. Safety-evaluation report related to renewal of the operating license for the Texas A and M University Research Reactor. Docket No. 50-128, License R-83

    International Nuclear Information System (INIS)

    1983-03-01

    This Safety Evaluation Report for the application filed by the Texas A and M University (Texas A and M) for a renewal of operating license number R-83 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Texas Engineering and Experiment Station of the Texas A and M University and is located on the campus in College Station, Brazos County, Texas. The staff concludes that the TRIGA reactor facility can continue to be operated by Texas A and M University without endangering the health and safety of the public

  3. Safety Evaluation Report related to the renewal of the operating license for the TRIGA training and research reactor at the University of Arizona (Docket No. 50-113)

    International Nuclear Information System (INIS)

    1990-05-01

    This Safety Evaluation Report for the application filed by the University of Arizona for the renewal of Operating License R-52 to continue operating its research reactor at an increased operating power level has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the University of Arizona campus in Tucson, Arizona. The staff concludes that the reactor can continue to be operated by the University of Arizona without endangering the health and safety of the public. 20 refs., 8 figs., 5 tabs

  4. Safety Evaluation Report related to the renewal of the operating license for the research reactor at Michigan State University (Docket No. 50-294)

    International Nuclear Information System (INIS)

    1984-08-01

    This Safety Evaluation Report for the application filed by the Michigan State University (MSU) for a renewal of operating license number R-114 to continue to operate the TRIGA Mark I research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Michigan State University and is located on the campus of Michigan State University in East Lansing, Ingham County, Michigan. The staff concludes that the TRIGA reactor facility can continue to be operated by MSU without endangering the health and safety of the public

  5. Safety Evaluation Report related to the renewal of the operating license for the training and research reactor at the University of Lowell (Docket No. 50-223)

    International Nuclear Information System (INIS)

    1985-11-01

    This Safety Evaluation Report for the application filed by the University of Lowell (UL) for renewal of operating license number R-125 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the North Campus of the University of Lowell in Lowell, Massachusetts. The staff concludes that the reactor can continue to be operated by the University of Lowell without endangering the health and safety of the public

  6. Safety evaluation report related to the renewal of the operating license for the University of Oklahoma Research Reactor (Docket No. 50-112)

    International Nuclear Information System (INIS)

    1983-09-01

    This Safety Evaluation Report for the application filed by the University of Oklahoma for a renewal of Operating License R-53 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Oklahoma and is located on the campus in Norman, Cleveland County, Oklahoma. The staff concludes that the Aerojet General Nucleonics (AGN) reactor facility can continue to be operated by University of Oklahoma without endangering the health and safety of the public

  7. University of Wisconsin Nuclear Reactor Laboratory annual report, 1981-1982

    International Nuclear Information System (INIS)

    1982-01-01

    Information is presented concerning operations at the UWNR reactor; operating statistics and fuel exposure; emergency shutdowns and inadvertent scrams; maintenance operations; radioactive waste disposal; summary of radiation exposures; results of environmental studies; and publications and presentations on work based on reactor use

  8. A design study on hyper-thermal neutron irradiation field for neutron capture therapy at Kyoto University Reactor

    International Nuclear Information System (INIS)

    Sakurai, Y.; Kobayashi, T.

    2000-01-01

    A study about the installation of a hyper-thermal neutron converter to a clinical collimator was performed, as a series of the design study on a hyper-thermal neutron irradiation field at the Heavy Water Neutron Irradiation Facility of Kyoto University Reactor. From the parametric-surveys by Monte Carlo calculation, it was confirmed that the practical irradiation field of hyper-thermal neutrons would be feasible by the modifications of the clinical collimator and the bismuth-layer structure. (author)

  9. Experimental determination of the total isothermal reactivity feedback coefficient for the University of Arizona TRIGA research reactor

    International Nuclear Information System (INIS)

    Spriggs, Gregory D.; Nelson, George W.

    1976-01-01

    An experiment was performed to measure the total isothermal (or bath) feedback coefficient of reactivity for the University of Arizona TRIGA Research Reactor (UARR). It was found that the bath coefficient was temperature-dependent and may be represented by the expression α iso .2634 x 10 -2 + .3428 x 10 -3 T - 2.471 x 10 -5 T 2 + 3.476 x 10 -7 T 3 for the temperature range of 7 C to 43 C. (author)

  10. Technical basis in support of the conversion of the University of Missouri Research Reactor (MURR) core from highly-enriched to low-enriched uranium - core neutron physics

    Energy Technology Data Exchange (ETDEWEB)

    Stillman, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Feldman, E. [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Foyto, L [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Kutikkad, K [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; McKibben, J C [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Peters, N. [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Stevens, J. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2012-09-01

    This report contains the results of reactor design and performance for conversion of the University of Missouri Research Reactor (MURR) from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL) and the MURR Facility. The core conversion to LEU is being performed with financial support of the U. S. government.

  11. Devonian lithofacies and reservoir styles in Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Krause, F.F.; Burrowes, O.G. (eds.)

    1987-01-01

    This conference presented papers on the stratigraphy, paleogeography, and geologic history of Devonian lithofacies of the Wabamun, Winterburn, Woodbend, Beaverhill Lake, and Elk Point Groups in Alberta. Separate abstracts were prepared for twelve papers of this conference.

  12. Reorganization of the radiologic protection of the nuclear reactor RA-0 for the next starting up at Cordoba National University

    International Nuclear Information System (INIS)

    Martin, H.R.; Chautemps, N.A.; Rumis, D.A.

    1991-01-01

    Due to the fulfillment to the tasks for the new starting up of the RA-0 Nuclear Reactor situated at the National University of Cordoba, it was necessary to plan and organize the service of Radiologic Protection to meet the future requirements in normal operation. The special characteristics that an installation of this type has in the university field, required special attention for making the university staff become aware in the working proceedings to follow up in normal conditions, such as the case of emergency that would originate in the installation. The training of the teaching and non teaching staff of the National University of Cordoba, the adjusting of the installations, the obtention of dosimetry and measurement equipment and the implementation of a monitor system of the staff were the main tasks confronted for the reorganization of the sector. (Author) [es

  13. Operation of the low power reactor assembly in the University of Illinois TRIGA bulk shielding facility

    International Nuclear Information System (INIS)

    Beck, G.P.; Thayer, G.

    1972-01-01

    The Low Power Reactor Assembly (LOPRA) is a rectangular assembly of TRIGA fuel elements located in the bulk shielding facility of the Illinois Advanced TRIGA Reactor (TRIGA). The LOPRA is coupled to the TRIGA by a thermal column that extends from the TRIGA core to the bulk shielding facility. The LOPRA will be utilized for studying steady-state and transient coupling between the two reactors. Spatial variations in the flux at the LOPRA will be measured for different operating conditions of the TRIGA. These measurements will be made with both systems in low power critical states or in subcritical states

  14. Status of social economy provision of wind electric energy in Alberta

    Energy Technology Data Exchange (ETDEWEB)

    MacArthur, J. [Simon Fraser University, Vancouver, BC (Canada)

    2010-01-15

    The development of cooperatives in Canada's energy sector has been mapped and studied through research performed by a doctoral candidate in Political Science at Simon Fraser University. This document has been prepared as part of the research program of the BC-Alberta Social Economy Research Alliance (BALTA). 34 refs.

  15. Knowledge, Power, and Social Policy: John M. MacEachran and Alberta's 1928 Sexual Sterilization Act

    Science.gov (United States)

    Puplampu, Korbla P.

    2008-01-01

    This article examines how academic knowledge and power have shaped the discourse on human classification and how political authorities use academic knowledge producers to legitimize public policy. Specifically, the article draws on the role of John M. MacEachran, a former academic at the University of Alberta, in the implementation of the Alberta…

  16. Safety-evaluation report related to the renewal of the operating license for the research reactor at the Iowa State University (Docket No. 50-116)

    International Nuclear Information System (INIS)

    1983-09-01

    This Safety Evaluation Report for the application filed by the Iowa State University (ISU) for a renewal of the Class 104 Operating License R-59 to continue to operate its Argonaut-type research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Iowa State University, and is located on the ISU campus in Ames, Story County, Iowa. The staff concludes that the reactor facility can continue to be operated by ISU without endangering the health and safety of the public. The principal matters reviewed are: design, testing, and performance of the reactor components and systems; the expected consequences of credible accidents; the licensee's management organization; the method used for the control of radiological effluents; the licensee's technical specifications; financial data and information; the physical protection program; procedures for training reactor operators; and emergency plans. 11 references, 15 figures, 13 tables

  17. Experimental and MCNP5 based evaluation of neutron and gamma flux in the irradiation ports of the University of Utah research reactor

    Directory of Open Access Journals (Sweden)

    Noble Brooklyn

    2012-01-01

    Full Text Available Neutron and gamma flux environment of various irradiation ports in the University of Utah training, research, isotope production, general atomics reactor were experimentally assessed and fully modeled using the MCNP5 code. The experimental measurements were based on the cadmium ratio in the irradiation ports of the reactor, flux profiling using nickel wire, and gamma dose measurements using thermo luminescence dosimeter. Full 3-D MCNP5 reactor model was developed to obtain the neutron flux distributions of the entire reactor core and to compare it with the measured flux focusing at the irradiation ports. Integration of all these analysis provided the updated comprehensive neutron-gamma flux maps of the existing irradiation facilities of the University of Utah TRIGA reactor.

  18. Safety Evaluation Report related to the renewal of the operating license for the TRIGA training and research reactor at the University of Utah (Docket No. 50-407)

    International Nuclear Information System (INIS)

    1985-03-01

    This Safety Evaluation Report for the application filed by the University of Utah (UU) for a renewal of operating license R-126 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Utah and is located on its campus in Salt Lake City, Salt Lake County, Utah. The staff concludes that this training reactor facility can continue to be operated by UU without endangering the health and safety of the public

  19. Safety-evaluation report related to the renewal of the operating license for the Cornell University TRIGA Research Reactor. Docket No. 50-157

    International Nuclear Information System (INIS)

    1983-08-01

    This Safety Evaluation Report for the application filed by the Cornell University for a renewal of Operating License R-80 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by Cornell University and is located on the Cornell campus in Ithaca, New York. The staff concludes that the TRIGA reactor facility can continue to be operated by Cornell without endangering the health and safety of the public

  20. Safety evaluation report related to the renewal of the operating license for the research reactor at the University of Florida. Docket No. 50-83

    International Nuclear Information System (INIS)

    1982-05-01

    This Safety Evaluation Report for the application filed by the University of Florida (UF) for a renewal of Operating License R-56 to continue to operate its Argonaut-type research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Florida and is located on the UF campus in Gainesville, Alachua County, Florida. The staff concludes that the reactor facility can continue to be operated by UF without endangering the health and safety of the public

  1. Safety evaluation report related to the renewal of the operating license for the training and research reactor at the University of Maryland (Docket No. 50-166)

    International Nuclear Information System (INIS)

    1984-03-01

    This Safety Evaluation Report for the application filed by the University of Maryland (UMD) for a renewal of operating license R-70 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Maryland and is located at a site in College Park, Prince Georges County, Maryland. The staff concludes that this training reactor facility can continue to be operated by UMD without endangering the health and safety of the public

  2. Safety evaluation report related to the renewal of the operating license for the Washington State University TRIGA reactor. Docket No. 50-27

    International Nuclear Information System (INIS)

    1982-05-01

    This Safety Evaluation Report for the application filed by the Washington State University (WSU) for a renewal of operating license number R-76 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Washington State University and is located on the WSU campus in Pullman, Whitman County, Washington. The staff concludes that the TRIGA reactor facility can continue to be operated by WSU without endangering the health and safety of the public

  3. Radioisotope radiotherapy research and achievements at the University of Missouri research reactor

    International Nuclear Information System (INIS)

    Ehrhardt, G.J.; Ketring, A.R.; Cutler, C.S.

    2002-01-01

    The University of Missouri Research Reactor (MURR) along with various other departments of the University of Missouri have been involved for many years in developing new means of internal radioisotopic therapy for cancer. These efforts have centered on methods of targeting radioisotopes such as brachytherapy, embolization of liver tumors with radioactive microspheres, small molecule-labeled chelate guidance for the treatment of bone cancer, and various means of radioimmunotherapy or labeled receptor agent targeting. All of this medical research and practical application of radioisotope therapy has been built on MURR's high neutron flux and outstanding reliability of operation, as well as MURR's flexibility in meeting the needs of researchers and the radiopharmaceutical industry. For many years MURR has produced Au-198 and Ir-192 wires for subsequent fabrication into brachytherapy sources for treatment of isolated tumors. An extension of this approach is embodied in Y-90 TheraSphere, which consists of Y-89-containing glass microspheres which are activated to contain Y-90 and injected in the blood supply of liver tumors. This approach leads to embolisation and very high radiation doses to tumor with minimal side effects, and is currently in use at six centers in the U.S. MURR has been instrumental in the development of bone agents such as Re-186 HEDP and Sm-153 Quadramet, the latter of which is now an approved drug for palliation of the pain from metastatic bone cancer. A related development is MURR's participation in trials using Ho-166 DOP to ablate diseased bone marrow in patients afflicted with multiple myeloma prior to reinfusion of cleansed, autologous marrow. This procedure has passed Phase I and II trials in the U.S., achieving approx. 50% complete remissions in multiple myeloma patients. MURR is currently upgrading its facilities to meet U.S. Food and Drug Administration (FDA) Current Good Manufacturing Practices (cGMP) requirements for Phase III of this

  4. Safety evaluation report related to the construction permit and operating license for the research reactor at the University of Texas (Docket No. 50-602)

    International Nuclear Information System (INIS)

    1992-01-01

    The Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to NUREG-1135, ''Safety Evaluation Report Related to the Construction Permit and Operating License for the Research Reactor at the University of Texas'' (SER) May 1985. The reactor facility is owned by The University of Texas at Austin (UT, the applicant) and is located at the University's Balcones Research Center in Austin, Texas. This supplement to the SER (SSER) describes the changes to the reactor facility design from the description in the SER. The SER and SSER together reflect the facility as built. The SSER also documents the reviews that the NRC has completed regarding the applicant's emergency plan, security plan, and technical specifications that were identified as open in the SER

  5. Alberta's clean energy future

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This paper deals with the future of clean energy in Alberta. With the present economic growth of the oil sands industry in Alberta, it is expected that there will be very considerable increases in job opportunities and GDP in both Canada and US. The challenges include high-energy demand and reduction of the carbon footprint. Alberta has adopted certain approaches to developing renewable and alternate forms of energy as well as to increasing the efficiency of present energy use and raising environmental consciousness in energy production. Three areas where the effects of clean energy will be felt are energy systems, climate change, and regional impacts, for instance on land, water, and wildlife. Alberta's regulatory process is shown by means of a flow chart. Aspects of oil sands environmental management include greenhouse gas targets, air quality assurance, and water quality monitoring, among others. Steps taken by Alberta to monitor and improve air quality and water management are listed. In conclusion, the paper notes that significant amounts of money are being pumped into research and development for greenhouse gas and water management projects.

  6. Ten years's reactor operation at the Technical University Zittau - operation report

    International Nuclear Information System (INIS)

    Konschak, K.

    1990-01-01

    The Zittau Training and Research Reactor ZLFR is in use for purposes of teaching the engineers who will operate the nuclear power plants in the GDR since 10 years. Since commissioning it was started up more than 1600 times, approximately two thirds of the start-ups being utilized for purposes of teaching. A number of teaching experiments were installed that demonstrate fundamental technological processes in nuclear reactors in a manner easy to understand. The high level of nuclear safety manifests itself, among other things, in extremely low radiation exposures of the operating personal and the persons to be trained. (author)

  7. Irradiation positions for fission-track dating in the University of Pavia TRIGA Mark II nuclear reactor

    International Nuclear Information System (INIS)

    Oddone, Massimo; Meloni, Sandro; Balestrieri, Maria Laura; Bigazzi, Giulio

    2002-01-01

    An irradiation position arranged is described in the present paper for fission-track dating in the Triga Mark II reactor of the University of Pavia. Fluence values determined using the NIST glass standard SRM 962a for fission-track dating and the traditional metal foils are compared. Relatively good neutron thermalization (φ th /φ f = 0.956) and lack of significant fluence spatial gradients are good factors for fission-track dating. Finally, international age standards (or putative age standards) irradiated in this new position yielded results consistent with independent reference ages. (author)

  8. The Southern Alberta Information Resources (SAIR Project

    Directory of Open Access Journals (Sweden)

    Kathy Crewdson

    2008-06-01

    Full Text Available Abstract Southern Alberta Information Resources (SAIR is a collaborative bibliography of published resources significant to southern Alberta. Objectives and progress with evolving methodology, technology, issues and challenges are explored within the context of the library field. We investigate a collaborative digital library that allows librarians and non-librarians alike to share information on specific topics through MARC records. An outcome of a collaborative digital library is how to create and sustain interest within the library community. Southern Alberta region was selected based on the authors’ familiarity with the region. Some issues and questions remain to be resolved. Digital formats present a number of challenges in terms of selection and presentation. Legal issues relating to technology such as linking and location information have emerged. Basic technical issues remain, such as, how best to update links.

  9. Safety evaluation report related to the renewal of the operating license for the research reactor at North Carolina State University

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    This safety evaluation report (SER) summarizes the findings of a safety review conducted by the staff of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR). The staff conducted this review in response to a timely application filed by North Carolina State University (the licensee or NCSU) for a 20-year renewal of Facility Operating License R-120 to continue to operate the NCSU PULSTAR research reactor. The facility is located in the Burlington Engineering Laboratory complex on the NCSU campus in Raleigh, North Carolina. In its safety review, the staff considered information submitted by the licensee (including past operating history recorded in the licensee`s annual reports to the NRC), as well as inspection reports prepared by NRC Region H personnel and first-hand observations. On the basis of this review, the staff concludes that NCSU can continue to operate the PULSTAR research reactor, in accordance with its application, without endangering the health and safety of the public. 16 refs., 31 figs., 7 tabs.

  10. Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia

    Science.gov (United States)

    Bortolussi, S.; Protti, N.; Ferrari, M.; Postuma, I.; Fatemi, S.; Prata, M.; Ballarini, F.; Carante, M. P.; Farias, R.; González, S. J.; Marrale, M.; Gallo, S.; Bartolotta, A.; Iacoviello, G.; Nigg, D.; Altieri, S.

    2018-01-01

    University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steady state power of 250 kW. It has been used for many years to support Boron Neutron Capture Therapy (BNCT) research. An irradiation facility was constructed inside the thermal column of the reactor to produce a sufficient thermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiation position, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated after borated drug administration. The facility is currently used for cell cultures and small animal irradiation. Measurements campaigns have been carried out, aimed at characterizing the neutron spectrum and the gamma dose component. The neutron spectrum has been measured by means of multifoil neutron activation spectrometry and a least squares unfolding algorithm; gamma dose was measured using alanine dosimeters. Results show that in a reference position the thermal neutron flux is (1.20 ± 0.03) ×1010 cm-2 s-1 when the reactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2 and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to the thermal neutron fluence is 1.2 ×10-13 Gy/(n/cm2).

  11. Safety evaluation report related to the renewal of the operating license for the research reactor at North Carolina State University

    International Nuclear Information System (INIS)

    1997-04-01

    This safety evaluation report (SER) summarizes the findings of a safety review conducted by the staff of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR). The staff conducted this review in response to a timely application filed by North Carolina State University (the licensee or NCSU) for a 20-year renewal of Facility Operating License R-120 to continue to operate the NCSU PULSTAR research reactor. The facility is located in the Burlington Engineering Laboratory complex on the NCSU campus in Raleigh, North Carolina. In its safety review, the staff considered information submitted by the licensee (including past operating history recorded in the licensee's annual reports to the NRC), as well as inspection reports prepared by NRC Region H personnel and first-hand observations. On the basis of this review, the staff concludes that NCSU can continue to operate the PULSTAR research reactor, in accordance with its application, without endangering the health and safety of the public. 16 refs., 31 figs., 7 tabs

  12. The analysis and attribution of the time-dependent neutron background resultant from sample irradiation in a SLOWPOKE-2 reactor

    International Nuclear Information System (INIS)

    Sellers, M.T.; Corcoran, E.C.; Kelly, D.G.

    2013-01-01

    The Royal Military College of Canada (RMCC) has commissioned a Delayed Neutron Counting (DNC) system for the analysis of special nuclear materials. A significant, time-dependent neutron background with an initial maximum count rate, more than 50 times that of the time-independent background, was characterised during the validation of this system. This time-dependent background was found to be dependent on the presence of the polyethylene (PE) vials used to transport the fissile samples, yet was not an activation product of vial impurities. The magnitude of the time-dependent background was found to be irradiation site specific and independent of the mass of PE. The capability of RMCC's DNC system to analyze the neutron count rates in time intervals 235 U contamination was present on each irradiated vial. However, Inductively Coupled Plasma-Mass Spectroscopy measurements of material leached from the outer vial surfaces after their irradiations found only trace amounts of uranium, 0.118 ± 0.048 ng of 235 U derived from natural uranium. These quantities are insufficient to account for the time-independent background, and in fact could not be discriminated from the noise associated with time-independent background. It is suggested that delayed neutron emitters are deposited in the vial surface following fission recoil, leaving the main body of uranium within the irradiation site. This hypothesis is supported by the physical cleaning of the site with materials soaked in distilled water and HNO 3 , which lowered the background from a nominal 235 U mass equivalent of 120 to 50 ng per vial. (author)

  13. Scottish Universities Research and Reactor Centre, East Kilbride. Report on session 1982-1983

    International Nuclear Information System (INIS)

    Wilson, H.W.

    1984-01-01

    The activities over the 1982-3 session are reviewed and all the research projects listed. These include reactor related activities (physics and radiochemistry, health physics and nuclear medicine and engineering), those of the isotope geology unit and NERC radiocarbon laboratory, the computing department and the teaching programme. The demand for irradiations, particularly for activation analysis has continued. There was no major maintenance shut-down in the year. (U.K.)

  14. Accident Analyses for Conversion of the University of Missouri Research Reactor (MURR) from Highly-Enriched to Low-Enriched Uranium

    Energy Technology Data Exchange (ETDEWEB)

    Stillman, J. A. [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Div., Research and Test Reactor Dept.; Feldman, E. E. [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Div., Research and Test Reactor Dept.; Wilson, E. H. [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Div., Research and Test Reactor Dept.; Foyto, L. P. [Univ. of Missouri, Columbia, MO (United States). Research Reactor; Kutikkad, K. [Univ. of Missouri, Columbia, MO (United States). Research Reactor; McKibben, J. C. [Univ. of Missouri, Columbia, MO (United States). Research Reactor; Peters, N. J. [Univ. of Missouri, Columbia, MO (United States). Research Reactor; Cowherd, W. M. [Univ. of Missouri, Columbia, MO (United States). College of Engineering, Nuclear Engineering Program; Rickman, B. [Univ. of Missouri, Columbia, MO (United States). College of Engineering, Nuclear Engineering Program

    2014-12-01

    This report contains the results of reactor accident analyses for the University of Missouri Research Reactor (MURR). The calculations were performed as part of the conversion from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL), the MURR Facility, and the Nuclear Engineering Program – College of Engineering, University of Missouri-Columbia. The core conversion to LEU is being performed with financial support from the U. S. government. This report contains the results of reactor accident analyses for the University of Missouri Research Reactor (MURR). The calculations were performed as part of the conversion from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL), the MURR Facility, and the Nuclear Engineering Program – College of Engineering, University of Missouri-Columbia. The core conversion to LEU is being performed with financial support from the U. S. government. In the framework of non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context most research and test reactors, both domestic and international, have started a program of conversion to the use of LEU fuel. A new type of LEU fuel based on an alloy of uranium and molybdenum (U-Mo) is expected to allow the conversion of U.S. domestic high performance reactors like MURR. This report presents the results of a study of core behavior under a set of accident conditions for MURR cores fueled with HEU U-Alx dispersion fuel or LEU monolithic U-Mo alloy fuel with 10 wt% Mo

  15. Alberta industrial synergy CO2 programs initiative

    International Nuclear Information System (INIS)

    Yildirim, E.

    1998-01-01

    The various industrial sectors within Alberta produce about 350,000 tonnes of CO 2 per day. This presentation was concerned with how this large volume and high concentration of CO 2 can be used in industrial and agricultural applications, because every tonne of CO 2 used for such purposes is a tonne that does not end up in the atmosphere. There is a good potential for an industrial synergy between the producers and users of CO 2 . The Alberta Industrial Synergy CO 2 Programs Initiative was established to ultimately achieve a balance between the producers of CO 2 and the users of CO 2 by creating ways to use the massive quantities of CO 2 produced by Alberta's hydrocarbon-based economy. The Alberta CO 2 Research Steering Committee was created to initiate and support CO 2 programs such as: (1) CO 2 use in enhanced oil recovery, (2) creation of a CO 2 production inventory, (3) survey of CO 2 users and potential users, (4) investigation of process issues such as power generation, oil sands and cement manufacturing, and (5) biofixation by plants, (6) other disposal options (e.g. in depleted oil and gas reservoirs, in aquifers, in tailings ponds, in coal beds). The single most important challenge was identified as 'rationalizing the formation of the necessary infrastructure'. Failing to do that will greatly impede efforts directed towards CO 2 utilization

  16. Technical Report on Alberta Essay Scales: Models.

    Science.gov (United States)

    Nyberg, Verner R.; Nyberg, Adell M.

    The supplementary information on "Alberta Essay Scales: Models" presented here includes similar models to employ in grading essays, the background and development of the scales, and the rationale for developing two scales of English mechanics and style/content. A standard is presented for evaluating current writing achievement by…

  17. Reliability of the Alberta Essay Scales.

    Science.gov (United States)

    Nyberg, V. R.; Nyberg, A. M.

    1980-01-01

    A respectable reliability of scoring twelfth-grade essays can be achieved through the use of essay models in the two Alberta Essay Scales (style-content and mechanics). The scales can assist classroom teachers in the day-to-day scoring of essays by providing a constant standard. (Author/SB)

  18. A Guide to Native Communities in Alberta.

    Science.gov (United States)

    Alberta Dept. of Native Affairs, Edmonton.

    Profiles of 83 Native communities, Indian bands, and Metis settlements in rural Alberta provide overviews of human and material resources. Included for each community are information on location, size, history, population, economic base, transportation, physical infrastructure, services, education, communications, local government, and community…

  19. Alberta air emissions : trends and projections

    International Nuclear Information System (INIS)

    2008-06-01

    This paper provided a summary of air emissions trends and projections for Alberta. Predicted regional distribution trends and industry sector emissions were presented. Historical and projected emissions included sulfur oxides (SO x ) nitrogen oxide (NO x ), volatile organic compounds (VOCs), and ammonia (NH 3 ). Results of the study indicated that carbon monoxide (CO) emissions were decreasing, while VOCs, NO x , SO x , PM 2.5 and NH 3 levels were increasing. Approximately 9 per cent of ammonia emissions were from point sources, while the majority of PM 2.5 emissions were attributed to unpaved roads and construction operations. Agricultural animal operations accounted for most of the VOC source emissions in the region. Increased development of the oil sands industry is contributing to increases in VOC emissions. Increases in NH 3 were attributed to growth in the agricultural sector and the increasing use of confined feeding operations in the region. Results of the study indicated that greenhouse gas (GHG) emissions in Alberta will keep increasing as a result of Alberta's growing economy. It was concluded that emissions from other industrial sectors are also expected to increase. In 2005, Alberta's total GHG emissions were 233 megatonnes of CO 2 equivalent, of which 168 megatonnes were attributed to industry. Results were presented in both graph and tabular formats. 3 tabs., 25 figs

  20. Calculation of the Activity Inventory for the TRIGA Reactor at the Medical University of Hannover (MHH) in Preparation for Dismantling the Facility

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, G.; Scheller, F.; Bernnat, W.; Pfister, G.; Klaux, U.; Gerhards, E.

    2002-02-25

    It is planned to dismantle the TRIGA reactor facility at the Medical University of Hannover (MHH). Radioactive waste resulting from this dismantling will be disposed of externally, any remaining materials as well as the building structures will then be measured to ensure there is no residual activity. In preparation for this and to plan the techniques which will be used to dismantle the reactor, calculations were made in order to determine the amount of activity and the dose rates for the reactor tank and its inside components as well as for the biological shield and its radial beam tube.

  1. Did you know? Petroleum industry fast facts : Alberta

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    A brief summary of Alberta`s petroleum industry is provided. In 1997, capital expenditures from the petroleum industry into Alberta`s economy were more than $13 billion. The province is the largest crude oil and natural gas producer in Canada, employing some 215,000 people across the province. Of these 165,00 are directly, or indirectly employed in upstream activities, and about 50,000 in downstream activities, including pipeline transportation. The industry utilizes an extensive pipeline network with nearly 260,000 kilometres of pipeline serving local, national and international markets. The Alberta oil sands have more than 300 billion barrels of potential recoverable deposits, comparable to the proven reserves in Saudi Arabia. Crude oil and natural gas make up nearly 56 per cent of Alberta`s exports. In 1997, the province supplied almost 12 per cent of the U.S. natural gas consumption. 3 figs.

  2. The contribution of a small triga university research reactor to nuclear research on an international level

    International Nuclear Information System (INIS)

    Villa, M.; Boeck, H.; Weber, H.W.

    2001-01-01

    The paper focuses especially on the important results in neutron- and solid state physics and the co-operation between the low power TRIGA reactor with high flux neutron sources in Europe such as the Institute Laue-Langevin (ILL) in Grenoble, the Paul Scherrer Institut (PSI) in Villigen, the Rutherford Appleton Laboratory (RAL) in Didcot and the Research Center Juelich. Experiments are set up for test purposes at the TRIGA reactor and then transferred to the powerful neutron sources. Different new perfect silicon channel-cut and interferometer crystals are prepared and then tested at the Bonse-Hart camera, which is a double crystal (or triple axis) diffractometer and at the interferometer set-up. Historically, the first verification of neutron interferometry at a perfect crystal device has been achieved at the 250 kW TRIGA-reactor in Vienna in the year 1974. Also the co-operation with the PSI and the TU Munich in the field of neutron radiography and neutron tomography and VESTA, an experiment for storing cold neutrons with a wavelength of 6.27 A, installed at the pulsed neutron source ISIS at RAL will be mentioned. The second topic treated in this paper shows the international co-operation in the field of superconductors. This research work is carried out under two European TMR-Network programs. The third topic in this paper focuses on the co-operation in the field of safeguard. Several projects have been carried out during the past years in co-operation with the IAEA such as establishing a gamma spectrum reference catalogue for CdZnTe detectors and tests of safeguard video cameras under neutron irradiation. Further an integrated safeguard surveillance network composed of a video camera, a gamma monitor and a neutron monitor is under development. (orig.)

  3. The contribution of a small TRIGA university research reactor to nuclear research on an international level

    International Nuclear Information System (INIS)

    Villa, M.; Bastuerk, M.; Boeck, H.

    2002-01-01

    The paper focuses especially on the important results in neutron- and solid state physics and the co-operation between the low power TRIGA reactor with high flux neutron sources in Europe such as the Institute Laue-Langevin (ILL) in Grenoble, the Paul Scherrer Institut (PSI) in Villigen, the Rutherford Appleton Laboratory (RAL) in Didcot and the Research Center Juelich. Experiments are set up for test purposes at the TRIGA reactor and then transferred to the powerful neutron sources. Different new perfect silicon channel-cut and interferometer crystals are prepared and then tested at the Bonse-Hart camera, which is a double crystal (or triple axis) diffractometer and at the interferometer set-up. Historically, the first verification of neutron interferometry at a perfect crystal device has been achieved at the 250 kW TRIGA-reactor in Vienna in the year 1974. Also the co-operation with the PSI and the TU Munich in the field of neutron radiography and neutron tomography and VESTA, an experiment for storing cold neutrons with a wavelength of 6.27A, installed at the pulsed neutron source ISIS at RAL are mentioned. The second topic in this paper focuses on the co-operation in the field of safeguard. Several projects have been carried out during the past years in co-operation with the IAEA such as establishing a gamma spectrum reference catalogue for CdZnTe detectors and tests of safeguard video cameras under neutron irradiation. Further an integrated safeguard surveillance network composed of a video camera, a gamma monitor and a neutron monitor is under development

  4. Utilization of a typical 250 kW TRIGA Mark II reactor at a University

    International Nuclear Information System (INIS)

    Villa, M.; Boeck, H.; Musilek, A.

    2007-01-01

    The 250 kW TRIGA Mark-II reactor operates since March 1962 at the Atominstitut Vienna/Austria. Its main tasks are nuclear education and training in the fields of neutron- and solid state physics, nuclear technology, reactor safety, radiochemistry, radiation protection and dosimetry, and low temperature physics and fusion research. Academic research is carried out by students in the above mentioned fields coordinated and supervised by about 70 staff members with the aim of a masters- or PhD degree in one of the above mentioned areas. During the past 15 years about 580 students graduated through the Atominstitut. In addition, the Atominstitut co-operates closely with the nearby located IAEA in research projects, coordinated research programs (CRP) and supplying expert services. Regular training courses are carried out for the IAEA for Safeguard Trainees, fellowship places are offered for scientists from developing countries and staff members carry out expert missions to research centres in Africa, Asia and South America. Special Nuclear Material (SNM) is stored for calibration purposes at the Atominstitut belonging to the IAEA. (author)

  5. Ohio State University reactor sharing program. Progress report, September 1, 1980-April 30, 1981

    International Nuclear Information System (INIS)

    1981-01-01

    The utilization of the OSURR and GRSS by colleges and universities is summarized. Two student laboratory exercises were developed during this period and are included: control rod calibration and approach to critical

  6. Safety evaluation report related to the renewal of the operating license for the Zero-Power Reactor at Cornell University, Docket No. 50-97

    International Nuclear Information System (INIS)

    1983-09-01

    This Safety Evaluation Report for the application filed by Cornell University (CU) for a renewal of Operating License R-80 to continue to operate a zero-power reactor (ZPR) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by Cornell University and is located on the Cornell campus in Ithaca, New York. The staff concludes that the ZPR facility can continue to be operated by CU without endangering the health and safety of the public

  7. Initial test results of the Omron face cue entry system at the University of Missouri-Rolla Reactor

    International Nuclear Information System (INIS)

    Tokuhiro, Akira T.; Vaughn, Brian J.

    2004-01-01

    The University of Missouri-Rolla Reactor facility is testing, in collaboration with Omron Transaction Systems, Inc., the Omron Face Cue facial recognition system for access control to its restricted area. The installation of this system is the first of its kind at a security-relevant facility in the U.S. and within the research reactor community. The Face Cue is an on-demand device based on facial recognition and storage technology. The image processing methodology is as follows: (1) facial position detection, (2) background elimination, (3) facial features discrimination via application of a wavelet transform. The extracted facial feature values are compared to the data archived in its database and access is provided upon meeting the authorization criteria. The current test phase consisted of assessing the functionality of the Face Cue during daily use and in terms of its robustness (flexibility) as a function of the following physical parameters: (1) subject's distance away from the Face Cue, (2) ambient lighting conditions, (3) subject's facial orientation, (4) subject's facial expression and (5) peripheral facial features/modifications. The system has operated at nearly 100% reliability during several test intervals with approximately 7,000 entry attempts to date. (author)

  8. Chemical Reactors.

    Science.gov (United States)

    Kenney, C. N.

    1980-01-01

    Describes a course, including content, reading list, and presentation on chemical reactors at Cambridge University, England. A brief comparison of chemical engineering education between the United States and England is also given. (JN)

  9. Gaia Assorted Mass Binaries Long Excluded from SLoWPoKES (GAMBLES): Identifying Ultra-wide Binary Pairs with Components of Diverse Mass

    Energy Technology Data Exchange (ETDEWEB)

    Oelkers, Ryan J.; Stassun, Keivan G.; Dhital, Saurav, E-mail: ryan.j.oelkers@vanderbilt.edu [Vanderbilt University, Department of Physics and Astronomy, Nashville, TN 37235 (United States)

    2017-06-01

    The formation and evolution of binary star systems are some of the remaining key questions in modern astronomy. Wide binary pairs (separations >10{sup 3} au) are particularly intriguing because their low binding energies make it difficult for the stars to stay gravitationally bound over extended timescales, and thus to probe the dynamics of binary formation and dissolution. Our previous SLoWPoKES catalogs, I and II, provided the largest and most complete sample of wide-binary pairs of low masses. Here we present an extension of these catalogs to a broad range of stellar masses: the Gaia Assorted Mass Binaries Long Excluded from SloWPoKES (GAMBLES), comprising 8660 statistically significant wide pairs that we make available in a living online database. Within this catalog we identify a subset of 543 long-lived (dissipation timescale >1.5 Gyr) candidate binary pairs, of assorted mass, with typical separations between 10{sup 3} and 10{sup 5.5} au (0.002–1.5 pc), using the published distances and proper motions from the Tycho -Gaia Astrometric Solution and Sloan Digital Sky Survey photometry. Each pair has at most a false positive probability of 0.05; the total expectation is 2.44 false binaries in our sample. Among these, we find 22 systems with 3 components, 1 system with 4 components, and 15 pairs consisting of at least 1 possible red giant. We find the largest long-lived binary separation to be nearly 3.2 pc; even so, >76% of GAMBLES long-lived binaries have large binding energies and dissipation lifetimes longer than 1.5 Gyr. Finally, we find that the distribution of binary separations is clearly bimodal, corroborating the findings from SloWPoKES and suggesting multiple pathways for the formation and dissipation of the widest binaries in the Galaxy.

  10. Gaia Assorted Mass Binaries Long Excluded from SLoWPoKES (GAMBLES): Identifying Ultra-wide Binary Pairs with Components of Diverse Mass

    International Nuclear Information System (INIS)

    Oelkers, Ryan J.; Stassun, Keivan G.; Dhital, Saurav

    2017-01-01

    The formation and evolution of binary star systems are some of the remaining key questions in modern astronomy. Wide binary pairs (separations >10 3 au) are particularly intriguing because their low binding energies make it difficult for the stars to stay gravitationally bound over extended timescales, and thus to probe the dynamics of binary formation and dissolution. Our previous SLoWPoKES catalogs, I and II, provided the largest and most complete sample of wide-binary pairs of low masses. Here we present an extension of these catalogs to a broad range of stellar masses: the Gaia Assorted Mass Binaries Long Excluded from SloWPoKES (GAMBLES), comprising 8660 statistically significant wide pairs that we make available in a living online database. Within this catalog we identify a subset of 543 long-lived (dissipation timescale >1.5 Gyr) candidate binary pairs, of assorted mass, with typical separations between 10 3 and 10 5.5 au (0.002–1.5 pc), using the published distances and proper motions from the Tycho -Gaia Astrometric Solution and Sloan Digital Sky Survey photometry. Each pair has at most a false positive probability of 0.05; the total expectation is 2.44 false binaries in our sample. Among these, we find 22 systems with 3 components, 1 system with 4 components, and 15 pairs consisting of at least 1 possible red giant. We find the largest long-lived binary separation to be nearly 3.2 pc; even so, >76% of GAMBLES long-lived binaries have large binding energies and dissipation lifetimes longer than 1.5 Gyr. Finally, we find that the distribution of binary separations is clearly bimodal, corroborating the findings from SloWPoKES and suggesting multiple pathways for the formation and dissipation of the widest binaries in the Galaxy.

  11. Accident Analyses for Conversion of the University of Missouri Research Reactor (MURR) from Highly-Enriched to Low-Enriched Uranium

    Energy Technology Data Exchange (ETDEWEB)

    Stillman, J. A. [Argonne National Lab. (ANL), Argonne, IL (United States); Feldman, E. E. [Argonne National Lab. (ANL), Argonne, IL (United States); Jaluvka, D. [Argonne National Lab. (ANL), Argonne, IL (United States); Wilson, E. H. [Argonne National Lab. (ANL), Argonne, IL (United States); Foyto, L. P. [Univ. of Missouri, Columbia, MO (United States); Kutikkad, K. [Univ. of Missouri, Columbia, MO (United States); McKibben, J. C. [Univ. of Missouri, Columbia, MO (United States); Peters, N. J. [Univ. of Missouri, Columbia, MO (United States)

    2017-02-01

    This report contains the results of reactor accident analyses for the University of Missouri Research Reactor (MURR). The calculations were performed as part of the conversion from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members in the Research and Test Reactor Department at the Argonne National Laboratory (ANL) and the MURR Facility. MURR LEU conversion is part of an overall effort to develop and qualify high-density fuel within the U.S. High Performance Research Reactor Conversion (USHPRR) program conducted by the U.S. Department of Energy National Nuclear Security Administration’s Office of Material Management and Minimization (M3).

  12. Suffield a cornucopia for Alberta energy company

    International Nuclear Information System (INIS)

    Thomas, A.

    1995-01-01

    Operations of the Alberta Energy Company's (AEC) Suffield properties in southern Alberta, the company's major production area, were reviewed. With a staff of just over 100, Suffield was said to produce an average of 180 million cubic feet of natural gas and more than 4100 barrels of oil per day. Suffield's remaining reserves were estimated to be 814 billion cubic feet of gas and 6.4 million barrels of oil. The field was expected to be in production for the next 20 years. A master plan to minimize normal field decline and control operating costs at Suffield was developed by AEC. Cloning gas storage plants was one of the methods used by for cost control. Designing and constructing identical gas plants was another means of producing major savings, especially in areas such as equipment purchase, and construction

  13. Alberta ambient air quality objectives : sulphur dioxide

    International Nuclear Information System (INIS)

    2011-02-01

    Sulphur dioxide (SO 2 ) is a colourless, non-flammable gas with a pungent odour. Exposure to SO 2 can result in numerous effects to the pulmonary system. This paper outlined current Alberta ambient air quality objectives in relation to SO 2 . The 1-hour average Alberta ambient air quality objective for SO 2 is currently 450 μg per m 3 . Studies conducted with healthy humans showed increased airway resistance and bronchoconstriction, as well as decreased maximum expiratory flow. Exercise can increase the severity of response to SO 2 in healthy and asthmatic individuals. Long-term exposure to SO 2 levels can also impact the metabolic activity of vegetation. The United States Environmental Protection Agency (EPA) recently announced their intention to reduce the 1-hour SO 2 standard to between 131 to 262 μg per m 3 . 7 refs.

  14. Ambient air quality trends in Alberta

    International Nuclear Information System (INIS)

    2007-01-01

    This document provided an overview of ambient air pollutant trends in Alberta. The report discussed the following pollutants having effect on human and environmental health: carbon monoxide (CO), hydrogen sulphide (H2 S ), nitrogen dioxide (NO 2 ), sulphur dioxide (SO 2 ), ozone (O 3 ), fine particulate matter (PM 2 .5), benzene, and benzopyrene. Each of these pollutants was described. The report provided data on annual average concentration trends and annual 99th percentile concentration as an indicator of peak concentrations. A map illustrating air quality monitoring stations in 2006 was also provided. The findings revealed that mean annual CO levels were the lowest they have been since 1990; hydrogen sulphide concentrations have fluctuated in time since 1990; most Edmonton and Calgary area stations showed significant decreasing trends in annual average NO 2 levels since 1990; and higher SO 2 concentrations have been found in the industrial areas of Alberta, such as the Redwater and Scotford oil sands locations. tabs., figs

  15. Asian interests in Alberta oil sands

    International Nuclear Information System (INIS)

    Du Plessis, D.; Laureshen, C.

    2004-01-01

    The growing Asian interest in Alberta's oil sands and import opportunities was discussed along with the feasibility of marketing bitumen to Asia. Asia is an obvious new market for Canadian heavy oil and bitumen due to an increasing demand for petroleum products in Japan, Korea, Taiwan and China. This paper examined the following three criteria that will determine the success of any initiative to move Canadian crude oil to Asian-Pacific markets: (1) a sustainable supply from Alberta; a pipeline to transport the crude to a deepwater port on the west coast; and, a guaranteed market at the other end. The basis for Asian interest in Alberta's oil sands is the sustainable secure supply of oil for growing Asian markets; heavy dependence on supplies from the Middle East; the desire to diversify supply sources; and, opportunities to invest in oil sands developments. Examples of Asian (Japan, Korea, Taiwan and China) missions to Alberta were presented along with the challenges of getting products to market with reference to Enbridge's new market access plan, Terasen's staged capacity expansion for heavy crudes and refined products, and sea transport from Prince Rupert. The paper also included graphs depicting world GDP; incremental increase in world primary energy demand by fuel for 2000 to 2020; world oil demand by region; oil demand by region in Asia; oil demand and supply in northeast Asia (Japan, China, Korea) and dependence level on Middle Eastern oil; oil demand and supply in China; China's petroleum production and consumption; refined products market forecast for 2000 to 2020; 2002 crude oil imports to Asia; 2004 refining capacity; product quality comparisons; cost competitive study; and energy policy objectives for China, Japan, Korea and Taiwan. 19 figs

  16. Deregulation and the Alberta experience : the implications for Ontario

    International Nuclear Information System (INIS)

    Charach, L.

    2002-01-01

    This paper provides a 15 month assessment of Alberta's new competitive electricity market. It also presents lessons that Ontario customers could learn from Alberta's experience. The goal for restructuring is to achieve lower electricity prices, competitive retail markets, increased flexibility of contracts, and to remove investment risks from consumers. Alberta's restructured market includes power generation, high voltage transmission, low voltage transmission and retail sales. Economists agree that deregulation has brought lower prices and other consumer benefits despite some imperfections. After one year, prices in Alberta have gone down from $130/MWh to $30/MWh. Power supply has increased along with demand response, market competitiveness, liquidity, and thermal and economic efficiency. In 2001, Alberta was a net exporter of electricity. In 2001, it was ranked by the Center for Advancement of Energy Markets (CAEM) which ranks states and provinces by 22 attributes for how they are restructuring their power markets. Alberta ranked first overall in North America. Ontario ranked sixteenth. 4 tabs., 5 figs

  17. Opportunities for CANDU for the Alberta oil sands

    International Nuclear Information System (INIS)

    Hopwood, J.M.; Bock, D.; Miller, A.; Kuran, S.; Keil, H.; Fiorino, L.; Hau, K.; Zhou, X.; Dunbar, R.B.

    2003-01-01

    The Alberta oil sands bitumen deposits comprise of one of the largest sources hydrocarbon in the world, and have emerged as the fastest growing, soon to be dominant, source of crude oil in Canada. The oil industry has made great strides in improving the effectiveness of gathering this resource. In particular, alternatives to open-pit mining have been developed which enable in-site recovery of underground deposits with a minimum of environmental disruption. The main challenge that remains is the large quantity of energy needed in the process of extracting the oil and upgrading it to commercial levels. For a typical in-situ extraction project, about 18% of the energy content of the oil produced is used up in the extraction process, while a further 5% is used in generating hydrogen to upgrade the bitumen to synthetic crude oil. Looking ahead, even as improvements in energy use efficiency, (and hydrocarbon use efficiency) counterbalance the increases in hydrocarbon demand from economic growth (particularly in the developing world), Canada and Alberta recognize that the oil sands resource will be needed, and both support the development of this resource in an environmentally responsible way. The large energy requirement for the oil sands extraction process represents a challenge with regard to both environmental impact and security of supply. The use of natural gas, the current energy supply, has impacts in terms of air quality (via NOX and other emissions) and also represents a large greenhouse gas emissions component. As the oil sands industry expands, the availability of natural gas also becomes a concern, as does price and price stability. With this background, the opportunity for nuclear reactors to provide an economical, reliable, virtually zero-emission source of energy for the oil sands becomes very important. Over the last few years, developments in oil sands extraction technology, and developments in CANDU technology through the Advanced CANDU Reactor, (ACR

  18. Science, Technology, and Competitiveness in Alberta's Agriculture and Food Sector

    OpenAIRE

    Veeman, Terrence S.; Peng, Yanning; Fantino, A.A.

    1997-01-01

    This project addresses several issues related to efficiency, productivity, and competitiveness in Alberta's agriculture and food sector, in both its primary agricultural sector and its secondary processing industry related to food and beverages. A major underlying theme of this work is that the competitiveness and economic sustainability of Alberta's agriculture and food sector is considerably driven by long run trends in productivity. Two emerging trends in Alberta's agriculture and food sec...

  19. A Cooperative Industry - Government Woodland Caribou Research Program in Northeastern Alberta

    Directory of Open Access Journals (Sweden)

    Blair Rippin

    1996-01-01

    the Alberta Departments of Environmental Protection and Energy. The research aspect of the program has been developed and implemented by staff of the University of Alberta, Alberta-Pacific Forest Industries, the Alberta Fish and Wildlife and Forest Services and the Alberta Environmental Centre. The program also incorporates a public information and liaison function. Newsletters, information videos, brochures and public consultation are the means used to accomplish this task.

  20. Fire, Aim… Ready? Alberta's Big Bang Approach to Healthcare Disintegration.

    Science.gov (United States)

    Donaldson, Cam

    2010-08-01

    Alberta's abolition in 2008 of its health regions and the creation of Alberta Health Services (AHS) was a bold move, but the reasons for the change remain hazy. The stated goals were to "help make Alberta's … system more effective and efficient" and to "provide equitable access to health services and long-term sustainability." Data show, however, that Alberta's health regions were already performing well on these goals relative to other provinces, and where changes have since occurred, they cannot necessarily be attributed to AHS.

  1. Barriers to convergence: legislative, regulatory and policy issues in Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Hyndman, R. [Alberta Energy and Natural Resources, Edmonton, AB (Canada)

    1997-02-01

    The restructuring of Alberta`s electric power industry has created potential for convergence with the natural gas industry. This presentation outlined some of the key issues dealing with convergence, including (1) the existing regulatory structures, (2) areas of convergence, (3) a comparison of the state of transition in Alberta of the electricity and natural gas to commodity markets in terms of supply, market, and legislative and regulatory jurisdiction, (4) price convergence and limiting factors, (5) key elements in the restructuring of the electric industry in Alberta, (6) the influence of restructuring on convergence, and (7) the barriers and limits to convergence. 37 figs.

  2. Feasibility study of the underwater neutron radiography facility using the University of Utah 100 kW TRIGA (UUTR) reactor

    International Nuclear Information System (INIS)

    Choe, D.; Xiao, S.; Jevremovic, T.; Yang, X.

    2010-01-01

    The University of Utah 100 kW TRIGA (UUTR) reactor provides usable neutron yields for neutron radiography. Currently, UUTR reactor has three irradiators (Central, Pneumatic, and Thermal irradiators) and one Fast neutron Irradiation Facility (FNIF). These irradiators are very small so they are not suitable for neutron radiography. UUTR has three beam ports but they are not available due to the structure of the core. All sides of the core are occupied by FNIF, Thermal Irradiator, and three ion chambers. The only available position for underwater vertical beam port is on the top of the FNIF. There are two factors necessary to fulfill to be able to realize vertical underwater beam port: noninterruption to other facilities and radiation shielding. Designing the vertical beam port as movable ensures good access to the core and pool, while still providing a good neutron radiography environment. Keeping the top of the beam port below the surface of the pool the water represents biological shield. Neutron radiographs, with a simple setup of efficient neutron converters and digital camera systems, can produce acceptable resolution with an exposure time as short as a few minutes. It is important to validate the design with calculations before constructing the beam port. The design of the beam port is modeled using the MCNP5 transport code. A minimum of 10 5 neutrons/cm 2 -sec thermal neutron flux is required for high resolution neutron radiography. Currently, the UUTRIGA is in the process of upgrading its power from 100 kW to 250 kW. Upon the completion of the upgrading, the maximum neutron flux in the core will be ∼7x10 12 neutrons/cm 2 -sec. This paper discusses a modeling and evaluation of capability for a neutron radiography facility. (author)

  3. Radiochemistry at the University of Missouri-Columbia. A joint venture with chemistry, nuclear engineering, molecular biology, biochemistry, and the Missouri University Research Reactor (MURR)

    International Nuclear Information System (INIS)

    Miller, W.H.; Duval, P.; Jurisson, S.S.; Robertson, J.D.; Wall, J.D.; Quinn, T.P.; Volkert, W.A.; Neumeyer, G.M.

    2005-01-01

    Missouri University, a recipient of a U.S. Department of Energy Radiochemistry Education Award Program (REAP) grant in 1999, has significantly expanded its education and research mission in radiochemistry. While MU had a viable radiochemistry program through existing faculty expertise and the utilization of the Missouri University Research Reactor, the REAP award allowed MU to leverage its resources in significantly expanding capabilities in radiochemistry. Specifically, the grant enabled the: (1) hiring of a new faculty member in actinide radiochemistry (Dr. Paul Duval); (2) support of six graduate students in radiochemistry; (3) purchase of new radiochemistry laboratory equipment; (4) more extensive collaboration with DOE scientists through interactions with faculty and graduate students, and (5) revised radiochemical curriculum (joint courses across disciplines and new courses in actinide chemistry). The most significant impact of this award has been in encouraging interdisciplinary education and research. The proposal was initiated by a joint effort between Nuclear Engineering and Chemistry, but also included faculty in biochemistry, radiology, and molecular biology. Specific outcomes of the REAP grant thus far are: (1) increased educational and research capabilities in actinide chemistry (faculty hire and equipment acquisition); (2) increased integration of biochemistry and radiochemistry (e.g., radiochemical analysis of uranium speciation in biological systems); (3) stronger interdisciplinary integration of molecular biology and radiochemical sciences (alpha-emitters for treating cancer); (4) new and more extensive interactions with national laboratory facilities (e.g., student internships at LANL and LLBL, faculty and lab scientist exchange visits, analytical measurements and collaboration with the Advanced Photon Source), and (7) new research funding opportunities based on REAP partnership. (author)

  4. The Alberta Electrical Grid: What to Expect in the Next Few Years in Alberta

    Directory of Open Access Journals (Sweden)

    Brian Livingston

    2018-04-01

    Full Text Available The Alberta government has stated that it wants to make significant changes to the supply of electricity to the current electrical grid for the province. These changes include the phasing out of coal generation by 2030, the supply of 30 per cent of electricity from renewables by 2030 and the introduction of a socalled capacity market in addition to the current electrical energy market. The achievement of these objectives will require a number of fundamental changes to the existing electrical grid. This paper provides an overall description of these changes. The paper first examines the current grid structure in which coal and gas provide the base load supply in the amount of 90 per cent of electricity demand, and renewables are a relatively small source of supply for the remaining 10 per cent. It then reviews the current simple energy market in Alberta that uses a single price auction to determine the wholesale price of electricity. The paper then notes that the achievement of these changes will require a large amount of investment in the next 15 years to create new generating capacity that currently does not exist. The Alberta Electric System Operator (AESO has forecast that by 2032, Alberta will need an additional 7,000 megawatts of gas generation, 5,000 megawatts of wind, 700 megawatts of solar and 350 megawatts of hydro. To put this in context, the Ontario grid currently has 4,213 megawatts of wind (11 per cent of total generating capacity and 380 megawatts of solar (one per cent of generating capacity. The Alberta government has made two fundamental changes in the electricity market to make this happen. First, it has introduced a Renewable Energy Program (REP to incent investment in renewables. They asked industry to bid on a 20 year contract for supply of electricity that offered a guaranteed fixed price that was independent of the existing wholesale market. The first round of bidding (REP 1 announced in December 2017 resulted in 600

  5. Implementation of the clean air strategy for Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Sandhu, H.S.; Angle, R.P. [Alberta Dept. of Environmental Protection, Alberta (Canada); Kelly, M. [Clean Air Strategic Alliance, Alberta (Canada)

    1995-12-31

    Air quality and its effects on the environment and human health have received considerable attention during the last three decades in Alberta, Canada. Among the issues receiving a high priority are acid deposition, smog and global warming. There are various sources of emissions to Alberta`s atmosphere, many of which relate to the extraction, processing, and burning of fossil fuels; pulp and paper manufacture; and transportation. There are also natural sources of contaminants, such as particulates from forest fires and methane from bogs. The extraction, processing and combustion of fossil fuels play an important role in Alberta`s economy. The province produces over 80 % of the oil and natural gas in Canada, and nearly half the coal. Low sulphur coal is used in power plants to supply more than 90 % of the electricity used in this province by nearly three million people. As a result, Alberta is responsible for about 27 % of the CO{sub 2}, 23 % of the nitrogen oxides, and 16 % of the SO{sub 2} emissions generated in Canada. Alberta`s air quality is monitored by the Government of Alberta at nine continuous, eight intermittent, over 250 static, and 12 precipitation monitoring stations. Parameters such as carbon monoxide, oxides of nitrogen, sulphur dioxide, particulates, and ion-content of precipitation are measured. Industry operates a large number of ambient and static SO{sub 2} and H{sub 2}S monitoring stations across Alberta, with monitoring costs estimated at 56-80 million USD annually. The unique features of the Clean Air Strategy for Alberta (CASA) have already been published elsewhere. This presentation discusses the mechanism and progress on its implementation. (author)

  6. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  7. Alberta electric industry annual statistics for 1998

    International Nuclear Information System (INIS)

    1999-06-01

    Tables containing data on electric energy generation and capacity for Alberta are provided for the following aspects: capacity and generation of power plants for 1998; capacity of power plants by type, unit, and energy resource for 1998; generating units approved for construction for 1998; generating units completed in 1998; transmission additions approved for construction and completed for 1998; net annual generating capacity and generation for 1988-1998; net monthly generation by plant for 1998; net annual generation by energy resource and type for 1988-1998; net monthly generation by energy resource and type for 1998; generation capacity reserve; relative capacity and generation by type of energy resource for 1998; capacity, generation and fuel consumption of isolated plants for 1998; other industrial on-site plant capacity and generation for 1998. Also listed are: energy resource consumption and energy conversion efficiency of thermal power plants for 1998; stack emissions from thermal generating plants for 1998; non-utility electric generators, wind and hydro for 1998; and hydroelectric energy utilization and conversion efficiency for 1998. Tables contain information on electric energy generation and capacity for hydroelectric energy stored in reservoirs in 1998; details of non-coincident net peak generation and load by utility operators for the Alberta electric system for 1998; and Alberta electric system generation and load at peak load hour for 1998. Further tables cover electric energy distribution for interchange and distribution for 1998 and 1981-1998; annual energy distribution to ultimate customers for 1988-1998 and to ultimate customers for 1998; and the number of electric utility customers in 1998. Final tables cover the transmission and distribution systems with data on: circuit km of such lines for 1988-1998; total circuit km of such lines by major electric utility for 1998 and number of rural electric utility customers for 1998

  8. Summary reports of activities under visiting research program in Research Reactor Institute, Kyoto University, first half of 1989

    International Nuclear Information System (INIS)

    1989-12-01

    This book contains 56 brief reports of studies carried out at the Research Reactor Institute of Kyoto University. These reports deal with 'Neutron Transmutation Doping on Compound Semiconductor', 'Study on the Influence of the Neutron Irradiation on the Low Temperature Strength of Various Welded Joint of Dissimilar Materials', 'Low Temperature Irradiation Effect on Iron-Alloys and Ceramics', 'Luminescent Phenomena from Some Kinds of Rock and Mineral Slices Accompanied with Gamma-irradiation', 'Study of Irradiation Effects on Simulated Waste Glass Irradiated Using 10 B(n,γ) 7 Li Reaction', 'Neutron Spectrometry with CR-39 Track Detector', 'Performance Study on Superconducting Magnet Materials in Thermonuclear Fusion Conditions', 'Fast Neutron Radiography with KUR-Linac', 'Study of Photo-Excited Metastable State and Their Relaxation of Irradiation Defects in Silicon and Diamond by Using a SQUID Magnetometer', 'Moessbauer Study on Radiation Damage of Metals and Alloys', 'Radiation Damages in Super Ionic Conductors', 'Basic Study on 74 As Production by (γ,n) Reaction', etc. (N.K.)

  9. Optimization study for an epithermal neutron beam for boron neutron capture therapy at the University of Virginia Research Reactor

    International Nuclear Information System (INIS)

    Burns, T.D. Jr.

    1995-05-01

    The non-surgical brain cancer treatment modality, Boron Neutron Capture Therapy (BNCT), requires the use of an epithermal neutron beam. This purpose of this thesis was to design an epithermal neutron beam at the University of Virginia Research Reactor (UVAR) suitable for BNCT applications. A suitable epithermal neutron beam for BNCT must have minimal fast neutron and gamma radiation contamination, and yet retain an appreciable intensity. The low power of the UVAR core makes reaching a balance between beam quality and intensity a very challenging design endeavor. The MCNP monte carlo neutron transport code was used to develop an equivalent core radiation source, and to perform the subsequent neutron transport calculations necessary for beam model analysis and development. The code accuracy was validated by benchmarking output against experimental criticality measurements. An epithermal beam was designed for the UVAR, with performance characteristics comparable to beams at facilities with cores of higher power. The epithermal neutron intensity of this beam is 2.2 x 10 8 n/cm 2 · s. The fast neutron and gamma radiation KERMA factors are 10 x 10 -11 cGy·cm 2 /n epi and 20 x 10 -11 cGy·cm 2 /n epi , respectively, and the current-to-flux ratio is 0.85. This thesis has shown that the UVAR has the capability to provide BNCT treatments, however the performance characteristics of the final beam of this study were limited by the low core power

  10. Worldwide market developments : lessons for Alberta

    International Nuclear Information System (INIS)

    Percival, J.F.

    1998-01-01

    A review of competitive retail electricity markets in Argentina, New Zealand, Australia and California were discussed, highlighting lessons for Alberta policy makers, market designers and electricity retailers. Some of the emerging strategies in the retail electricity marketplace such as horizontal integration, generation retailing, defensive retailing and virtual vertical integration were explored. Emphasis was on showing that electricity retailing is not an easy business. It is a business for large and existing players, and although horizontal and vertical integration have growth and profit potential, there are also risks

  11. Education in Alberta: Some Major Societal Trends. Revised.

    Science.gov (United States)

    Alberta Dept. of Education, Edmonton. Planning and Policy Secretariat.

    The major societal trends happening in Alberta, Canada, have an impact on educational effectiveness in the region. Statistics are provided in the areas of demographics, family and society, Alberta's youth, labor force, and advances in science and technology. The section on demographics includes data on population growth, births, fertility rates,…

  12. Education Reform in Alberta: Where Do We Go from Here?

    Science.gov (United States)

    Spencer, Brenda L.; Webber, Charles F.

    This paper discusses what educational leadership might look like at the start of the 21st century, specifically within the context of Alberta. It also provides a brief synopsis of some of Alberta's major reforms of the past decade, and it presents some of the key findings and recommendations of a 1998 study entitled "An Analysis of Attitudes…

  13. Dante in Alberta: chronicle of an oil addicted civilization

    International Nuclear Information System (INIS)

    Akram, Belkaid

    2010-01-01

    According to the author, Alberta, an heavenly province of Western Canada, is the theater of the biggest ecological crime of the moment in the form of oil exploitation. Alberta gathers all the aberrations and dramas that have been seen before in other oil producing countries, in particular in Africa, Middle-East and Asia: corruption, defiance of minority rights, terror threats, environment destruction etc

  14. Circle of Courage Infusion into the Alberta Indigenous Games 2011

    Science.gov (United States)

    Marchand, Dawn Marie

    2011-01-01

    Thousands of indigenous people from across North America came to the Enoch Cree Nation for the Alberta Indigenous Games, six days of sport, education, and cultural awakening. The vision of the Alberta Indigenous Games is to recognize the value and potential of Indigenous culture and the young people. Activities include sports, indigenous arts,…

  15. Learning and Technology in Alberta (1975 to 2009)

    Science.gov (United States)

    Alberta Education, 2009

    2009-01-01

    Alberta's education system is a leader in the use of technology in teaching and learning. New information technologies create options for how teachers teach, how students learn, and how classrooms look and operate. This document chronicles the history of computer technology in Alberta from 1975-2009. The information is arranged in a tabulated…

  16. Evolving Nature of School Psychology in Alberta: Politics and Practice

    Science.gov (United States)

    Johnson, R. Coranne; Zwiers, Michael L.

    2016-01-01

    Over the past 15 years, the practice of school psychology in the province of Alberta reflects the entrenchment of assessment with the emerging possibility of a broader service provider role. This article articulates the influence that politics and government has had on the role of school psychologists in Alberta schools as special education…

  17. Predicting lodgepole pine site index from climatic parameters in Alberta.

    Science.gov (United States)

    Robert A. Monserud; Shongming Huang; Yuqing. Yang

    2006-01-01

    We sought to evaluate the impact of climatic variables on site productivity of lodgepole pine (Pinus contorta var. latifolia Engelm.) for the province of Alberta. Climatic data were obtained from the Alberta Climate Model, which is based on 30-year normals from the provincial weather station network. Mapping methods were based...

  18. A nuclear reactor for district heating

    International Nuclear Information System (INIS)

    Bancroft, A.R.; Fenton, N.

    1989-07-01

    Global energy requirements are expected to double over the next 40 years. In the northern hemisphere, many countries consume in excess of 25 percent of their primary energy supply for building heating. Satisfying this need, within the constraints now being acknowledged for sustainable global development, provides an important opportunity for district heating. Fuel-use flexibility, energy and resource conservation, and reduced atmospheric pollution from acid gases and greenhouse gases, are important features offered by district heating systems. Among the major fuel options, only hydro-electricity and nuclear heat completely avoid emissions of combustion gases. To fill the need for an economical nuclear heat source, Atomic Energy of Canada Limited has designed a 10 MW plant that is suitable as a heat source within a network or as the main supply to large individual users. Producing hot water at temperatures below 100 degrees C, it incorporates a small pool-type reactor based on AECL's successful SLOWPOKE Research Reactor. A 2 MW prototype for the commercial unit is now being tested at the Whiteshell Nuclear Research Establishment in Manitoba. With capital costs of $7 million (Canadian), unit energy costs are projected to be $0.02/kWh for a 10 MW unit operating in a heating grid over a 30-year period. By keeping the reactor power low and the water temperature below 100 degrees C, much of the complexity of the large nuclear power plants can be avoided, thus allowing these small, safe nuclear heating systems to be economically viable

  19. MAPLE: a Canadian multipurpose reactor concept for national nuclear development

    International Nuclear Information System (INIS)

    Lidstone, R.F.

    1984-06-01

    Atomic Energy of Canada Limited, following an investigation of Canadian and international needs and world-market prospects for research reactors, has developed a new multipurpose concept, called MAPLE (Multipurpose Applied Physics Lattice Experimental). The MAPLE concept combines H 2 O- and D 2 O-moderated lattices within a D 2 O calandria tank in order to achieve the flux advantages of a basic H 2 O-cooled and moderated core along with the flexibility and space of a D 2 O-moderated core. The SUGAR (Slowpoke Uprated for General Applied Research) MAPLE version of the conept provides a range of utilization that is well suited to the needs of countries with nuclear programs at an early stage. The higher power MAPLE version furnishes high neutron flux levels and the variety of irradiation facilities that are appropriate for more advanced nuclear programs

  20. Fabrication and testing of a 4-node micro-pocket fission detector array for the Kansas State University TRIGA Mk. II research nuclear reactor

    Science.gov (United States)

    Reichenberger, Michael A.; Nichols, Daniel M.; Stevenson, Sarah R.; Swope, Tanner M.; Hilger, Caden W.; Unruh, Troy C.; McGregor, Douglas S.; Roberts, Jeremy A.

    2017-08-01

    Advancements in nuclear reactor core modeling and computational capability have encouraged further development of in-core neutron sensors. Micro-Pocket Fission Detectors (MPFDs) have been fabricated and tested previously, but successful testing of these prior detectors was limited to single-node operation with specialized designs. Described in this work is a modular, four-node MPFD array fabricated and tested at Kansas State University (KSU). The four sensor nodes were equally spaced to span the length of the fuel-region of the KSU TRIGA Mk. II research nuclear reactor core. The encapsulated array was filled with argon gas, serving as an ionization medium in the small cavities of the MPFDs. The unified design improved device ruggedness and simplified construction over previous designs. A 0.315-in. (8-mm) penetration in the upper grid plate of the KSU TRIGA Mk. II research nuclear reactor was used to deploy the array between fuel elements in the core. The MPFD array was coupled to an electronic support system which has been developed to support pulse-mode operation. Neutron-induced pulses were observed on all four sensor channels. Stable device operation was confirmed by testing under steady-state reactor conditions. Each of the four sensors in the array responded to changes in reactor power between 10 kWth and full power (750 kWth). Reactor power transients were observed in real-time including positive transients with periods of 5, 15, and 30 s. Finally, manual reactor power oscillations were observed in real-time.

  1. Vision 20/20 : saving for the future Alberta advantage

    International Nuclear Information System (INIS)

    Milke, M.

    2006-03-01

    As part of the Alberta Vision 20/20 project, Alberta's past and present spending patterns on natural resources and choices for the future were examined. Trust funds in Alberta, Alaska, and Norway were also compared, in order to learn from other jurisdictions. This report presented findings from Phase 3 of Vision 2020. The objectives of the study were to provide insight on what Alberta's economic, social and policy landscape might look like in the coming decades given expected demographic changes; benchmark Alberta's performance on key economic and social indicators and analyze government performance in related policy areas; supply useful, accessible information and possible solutions to Albertans about some of the challenges that demographic change is likely to bring; encourage discussion of issues among Albertans, including legislators and the media; and, where appropriate, encourage actions to mitigate or alleviate foreseeable problems. The guiding principles of the Vision 20/20 were first presented. Alberta's fiscal context and labyrinth of savings funds were examined. A detailed explanation and literature review of resource trust funds in Norway, Alaska, and Alberta were then provided followed by a comparison of the Alberta, Alaska, and Norway funds. Last, the report presented Alberta's options and discussion as well as recommendations. It was recommended that Alberta's annual per capita spending should not exceed population growth and inflation; the province should consider transfers of additional resource revenue into the Heritage Fund in the manner of the state of Alaska; and the province should deposit between 30 per cent and 40 per cent of all nonrenewable resource revenues in the Heritage Fund annually. 38 refs., 4 tabs., 17 figs., 4 appendices

  2. New production techniques for alberta oil sands.

    Science.gov (United States)

    Carrigy, M A

    1986-12-19

    Low world oil prices represent a serious threat to expanded commercial development of the Canadian oil sands in the near term, as they do to all of the higher cost alternatives to crude oil such as oil shales and coal liquefaction. Nonetheless, research and field testing of new technology for production of oil from oil sands are being pursued by industry and government in Alberta. New production technology is being developed in Canada to produce synthetic oil from the vast resources of bitumen trapped in the oil sands and bituminous carbonates of northern Alberta. This technology includes improved methods of mining, extraction, and upgrading of bitumen from near-surface deposits as well as new drilling and production techniques for thermal production of bitumen from the more deeply buried reservoirs. Of particular interest are the cluster drilling methods designed to reduce surface disturbance and the techniques for horizontal drilling of wells from underground tunnels to increase the contact of injection fluids with the reservoir.

  3. The Alberta smoke plume observation study

    Science.gov (United States)

    Anderson, Kerry; Pankratz, Al; Mooney, Curtis; Fleetham, Kelly

    2018-02-01

    A field project was conducted to observe and measure smoke plumes from wildland fires in Alberta. This study used handheld inclinometer measurements and photos taken at lookout towers in the province. Observations of 222 plumes were collected from 21 lookout towers over a 6-year period from 2010 to 2015. Observers reported the equilibrium and maximum plume heights based on the plumes' final levelling heights and the maximum lofting heights, respectively. Observations were tabulated at the end of each year and matched to reported fires. Fire sizes at assessment times and forest fuel types were reported by the province. Fire weather conditions were obtained from the Canadian Wildland Fire Information System (CWFIS). Assessed fire sizes were adjusted to the appropriate size at plume observation time using elliptical fire-growth projections. Though a logical method to collect plume observations in principle, many unanticipated issues were uncovered as the project developed. Instrument limitations and environmental conditions presented challenges to the investigators, whereas human error and the subjectivity of observations affected data quality. Despite these problems, the data set showed that responses to fire behaviour conditions were consistent with the physical processes leading to plume rise. The Alberta smoke plume observation study data can be found on the Canadian Wildland Fire Information System datamart (Natural Resources Canada, 2018) at datamart" target="_blank">http://cwfis.cfs.nrcan.gc.ca/datamart.

  4. The Alberta smoke plume observation study

    Directory of Open Access Journals (Sweden)

    K. Anderson

    2018-02-01

    Full Text Available A field project was conducted to observe and measure smoke plumes from wildland fires in Alberta. This study used handheld inclinometer measurements and photos taken at lookout towers in the province. Observations of 222 plumes were collected from 21 lookout towers over a 6-year period from 2010 to 2015. Observers reported the equilibrium and maximum plume heights based on the plumes' final levelling heights and the maximum lofting heights, respectively. Observations were tabulated at the end of each year and matched to reported fires. Fire sizes at assessment times and forest fuel types were reported by the province. Fire weather conditions were obtained from the Canadian Wildland Fire Information System (CWFIS. Assessed fire sizes were adjusted to the appropriate size at plume observation time using elliptical fire-growth projections. Though a logical method to collect plume observations in principle, many unanticipated issues were uncovered as the project developed. Instrument limitations and environmental conditions presented challenges to the investigators, whereas human error and the subjectivity of observations affected data quality. Despite these problems, the data set showed that responses to fire behaviour conditions were consistent with the physical processes leading to plume rise. The Alberta smoke plume observation study data can be found on the Canadian Wildland Fire Information System datamart (Natural Resources Canada, 2018 at http://cwfis.cfs.nrcan.gc.ca/datamart.

  5. New Alberta sulfur deliveries to US Gulf

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Christopher E. [Oil and Gas Journal (Canada)

    2011-07-01

    This document presents a review of the new perspectives for Alberta sulphur deliveries to the US Gulf. The sulphur market is growing, both globally and in Canada (Alberta) and there is a need for more transport facilities and capacity to ensure the future of this industry. Sulphur is a by-product of bitumen refining and is in great demand in the US Gulf area. One concept for promoting sulphur would be to move bitumen by rail to create new markets, especially in the U.S. Rail capacity at the present time is 6,000b/d and the railway serves Chicago, Toledo/ Detroit, the Lower Mississippi and Puget Sound. The rail timeline for sulphur deliveries is to achieve 60,000 b/d by 2015, this includes deliveries within Canada as well as to the US market. A second way to transport sulphur to the US Gulf would be by pipeline. Many pipeline projects are expected to be be completed by 2015, adding more than one million barrels per day of capacity.

  6. Positive year for Alberta power pool

    International Nuclear Information System (INIS)

    Reid-Carlson, D.

    1997-01-01

    The electricity power pool in Alberta completed its first year under deregulation. Results to date indicate that the competitive market has operated as intended. The effects of electricity pricing on the oil industry following deregulation were described, given the fact that electricity prices represent the second largest cost item to the oil industry after labour. The peculiarities of the mechanism of electricity pricing (based on hourly matching of supply offers to demand bids) were explained, highlighting the opportunities and risks to the oil industry caused by the hourly price variations and the difficulties involved in accurately forecasting on-peak and off-peak prices a full year in advance. In 1996 predicted average price was $14 to $17/MWh. The actual average price was $13.40/MWh. The general conclusion was that Alberta continues to have a surplus of electricity generation and is well positioned to to take advantage of its low generating costs, at least over the longer term. Short term bidding practices, however, may results in slightly higher system marginal prices

  7. Groundwater and underground coal gasification in Alberta

    International Nuclear Information System (INIS)

    Haluszka, A.; MacMillan, G.; Maev, S.

    2010-01-01

    Underground coal gasification has potential in Alberta. This presentation provided background information on underground coal gasification and discussed groundwater and the Laurus Energy demonstration project. A multi-disciplined approach to project assessment was described with particular reference to geologic and hydrogeologic setting; geologic mapping; and a hydrogeologic numerical model. Underground coal gasification involves the conversion of coal into synthesis gas or syngas. It can be applied to mined coal at the surface or applied to non-mined coal seams using injection and production wells. Underground coal gasification can effect groundwater as the rate of water influx into the coal seams influences the quality and composition of the syngas. Byproducts created include heat as well as water with dissolved concentrations of ammonia, phenols, salts, polyaromatic hydrocarbons, and liquid organic products from the pyrolysis of coal. A process overview of underground coal gasification was also illustrated. It was concluded that underground coal gasification has the potential in Alberta and risks to groundwater could be minimized by a properly designed project. refs., figs.

  8. Status report about the works for the start up of the RA-0 'zero power' nuclear reactor at the Cordoba National University

    International Nuclear Information System (INIS)

    Martin, H.R; Carballido, C.; Oliveras, T.

    1991-01-01

    After two years of works at the Cordoba National University for the new start-up of the RA-0 'zero power' nuclear reactor, the results obtained are herein presented. Starting with practically null infrastructure at the beginning, specially in human resources and instrumentation of the reactor, the objectives can be considered satisfactory. The training in work of the future operational staff, the design and the construction of the instrumentation and the fitting of the installations are the principal items described in this paper. An special attention is devoted to the insertion of this type of installation in the university organization, usually not prepared for the quality and control activities, which is necessarily considered in these type of works. (Author) [es

  9. Proceedings of the 18th technical meeting on nuclear reactor and radiation for KURRI engineers and the 9th technical official group section 5 meeting in Kyoto University

    International Nuclear Information System (INIS)

    2010-03-01

    This report is a summary of 18th Technical Meeting on Nuclear Reactor and Radiation for KURRI Engineers in Kyoto University. This was also the 9th meeting for technical official group section 5 (nuclear and radiation) in Kyoto University. In the workshop, three special lectures held were: (1) 'On Border Between Subcritical and Supercritical', (2) 'Memories of Nuclear Power Plant Management for 40 Years', and (3) 'Introduction of Technical Office in Faculty of Engineering, Kyoto University'. The technical presentations held were: (1) 'Radiation Background Study of Specialty Products in Senshu Region', (2) 'Introduction of Radioactivation Analysis at KUR', (3) 'Consideration of Critical Approach Method for KUR Low-Enrichment Fuel Reactor Core Using SRAC', (4) 'Evaluation of Temperature Coefficient of KUR Low-Enrichment Fuel Reactor Core Using SRAC'. As training for technical staffs in Technical Office, we visited the facility in Ashiu Research Forest. An introduction of this facility and the comments from the participants were included in this report. (S.K.)

  10. Optimization study for an epithermal neutron beam for boron neutron capture therapy at the University of Virginia Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Burns, Jr., Thomas Dean [Univ. of Virginia, Charlottesville, VA (United States)

    1995-05-01

    The non-surgical brain cancer treatment modality, Boron Neutron Capture Therapy (BNCT), requires the use of an epithermal neutron beam. This purpose of this thesis was to design an epithermal neutron beam at the University of Virginia Research Reactor (UVAR) suitable for BNCT applications. A suitable epithermal neutron beam for BNCT must have minimal fast neutron and gamma radiation contamination, and yet retain an appreciable intensity. The low power of the UVAR core makes reaching a balance between beam quality and intensity a very challenging design endeavor. The MCNP monte carlo neutron transport code was used to develop an equivalent core radiation source, and to perform the subsequent neutron transport calculations necessary for beam model analysis and development. The code accuracy was validated by benchmarking output against experimental criticality measurements. An epithermal beam was designed for the UVAR, with performance characteristics comparable to beams at facilities with cores of higher power. The epithermal neutron intensity of this beam is 2.2 x 108 n/cm2 • s. The fast neutron and gamma radiation KERMA factors are 10 x 10-11cGy•cm2/nepi and 20 x 10-11 cGy•cm2/nepi , respectively, and the current-to-flux ratio is 0.85. This thesis has shown that the UVAR has the capability to provide BNCT treatments, however the performance characteristics of the final beam of this study were limited by the low core power.

  11. Alberta's Estonians 1899 - Present TLÜ Akadeemilises Raamatukogus / Sander Jürisson

    Index Scriptorium Estoniae

    Jürisson, Sander

    2014-01-01

    Tallinna Ülikooli Akadeemilises Raamatukogus on üleval näitus "Alberta's Estonians 1899 - Present", mis annab ülevaate Kanada Alberta provintsi eestlaste loost. Näitus valmis Alberta Eesti Kultuuripärandi Seltsi koostöös Alberta Provintsi Arhiivi Kultuuripärandi Osakonnaga Edmontonis

  12. Deregulation and the Alberta experience : the implications for Ontario

    International Nuclear Information System (INIS)

    Desrochers, J.P.

    2002-01-01

    An overview of the first year of electric power industry deregulation in Alberta was presented. The way in which electricity is bought and sold in Ontario and throughout North America is changing. Costs are no longer fixed and regulated. Electricity is becoming a commodity with high levels of price volatility. The paper presented hedging options for Alberta consumers, contracting lessons, market issues and lessons for Ontario. A comparison of Alberta's deregulation schedule with that of Ontario's was included. One year after market opening in Alberta, power prices have dropped significantly. There is a greater than expected demand side response, increased development in power generation, and a decrease in natural gas prices. Issues that still need to be addressed in Alberta include billing and load settlement issues, invoicing/billing standards, the lack of competition at the retail level, and future balancing of pool charges. Energy Advantage Inc. (EA) does not foresee the same drastic increase in price as seen in Alberta market opening, but suggests that uncertainty and volatility will exist in Ontario. In Alberta, customers who did nothing and stayed on default were the ones who benefited, but took a great risk. EA suggests that customers must understand how and when they use electricity, how much is used during on- and off-peak hours, and in the summer versus the winter. When electricity is priced hourly, it is important to know consumption patterns. 7 figs

  13. Final progress report on Grant No. DE-FG02-81ER10229, U.S. Department of Energy Reactor Sharing Program at the University of Wisconsin, July 15, 2000 - May 31, 2001

    Energy Technology Data Exchange (ETDEWEB)

    Agasie, Robert J.

    2001-12-27

    The Reactor Sharing Program makes the facilities of the University of Wisconsin Nuclear Reactor Laboratory available to other educational institutions. Uses include direct instruction, student theses projects, and staff research projects. A list of using institutions and a brief description of use is given.

  14. Alberta Advisory Council on Electricity report to the Alberta Minister of Energy

    International Nuclear Information System (INIS)

    2002-06-01

    This report presents the deliberations of the Alberta Advisory Council on Electricity regarding the restructuring of the electric power industry in the province of Alberta. Strategic issues affecting restructuring over the long term were considered with particular attention to small consumers. The long term vision (Vision 2012) for electric power restructuring is to promote efficient and competitive markets attracting investment and innovation that will result in fair and equitable prices for consumers. It was noted that while the restructuring system is currently in place, progress has not been even across the system. It is expected that it will take several years before a restructured electricity industry is fully functioning. Recommendations were presented to establish a plan to address issues regarding restructuring within power generation, transmission, distribution and export/import policies. The issue of market power, competitiveness and consumer education was also discussed. It was also noted that there are many external forces that impact the electricity system, many of which come from outside Alberta. These include fluctuations in gas prices, electricity demand, changes in the United States, regulatory decisions in other jurisdictions and unexpected business events. It was emphasized that a strong, liquid and competitive wholesale market is vital to achieving Vision 2012. Key factors for a competitive wholesale market include adequate generation, transmission capability and export/import capacity. The report presents the following 3 scenarios: business as usual, managed transition, and freedom 2012. A review of restructuring in several other jurisdictions around the world was also provided. 1 tab., 1 fig

  15. Overview of naphthenic acids analyses at the University of Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Fedorak, P. [Alberta Univ., Edmonton, AB (Canada). Dept. of Biological Sciences

    2004-02-05

    Naphthenic acids (NA) are natural components found in most petroleum sources including the Athabasca oil sands. The complex mixtures of alkyl-substituted acyclic and cycloaliphatic carboxylic acids are released from oil sands during aqueous extraction at elevated pH levels, and are present in tailings ponds at 40 to 120 mg/L. They are major contributors to the acute toxicity of the oil sands extraction water. The toxicity of the tailings water decreases with time due to biodegradation. It is not known which components of naphthenic acids are responsible for toxicity. This paper presented current and new methods for analyzing naphthenic acids, including different mass spectrometry methods, carbon number distribution methods, fast atom bombardment, negative ion atmospheric pressure chemical ionization methods, and the combination of gas chromatography and mass spectrometry. It was determined that biodegradation decreases toxicity by removing low molecular weight acids, thereby increasing the abundance of clusters of naphthenic acids with carbon numbers 22 to 33 in Z families 0 to -12 (C22 clusters). refs., tabs., figs.

  16. Health status of refugees settled in Alberta: changes since arrival.

    Science.gov (United States)

    Maximova, Katerina; Krahn, Harvey

    2010-01-01

    This paper sought to examine which pre- and post-migration factors might be associated with changes in refugees' health status. Using linear regression, the associations between pre- and post-migration factors and changes in self-rated mental and physical health status were examined in 525 refugees from the 1998 Settlement Experiences of Refugees in Alberta study. Having spent time in a refugee camp and having held professional/managerial jobs in one's home country were associated with a greater decline in mental health status since arrival in Canada. Having completed a university degree in one's home country was associated with a greater decline in physical health status. Being employed was associated with greater improvements in mental health status. Perceived economic hardship was associated with greater declines in physical health status. A higher number of settlement services received during the first year in Canada was associated with greater improvements in both mental and physical health status. Longer residence in Canada was associated with greater declines in physical health status but not in mental health status. While little can be done to alter refugees' pre-migration experiences, public policies can affect many post-migration experiences in order to mitigate the negative health consequences associated with resettlement. Results of this study point to the need for continued provision of settlement services to assist refugees with job training, labour market access, and credential recognition, as well as counseling for refugees who experienced the trauma of living in a refugee camp.

  17. Development of differential absorption lidar (DIAL) for detection of CO2, CH4 and PM in Alberta

    Science.gov (United States)

    Wojcik, Michael; Crowther, Blake; Lemon, Robert; Valupadas, Prasad; Fu, Long; Leung, Bonnie; Yang, Zheng; Huda, Quamrul; Chambers, Allan

    2005-05-01

    Rapid expansion of the oil and gas industry in Alberta, including the oil sands, has challenged the Alberta Government to keep pace in its efforts to monitor and mitigate the environmental impacts of development. The limitations of current monitoring systems has pushed the provincial government to seek out advanced sensing technologies such as satellite imagery and laser based sensors. The Space Dynamics Laboratory (SDL) of Utah State University, in cooperation with Alberta Environmental Monitoring, Evaluation and Reporting Agency (AEMERA), has developed North America's first mobile differential absorption lidar (DIAL) system designed specifically for emissions measurement. This instrument is housed inside a 36' trailer which allows for mobility to travel across Alberta to characterize source emissions and to locate fugitive leaks. DIAL is capable of measuring concentrations for carbon dioxide (CO2) and methane (CH4) at ranges of up to 3 km with a spatial resolution of 10 meters. DIAL can map both CO2 and CH4, as well as particulate matter (PM) in a linear fashion; by scanning the laser beam in both azimuth and elevation DIAL can create images of emissions in two dimensions. DIAL imagery may be used to understand and control production practices, characterize source emissions, determine emission factors, locate fugitive leaks, assess plume dispersion, and confirm air dispersion modeling. A system overview of the DIAL instrument and some representative results will be discussed.

  18. Getting the Foundations Right: Alberta's Approach to Healthcare Reform

    OpenAIRE

    Duckett, Stephen

    2011-01-01

    Alberta's abolition of its health regions and the creation of Alberta Health Services in 2008 has integrated previously disparate providers of healthcare services. The long-term benefits of this “second-wave” approach to health systems structuring include lower administrative costs, greater equity of access, improved intraprovincial learning and economies of scale. Some benefits have begun to be realized but, as with any merger, performance should be judged over a multi-year time frame.

  19. An annotated list of the Lepidoptera of Alberta, Canada

    OpenAIRE

    Pohl, Greg; Anweiler, Gary; Schmidt, Christian; Kondla, Norbert

    2010-01-01

    This checklist documents the 2367 Lepidoptera species reported to occur in the province of Alberta, Canada, based on examination of the major public insect collections in Alberta and the Canadian National Collection of Insects, Arachnids and Nematodes. Records from relevant literature sources published since 1950 and from selected older works are also included. The entry for each species includes the scientific name, the author and year of publication of the original description, occurrence s...

  20. Improving cumulative effects assessment in Alberta: Regional strategic assessment

    International Nuclear Information System (INIS)

    Johnson, Dallas; Lalonde, Kim; McEachern, Menzie; Kenney, John; Mendoza, Gustavo; Buffin, Andrew; Rich, Kate

    2011-01-01

    The Government of Alberta, Canada is developing a regulatory framework to better manage cumulative environmental effects from development in the province. A key component of this effort is regional planning, which will lay the primary foundation for cumulative effects management into the future. Alberta Environment has considered the information needs of regional planning and has concluded that Regional Strategic Assessment may offer significant advantages if integrated into the planning process, including the overall improvement of cumulative environmental effects assessment in the province.

  1. Screening with Papanicolaou tests in Alberta: Are we Choosing Wisely?

    Science.gov (United States)

    Symonds, Christopher J; Chen, Wenxin; Rose, Marianne Sarah; Cooke, Lara J

    2018-01-01

    To describe the prevalence and geographic distribution of cervical cancer screening, as well as the age groups of those undergoing screening, in Alberta, and to determine if screening practices conform to current guidelines and follow Choosing Wisely Canada recommendations. Descriptive study using data from the Alberta Ministry of Health Analytics and Performance Reporting Branch. Alberta. Women who had 1 or more Papanicolaou tests between 2011 and 2013. Number of women aged 15 to 20 and those aged 70 and older who had 1 or more Pap tests in a 3-year period; year-to-year trends in screening rates for women in these 2 age groups; trends in screening rates in various geographic regions (ie, cities and zones) in Alberta; and the discipline of clinicians who ordered the Pap tests. Between 2011 and 2013, 805 632 women in the province of Alberta had 1 or more Pap tests for cervical cancer screening. Overall, 25 511 (17.5%) women aged 15 to 20 and 16 818 (10.3%) aged 70 and older were screened contrary to most existing guidelines. Screening rates varied markedly in different geographic regions of the province. Most Pap tests were ordered by family physicians or general practitioners. Within the geographic regions of Alberta, provincial, national, and international guidelines for screening with Pap tests are inconsistently followed. This strongly echoes the need for clinicians and patients to consider the Choosing Wisely Canada recommendations and current guidelines for cervical cancer screening. Copyright© the College of Family Physicians of Canada.

  2. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

    This pamphlet describes how reactors work; discusses reactor design; describes research, teaching, and materials testing reactors; production reactors; reactors for electric power generation; reactors for supply heat; reactors for propulsion; reactors for space; reactor safety; and reactors of tomorrow. The appendix discusses characteristics of U.S. civilian power reactor concepts and lists some of the U.S. reactor power projects, with location, type, capacity, owner, and startup date.

  3. Is the restructuring of Alberta's power market on the right track? Evaluating Alberta's first two years of deregulation

    International Nuclear Information System (INIS)

    Wellenius, K.; Adamson, S.

    2003-07-01

    The performance of Alberta's restructured electricity market was evaluated since its move to wholesale competition in January 2001. This paper presents the following eight conclusions that the authors arrived at following the evaluation: (1) To meet growing demand, the electricity prices in Alberta would have increased regardless of the type of environment (regulated or not). Capacity investment was required, and it was believed that moving to competition was the best way to attract investors. (2) Success in attracting private investment was attained as a result of Alberta's open market. It has restored reliability of supply and moderated prices. (3) Price comparisons must take into account what the prices would have been if the market had remained regulated. Due to unique generation costs and regulatory environments, comparisons with other regulated jurisdictions is inappropriate. (4) Convergence with other energy rates that would have been seen under regulation is being noted with respect to Alberta's market prices. (5) Under deregulation, prices increase according to the need for new investment and fall after the investment is made. Alberta has been on a path toward continued reduction in wholesale prices since 2001. (6) The non-price benefits of restructuring include improved generation efficiency, captured residual value from regulated assets, and shifting investment risk of new capacity additions from consumers to generators. (7) Downward pressure on prices was noted as a result of deregulation, as expected. (8) Significant value for consumers was captured through Alberta's restructuring process. 7 tabs., 7 figs

  4. Research, Education and Service Utilizations of Borazole Nuclear Reactor at the Radiation Science and Engineering Center at the Pennsylvania State University

    Energy Technology Data Exchange (ETDEWEB)

    Unlu, Kenan; Heidrich, Brenden [Pennsylvania State Univ., Pennsylvania (United States)

    2013-07-01

    The Radiation Science and Engineering Center (RSEC) facilities at the Pennsylvania State University include Penn State Breazeale Reactor (PSBR), gamma irradiation facilities, several radiation detection and measurement laboratories and neutron irradiation facilities. The PSBR is a 1 MW, TRIGA with moveable core in a large pool with pulsing capabilities. A variety of dry tubes and fixtures are available for in or near core irradiations. The RSEC facilities are heavily used for nuclear science and engineering research, education and services. Examples of multidisciplinary nuclear science and engineering research, educational as well as industrial service utilizations at the RSEC will be presented.

  5. Annual compensation for pipelines in Alberta

    International Nuclear Information System (INIS)

    2008-11-01

    The Surface Rights Board (SRB) in Alberta held a hearing in November 2007 to address three issues involving a pipeline for Enbridge Pipelines (Athabasca) Inc. as well as several land owner issues in Townships 66-68 and Ranges 17-19, all west of the 4th Meridian. The issues the SRB examined were the appropriate amount (i.e. magnitude) of compensation payable under right of entry orders under consideration; the appropriate structure of the compensation award; and to whom the compensation was payable. This document presented a review by the Farmer's Advocate Office (FAO) of the published decision of the SRB. The verbatim decision and rationale used by the SRB to award annual compensation for loss and/or ongoing nuisance and inconvenience was presented. The document could be useful to landowners as they determine their negotiation strategy when faced with considering future pipeline access agreements. The document included a discussion of the context for the decision and a case review. Specific topics that were covered included the rationale for the decision; long term effects of pipeline arguments and SRB commentary; the award and determination; and what still needs to be done. It was concluded that the SRB requires evidence in order to answer several questions regarding the magnitude of any losses, and to what degree, if any, had the nuisance, inconvenience, and loss of rights already been anticipated and factored into the operator's final offer

  6. A retailer's perspective on generation in Alberta

    International Nuclear Information System (INIS)

    Willerton, K.

    2003-01-01

    There are several reasons for a retailer to invest in power generation. This investment acts as a risk management hedge against fixed price retail load, while improving competitiveness in illiquid wholesale markets. Investing in power generation leverages the retailer's wholesale trading capabilities. It also provides appropriate returns. Some of the factors that ensure the success of a retailer investing in power generation are low cost structure, low risk, strong forward commodity market, owners with large healthy balance sheets, and willingness to finance projects entirely with equity. A cost comparison was presented for different generation technologies. ENMAX chose to invest in wind power since the costs were comparable to that of other technologies. In addition, green credits will lower the cost of wind power. With low environmental impacts and no fuel risk, wind energy fitted ENMAX's retail strategy. Green power at ENMAX (GREENMAX) was the first to implement a Green Power Residential program in 1998, followed by the Green Power Commercial program in 2000. The author discussed the McBride Lake Wind Farm located near Fort MacLeod, Alberta. figs

  7. Alberta books big revenues in 1996

    International Nuclear Information System (INIS)

    Curran, R.

    1996-01-01

    A 17.9 per cent increase over 1995 in oil and gas revenues were reported for Alberta through August 1996. Revenues from crude oil were up 12.6 per cent and from natural gas 30.7 per cent. The level of increase in revenues is expected to hold for the remainder of the year, save for the prospects of Iraq re-entering the market in force. This would cause a steep decline in prices and some panic trading in energy stocks. Nevertheless, producers are well positioned for the year ahead, as capital spending and drilling activity are based on lower price forecasts. Oil production over 1995 was down slightly through August. Light and medium crude production was down 4.5 per cent. Synthetic production fell by 0.8 per cent. Natural gas production will have a record year. Through August output was up 4.6 per cent over 1995, sales were up 19.3 per cent, and exports were ahead by just under one per cent. Natural gas liquids were the biggest revenue booster, increasing by 46.3 per cent over 1995

  8. Refining the focus: Alberta's international marketing strategy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This strategic plan is the key initiative established under 'Alberta's Framework for International Strategies'. Its objective is to ensure the wellbeing of Albertans, sustaining Alberta's environment, and economic growth through successfully taking advantage of Alberta's many opportunities for marketing its goods, products, and services. It is predicated on industry and government continuing to work together to sustain a strong market-driven economy, strengthen Alberta's economic advantages and build an economic environment conducive to investment and growth in quality jobs. At present more than 150 foreign markets buy Alberta's goods and services, but the obvious focus of any strategy must be those regions and sectors of industry that offer the greatest possibilities for new and expanded opportunities for Alberta business. Accordingly, this strategy identifies priorities, selects the best initiatives and develops activities to achieve economic growth. Adding value to Albertan commodities before they are being shipped to export markets is a particular objective of the plan. An equally important consideration is to achieve growth through expansion of existing investments, attract new investment to the province, and to increase exports in response to international market and investment opportunities for Alberta's goods and services. Major topics discussed in the document include a discussion of the importance of trade and investment, a thorough analysis of the marketing priorities, the strategic framework, and priority market profiles for the United States, Japan,China, other Asia-Pacific markets, the European Union, Mexico, the Middle East and South Asia, and South America.

  9. Universe

    CERN Document Server

    Doudna, Kelly

    2015-01-01

    The Universe explores the science of what we see in the night sky. Kids will learn about the life cycle of a star, find out how our universe was created, explore nebulae, galaxies, black holes, giant stars and more. Engaging photos, exciting graphics, and a fun quiz at the end of each book will keep them learning. Aligned to Common Core Standards and correlated to state standards. Super Sandcastle is an imprint of Abdo Publishing, a division of ABDO.

  10. Preparation and planning for the replacement of the Oregon State University TRIGA reactor rotary specimen rack assembly

    International Nuclear Information System (INIS)

    Anderson, T.V.; Dodd, B.; Johnson, A.G.; Carpenter, W.T.

    1984-01-01

    Recently there have been a number of indications that the rotating rack may be approaching the end of its useful life. In order to benefit from the experience of other reactors who have removed and replaced their rotating racks, General Atomic (GA) was contacted and previous TRIGA Conference proceedings were scanned. It was determined that a number of facilities, had experienced difficulties with their lazy susans and eventually had to replace them. However, most of the written descriptions of this project were not sufficiently detailed to be of great use. The purpose of this paper is to identify some of the more important questions related to the replacement of our rotating rack assembly and OSU's currently proposed solutions, with a view towards soliciting ideas from other members of the TRIGA reactor community

  11. Power Pool of Alberta annual report 2000 : building a market

    International Nuclear Information System (INIS)

    2001-01-01

    As of January 1, 2001, deregulation of the electricity market in Alberta became a reality, and was accompanied by steady growth in demand for electricity combined with other factors that pushed the price of electricity upward. The Power Pool of Alberta ensures that market operations are open and fair. Its mandate, under the Electric Utilities Act, is the overall market surveillance in Alberta's electric industry. It is accomplished by working closely with industry and seeking feedback through four standing committees: Human Resources, Operations, Finance and Audit, and Balancing Pool. The goal for the coming years is to build confidence in the market, whereby consumers are confident about the fairness of the market price for electricity in Alberta, the choices available, and the continued reliability of the electric system in Alberta. The Energy Trading System was explained with information about system control and customer service, and details provided on the consultation and collaboration processes. The financial analysis of the year 2000 was provided, as well as a statement of operation, a balance sheet, and a statement of cash flows. tabs., figs

  12. Heating up in Alberta : climate change, energy development and water

    International Nuclear Information System (INIS)

    Griffiths, M.; Woynillowicz

    2009-02-01

    The advantages and disadvantages of energy sources for the future have been discussed in Alberta for several years. The heavy reliance of the province's economy on extracting oil, gas and bitumen has led politicians and industrialists to support these activities, despite the environmental cost. However, a large percentage of Alberta's citizens would like to see a switch to an economy based on cleaner, less environmentally damaging sources of energy. This report discussed Alberta's climate change challenge with particular reference to greenhouse gas emissions, changing precipitation, and water use for energy production in Alberta. The report discussed water use for electricity production, such as coal-fired electricity generation; electricity from gas; nuclear energy; hydroelectricity and run-of-river hydro; and other types of renewable energy. Water use for gas and oil production was examined. This included well development; natural gas production; conventional oil production; oil from bitumen; and future water demands for the oil and gas sector. The report concluded with a discussion of implications for Alberta's energy production and recommendations. The report also recommended that efforts should be increased to reduce greenhouse gas emissions and practical steps should be taken to reduce fresh water use. 349 refs., 2 tabs., 22 figs

  13. Providing geoscience information for geoexchange technology implementation in Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Grobe, M. [Alberta Geological Survey, Edmonton, AB (Canada). Earth Systems Section

    2007-07-01

    The mission of the Alberta Geological Survey (AGS) is to provide, data, information, knowledge, and advice about the geology of Alberta needed by government, industry, and the public for earth-resource stewardship and sustainable development in Alberta. This presentation discussed the provision of geoscience information for geoexchange technology implementation in Alberta. Surficial and bedrock geology influences the selection, installation cost and performance of geoexchange systems. The AGS is currently examining the feasibility of transforming geological maps to geothermal property maps for geoexchange design purposes and decision making by policy makers and industry. Shallow or ground-source geothermal energy in Alberta and the role of geoscience information were presented. The role of the AGS and its activities were outlined. The presentation also identified a project approach to two studies, notably a geoscience needs and utilities assessment as well as a pilot study in the Edmonton area. Data compilation and maps of the pilot study were presented. Last, the presentation discussed drilling, sampling and thermal testing in an area of thick drift over bedrock. It was determined that quality geoscience information is an important factor for site assessment and proper geoexchange design and decision making. The sharing data and experience for better decision making was found to be an important benefit. tabs., figs.

  14. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    Edwards, R.M.; Power, M.A.; Bryan, M.

    1992-01-01

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

  15. Alberta Heritage Savings Trust Fund : 1998 annual report

    International Nuclear Information System (INIS)

    1999-01-01

    A review of the Alberta Heritage Savings Trust Fund as it operated under the new investment framework established in 1997 was presented. The new statutory mission of the Fund is to provide stewardship of the savings from Alberta's non-renewable resources by providing the greatest financial returns on those savings for current and future generations of Albertans. In 1998, the Fund earned $947 million in income with nearly $25 million of income being retained to ensure that the value of the Fund grows to off-set the effects of inflation. Net assets of the Fund on March 31, 1998 was $ 12.3 billion. Operation of the Fund, the accounting method used, and details about the Transition Portfolio and the Endowment Portfolio are provided. An assessment of Alberta's economic climate accompanies the auditor's report and the detailed financial statements of the Fund. tabs

  16. Threshold Considerations and Wetland Reclamation in Alberta's Mineable Oil Sands

    Directory of Open Access Journals (Sweden)

    Lee Foote

    2012-03-01

    Full Text Available Oil sand extraction in Alberta, Canada is a multibillion dollar industry operating over 143 km² of open pit mining and 4600 km² of other bitumen strata in northern boreal forests. Oil production contributes to Canada-wide GDP, creates socio-cultural problems, provides energy exports and employment, and carries environmental risks regarding long-term reclamation uncertainties. Of particular concern are the implications for wetlands and water supply management. Mining of oil sands is very attractive because proven reserves of known quality occur in an accessible, politically stable environment with existing infrastructure and an estimated 5.5 billion extractable barrels to be mined over the next five decades. Extraction occurs under a set of limiting factors or thresholds including: limited social tolerance at local to international levels for externalities of oil sand production; water demands > availability; limited natural gas supplies for oil processing leading to proposals for hydroelectric dams and nuclear reactors to be constructed; difficulties in reclaiming sufficient habitat area to replace those lost. Replacement of the 85 km² of peat-forming wetlands forecast to be destroyed appears unlikely. Over 840 billion liters of toxic fluid byproducts are currently held in 170 km² of open reservoirs without any known process to purify this water in meaningful time frames even as some of it leaches into adjacent lands and rivers. Costs for wetland reclamation are high with estimates of $4 to $13 billion, or about 6% of the net profits generated from mining those sites. This raises a social equity question of how much reclamation is appropriate. Time frames for economic, political, and ecological actions are not well aligned. Local people on or near mine sites have had to change their area use for decades and have been affected by industrial development. Examining mining effects to estimate thresholds of biophysical realities, time scales

  17. Should upgrading and refining be enhanced in Alberta?

    International Nuclear Information System (INIS)

    Asgarpour, S.

    2006-01-01

    Although world oil prices are rising, the price of bitumen remains stable. It was noted that surplus refinery capacity is disappearing and that skilled labour, infrastructure, transportation systems, environmental management and technology development are among some of the challenges facing heavy hydrocarbon development. Pie charts indicating global reserves of crude oil and heavy crude oil showed that although the Middle East leads in world proven oil reserves, nearly half of the heavy crude oil and natural bitumen deposits are in Canada. As a global energy leader, Alberta is using its' world class expertise to develop the vast energy resources of the province and to market these resources and abilities to the world. This presentation summarized processing activities in Alberta and outlined the markets for petrochemicals. A graph representing North American petroleum supply and demand from 2001 to 2019 was also presented along with a review of Alberta's upgrading and refining capacity and infrastructure opportunities for crude oil, natural gas, petrochemicals and electricity. Alberta's crude oil markets by 2020 are likely to be the Far East, California, Heredity's, Wyoming, Chicago, Cushing, United States Gulf Coast, and the East Coast. The benefits of upgrading in Alberta include inexpensive feedstock, existing upgrader and petrochemical sites and low transportation costs. In addition, more refining capacity in the province would provide market diversification for bitumen products; higher investment and value-added in Alberta; opportunity to provide feedstock to petrochemicals; production of synthetic diluent in the province; and, smaller environmental footprint and greater energy efficiency. The cumulative impact of oil sands development on government revenues was discussed along with the challenge of addressing the issue of a skilled labour shortage, infrastructure needs, and developing a business case for a carbon dioxide pipeline. tabs., figs

  18. Alberta interconnected electric system transmission development plan 2002 - 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-03-13

    Alberta's independent Transmission Administrator, ESBI Alberta Ltd., has committed to publish annually an updated 10-year plan for the development of the Alberta Interconnected Electric System transmission grid. This report is its fourth annual publication which provides valuable information for those wishing to enter the power generation market or for those interested in competing for the provision of new transmission facilities. From 2002-2011, peak demand is projected to increase from 8,000 MW to nearly 10,000 MW. Full competition in power generation came into effect in Alberta in 2001. This stimulated interest in developing new generation in the province, particularly in Lake Wabamun, Fort McMurray, and Southern Alberta. It was noted that the existing transmission infrastructure has performed well, but since there has been no major investment since 1985, it is time to seriously consider new major investments into the system in order to continue to provide secure, reliable service. In 2001 ESBI conducted a conceptual study of the transmission infrastructure that would be needed if Alberta were to export its power. This study is being expanded to include power generation additions. The variables are the location of generation additions and the amount of surplus generation available for export. In 2001, more than $200 M worth of transmission reinforcement projects were initiated. The same level of investment is expected in 2002. Close cooperation between the Transmission Administrator and project developers, regulators and government is needed now more than ever because of the deregulation in power generation. The role of ESBI is to continue the stakeholder consultation process that helps to ensure excellence in power transmission in the province. This report reviews 500 kV, 240 kV and 138/144 kV transmission system reinforcements. It presented an economic outlook for Alberta with reference to underlying economic assumptions, oil and natural gas prices, and

  19. Governance in Transformation: Alberta School Board Chairs’ Perspectives on Governance

    Directory of Open Access Journals (Sweden)

    Jim Gibbons

    2012-01-01

    Full Text Available School boards are typically removed from nonprofit sector analyses because they are part of the “MUSH” set of organizations (municipalities, universities, schools, and hospitals that both stand outside of the more typical nonprofit sector and tend to be closely affiliated with government. Nevertheless, school boards offer a unique opportunity to examine the governance of a large system of regulated activity that affects millions of citizens. How such systems should be governed has been a matter of concern for nearly 40 years. This study presents data from Alberta school board chairs regarding their perception of governance transformation being brought about by legislative changes. Five dimensions of governance are proposed as defining the current and anticipated governance domain within which school boards operate. Tensions within and between these dimensions signify symbolic boundary constructions that need to be scrutinized in anticipation of the governance transformation and boundary spanning activities of school boards required by the new legislation. / Les conseils scolaires sont généralement retirés des analyses du secteur communautaire parce qu’ils font partie de l’ensemble d’organisations « MUSH » (les municipalités, les universités, les écoles et les hôpitaux; ces organisations se distinguent du secteur communautaire typique et ont tendance à être étroitement associées au gouvernement. Néanmoins, les conseils scolaires offrent une occasion unique d’observer la gouvernance d’un vaste système d’activités réglementées qui affecte des millions de citoyens. La façon dont de tels systèmes devraient être gérés fait l’objet de préoccupations depuis presque 40 ans. Cette étude présente les perceptions de présidents de conseils scolaires de l’Alberta en ce qui a trait à la transformation de la gouvernance apportée par des modifications à la loi. Cinq dimensions de la gouvernance sont propos

  20. A parametric study of the steady-state operational characteristics of the Ohio State University natural circulation indirect-cycle, inherently safe boiling water reactor

    International Nuclear Information System (INIS)

    Aybar, H.S.

    1995-01-01

    The Ohio State University Inherently Safe Reactor (OSU-ISR) is a conceptual design for a 340-MW(electric) [1,000-MW(thermal)], natural circulation, indirect-cycle, small boiling water reactor. All the OSU-ISR primary loop components are housed within a prestressed concrete reactor vessel (PCRV). The OSU-ISR performance has been investigated as a function of several design parameters in an attempt to better understand the interdependency among the system variables and hence to establish a knowledge base for the refinement of the conceptual design. The computational tool used in the study is a Dynamic Simulation for Nuclear Power Plants (DSNP) code whose predictions for the steady-state OSU-ISR performance compare favorably with RELAP5/MOD3 results for most of the operational characteristics of interest. The results show that (a) the key quantity that governs the OSU-ISR steady-state performance is the pressure difference between the primary and the secondary loops, (b) the magnitude of water-level swell (which occurs due to void formation in the core during operation and which affects the size of the steam separators that need to be used) can be more effectively controlled by varying the PCRV water level at cold shutdown rather than by varying the internal PCRV dimensions, (c) turbine inlet steam quality can be controlled without substantially affecting the other operational parameters by varying the secondary mass flow rate, and (d) the PCRV pressure and core exit steam quality are most sensitive to changes in the secondary loop pressure. The results also show that if there is a large drop in the secondary loop pressure (e.g., due to a steam line break), then although this pressure drop may induce a large drop in the PCRV pressure, the core flow, and hence core cooling capability, will not be appreciably affected

  1. Training the next generation of Space and Earth Science Engineers and Scientists through student design and development of an Earth Observation Nanosatellite, AlbertaSat-1

    Science.gov (United States)

    Lange, B. A.; Bottoms, J.

    2011-12-01

    This presentation addresses the design and developmental process of a Nanosatellite by an interdisciplinary team of undergraduate and graduate students at the University of Alberta. The Satellite, AlbertaSat-1, is the University of Alberta's entry in the Canadian Satellite Design Challenge (CDSC); an initiative to entice Canadian students to contribute to space and earth observation technologies and research. The province of Alberta, while home to a few companies, is very limited in its space industry capacity. The University of Alberta reflects this fact, where one of the major unifying foci of the University is oil, the provinces greatest resource. For students at the U of A, this lack of focus on astronautical, aerospace and space/earth observational research limits their education in these industries/disciplines. A fully student operated project such as AlbertaSat-1 provides this integral experience to almost every discipline. The AlbertaSat-1 team is comprised of students from engineering, physics, chemistry, earth and atmospheric science, business, and computer science. While diverse in discipline, the team is also diverse in experience, spanning all levels from 1st year undergraduate to experienced PhD. Many skill sets are required and the diverse group sees that this is covered and all opinions voiced. Through immersion in the project, students learn quickly and efficiently. The necessity for a flawless product ensures that only the highest quality of work is presented. Students participating must research and understand their own subsystem as well as all others. This overall system view provides the best educational tool, as students are able to see the real impacts of their work on other subsystems. As the project is completely student organized, the participants gain not only technical engineering, space and earth observational education, but experience in operations and financial management. The direct exposure to all aspects of the space and earth

  2. Universe

    CERN Document Server

    2009-01-01

    The Universe, is one book in the Britannica Illustrated Science Library Series that is correlated to the science curriculum in grades 5-8. The Britannica Illustrated Science Library is a visually compelling set that covers earth science, life science, and physical science in 16 volumes.  Created for ages 10 and up, each volume provides an overview on a subject and thoroughly explains it through detailed and powerful graphics-more than 1,000 per volume-that turn complex subjects into information that students can grasp.  Each volume contains a glossary with full definitions for vocabulary help and an index.

  3. Universe

    CERN Document Server

    2011-01-01

    Updated for 2011, the Universe, is one book in the Britannica Illustrated Science Library Series that covers today's most popular science topics, from digital TV to microchips to touchscreens and beyond. Perennial subjects in earth science, life science, and physical science are all explored in detail. Amazing graphics-more than 1,000 per title-combined with concise summaries help students understand complex subjects. Correlated to the science curriculum in grades 5-9, each title also contains a glossary with full definitions for vocabulary.

  4. Framing a New Standard for Teaching in Alberta

    Science.gov (United States)

    Hull, John E.

    2013-01-01

    A research panel asked to frame the discussion for a new Teaching Quality Standard in Alberta assumes this task requires a paradigm shift away from the status quo efficiency movement. As a member of the panel, the author provides an analysis of paradigm shifts in education and recounts important lessons to be learned. The author challenges the…

  5. School Identity in the Context of Alberta Charter Schools

    Science.gov (United States)

    Thompson, Merlin; Gereluk, Dianne; Kowch, Eugene

    2016-01-01

    The central tenet of this investigation is that educational institutions possess their own school identity. Acknowledging that school identity is influenced by institutional mechanisms and personal dynamics, we examine school identity in the context of 13 Alberta charter schools. Narratives of 73 educational stakeholders across the network of…

  6. The Saskatchewan-Alberta large acceptance detector for photonuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Cairns, E.B.; Cameron, J.; Choi, W.C.; Fielding, H.W.; Green, P.W.; Greeniaus, L.G.; Hackett, E.D.; Holm, L.; Kolb, N.R.; Korkmaz, E.; Langill, P.P.; McDonald, W.J.; Mack, D.; Olsen, W.C.; Peterson, B.A.; Rodning, N.L.; Soukup, J.; Zhu, J. (Alberta Univ., Edmonton, AL (Canada). Centre for Subatomic Research); Hutcheon, D. (TRIUMF, Vancouver, BC (Canada)); Caplan, H.S.; Pywell, R.E.; Skopik, D.M.; Vogt, J.M. (Saskatchewan Accelerator Lab., Saskatoon, SK (Canada)); Van Heerden, I.J. (Western Cape Univ., Bellville (South Africa))

    1992-09-15

    The Saskatchewan-Alberta Large Acceptance Detector (SALAD) is a 4[pi] detector designed and built for studies of photonuclear reactions with a tagged photon beam. The design and performance of the detector are described. Its characteristics have been studied by examining p-p elastic scattering with a proton beam at TRIUMF. (orig.).

  7. Market making vs. market manipulation : an Alberta perspective

    International Nuclear Information System (INIS)

    Johnston, P.M.

    1998-01-01

    The Alberta Stock Exchange's (ASE's) filing and disclosure requirements for market making and promotion contracts are outlined. The discussion focuses on the differences between market making and market manipulation, acceptable and unacceptable methods of market making and promotion and common trading and securities legislation violations associated with these types of activities

  8. Tourism and recreation system planning in Alberta provincial parks

    Science.gov (United States)

    Paul F.J. Eagles; Angela M. Gilmore; Luis X. Huang; Denise A. Keltie; Kimberley Rae; Hong Sun; Amy K. Thede; Meagan L. Wilson; Jennifer A. Woronuk; Ge Yujin

    2007-01-01

    Traditionally, system planning in parks and protected areas concentrated on biogeographical concepts, while neglecting tourism and recreation. The existing system plan for parks and protected areas in Alberta, Canada, divides the province into six natural regions based on a geographic classifi cation system (Grassland, Parkland, Foothills, Rocky Mountains, Boreal...

  9. Biomass and biomass change in lodgepole pine stands in Alberta

    Science.gov (United States)

    Robert A. Monserud; Shongming Huang; Yuqing Yang

    2006-01-01

    We describe methods and results for broad-scale estimation and mapping of forest biomass for the Canadian province of Alberta. Differences over successive decades provided an estimate of biomass change. Over 1500 permanent sample plots (PSP) were analyzed from across the range of lodgepole pine (Pinus contorta var. latifolia Engelm...

  10. Issues and strategies for large power buyers in Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Davies, D. [ENRON Canada Corp., Calgary, AB (Canada)

    2001-07-01

    America's leading commodity risk management company, Enron has 100 billion dollars in annual revenues in 2000. It operates EnronOnline, the largest e-commerce site in the world. With some corporate profile information on Enron and Enron Canada and its involvement in the Alberta electricity market, the author proceeded to discuss risk management issues and program development. It was stated that Enron believes that future outcomes can be changed, and risk management is a dynamic and iterative process used as a tool to decrease uncertainty. The risk appetite is defined and electricity risks clarified, then a review of physical operation characteristics is conducted. The risk management program and policy are defined, as well as the controls and reporting. The tools and tactics are defined and one is now ready for the implementation phase. The next section was devoted to credit and contracting issues before moving to the Alberta electricity market fundamentals and pricing and some insight provided on questions such as import/export in Alberta, regulatory issues, prices in Alberta. The last section of the presentation touched on EnronOnline which is a free, Internet-based global transaction system where one can view real time prices. tabs., figs.

  11. Incidence of melanoma in organ transplant recipients in Alberta, Canada.

    Science.gov (United States)

    Tran, Mimi; Sander, Megan; Ravani, Pietro; Mydlarski, P Régine

    2016-10-01

    Many studies have documented the increased risk of non-melanoma skin cancers in organ transplant recipients (OTRs). However, the incidence of melanoma is less well defined. To date, there have been no studies on the incidence of melanoma in Canadian OTRs. Herein, we determine the incidence and clinical features of melanoma in a cohort of OTRs in Southern Alberta, Canada. We used the Southern Alberta Transplant database to identify kidney and liver transplant recipients between the years 2000 and 2012. This population was cross-referenced with the Alberta Cancer Registry for a diagnosis of melanoma. The clinical features of all cases were obtained, and the standardized incidence rate was calculated. We identified 993 OTR patients, representing 5955 person-years. Only one patient developed a melanoma post-transplant, and this was a nodular melanoma. The age-standardized incidence rate was 11 per 100 000 (0.6 per 5955), compared to 13.4 per 100 000 in the general Alberta population (incidence rate ratio of 1.29, with 95% confidence interval of 0.17 to 9.82). This is the first Canadian study to investigate the association between organ transplantation and melanoma. Our study did not identify an increased risk of developing a de novo melanoma post-transplant. © 2016 John Wiley & Sons A/S. Published by John Wiley & Sons Ltd.

  12. Alberta's oil sands fiscal system : historical context and system performance

    International Nuclear Information System (INIS)

    2007-01-01

    This report described the fiscal system applied to Alberta's oil sands. It is the first technical report forming part of a series designed to provide information and to invite comment as part of the Government of Alberta's public review of the fiscal system applied to the province's oil and gas resources. Specifically, this report assessed the robustness of Alberta's oil sands fiscal system and assessed how the regime balanced the risks and rewards to both investors and Albertans across a range of expected and probable economic outcomes. The report provided an explanation of the history and context of Alberta's royalty regime and included a case-by-case approach. It also provided a discussion of the oil sands fiscal system description. Next, it described the methodology employed for the analysis of the oil sands fiscal system. It also provided the assumptions for 5 scenario cases and presented the fiscal map approach for assessing project economics and fiscal system performance. Last, summary observations were presented. It was found that the oil sands fiscal system is very flexible for adverse economic conditions and much less so for highly profitable conditions. tabs., figs

  13. As good as it gets : Alberta economic profile and forecast

    International Nuclear Information System (INIS)

    Hirsch, T.

    2006-04-01

    This economic profile and forecast report for the province of Alberta revealed that nearly every sector of the economy is operating at full, or near full capacity. Alberta's strong economy is a result of high energy prices, rapid population growth and rising employment. Increased provincial government spending along with tax reductions for businesses also contribute to a strong economy. However, the the province still faces some economic challenges, including a general labour shortage. Forestry and agriculture are under pressure of low commodity prices and high input costs, and the province has not articulated a long-term strategy for managing non-renewable natural resource revenue. In addition, the provincial economy is highly dependent upon volatile energy prices. Despite these challenges, the report states that the momentum is on the side of continued economic growth in Alberta. The Canada West Foundation is forecasting real growth in the gross domestic product of 5.2 per cent for 2006 and 4.7 per cent for 2007. The strong energy sector is largely responsible for much of Alberta's economic growth. An estimated 20,000 wells will be drilled in the province in 2006, and high oil prices will lead to record drilling and oil sands investment. This report also highlighted the economic activity in other sectors, including manufacturing, tourism, international exports, hi-tech, forestry, agriculture, and construction. Information regarding interprovincial migration and population growth was included along with public finances. 16 figs

  14. A Review of School Board Cyberbullying Policies in Alberta

    Science.gov (United States)

    Nosworthy, Nicole; Rinaldi, Christina

    2012-01-01

    An online search for school board cyberbullying/bullying policies in Alberta was conducted. The results showed that while only five school boards had a bullying policy, many schools had technology or Internet use guidelines. The online search included an assessment of one extensive school board cyberbullying policy as well as Internet use…

  15. Alberta's air quality index : facts at your fingertip

    International Nuclear Information System (INIS)

    2003-06-01

    Alberta Environment measures the airborne concentrations of carbon dioxide, fine particulate matter, nitrogen dioxide, ozone and sulphur dioxide on a continuous basis at air quality monitoring stations in Edmonton, Calgary, Red Deer and Beaverlodge. Every hour, the readings are converted to an Air Quality Index (AQI) number to report on Alberta's outdoor air quality as either good, fair, poor or very poor. The categories relate to guidelines under Alberta's Environmental Protection and Enhancement Act and reflect the maximum acceptable levels specified by the National Ambient Air Quality Objectives. Current air quality conditions are available to the public through Alberta Environment's web site or by phoning a toll free number. Both Edmonton and Calgary report good air quality at least 90 per cent of the time. Occasionally, air quality in the two cities may reach the fair category, but it is seldom poor. Fair, poor or very poor air quality occurs with strong temperature inversion and light winds. Under these conditions, air pollutants, usually from automobiles, are trapped in a layer of stagnant air. Fair and poor air quality can also be caused by summer heat when photochemical smog forms by chemical reactions with oxides of nitrogen and volatile hydrocarbons. 1 ref., 1 tab., 1 fig

  16. Alberta High School, College Elevate Learning with Rare Joint Venture

    Science.gov (United States)

    Pearson, George

    2012-01-01

    The refusal by a group of parents in Olds, Alberta, in 2003 to accept a provincial grant to renovate their high school set in motion a remarkable collaboration that spawned an innovative learning campus for an entire community and beyond. The new Olds High School, which opened in 2010, is part of a new Community Learning Campus (CLC), a joint…

  17. The low power miniature neutron source reactors: Design, safety and applications

    International Nuclear Information System (INIS)

    Ahmed, Y.A.; Ewa, I.O.B.; Umar, M.; Bezboruah, T.; Johri, M.; Akaho, E.H.K.

    2006-04-01

    The Chinese Miniature Neutron Source Reactor (MNSR) is a low power research reactor with maximum thermal neutron flux of 1 x 10 12 n.cm -2 .s -1 in one of its inner irradiation channels and thermal power of approximately 30kW. The MNSR is designed based on the Canadian SLOWPOKE reactor and is one of the smallest commercial research reactors presently available in the world. Its commercial versions currently in operation in China, Ghana, Iran, Nigeria, Pakistan and Syria, is considered as an excellent tool for Neutron Activation Analysis (NAA), training of Scientist, and Engineers in nuclear science and technology and small scale radioisotope production. The paper highlights the basic design and theory of the commercial MNSR, its safety features, applications and advantages over the Chinese Prototype. The experimental flux characteristics determined in this work and in similar studies by other authors reveal that the commercial MNSR has more flux stability, longer life span, higher negative temperature coefficient of reactivity and low under-moderation compared to its prototype in China. The result shows that the facility is safe for reactor physics experiments, teaching and training of students and also ideal for application of NAA for the determination of elemental composition of biological and environmental samples. It can also be a useful tool for geochemical and soil fertility mapping. (author)

  18. The Challenge of Integrating Renewable Generation in the Alberta Electricity Market

    Directory of Open Access Journals (Sweden)

    G. Kent Fellows

    2016-09-01

    Full Text Available Renewable electric generation is forecast to enjoy an increasing share of total capacity and supply regimes in the future. Alberta is no exception to this trend, having initiated policy incentives in response to calls for increasing the fraction of wind and solar energy available to the province over the next decade.1 This call is coming from various sectors including advocacy groups, the provincial government and some utilities. The University of Calgary’s School of Public Policy convened a roundtable discussion on Sept. 15, 2015. Given the wide-ranging aspects of increased renewables integration (for example the policy options, economic forces and engineering/technical issues the topic demands attention from a wide range of experts and stakeholders. To that end, we endeavoured to group expert panellists and representatives of utilities, public agencies, academe and consumer groups to consider the planning necessary to integrate new renewable capacity into the existing and future grid system in the province and its potential impact. The purpose of the roundtable was to facilitate and foster a knowledge exchange between interested and knowledgeable parties while also aggregating this knowledge into a more complete picture of the challenges and potential strategies associated with increased renewables integration in the Alberta electricity grid.

  19. Source Apportionment of VOCs in Edmonton, Alberta

    Science.gov (United States)

    McCarthy, M. C.; Brown, S. G.; Aklilu, Y.; Lyder, D. A.

    2012-12-01

    Regional emissions at Edmonton, Alberta, are complex, containing emissions from (1) transportation sources, such as cars, trucks, buses, and rail; (2) industrial sources, such as petroleum refining, light manufacturing, and fugitive emissions from holding tanks or petroleum terminals; and (3) miscellaneous sources, such as biogenic emissions and natural gas use and processing. From 2003 to 2009, whole air samples were collected at two sites in Edmonton and analyzed for over 77 volatile organic compounds (VOCs). VOCs were sampled in the downtown area (Central) and the industrial area on the eastern side of the city (East). Concentrations of most VOCs were highest at the East site. The positive matrix factorization (PMF) receptor model was used to apportion ambient concentration measurements of VOCs into eleven factors, which were associated with emissions source categories. Factors of VOCs identified in the final eleven-factor solution include transportation sources (both gasoline and diesel vehicles), industrial sources, a biogenic source, and a natural-gas-related source. Transportation sources accounted for more mass at the Central site than at the East site; this was expected because Central is in a core urban area where transportation emissions are concentrated. Transportation sources accounted for nearly half of the VOC mass at the Central site, but only 6% of the mass at the East site. Encouragingly, mass from transportation sources has declined by about 4% a year in this area; this trend is similar to the decline found throughout the United States, and is likely due to fleet turnover as older, more highly polluting cars are replaced with newer, cleaner cars. In contrast, industrial sources accounted for ten times more VOC mass at the East site than at the Central site and were responsible for most of the total VOC mass observed at the East site. Of the six industrial factors identified at the East site, four were linked to petrochemical industry production

  20. Economic impacts of Alberta's oil sands, volume 1

    International Nuclear Information System (INIS)

    Timilsina, G.R.; LeBlanc, N.; Walden, T.

    2005-01-01

    In 2004, the international media recognized Alberta's oil sands as part of the global oil reserves, thereby establishing Canada as second to Saudi Arabia as potential oil producing nations. The economic impacts of Alberta's oil sands industry on economies were assessed at regional, provincial and international levels for the 2000 to 2020 period. A customized input-output model was used to assess economic impacts, which were measured in terms of changes in gross domestic product; employment and labour income; and, government revenues. Cumulative impacts on employment by sector and by jurisdiction were also presented. An investment of $100 billion is expected through 2020, resulting in production of crude bitumen and synthetic crude oil outputs valued at about $531 billion. The impact of the oil sands industry on local employment was also evaluated. It was shown that activities in the oil sands industry will lead to significant economic impact in Alberta, Ontario, Quebec and the rest of Canada. Alberta's local economy would be the main beneficiary of oil sands activities with nearly 3.6 million person years employment created in Alberta during the 2000 to 2020. Another 3 million person years employment would be created in other Canadian provinces and outside Canada during the same time period. A sensitivity analysis on the responsiveness to oil prices and the removal of various constraints incorporated in the main analysis was also presented. The federal government will be the largest recipient of revenues generated to to oil sands activities. The results of the study were compared with that of the National Task Force on Oil Sands Strategies. This first volume revealed the results of the study while the second volume includes the data and detailed results. 48 refs., 57 tabs., 28 figs

  1. Adverse events following HPV vaccination, Alberta 2006-2014.

    Science.gov (United States)

    Liu, Xianfang C; Bell, Christopher A; Simmonds, Kimberley A; Svenson, Lawrence W; Russell, Margaret L

    2016-04-04

    In Canada, private purchase of human papilloma virus (HPV) vaccines has been possible since 2006. In Alberta, Canada, a publicly funded quadrivalent HPV vaccine program began in the 2008/2009 school year. There have been concerns about adverse events, including venous thromboembolism (VTE) associated with HPV vaccines. We describe the frequencies of adverse events following HPV vaccination among Alberta females aged 9 years or older and look at VTE following HPV vaccination. We used the Alberta Immunization and Adverse Reaction to Immunization (Imm/ARI) repository (publicly funded vaccine), the population-based Pharmaceutical Information Network (PIN) information system (dispensing of a vaccine), and the Alberta Morbidity and Ambulatory Care Abstract reporting system (MACAR) for June 1, 2006-November 19, 2014. Deterministic data linkage used unique personal identifiers. We identified all reported adverse events following immunization (AEFI) and all emergency department (ED) utilization or hospitalizations within 42 days of immunization. We calculated the frequency of AEFI by type, rates per 100,000 doses of HPV vaccine administered and the frequencies of ICD-10-CA codes for hospitalizations and emergency department visits. Over the period 195,270 females received 528,913 doses of HPV vaccine. Of those receiving at least one dose, 192 reported one or more AEFI events (198 AEFI events), i.e., 37.4/100,000 doses administered (95% CI 32.5-43.0). None were consistent with VTE. Of the women who received HPV vaccine 958 were hospitalized and 19,351 had an ED visit within 42 days of immunization. Four women who had an ED visit and hospitalization event were diagnosed with VTE. Three of these had other diagnoses known to be associated with VTE; the fourth woman had VTE among ED diagnoses but not among those for the hospitalization. Rates of AEFI after HPV immunization in Alberta are low and consistent with types of events seen elsewhere. Copyright © 2016 The Authors

  2. The regulatory context of gas flaring in Alberta

    International Nuclear Information System (INIS)

    Gilmour, B.S.; Cook, C.

    1999-01-01

    The legislative and regulatory regime regarding gas flaring in Alberta was reviewed. The issue of gas flaring has received much attention from petroleum industry regulators in Alberta. Residents living in the vicinity of flares have identified them as sources of odour, smoke, noise and air quality-related health concerns. Sulfur dioxide and carbon dioxide emissions from the flare stacks may contribute to acid rain and the greenhouse effect. The Strosher Report, released by the Alberta Research Council in 1996, has also identified about 250 different compounds in flare emissions, including volatile organic compounds (VOCs), polycyclic aromatic hydrocarbons (PAHs) and other products of incomplete combustion. The public opposition to solution gas flaring has caused regulators to consider new options designed to reduce the adverse economic and environmental impacts that may be associated with gas flaring. This paper discusses the roles of the Alberta Energy and Utilities Board (EUB) and Alberta Environmental Protection in administering legislation that impacts on gas flaring. In March 1999, the EUB released a guide containing the following five major points regarding gas flaring: (1) implementation of the Clean Air Strategic Alliance's (CASA's) recommendations to eventually eliminate flaring, by starting immediately to reduce flaring, and improve the efficiency of flares, (2) adoption of the CASA schedule of reduction targets for solution gas flaring, (3) conducting a review of the current approval process for small-scale electrical generation systems to encourage co-generation as a productive use of solution gas that is being flared, (4) creating better public notification requirements for new and existing facilities, and (5) discussing conflict resolution between operators and landowners. 26 refs

  3. US Department of Energy Nuclear Energy University program in robotics for advanced reactors: Program plan, FY 1987-1991

    International Nuclear Information System (INIS)

    Mann, R.C.; Gonzalez, R.C.; Tulenko, J.S.; Tesar, D.; Wehe, D.K.

    1987-07-01

    The US Department of Energy has provided support to four universities and the Oak Ridge National Laboratory in order to pursue research leading to the development and deployment of an advanced robotic system capable of performing tasks that are hazardous to humans, that generate significant occupational radiation exposure, and/or whose execution times can be reduced if performed by an automated system. The goal is to develop a generation of advanced robotic systems capable of performing surveillance, maintenance, and repair tasks in nuclear facilities and other hazardous environments. This goal will be achieved through a team effort among the Universities of Florida, Michigan, Tennessee, Texas, and the Oak Ridge National Laboratory, and their industrial partners, Combustion Engineering, Martin Marietta Baltimore Aerospace, Odetics, Remotec, and Telerobotics International. Each of the universities and ORNL have ongoing activities and corresponding facilities in areas of R and D related to robotics. This program is designed to take full advantage of these existing resources at the participating institutions

  4. Organic petrology of an early Paleocene coal zone, Wabamun, Alberta: palynology, petrography and geochemistry. [Canada - Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Demchuk, T.; Cameron, A.R.; Hills, L.V. (Amoco Production Co., Houston, TX (USA). Exploration Technical Services)

    1993-02-01

    An interdisciplinary investigation of a section through the early Paleocene Ardley coal zone at Wabamun, Alberta reveals that there are distinct vertical variations in the palynological, petrographical and geochemical properties reflecting changes in the original depositional environments. Coal petrography reveals that these coals are inertinite-rich. Thinner, stratigraphically lower seams at Wabamun (seams Nos. 6-3) consist predominantly of bright coal with high huminite contents. Palynofloral assemblages are comprised of [ital T. hiatus] with few abundances of other palynomorphs, suggesting that the original depositional environment was low-lying, dominated by taxodiaceous vegetation, and frequently flooded as evidenced by numerous shale partings, high ash contents and relatively high sulphur percentages. The thick No. 2 seams displays a distinct dulling-up petrographic profile resulting from increasing inertinite contents. The No. 1 seam consists of abundant fibrous (fusain-rich) coal. Modes of origin of this fibrous coal include extreme oxidation due to prolonged drought and possibly forest fires. Elevated ash contents within the Nos. 1 and 2 seams may be a result of this oxidation of organic matter and concentration of the inorganics, as well as airborne volcanic ash as evidenced by numerous bentonite bands within these coals. Sulphur contents are extremely low, as low as 0.05%, reflecting a terrestrial depositional environment. 46 refs., 6 figs., 1 tab.

  5. Studies Related to the Oregon State University High Temperature Test Facility: Scaling, the Validation Matrix, and Similarities to the Modular High Temperature Gas-Cooled Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Paul D. Bayless; Richard W. Johnson; William T. Taitano; James R. Wolf; Glenn E. McCreery

    2010-09-01

    The Oregon State University (OSU) High Temperature Test Facility (HTTF) is an integral experimental facility that will be constructed on the OSU campus in Corvallis, Oregon. The HTTF project was initiated, by the U.S. Nuclear Regulatory Commission (NRC), on September 5, 2008 as Task 4 of the 5 year High Temperature Gas Reactor Cooperative Agreement via NRC Contract 04-08-138. Until August, 2010, when a DOE contract was initiated to fund additional capabilities for the HTTF project, all of the funding support for the HTTF was provided by the NRC via their cooperative agreement. The U.S. Department of Energy (DOE) began their involvement with the HTTF project in late 2009 via the Next Generation Nuclear Plant project. Because the NRC interests in HTTF experiments were only centered on the depressurized conduction cooldown (DCC) scenario, NGNP involvement focused on expanding the experimental envelope of the HTTF to include steady-state operations and also the pressurized conduction cooldown (PCC). Since DOE has incorporated the HTTF as an ingredient in the NGNP thermal-fluids validation program, several important outcomes should be noted: 1. The reference prismatic reactor design, that serves as the basis for scaling the HTTF, became the modular high temperature gas-cooled reactor (MHTGR). The MHTGR has also been chosen as the reference design for all of the other NGNP thermal-fluid experiments. 2. The NGNP validation matrix is being planned using the same scaling strategy that has been implemented to design the HTTF, i.e., the hierarchical two-tiered scaling methodology developed by Zuber in 1991. Using this approach a preliminary validation matrix has been designed that integrates the HTTF experiments with the other experiments planned for the NGNP thermal-fluids verification and validation project. 3. Initial analyses showed that the inherent power capability of the OSU infrastructure, which only allowed a total operational facility power capability of 0.6 MW, is

  6. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

    After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

  7. Dante in Alberta: chronicle of an oil addicted civilization; Dante en Alberta: chroniques d'une civilisation droguee au petrole

    Energy Technology Data Exchange (ETDEWEB)

    Akram, Belkaid

    2010-07-01

    According to the author, Alberta, an heavenly province of Western Canada, is the theater of the biggest ecological crime of the moment in the form of oil exploitation. Alberta gathers all the aberrations and dramas that have been seen before in other oil producing countries, in particular in Africa, Middle-East and Asia: corruption, defiance of minority rights, terror threats, environment destruction etc

  8. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    Lu, Hong; Miller, D.W.

    1991-01-01

    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

  9. Proceedings of the 44. annual Alberta Soil Science Workshop

    International Nuclear Information System (INIS)

    Hao, X.; Shaw, C.

    2007-01-01

    The Alberta Soil Science Workshop is held annually in order to provide a forum for the discussion of issues related to soil sciences in Alberta. Attendees at the conference discussed a wide range of subjects related to soil sciences and measuring the environmental impacts of oil and gas activities in the province. The role of soil science in sustainable forest management was also examined. Issues related to acid deposition were reviewed, and recent developments in soil chemistry analysis for agricultural practices were discussed. Other topics included wildland soil analysis methods; the long-term impacts of sulphate deposition from industrial activities; and water chemistry in soils, lakes and river in the Boreal regions. Projects initiated to assess cumulative land use impacts on rangeland ecosystems were outlined along with a review of tools developed to optimize soil analysis techniques. One of the 46 presentations featured at this conference has been catalogued separately for inclusion in this database. refs., tabs., figs

  10. Management of routine solution gas flaring in Alberta

    International Nuclear Information System (INIS)

    1998-01-01

    Alberta's Clean Air Strategic Alliance (CASA) shares decision-making responsibilities with the Government of Alberta for strategic aspects of air quality. In 1997, the Alliance established the Flaring Project Team to develop recommendations that address potential and observed impacts associated with flaring, with particular focus on 'upstream solution gas' flaring. The upstream industry explores for, acquires, develops, produces and markets crude oil and natural gas. Essentially, solution gas at upstream sites is 'co-produced' during crude oil production. The project team was established to collect and summarize information on flaring and its impacts and to develop recommendations for short-term actions to minimize the practice of routine flaring of solution gas. Another goal of the team is to develop a research strategy to better understand flaring emissions and their effects on human, animal and environmental health. The team is working on developing long-term strategies for actions to address the gas flaring issue. 5 refs., 1 tab., 7 figs

  11. Public health preparedness in Alberta: a systems-level study

    Directory of Open Access Journals (Sweden)

    Noseworthy Tom

    2006-12-01

    Full Text Available Abstract Background Recent international and national events have brought critical attention to the Canadian public health system and how prepared the system is to respond to various types of contemporary public health threats. This article describes the study design and methods being used to conduct a systems-level analysis of public health preparedness in the province of Alberta, Canada. The project is being funded under the Health Research Fund, Alberta Heritage Foundation for Medical Research. Methods/Design We use an embedded, multiple-case study design, integrating qualitative and quantitative methods to measure empirically the degree of inter-organizational coordination existing among public health agencies in Alberta, Canada. We situate our measures of inter-organizational network ties within a systems-level framework to assess the relative influence of inter-organizational ties, individual organizational attributes, and institutional environmental features on public health preparedness. The relative contribution of each component is examined for two potential public health threats: pandemic influenza and West Nile virus. Discussion The organizational dimensions of public health preparedness depend on a complex mix of individual organizational characteristics, inter-agency relationships, and institutional environmental factors. Our study is designed to discriminate among these different system components and assess the independent influence of each on the other, as well as the overall level of public health preparedness in Alberta. While all agree that competent organizations and functioning networks are important components of public health preparedness, this study is one of the first to use formal network analysis to study the role of inter-agency networks in the development of prepared public health systems.

  12. Consultation with First Nations stakeholders : an Alberta perspective

    Energy Technology Data Exchange (ETDEWEB)

    Rutwind, S. [Alberta Justice, Edmonton, AB (Canada). Aboriginal Law

    2005-07-01

    Aboriginal issues present risks and challenges to resource development in Alberta. This paper provided an overview of significant precedents and acts which may impact on oil and gas activities. The Constitution Act of 1982 acknowledged that existing Aboriginal and treaty rights of the Aboriginal peoples of Canada were recognized and confirmed. In the case of R v. Sparrow, justification was established where there was a valid legislative objective, such as conservation and resource management, and a precedent was set regarding the interpretation of disputes of section 35 subsection 1 concerning legal restriction of the exercise of treaty rights, such as hunting and fishing. In R v. Badger, the Supreme Court of Canada (SCC) advised that the framework applied to treaty rights as well as Aboriginal rights. The Natural Resources Transfer Agreement transferred powers over natural resources from Canada to Alberta in relation to hunting rights. Proof of rights issues were discussed in Taku River Tlingit First Nation v. Tulesequa Chief Mine Project, as well as in Haida Nation v. British Columbia, where it was concluded that an Aboriginal right need not be proven before a duty to consult arises. A review of Alberta's consultation practices was presented, as well as the Aboriginal issues and resource development initiative, which recognizes the importance of consultation with affected Aboriginal people and communities when regulatory and development activities infringe their existing treaty and other constitutional rights, such as the rights to hunt, fish and trap for food. Details of the Consultation Coordination Group were presented. A draft of the Government of Alberta's First Nations Consultation Policy on Land Management and Resource Development was also presented. tabs, figs.

  13. Misplaced generosity: extraordinary profits in Alberta's oil and gas industry

    International Nuclear Information System (INIS)

    Boychuk, R.

    2010-11-01

    This document gives a picture extended over a decade of the revenues, investment levels and profits of the Alberta's oil and gas industry. It also investigates on the distribution of those revenues and profits that were accrued to the provincial government through royalties and land sales. This document, tries to fill the information gaps left by the current government's achievement as Albertans' oil and gas trustee, pointing out the ongoing lack of responsibility in this province's most important economic sector.

  14. Proceedings of Alberta's environment conference 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This conference addressed issues regarding the sustainable management of Alberta's earth resources and the importance of balancing resource exploitation with environmental protection and satisfying societal needs. The conference featured 36 sessions dealing with a range of subjects such as regulatory tools; social science; flood events and water infrastructure; perspectives on oil sands region; forest ecology; climate change; innovative technologies; emerging issues on wildlife; working together for the preservation of Alberta parks; First Nations; integrated land management; innovations in waste management; innovative technologies associated with natural gas; human health and wastewater contaminants; focus on partnerships; building environmental stewards; focus on agriculture; coalbed methane challenges and opportunities; sustainable municipalities; focus on water; Lake Wabamun situation and response; focus on lakes science and stewardship; biodiversity and geology; focus on water supply; focus on energy development; Alberta's environment industry; shared governance of the environment; irrigation; and, focus on water management. Five of the 135 presentations have been catalogued separately for inclusion in this database. refs., tabs., figs.

  15. Deregulation and the Alberta experience : the implications for Ontario

    International Nuclear Information System (INIS)

    Spearman, C.

    2002-01-01

    The government of Alberta deregulated its electric power industry to introduce industry structure and regulatory reforms that would promote competitive electricity prices. The objective was to ensure fairness for customers and generating facilities. A graph depicting power pool prices shows the reality of soaring prices at the onset of deregulation in Alberta. Today, there remains uncertainty in the development of retail choice, additional rate riders, new generation, transmission expansion, other jurisdictions and future prices. Consumers are still poorly equipped to make decisions and farmers have no means of protection from fluctuating electricity prices. They see deregulation as a complete failure because costs are up and benefits are nowhere to be seen. Ontario can learn from the Alberta experience by adopting the recommendations to set financial penalties for incompetence, financial compensation to customers for errors, and to be fully ready with systems tested ahead of deregulation. Anticipated customer benefits should be clearly identified in advance. The future electric power industry in Ontario needs vision, stability, a cohesive plan, and leadership devoid of complacency. 1 fig

  16. Asian-Pacific markets : a new strategy for Alberta oil

    International Nuclear Information System (INIS)

    Laureshen, C.J.; Du Plessis, D.; Xu, C.M.; Chung, K.H.

    2004-01-01

    Alberta's oil sands contain an estimated crude bitumen-in-place of nearly 2.5 trillion barrels. Production has increased to the point where it has overtaken non-conventional sources, and is expected to reach more than 2 million barrels per day by 2012, and over 5 million barrels per day by 2030. Although it is assumed that most of this production will be marketed in the United States, the industry is facing many constraints that could affect potential crude oil production and existing market share. The Asian-Pacific region is an obvious new market for Canadian heavy oil and bitumen due to an increasing demand for petroleum products in that region and the potential for reaching the California market with the same pipeline. This paper examined the following three criteria that will determine the success of any initiative to move Canadian crude oil to Asian-Pacific markets: (1) a sustainable supply of crude from Alberta; a pipeline to transport the crude to a deepwater port on the west coast; and, a guaranteed market at the other end. The feasibility of marketing Alberta heavy oil and bitumen to Asia was also discussed. 12 refs., 1 tab., 8 figs

  17. CO2 in Alberta - a vision of the future

    International Nuclear Information System (INIS)

    Edwards, K.

    1999-01-01

    The potential to develop a province-wide infrastructure for carbon dioxide (CO 2 ) collection and transmission was discussed. The petroleum industry's original interest in CO 2 was its potential for enhanced oil recovery (EOR) for Alberta's depleted oil fields. However, new interest has stemmed from its perceived role in global climate change and the potentially negative business and economic implications of emitting CO 2 into the atmosphere. It was suggested that the development of a province wide infrastructure to collect CO 2 would address both interests. A simple screening of the reservoirs was carried out to determine if Alberta has the right oil reservoirs and sufficient CO 2 supplies to support a large-scale CO 2 infrastructure. The proposed infrastructure would consist of CO 2 supplies from electrical power generation plants, CO 2 trunklines, feeder pipelines to deliver CO 2 from the trunklines to the field and the oil reservoirs where the CO 2 would be injected. Such infrastructures already exist in Texas and Mexico where more than 1 billion scf per day of CO 2 is used for EOR. This study compared the factors leading to a large-scale CO 2 industry with factors in place during the 1970s and 1980s, when most of the hydrocarbon miscible floods were initiated in Alberta. It was concluded that the preliminary economics suggest that the concept has merit. 12 refs., 3 tabs., 9 figs

  18. Natural gas from coal : the community consultation process in Alberta

    International Nuclear Information System (INIS)

    Robinson, G.

    2005-01-01

    The community consultation process was examined with reference to natural gas from coal (NGC) development in Alberta. It was suggested that NGC has a huge potential in Canada, and can be developed in an environmentally responsible manner which considers all stakeholders. However, water supply shortages and the effects of development on groundwater remain key stakeholder concerns in Alberta. Issues concerning water protection and handling were discussed, along with issues concerning surface disruption during resource development activities. An outline of road needs and pipeline corridors was presented. An outline of a typical NGC compressor station were given. Issues concerning public anxiety over air quality were discussed with reference to flaring and landowner complaints. It was noted NGC is not sour and contains no liquid hydrocarbons or foreign contaminants. A review of government regulations and best practices was presented with regards to flaring. Multi-stakeholder advisory committee practices were reviewed. It was concluded that Alberta is currently using a variety of consultation processes to enable better communications between industry and stakeholders. figs

  19. Mental health services costs within the Alberta criminal justice system.

    Science.gov (United States)

    Jacobs, Philip; Moffatt, Jessica; Dewa, Carolyn S; Nguyen, Thanh; Zhang, Ting; Lesage, Alain

    2016-01-01

    Mental illness has been widely cited as a driver of costs in the criminal justice system. The objective of this paper is to estimate the additional mental health service costs incurred within the criminal justice system that are incurred because of people with mental illnesses who go through the system. Our focus is on costs in Alberta. We set up a model of the flow of all persons through the criminal justice system, including police, court, and corrections components, and for mental health diversion, review, and forensic services. We estimate the transitional probabilities and costs that accrue as persons who have been charged move through the system. Costs are estimated for the Alberta criminal justice system as a whole, and for the mental illness component. Public expenditures for each person diverted or charged in Alberta in the criminal justice system, including mental health costs, were $16,138. The 95% range of this estimate was from $14,530 to $19,580. Of these costs, 87% were for criminal justice services and 13% were for mental illness-related services. Hospitalization for people with mental illness who were reviewed represented the greatest additional cost associated with mental illnesses. Treatment costs stemming from mental illnesses directly add about 13% onto those in the criminal justice system. Copyright © 2016 Elsevier Ltd. All rights reserved.

  20. Imports, exports, and Alberta's transmission system impact on price fluctuation

    International Nuclear Information System (INIS)

    Johnson, K.

    2002-01-01

    The roles, responsibilities and objectives of ESBI, a private for-profit company, appointed by the Alberta Government to be the Independent Transmission Administrator in the province, is sketched, prior to a discussion of price volatility in electricity, Alberta interconnections, intertie issues, the economic theory and the reality impact on prices. Given that imports and exports constitute a relatively small proportion of total generation or load in Alberta, price volatility is considered to have been only minimally affected by imports/exports. In contrast, transmission constraints, i.e. the limits on physical capacity of the existing transmission system to accommodate all desired transactions, have significant impact on imports/exports. Factors underlying constraints and price volatility such as uncertainty of generation dispatch, leading to reduced interest to invest, which in turn leads to scarce capacity for imports/exports, and the actions required to reduce uncertainty and address other issues such as congestion management, tariff design and the creation of regional transmission organizations, are also discussed to provide further clarification of the issues. It is suggested that these and other related issues need to be resolved to provide the clarity around transmission access and the tools required to manage price fluctuations

  1. Alberta bitumen strategies and royalties delivered in kind

    Energy Technology Data Exchange (ETDEWEB)

    Ekelund, Mike [Alberta Department of Energy (Canada)

    2011-07-01

    With North America's growing energy demands, Alberta's oil sands will provide a secure source of energy, especially considering the region's bitumen production growth potential for years to come. The Government of Alberta's provincial energy strategy is a guiding document for resource development, which includes bitumen production. Bitumen production policies developed under the strategy aim to support clean energy development, wise energy use, and sustained economic prosperity. Such policies include reducing CO2 emissions through carbon capture and storage projects, and improved monitoring, aligned regulations and efficient enforcement in the industry though a regulatory enhancement project. Bitumen Royalty in Kind (BRIK) has been one tool used to implement some aspects of the trategy, such as fostering value-added oil sands development, enhancing the bitumen market in Alberta, and sharing in the gains while working to mitigate the risks from processing bitumen into further value added products. Work continues on many policies and strategies involving BRIK that will impact bitumen development and markets.

  2. Alberta's conventional oil supply: How much? How long?

    International Nuclear Information System (INIS)

    Heath, M.

    1992-01-01

    To assess the future conventional crude oil supply potential in Alberta, a modelling system was designed with the capacity to determine the fraction of existing and potential reserves which could prove technically, economically and/or commercially viable over time. The reference case analysis described assumed constant real oil prices and fiscal burdens, capital and operating costs. Reserve additions from new pool discoveries were summed with reserves from existing pools to arrive at an estimate of the potential supply of established reserves in each play area. The established reserves from all plays were then totalled to provide the provincial conventional oil resource potential. Alberta's recoverable conventional crude oil reserves were shown to be declining at about 2 percent per year. However, even with declining recoverable reserves and relatively low prices, the results of the study indicated that the conventional oil industry remained a major revenue generator for the province and would continue to be so over the next 15 to 20 years. Improved operating efficiencies, cost reductions, reasonable prices and cooperation between industry and government were shown to be necessary to assure the continued viability of Alberta's conventional oil industry. figs., tabs., 11 refs

  3. Discrimination of Earthquake and Blast Seismicity in Western Alberta

    Science.gov (United States)

    Spriggs, N.; Law, A.; Yenier, E.; Reynen, A.; Baturan, D.

    2015-12-01

    Recorded seismicity in western Alberta is caused by natural and induced earthquakes or blast events from mining and quarry operations. Accurate discrimination of earthquakes from blast events is crucial for evaluating recent seismicity with respect to the historical catalog and for assessing seismic hazards associated with naturally occurring or induced seismicity. In general, blast events are discriminated from earthquakes based on their proximity to active mines and quarries in addition to day-of-week and time-of-day timing patterns. In some parts of western Alberta, however, seismicity originates in regions with active mines, historical earthquake seismicity, and hydraulic fracturing operations. Based on timing patterns or event locations alone, natural or induced seismicity may be misidentified as mining activity. Several studies report that relative differences in Fourier or response spectra can be used to discriminate blast and earthquake events. Other studies report that the relative timing and amplitude of seismic phases may provide useful metrics for classifying blast events. Here we propose an alternative method that accounts for both differences in phase spectra and phase timing and amplitude. In particular, we evaluate the normalized time integral for characteristic functions of particle motion from confirmed blast and earthquake events recorded by regional Alberta seismic networks. We then use these time-integral profiles to re-classify events that are initially categorized as suspected blasts based on timing pattern and event location indicators.

  4. The Alberta Hip and Knee Replacement Project: a model for health technology assessment based on comparative effectiveness of clinical pathways.

    Science.gov (United States)

    Gooch, Katherine L; Smith, Douglas; Wasylak, Tracy; Faris, Peter D; Marshall, Deborah A; Khong, Hoa; Hibbert, Julie E; Parker, Robyn D; Zernicke, Ronald F; Beaupre, Lauren; Pearce, Tim; Johnston, D W C; Frank, Cyril B

    2009-04-01

    baseline characteristics of patients in the two study arms, including demographics, comorbidity as measured by CDS and exposure to pain medications, and health-related quality of life, as measured by Western Ontario and McMaster Universities Osteoarthritis Index and Short Form-36, were similar. The Alberta Hip and Knee Replacement Project demonstrates the feasibility and advantages of applying a pragmatic randomized controlled trial to ascertain comparative effectiveness. This is a model for health technology assessment that incorporates how clinical pathways can be effectively evaluated.

  5. 81.114- University Reactor Infrastructure and Education Support / Prompt Gamma-ray Activation Analysis of Lithioum Ion Battery Cathodes

    Energy Technology Data Exchange (ETDEWEB)

    Manthiram, Arumugam; Landsberger, S.

    2006-11-11

    This project focuses on the use of the Prompt Gamma-ray Activation Analysis (PGAA) technique available at the Nuclear Engineering Teaching Laboratory of the University of Texas at Austin to precisely determine the hydrogen (proton) contents in layered oxide cathode samples obtained by chemical lithium extraction in order to obtain a better understanding of the factors limiting the practical capacities and overall performance of lithium ion battery cathodes. The project takes careful precautionary experimental measures to avoid proton contamination both from solvents used in chemical delithiation and from ambient moisture. The results obtained from PGAA are complemented by the data obtained from other techniques such as thermogravimetric analysis, redox titration, atomic absorption spectroscopy, X-ray diffraction, and mass spectroscopic analysis of the evolved gas on heating. The research results broaden our understanding of the structure-property-performance relationships of lithium ion battery cathodes and could aid the design and development of new better performing lithium ion batteries for consumer (portable and electric vehicles), military, and space applications.

  6. Assessment of the National Research Universal Reactor Proposed New Stack Sampling Probe Location for Compliance with ANSI/HPS N13.1-1999

    Energy Technology Data Exchange (ETDEWEB)

    Glissmeyer, John A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Antonio, Ernest J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Flaherty, Julia E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-02-29

    This document reports on a series of tests conducted to assess the proposed air sampling location for the National Research Universal reactor (NRU) complex exhaust stack, located in Chalk River, Ontario, Canada, with respect to the applicable criteria regarding the placement of an air sampling probe. Due to the age of the equipment in the existing monitoring system, and the increasing difficulty in acquiring replacement parts to maintain this equipment, a more up-to-date system is planned to replace the current effluent monitoring system, and a new monitoring location has been proposed. The new sampling probe should be located within the exhaust stack according to the criteria established by the American National Standards Institute/Health Physics Society (ANSI/HPS) N13.1-1999, Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stack and Ducts of Nuclear Facilities. These criteria address the capability of the sampling probe to extract a sample that represents the effluent stream. The internal Pacific Northwest National Laboratory (PNNL) project for this task was 65167, Atomic Energy Canada Ltd. Chalk River Effluent Duct Flow Qualification. The testing described in this document was guided by the Test Plan: Testing of the NRU Stack Air Sampling Position (TP-STMON-032).

  7. H Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

  8. Cadmium-emitter self-powered thermal neutron detector performance characterization & reactor power tracking capability experiments performed in ZED-2

    Energy Technology Data Exchange (ETDEWEB)

    LaFontaine, M.W., E-mail: physics@execulink.com [LaFontaine Consulting, Kitchener, Ontario (Canada); Zeller, M.B. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Nielsen, K. [Royal Military College of Canada, SLOWPOKE-2 Reactor, Kingston, Ontario (Canada)

    2014-07-01

    Cadmium-emitter self-powered thermal neutron flux detectors (SPDs), are typically used for flux monitoring and control applications in low temperature, test reactors such as the SLOWPOKE-2. A collaborative program between Atomic Energy of Canada, academia (Royal Military College of Canada (RMCC)) and industry (LaFontaine Consulting) was initiated to characterize the incore performance of a typical Cd-emitter SPD; and to obtain a definitive measure of the capability of the detector to track changes in reactor power in real time. Prior to starting the experiment proper, Chalk River Laboratories' ZED-2 was operated at low power (5 watts nominal) to verify the predicted moderator critical height. Test measurements were then performed with the vertical center of the SPD emitter positioned at the vertical mid-plane of the ZED-2 reactor core. Measurements were taken with the SPD located at lattice position L0 (near center), and repeated at lattice position P0 (in D{sub 2}O reflector). An ionization chamber (part of the ZED-2 control instrumentation) monitored reactor power at a position located on the south side of the outside wall of the reactor's calandria. These experiments facilitated measurement of the absolute thermal neutron sensitivity of the subject Cd-emitter SPD, and validated the power tracking capability of said SPD. Procedural details of the experiments, data, calculations and associated graphs, are presented and discussed. (author)

  9. Woodland caribou management in Alberta: historical perspectives and future opportunities

    Directory of Open Access Journals (Sweden)

    Elston H. Dzus

    2007-04-01

    Full Text Available Woodland caribou conservation has been the topic of much debate for the past few decades. By the late 1970s there was growing concern about declining woodland caribou populations and the interaction between industrial activities and woodland caribou. Initial concerns led to the closure of the licensed hunting season in 1981. Early confrontation between government and industry in the late 1980s transformed into a series of evolving collaborative ventures. Improving our understanding of the basic ecology of woodland caribou in Alberta was at the center of early research efforts; more recent studies have examined the effects of industrial activities on caribou and effectiveness of various mitigation factors. Despite having amassed an impressive body of information from a research and monitoring perspective, progress on implementing effective management actions has been less dramatic. Industry has endured significant costs implementing a variety of perceived conservation initiatives, but caribou populations continued to decline through the last few decades. While some parties feel more research is needed, there is growing consensus that changes to habitat as induced by human activities are important factors influencing current caribou declines. Predation is a proximate cause of most caribou mortality. Climate change mediated alterations to habitat and predator-prey interactions remain a key source of uncertainty relative to future caribou population trends. Management actions will need to deal with long term habitat changes associated with human land use and short term implications of increased predation. In 2005, the provincial minister responsible for caribou conservation responded to the draft 2004 recovery plan and created the Alberta Caribou Committee (ACC. The goal of the ACC is to maintain and recover woodland caribou in Alberta’s forest ecosystems while providing opportunities for resource development, following guidance provided by the

  10. Enhancing the Alberta Tax Advantage with a Harmonized Sales Tax

    Directory of Open Access Journals (Sweden)

    Philip Bazel

    2013-09-01

    Full Text Available Alberta enjoys a reputation as a fiercely competitive jurisdiction when it comes to tax rates. But the reality is that the province can do better with a tax mix that has greater emphasis on consumption, rather than income tax levies. While Alberta has a personal tax advantage compared to other Canadian jurisdictions — but not the United States — it relies most heavily on income taxes and non-resource revenues that impinges on investment and saving. Taxes on new investment in Alberta’s non-resource sectors are no better than average, compared to other countries in the Organization for Economic Cooperation and Development, or OECD, so it is not exceptionally attractive to many different kinds of investors. And Alberta’s corporate income tax rate is not much more competitive than the world average for manufacturing and service companies. By introducing the Harmonized Sales Tax with a provincial rate of 8 per cent (in addition to the federal 5 per cent rate, Alberta has the ability to make its tax system more competitive. An HST would even allow the province to entirely eliminate income tax for the majority of families. And because the HST would be easily administered using the same collection mechanisms that already exist for the GST, implementing a new Alberta HST could be done relatively smoothly and with minimal additional administration costs. Adopting an Alberta HST is the simplest, most efficient and fairest way to reform the provincial tax system, and will deliver noticeable benefits to Albertans, most visibly in the form of significant income tax relief. It would enable the province to raise the income-tax exemption from $17,593 to $57,250, making it possible for couples to earn up to $114,500 free of any provincial income taxes. In addition, the province could lower income tax rates for income over that amount from 10 to nine per cent. And with the revenue from the HST, Alberta would have the capacity to lower its general corporate

  11. Advantage or illusion: is Alberta's progress sustainable?

    Energy Technology Data Exchange (ETDEWEB)

    Anielski, M. [Pembina Institute for Appropriate Development, Drayton Valley, AB (Canada)

    2001-08-01

    A new indicator of economic and environmental well-being, the Genuine Progress Indicators, of GPI, is discussed as part of an attempt to gauge the state of health of Alberta's economy, and to establish whether the tremendous apparent economic progress made by the province in recent decades is real or illusory. The GPI, an accounting system by which nations can measure real progress and real wealth, was developed by the Pembina Institute for Appropriate Development of Alberta. It combines 51 indicators of economic, social and environmental measures, and is consistent with international efforts to find new measures of well-being and human development. Based on a study using the GPI system, real disposable income of Albertans was 5.5 per cent lower in 1999 than in 1982, despite a 36.3 per cent rise in Alberta's GDP per capita. This finding suggests that not all people are sharing in the the economic good times. Personal and household debt has also risen substantially and now exceeds real disposable income for the first time in history. Ability to save has been squeezed, resulting in protracted decline in personal savings, while Albertans pay 500 per cent more taxes in real dollars since 1961. Social and human health indicators highlight signs of social stress, such as rising levels of divorce, problem gambling and falling voter participation. Other indicators raise concerns about the condition of Alberta's natural capital, such as forests, agricultural soils, air and water quality, fish, wildlife and protected areas. Environmental GPIs show that Albertans have the fourth-highest ecological footprint in the world, exceeded only by the Arab Emirates, Singapore and the United States. The bigger the footprint the more is someone else on the planet shortchanged. The Pembina Institute report concludes that the development of Alberta's fossil fuel energy resources has come with a tremendous ecological price tag. It also shows that conventional crude oil

  12. Canadian Mathematics Education Study Group = Groupe Canadien d'Etude en Didactique des Mathematiques. Proceedings of the Annual Meeting (25th, Edmonton, Alberta, Canada, May 25-29, 2001).

    Science.gov (United States)

    Simmt, Elaine, Ed.; Davis, Brent, Ed.

    2001-01-01

    This document contains the proceedings of the 2001 annual meeting of the Canadian Mathematics Education Study Group (CMESG) held at the University of Alberta, May 25-39, 2000. The proceedings consist of two plenary lectures, four working groups, five topic sessions, new Ph.D. reports, an AD Hoc Session, and panel discussions. Papers include: (1)…

  13. Proceedings of the 2006 Annual Meeting of the Canadian Mathematics Education Study Group = Actes de la Rencontre Annuelle 2006 du Groupe Canadien d'Etude en Didactique des Mathematiques (30th, Calgary, Alberta, Canada, Jun 3-7, 2006)

    Science.gov (United States)

    Liljedahl, Peter, Ed.

    2007-01-01

    This submission contains the Proceedings of the 2006 Annual Meeting of the Canadian Mathematics Education Study Group (CMESG), held at the University of Calgary in Calgary, Alberta. The CMESG is a group of mathematicians and mathematics educators who meet annually to discuss mathematics education issues at all levels of learning. The aims of the…

  14. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    Hicks, D.

    1970-04-01

    The principles of nuclear, thermal and hydraulic performance calculations for water cooled reactors are discussed. The principles are illustrated by describing their implementation in the UKAEA PATRIARCH scheme of computer codes. This material was originally delivered as a course of lectures at the Technical University of Helsinki in Summer of 1969.

  15. Reserve growth in oil pools of Alberta: Model and forecast

    Science.gov (United States)

    Verma, M.; Cook, T.

    2010-01-01

    Reserve growth is recognized as a major component of additions to reserves in most oil provinces around the world, particularly in mature provinces. It takes place as a result of the discovery of new pools/reservoirs and extensions of known pools within existing fields, improved knowledge of reservoirs over time leading to a change in estimates of original oil-in-place, and improvement in recovery factor through the application of new technology, such as enhanced oil recovery methods, horizontal/multilateral drilling, and 4D seismic. A reserve growth study was conducted on oil pools in Alberta, Canada, with the following objectives: 1) evaluate historical oil reserve data in order to assess the potential for future reserve growth; 2) develop reserve growth models/ functions to help forecast hydrocarbon volumes; 3) study reserve growth sensitivity to various parameters (for example, pool size, porosity, and oil gravity); and 4) compare reserve growth in oil pools and fields in Alberta with those from other large petroleum provinces around the world. The reported known recoverable oil exclusive of Athabasca oil sands in Alberta increased from 4.5 billion barrels of oil (BBO) in 1960 to 17 BBO in 2005. Some of the pools that were included in the existing database were excluded from the present study for lack of adequate data. Therefore, the known recoverable oil increased from 4.2 to 13.9 BBO over the period from 1960 through 2005, with new discoveries contributing 3.7 BBO and reserve growth adding 6 BBO. This reserve growth took place mostly in pools with more than 125,000 barrels of known recoverable oil. Pools with light oil accounted for most of the total known oil volume, therefore reflecting the overall pool growth. Smaller pools, in contrast, shrank in their total recoverable volumes over the years. Pools with heavy oil (gravity less than 20o API) make up only a small share (3.8 percent) of the total recoverable oil; they showed a 23-fold growth compared to

  16. Sulphur recovery guidelines for sour gas plants in Alberta

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-01

    This report presents the decision of Alberta Environment (AE) and the Energy Resources Conservation Board (ERCB) on sulfur recovery guidelines for sour gas plants in Alberta. The report also includes a summary of the review process and the recommendations and views of the participants. AE and ERCB agree that generally, the sour gas industry operates well within Alberta's stringent standards for ambient air sulfur dioxide concentrations, and that there is no evidence to date that demonstrates that sulfur emissions from that industry have had a deleterioius effect on local health or environment. However, in the view that the long term objective must be to limit atmospheric loading of pollutants to the extent that is practical, AE and ERCB have concluded that some upward adjustment to the requirements would be in the public interest, particularly where the technlogy appears to be available and the cost is not prohibitive. Effective immediately, new plants sized at 2,000 tonnes/d or larger will be subject to sulfur recovery requirements which have increased from 99 to 99.8%, with lower requirements for plants of lower sizes. It is important to note that for individual plants, AE and ERCB would consider requiring sulfur recovery levels higher than set out in the guidelines if a site-specific need were shown to exist. In addition, it is believed that some degree of sulfur recovery should be required for plants in the 1 to 10 tonne/d range, at which sulfur recovery is not now required. The new requirements apply to all new plants, to existing plants with substantial capacity expansion or process modification, or in cases where substantial new sour gas volumes, not in the original plant approval, have occurred. 3 figs.

  17. U.S. Domestic Reactor Conversion Programs

    International Nuclear Information System (INIS)

    Woolstenhulme, Eric

    2008-01-01

    The Conversion Projects Include: the revision of the facilities safety basis documents and supporting analysis, the fabrication of new LEU fuel, the change-out of the reactor core, and the removal of the used HEU fuel (by INL University Fuels Program or DOE-NE). The major entities involved are: the U.S. Nuclear Regulatory Commission, the University reactor department, the fuel and hardware fabricators, the Spent fuel receipt facilities, the Spent fuel shipping services, and the U.S. Department of Energy and their subcontractors. Three major Reactor Conversion Program milestones have been accomplished since 2006: the conversion of the TRIGA reactor at Texas A and M University Nuclear Science Center, the conversion of the University of Florida Training Reactor, and the conversion of the Purdue University Reactor. Four Reactor Conversion Program milestones yet to be accomplished in 2008 and 2009: the Washington State University Nuclear Radiation Center reactor, the Oregon State University TRIGA Reactor, the University of Wisconsin Nuclear Reactor, and the Neutron Radiography Reactor Facility. NNSA is committed to doing things cheaper, better, smarter, safer through a 'Lessons Learned' process. The conversion team assessed each major activity grouping: Project Initiation, Conversion Proposal Development, Fuel Fabrication and Hardware, Core Conversion, and Spent Nuclear Fuel Removal. Issues were identified and recommendations were given

  18. Research reactor standards and their impact on the TRIGA reactor community

    International Nuclear Information System (INIS)

    Richards, W.J.

    1980-01-01

    The American Nuclear Society has established a standards committee devoted to writing standards for research reactors. This committee was formed in 1971 and has since that time written over 15 standards that cover all aspects of research reactor operation. The committee has representation from virtually every group concerned with research reactors and their operation. This organization includes University reactors, National laboratory reactors, Nuclear Regulatory commission, Department of Energy and private nuclear companies and insurers. Since its beginning the committee has developed standards in the following areas: Standard for the development of technical specifications for research reactors; Quality control for plate-type uranium-aluminium fuel elements; Records and reports for research reactors; Selection and training of personnel for research reactors; Review of experiments for research reactors; Research reactor site evaluation; Quality assurance program requirements for research reactors; Decommissioning of research reactors; Radiological control at research reactor facilities; Design objectives for and monitoring of systems controlling research reactor effluents; Physical security for research reactor facilities; Criteria for the reactor safety systems of research reactors; Emergency planning for research reactors; Fire protection program requirements for research reactors; Standard for administrative controls for research reactors. Besides writing the above standards, the committee is very active in using communications with the nuclear regulatory commission on proposed rules or positions which will affect the research reactor community

  19. Team effectiveness in primary care networks in Alberta.

    Science.gov (United States)

    Drew, Peter; Jones, Brad; Norton, Douglas

    2010-01-01

    Primary care networks (PCNs) are interdisciplinary programs in a geographical area that are designed to improve patient care, team collaboration and appropriate resource allocation. They are one of government's approaches to delivering quality healthcare with finite resources. The primary objective of this study was to explore the level of perceived team effectiveness in PCNs within three former health regions in Alberta. A descriptive, cross-sectional, exploratory, semi-structured questionnaire study design was employed. Respondents identified five themes for strategies to improve team effectiveness. Although many factors and strategies were identified, more work is needed to explore the study's findings.

  20. Alberta's economic development of the Athabasca oil sands

    Science.gov (United States)

    Steinmann, Michael

    This dissertation examines the 61-year evolution of public policies pertaining to development of Alberta's non-conventional source of crude oil. The Athabasca oil sands contain an estimated 1.5 trillion barrels and provide for a safe continental supply. The Provincial Government first sponsored this undertaking in 1943. The period from then to 1971 was one of a transition from a wheat economy to a natural-resource economic base. A stable government emerged and was able to negotiate viable development policies. A second period, 1971 to 1986, was marked by unstable world conditions that afforded the Alberta government the ability to set terms of development with multi-national oil firms. A 50% profit-sharing plan was implemented, and basic 1973 terms lasted until 1996. However, 1986 was a critical year because the Organization of Petroleum Exporting Countries (OPEC) reduced prices, causing the Alberta economy to lapse into recession. During a third period, 1986 to 1996, the Alberta Government was unable to adapt quickly to world conditions. A new leadership structure in 1996 made major changes to create ongoing fiscal and development policies. That history provides answers to two primary research questions: How do public policies affect the behaviors of the modern corporation and visa versa? What are the implications for development theory? Two sources of information were used for this study. First, it was possible to review the Premier's files located in the Provincial Archives. Materials from various government libraries were also examined. Some 7,000 documents were used to show the evolution of government policymaking. Second, interviews with leaders of oil companies and federal research facilities were important. Findings support the thesis that, to facilitate oil sands development, government and the private sector have closely collaborated. In particular, revenue policies have allowed for effective R&D organization. Relying on intensive technological

  1. Recommendations and final report on the Alberta transmission administrator function

    International Nuclear Information System (INIS)

    Billinton, R.; Wallace, R.B.

    1997-01-01

    In May 1995, the Electric Utilities Act (EUA) was passed formalizing the Alberta government's policy of electric industry restructuring. The Act established two new important market entities: a power pool and a transmission administrator (TA). Combined, these two entities create the open access required to enable competition in generation. Functionally, the TA acts as a single transmission service agent for all transmission wire owners. The TA leases the wires from owners then provides a province-wide tariff schedule for transmission services to recover the required revenue. Customers can only purchase transmission service from the TA. Both the lease wire cost and the TA tariff schedule must be approved by the regulator

  2. Alberta Consumers' Valuation of Extrinsic and Intrinsic Red Meat Attributes

    DEFF Research Database (Denmark)

    Steiner, Bodo; Gao, Fei; Unterschultz, Jim

    2010-01-01

    This paper analyzes Alberta consumers’ perceptions toward extrinsic and intrinsic attributes of bison and beef steaks. In contrast to published Canadian consumer studies on bison meat that were undertaken prior to May 2003, before the first BSE case of Canadian origin was identified in beef cattle......, this study provides a “post-BSE” assessment of consumer perceptions toward selected bison meat attributes. The results from an attribute-based choice experiment provide little support that simple traceability assurance schemes have value to consumers of bison and beef steaks, thus confirming similar findings...

  3. Preventing Domestic Violence in Alberta: A Cost Savings Perspective

    Directory of Open Access Journals (Sweden)

    Lana Wells

    2012-06-01

    Full Text Available Recent studies show that Alberta has the fifth highest rate of police reported intimate partner violence and the second highest rate of self reported spousal violence in Canada, and despite a 2.3 percent decline over the last decade, the province’s rate of self-reported domestic violence has stubbornly remained among the highest in Canada; rates of violence against women alone are 2.3 percentage points higher than the national average. In fact, every hour of every day, a woman in Alberta will undergo some form of interpersonal violence from an ex-partner or ex-spouse. Besides the devastating toll that domestic violence has on victims and their families, the ongoing cost to Albertans is significant. In the past five years alone it is estimated that over $600 million will have been spent on the provision of a few basic health and non health supports and that the majority of this cost ($521 million is coming out of the pockets of Albertans in the form of tax dollars directed at the provision of services. Fortunately, investment in quality prevention and intervention initiatives can be very cost effective, returning as much as $20 for every dollar invested. Recent research on preventative programming in the context of domestic violence shows promising results in reducing incidents of self-reported domestic violence. The economic analysis of this preventative programming suggests that the benefits of providing the various types of programming outweighed the costs by as much as 6:1. The potential cost savings for the Alberta context are significant; the implementation of these preventative programs has been estimated to be approximately $9.6 million while generating net cost-benefits of over $54 million. Domestic violence is a persistent blight, and continues to have a significant impact on individuals and families in Alberta, but potent tools exist to fight it. This brief paper offers a cogent summary of its costs, and the benefits that could be

  4. Government Policy and Postsecondary Education in Alberta: A "Field Theory" Analysis

    Science.gov (United States)

    Schmaus, David; Wimmer, Randolph

    2013-01-01

    While the landscape of postsecondary education in Alberta continues to expand and diversify, there seems to be very little written about the organization of postsecondary education in the province over the past 15 to 20 years (Wimmer & Schmaus, 2010). This paper provides an analysis of postsecondary education in Alberta over the past 15 to 20…

  5. Comparative analysis of fiscal terms for Alberta oil sands and international heavy and conventional oils

    International Nuclear Information System (INIS)

    Van Meurs, P.

    2007-01-01

    There are considerable differences between international heavy oil and Alberta oil sands projects, notably the high viscosity of the bitumen in the oil sands reservoirs. The oil sands bitumen do not flow to wells without heating the bitumen, thereby adding to the already high cost of Alberta oil sand operations. This report provided an economic comparison of Alberta oil sands and international heavy oil projects. It also included a brief scoping review to compare with conventional oil regimes. Full exploration costs including the costs of dry holes were allocated to conventional oil operations in order to obtain a proper comparison. This investigation included the costs of dry holes. The report was a follow up to an earlier study released on April 12, 2007 on the preliminary fiscal evaluation of Alberta oil sand terms. The report provided an economic framework and described project selection. It then provided a discussion of production, costs and price data. Four adjusted projects were presented and compared with Alberta. The Venezuelan royalty formula was also discussed. Last, the report provided a detailed fiscal analysis. Comparisons were offered with Cold Lake and Athabasca Mine. A review of some other fiscal systems applicable to conventional oil were also outlined. It was concluded that Alberta oil sands developments are very competitive. It would be possible to modestly increase government revenues, without affecting the international competitive position of Alberta with respect to conventional oil. There is also some possibility to increase the base royalty on the Alberta oil sands without losing competitiveness. tabs., figs

  6. Potential change in lodgepole pine site index and distribution under climatic change in Alberta.

    Science.gov (United States)

    Robert A. Monserud; Yuqing Yang; Shongming Huang; Nadja Tchebakova

    2008-01-01

    We estimated the impact of global climate change on lodgepole pine (Pinus contorta Dougl. ex. Loud. var. latifolia Engelm.) site productivity in Alberta based on the Alberta Climate Model and the A2 SRES climate change scenario projections from three global circulation models (CGCM2, HADCM3, and ECHAM4). Considerable warming is...

  7. Alberta's systems approach to chronic disease management and prevention utilizing the expanded chronic care model.

    Science.gov (United States)

    Delon, Sandra; Mackinnon, Blair

    2009-01-01

    Alberta's integrated approach to chronic disease management programming embraces client-centred care, supports self-management and facilitates care across the continuum. This paper presents strategies implemented through collaboration with primary care to improve care of individuals with chronic conditions, evaluation evidence supporting success and lessons learned from the Alberta perspective.

  8. Long-term outlook for Alberta's primary petrochemical industry : panel discussion : sustainability, feedstocks, infrastructure, transportation

    International Nuclear Information System (INIS)

    Lauzon, D.

    1997-01-01

    The long-term outlook for Dow Chemical's involvement in Alberta's petrochemical industry was discussed. Dow Chemical Canada is a company with annual sales of more than $20 billion that manufactures and supplies chemicals, plastics, energy, agricultural products, consumer goods and environmental services in 157 countries in the world. Alberta is the centre of growth and development for the Canadian petrochemical industry because of the proximity to feedstocks. Alberta is seen as a good, long-term source of ethane. Dow Chemical intends to continue being a major player in the further development of the industry in Alberta. As proof of that confidence, there are 11 capital projects in progress at Dow's Western Canada Operation, totaling $600 million. An important ingredient of the continuing success of the petrochemical industry in Alberta will be the willingness and ability of the federal and provincial governments to work in partnership with industry to develop support infrastructure and policies

  9. Reactor Sharing at Rensselaer Critical Facility

    International Nuclear Information System (INIS)

    D. Steiner, D. Harris, T. Trumbull

    2006-01-01

    This final report summarizes the reactor sharing activities at the Rensselaer Critical Facility. An example of a typical tour is also included. Reactor sharing at the RCF brings outside groups into the facility for a tour, an explanation of reactor matters, and a reactor measurement. It has involved groups ranging from high school classes to advanced college groups and in size from a few to about 50 visitors. The RCF differs from other university reactors in that its fuel is like that of large power reactors, and its research and curriculum are dedicated to power reactor matters

  10. Frasnian-Famennian boundary near Jasper, Alberta, Canada

    Energy Technology Data Exchange (ETDEWEB)

    Geldsetzer, H.; Goodfellow, W.D.; McLaren, D.; Orchard, M.J.

    1985-01-01

    The extinction event at the Frasnian-Famennian boundary cannot be associated with a first-order event, whether impact, volcanic or other. However, data from Alberta and western Australia suggest a sudden flooding of cratonic areas by anoxic water as the immediate or second-order cause. In the Rocky Mountains near Jasper, Alberta abrupt sedimentological, geochemical and faunal changes occur between bioturbated dolomitic siltstones below and thinly laminated, very pyritic, argillaceous lime mudstones above. The siltstones which overlie thick subtidal sediments that infilled Middle Frasnian reef topography, were deposited in shallow, well oxygenated water and contain a Frasnian gigas Zone conodont fauna. In contrast, the overlying lime mudstones which pass upward into beds with Famennian triangularis Zone conodonts, represent deposition under strongly anoxic conditions; the contained pyrite has anomalously high delta/sup 34/S values suggesting prolonged bacterial reduction of sulfate to sulfide. The abrupt change to anoxic conditions could have been triggered by an ocean turn-over event as a result of which cratonic areas were flooded with anoxic water. This in turn would have caused a sharp reduction of the biomass and large-scale faunal extinctions.

  11. Improving the competitiveness of Alberta's retail electricity market

    International Nuclear Information System (INIS)

    2002-03-01

    Navigant Consulting Limited (Navigant) was commissioned by Alberta Energy to provide an independent review of the issues and recommendations contained in the Report of the Retail Issues Subcommittee, published in September 2001, on the Alberta Retail Electricity Markets. It was also asked to identify and other significant issues, and making recommendations pertaining to the issues. The principles of a well-functioning retail market followed an introduction to the document. A definition of a competitive market, according to that used by the Retail Issues Subcommittee (RIS) was provided, and a discussion of each of the elements of such a market was included. Highlights from the United Kingdom retail electricity market were provided. A detailed discussion of each of the major issues identified in the RIS report was presented, and recommendations on each topic areas from the RIS report included. The expected impact of the recommendations was explored. A summary of the recommendations and implementation considerations was provided in the last section of the document. tabs., figs

  12. The need for a marketing strategy for Alberta bitumen

    International Nuclear Information System (INIS)

    Redford, D.A.

    1993-01-01

    Over the past 15 years, government and industry have invested heavily in research and development of new technology for extracting bitumen from the Alberta oil sands. The results have been a dramatic increase in the fraction of oil sands deposits that could be economically exploited and a drop in production costs. However, no rapid increase in bitumen recovery has been achieved and most new bitumen production projects have been postponed or cancelled. This is the result of very variable prices for bitumen and the inadequacy of a marketing strategy which relies on the sale of raw bitumen. Options such as transport of bitumen to southern markets are limited by the need to reduce bitumen viscosity for pipelining and by the limited market for emulsified or diluted bitumen. Another possible strategy, conversion of the bitumen to synthetic crude oil, is limited by high costs, product characteristics (too much diesel and not enough gasoline), and a market limited to specialized refineries. A third strategy is to convert and refine bitumen to transportation fuels in Alberta, using inexpensive local natural gas, and transporting the products through existing pipeline facilities. 3 figs

  13. The need for a marketing strategy for Alberta bitumen

    Energy Technology Data Exchange (ETDEWEB)

    Redford, D.A. (Alberta Oil Sands Technology and Research Authority, Edmonton, AB (Canada))

    1993-03-01

    Over the past 15 years, government and industry have invested heavily in research and development of new technology for extracting bitumen from the Alberta oil sands. The results have been a dramatic increase in the fraction of oil sands deposits that could be economically exploited and a drop in production costs. However, no rapid increase in bitumen recovery has been achieved and most new bitumen production projects have been postponed or cancelled. This is the result of very variable prices for bitumen and the inadequacy of a marketing strategy which relies on the sale of raw bitumen. Options such as transport of bitumen to southern markets are limited by the need to reduce bitumen viscosity for pipelining and by the limited market for emulsified or diluted bitumen. Another possible strategy, conversion of the bitumen to synthetic crude oil, is limited by high costs, product characteristics (too much diesel and not enough gasoline), and a market limited to specialized refineries. A third strategy is to convert and refine bitumen to transportation fuels in Alberta, using inexpensive local natural gas, and transporting the products through existing pipeline facilities. 3 figs.

  14. Preliminary fiscal evaluation of Alberta oil sands terms

    International Nuclear Information System (INIS)

    Van Meurs, P.

    2007-01-01

    The cost of oil sands projects varies significantly. While costs have escalated considerably over the past few years, oil prices have gone significantly higher. This report provided an economic evaluation of the current fiscal terms applicable to Alberta oil sands. The analysis was done to evaluate the profitability of oil sand projects to investors under current conditions based on the generic royalty regime based on bitumen values. The objective of the royalty review was to determine whether Albertans received a fair share from their oil and gas resources. It discussed the wide variety of oil sands projects in Alberta using five case studies as examples. Cases involving steam assisted gravity drainage (SAGD) operations were assessed for both the Athabasca Mine and Cold Lake. The report provided a discussion of the economic assumptions including economic cases as well as production, costs and price data. It then provided the preliminary results of the economic-fiscal evaluation from the investor perspective including profitability indicators; international comparisons; internal rate of return; and net present value. The government perspective was also discussed with reference to attractiveness indicators; royalties as a percentage of bitumen values; and non-discounted and discounted government take. A royalty and tax feature analysis was also provided. Several issues for possible further review were also presented. tabs

  15. Sage-grouse habitat selection during winter in Alberta

    Science.gov (United States)

    Carpenter, Jennifer L.; Aldridge, Cameron L.; Boyce, Mark S.

    2010-01-01

    Greater sage-grouse (Centrocercus urophasianus) are dependent on sagebrush (Artemisia spp.) for food and shelter during winter, yet few studies have assessed winter habitat selection, particularly at scales applicable to conservation planning. Small changes to availability of winter habitats have caused drastic reductions in some sage-grouse populations. We modeled winter habitat selection by sage-grouse in Alberta, Canada, by using a resource selection function. Our purpose was to 1) generate a robust winter habitat-selection model for Alberta sage-grouse; 2) spatially depict habitat suitability in a Geographic Information System to identify areas with a high probability of selection and thus, conservation importance; and 3) assess the relative influence of human development, including oil and gas wells, in landscape models of winter habitat selection. Terrain and vegetation characteristics, sagebrush cover, anthropogenic landscape features, and energy development were important in top Akaike's Information Criterionselected models. During winter, sage-grouse selected dense sagebrush cover and homogenous less rugged areas, and avoided energy development and 2-track truck trails. Sage-grouse avoidance of energy development highlights the need for comprehensive management strategies that maintain suitable habitats across all seasons. ?? 2010 The Wildlife Society.

  16. Feasibility of ground source heat pumps in Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Miller, D.; Maynes, T.

    2008-03-15

    This paper examined the use of ground source heat pumps (GSHPs) in the heating and cooling of residential, industrial and commercial buildings in Alberta. GSHPs extract heat from the earth beneath the frost line or from a body of water and transfer it to buildings for heating in the winter or cooling in the summer. The economics of GSHPs were investigated as well as their potential for reducing greenhouse gas (GHG) emissions. The study showed that while GSHPs are becoming more economical for residential and small commercial and institutional applications, they are not as economical as conventional forced air gas furnaces and have higher associated GHG emissions in residential applications in Alberta. The higher cost was attributed to the current pricing structure of natural gas and electricity in the province. It was concluded that lower GHG emissions are associated with GSHPs when green power purchasing is also available. Higher natural gas costs will enhance the economics of the GSHPs. 3 refs., 6 tabs., 2 figs.

  17. Grasping at Straws: Comments on the Alberta Pipeline Safety Review

    Directory of Open Access Journals (Sweden)

    Jennifer Winter

    2013-09-01

    Full Text Available The release last month of the Alberta Pipeline Safety Review was meant to be a symbol of the province’s renewed commitment to environmental responsibility as it aims for new export markets. The report’s authors, Group 10 Engineering, submitted 17 recommendations covering public safety and pipeline incidents, pipeline integrity management and pipeline safety near bodies of water — and many of them run the gamut from the obvious to the unhelpful to the contradictory. That the energy regulator ought to be staffed to do its job should go without saying; in fact, staffing levels were never identified as an issue. The recommendation that record retention and transfer requirements be defined for mergers and acquisitions, sales and takeovers is moot. There is no reason a purchasing party would not want all relevant documents, and no real way to enforce transparency if the seller opts to withhold information. Harmonizing regulations between provinces could reduce companies’ cost of doing business, but could also prove challenging if different jurisdictions use performance-based regulations — which is what the Review recommended Alberta consider. This very brief paper pries apart the Review’s flaws and recommends that the province go back to the drawing board. Safety is a serious issue; a genuine statistical review linking pipeline characteristics to failures and risk-mitigation activities would be a better alternative by far.

  18. Our fair share : report of the Alberta Royalty Review Panel

    International Nuclear Information System (INIS)

    Hunter, W.M.; Chrapko, E.; Dwarkin, J.; McKenzie, K.; Plourde, A.; Spanglet, S.

    2007-01-01

    This final report conducted by the Alberta Royalty Review Panel determined that Albertans are not currently receiving their fair share from energy developments within the province. Royalty rates have not kept pace with recent changes in resource development in the province or with changes in world energy markets. It was argued that since Albertans own their resources, the government of Alberta must alter the royalty and tax system in order to ensure that appropriate royalties are paid. An equitable and flexible administrative framework should be developed to maintain the province's competitive edge in the global energy market. It was recommended that total shares for Albertans from oil sands developments be increased from 47 per cent to 64 per cent; conventional oil shares should be increased from 44 per cent to 49 per cent; and shares for natural gas should be increased from 58 per cent to 63 per cent. Target rates were designed to close tax gaps between economic sectors. Simplified royalty frameworks were presented for natural gas and conventional oil categories, as well as for oil sands developments. Increases of $1.9 billion in provincial revenue are anticipated as a result of the increased royalties. 5 tabs., 31 figs

  19. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  20. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  1. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  2. University of Illinois nuclear pumped laser program. [experiments with a TRIGA pulsed reactor with a broad pulse and a low peak flux

    Science.gov (United States)

    Miley, G. H.

    1979-01-01

    The development of nuclear pumped lasers with improved efficiency, energy storage capability, and UF6 volume pumping is reviewed. Results of nuclear pumped laser experiments using a TRIGA-type pulsed reactor are outlined.

  3. Alberta's economic performance and outlook

    Energy Technology Data Exchange (ETDEWEB)

    Pyear, D. [Government of Alberta, Edmonton, AB (Canada). Economic Development

    2000-07-01

    The economic climate in Alberta is characterized as being strong and vibrant, with an efficient and modern infrastructure, a young, skilled and productive workforce, a competitive business climate, the lowest overall taxes of any of the provinces, a culturally diverse province with a high quality of life and a fiscally responsible government. All of these attributes add up to the 'Alberta Advantage', the campaign slogan used by the Alberta Government to attract business to the province. Economic highlights from 1999 show that Alberta was the fastest growing province in the country, with 38,000 new jobs created, exports of $34.5 billion, the lowest unemployment rate in the country, and leading all provinces in per capita investment. Total GDP in 1998 amounted to $95.8 billion (up from $61.3 billion in 1985). Even more significant is the fact that only 18.5 per cent of GDP was generated from the energy sector in 1998, as opposed to 37.2 per cent in 1985. Real GDP growth in Alberta was 2.3 per cent in 1999, projected at 6.1 per cent for 2000 and 5.2 per cent for 2001. The corresponding figures for Canada as a whole are 4.1, 4.2 and 3.0 per cent, respectively. Except for agriculture and public administration, which declined by 11.9 per cent and 13.4 per cent respectively, all other sectors of the economy showed significant growth during the period of 1993 to 1999. Technology employment grew by six per cent between 1989 and 1999, fully 33 per cent higher than anywhere else in the country. Energy industry revenue increased by 35 per cent from 1998 to 1999 and industry reinvestment was high at 150 per cent of internal cash flow. Total investment in the province amounted to $31.3 billion in 1999; it is expected to top $34.0 billion in 2000. A list of current major investment projects shows a total of 810 projects in all sectors of the economy, with a total value of $61.14 billion dollars. Growth targets include 295,000 new jobs, value added exports to $26 billion

  4. The Case for a Carbon Tax in Alberta

    Directory of Open Access Journals (Sweden)

    Sarah Dobson

    2015-11-01

    Full Text Available In 2007, Alberta demonstrated that it could be a leader in the effort to reduce greenhouse gas emissions by becoming the first North American jurisdiction to put a price on carbon. Given that the province had long been criticized for its central role in the carbon-based economy, Alberta’s move was important for its symbolism. Unfortunately, the emissions policy itself has delivered more in symbolism than it has in actually achieving meaningful reductions in greenhouse gas emissions. The Specified Gas Emitters Regulation (SGER, as the carbon-pricing system is formally called, has only helped Alberta achieve a three per cent reduction in total emissions, relative to what they would have been without the SGER. And emissions keep growing steadily, up by nearly 11 per cent between 2007 and 2014, with the SGER only slowing that growth by a marginal one percentage point. Alberta’s carbon-pricing policy simply fails to combat emissions growth; the province needs a new one. Lack of progress in reducing emissions appears to be partly attributable to the fact that many large emitters find it more economical to allow their emissions to rise beyond the provincially mandated threshold, and instead are purchasing amnesty at a lower cost through carbon offsets or by paying the levies that the SGER imposes on excess emissions. But it is also partly attributable to the fact that the SGER only applies to large emitters who annually produce 100,000 tonnes of CO2-equivalent all at one site: mainly oil sands operations and facilities that generate heat and electricity. This excludes operations that emit well over that threshold, but across diffuse locations. The transportation sector, which is typically spread out in just such a way, is the third-largest sector for emissions in Alberta. Its emissions are also growing faster than those of the mining and oil and gas sector, even as emissions in the electricity and heat generation sector are actually declining. And

  5. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  6. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  7. Alberta Oil Sands Equity annual report, 1992-93. Partnership and progress in Alberta's oil sands development

    International Nuclear Information System (INIS)

    1993-01-01

    Alberta Oil Sands Equity (AOSE) manages the Alberta government's equity investments in oil sands and heavy oil projects. AOSE is a 16.74% participant in the Syncrude Project, a 10% participant in the OSLO (Other Six Leases Operation) Commercial Project and the OSLO New Ventures project, and a 24.17% participant in the Lloydminster Bi-Provincial Upgrader. Syncrude produces ca 12% of Canadian crude oil requirements, and AOSE's share yielded $44 million profit for 1992/93, slightly higher than the the $43.3 million the previous year. The OSLO Commercial Project is a proposed commercial oil sands plant with a mine site and extraction plant to be located north of Fort McMurray, and an upgrading facility to be situated north of Edmonton. Work on this project was suspended in early 1992. The OSLO New Ventures project will handle the exploration and development of the remaining five oil sands leases plus the southern portion of Lease 31. As of March 31, 1993, the project owners were considering a commercial demonstration project utilizing dredging and cold-water extraction processes. Two of the owners are unable to provide funding and discussions are under way to resolve the matter and move the program forward. The Lloydminster Bi-Provincial Upgrader opened Noveber 20, 1992, and production has reached 41,000 bbl/d, or 89% of design capacity. The upgrader will increase the value of heavy crude oil and thereby increase its demand. 5 figs., 3 tabs

  8. An annotated list of the Lepidoptera of Alberta, Canada

    Directory of Open Access Journals (Sweden)

    Greg Pohl

    2010-03-01

    Full Text Available This checklist documents the 2367 Lepidoptera species reported to occur in the province of Alberta, Canada, based on examination of the major public insect collections in Alberta and the Canadian National Collection of Insects, Arachnids and Nematodes. Records from relevant literature sources published since 1950 and from selected older works are also included. The entry for each species includes the scientific name, the author and year of publication of the original description, occurrence status, provincial distribution (according to ecoclimatic region, and adult phenology. The most recent taxonomic references are given, and common names are listed for butterflies and conspicuous moth species. The sources of specimen- and literature-based records are provided for each species. An additional 138 species whose occurrence in Alberta is probable are appended to the list. For 1524 of the listed species and subspecies, annotations are given, with selected information on taxonomy, nomenclature, distribution, habitat, and biology. An additional section provides details on 171 species erroneously reported from Alberta in previous works. Introductory sections to the volume provide a general overview of the order Lepidoptera and review the natural regions of Alberta, the state of knowledge of their Lepidoptera faunas, and the history and current state of knowledge of Alberta Lepidoptera. Each of the 63 families (and selected subfamilies occurring in Alberta is briefly reviewed, with information on distinguishing features, general appearance, and general biology. A bibliography and an index of genus-level, species-level, and subspecies-level names are provided. The list is accompanied by an appendix of proposed nomenclature changes, consisting of revised status for 25 taxa raised from synonymy to species level, and new synonymy for 20 species-level and one genus-level taxa here considered to be subjective synonyms, with resultant revised synonymy for one

  9. 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.

  10. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

    Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)

  11. Predictors of exclusive breastfeeding: observations from the Alberta pregnancy outcomes and nutrition (APrON) study

    Science.gov (United States)

    2013-01-01

    Background Despite growing evidence that supports the importance of 6-month exclusive breastfeeding, few Canadian mothers adhere to this, and early weaning onto solids is a common practice. This study assessed infant feeding transitions during the first 6 months postpartum and factors that predicted exclusive breastfeeding to 3 and 6 months. Methods This prospective cohort study was part of the Alberta Pregnancy Outcomes and Nutrition study (APrON). From an initial sample of 600 pregnant women recruited from Edmonton and Calgary, 402 mothers provided complete details at 3 months postpartum; 300 stayed on to provide information at 6 months postpartum. During pregnancy and at 3 and 6 months postpartum, data on maternal and infant socio-demographic, behavior, and feeding were collected. Results Even though there was a high rate of “ever having breastfed” (98.6%), exclusive breastfeeding rates for 3 and 6 months were 54.0% and 15.3%, respectively. After controlling for potential confounders, the study showed that mothers who held post-graduate university degrees were 3.76 times more likely to breastfeed exclusively for 6 months than those without a university degree (95% CI: 1.30-10.92; p = 0.015). In addition, mother of previous children were more likely to breastfeed exclusively for 6 months (OR: 2.21, 95% CI: 1.08-4.52; p = 0.031). Mothers who were in the highest quartile of the Iowa Infant Feeding Attitude Score were 4.29 and 5.40 times more likely to breastfeed exclusively for 3 months (95% CI: 1.31-14.08; p-trend breastfeeding rate in Alberta is considerably below national and international breastfeeding recommendations. Professional advice that focuses on prenatal maternal knowledge, attitudes, and misperceptions may promote adherence to World Health Organization breastfeeding guidelines. Knowing that exclusive breastfeeding is less likely to take place among lower-educated, primiparous women may help health practitioners focus their

  12. Reactor Neutrinos

    OpenAIRE

    Kim, Soo-Bong; Lasserre, Thierry; Wang, Yifang

    2013-01-01

    We review the status and the results of reactor neutrino experiments. Short-baseline experiments have provided the measurement of the reactor neutrino spectrum, and their interest has been recently revived by the discovery of the reactor antineutrino anomaly, a discrepancy between the reactor neutrino flux state of the art prediction and the measurements at baselines shorter than one kilometer. Middle and long-baseline oscillation experiments at Daya Bay, Double Chooz, and RENO provided very ...

  13. BOILING REACTORS

    Science.gov (United States)

    Untermyer, S.

    1962-04-10

    A boiling reactor having a reactivity which is reduced by an increase in the volume of vaporized coolant therein is described. In this system unvaporized liquid coolant is extracted from the reactor, heat is extracted therefrom, and it is returned to the reactor as sub-cooled liquid coolant. This reduces a portion of the coolant which includes vaporized coolant within the core assembly thereby enhancing the power output of the assembly and rendering the reactor substantially self-regulating. (AEC)

  14. Reactor vessel

    NARCIS (Netherlands)

    Makkee, M.; Kapteijn, F.; Moulijn, J.A.

    1999-01-01

    A reactor vessel (1) comprises a reactor body (2) through which channels (3) are provided whose surface comprises longitudinal inwardly directed parts (4) and is provided with a catalyst (6), as well as buffer bodies (8, 12) connected to the channels (3) on both sides of the reactor body (2) and

  15. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  16. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  17. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

    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. Sulfur impacts on forest health in west-central Alberta

    International Nuclear Information System (INIS)

    Maynard, D.G.; Stadt, J.J.; Mallett, K.I.; Volney, W.J.A.

    1994-01-01

    A study was conducted to evaluate forest health and tree growth in relation to sulfur deposition in mature and immature lodgepole pine and mature trembling aspen. Soil samples were taken in forests near two sour gas processing plants in west-central Alberta. The soil sample sites were classified into high, medium and low deposition classes. The impact of sulfur deposition on soil and foliar chemistry, tree growth, and forest health was evaluated. The analysis of tree growth, using radial increments, revealed no impact associated with the sulfur deposition class. The only indicators of extensive sulfur impacts on major forest communities detected to date are elevated sulfur concentrations in the surface organic horizon and foliage, the proportion of healthy lodgepole pines, and a depression in the annual specific volume increment. No evidence of widespread forest decline has been found. 42 refs., 35 tabs., 29 figs

  19. A Case Study of Anomalous Snowfall with an Alberta Clipper

    Directory of Open Access Journals (Sweden)

    Scott M. Rochette

    2017-01-01

    Full Text Available An Alberta clipper moved over western New York state on 11-12 January 2004, producing snowfall amounts of up to 27 cm in portions of the region during a roughly 12-h period. In addition, lightning and thunder were reported. Such systems, known primarily for their fast motion and relatively dry nature, are not generally associated with significant snowfalls. A postmortem analysis of this event, following an ingredients-based methodology, revealed that as the weak low approached the lower Great Lakes, it came under the influence of coupled 300-hPa jets that produced enhanced divergence and significant upward vertical motion over western New York, resulting in the enhanced convective snowfall over the region for a limited time. Instability and possible enhancement via the Great Lakes are also investigated, which show that while there was at least modest instability over the region during the time of heavy snowfall, lake enhancement was unlikely.

  20. The Devonian Palliser Formation and its equivalents, southern Alberta, Canada

    Energy Technology Data Exchange (ETDEWEB)

    Meijer Drees, N.C.; Johnston, D.I.; Richards, B.C.

    1993-10-01

    In southern Alberta, the Upper Devonian (Famennian) carbonates and interbedded evaporites form a well-defined, thick-bedded succession that overlies thin-bedded carbonates and is overlain by dark shale. In the Rocky Mountains near Banff, the carbonate succession is represented by the Palliser Formation, which includes five distinct lithologic units in the type area. In the subsurface of the Alberta plains, Famennian carbonates are mapped as the Wabamun Group and contain large amounts of sour gas. In the Palliser Formation, the vertical changes in lithology, sedimentary structures, and fossil content in the lowest three units (the Morro member) suggest a change in the environment during carbonate deposition from intertidal to shallow subtidal, to deeper subtidal above average wave-base, returning to shallow subtidal. The boundary between the Morro member and the upper two units (the Costigan member) is sharp and coincides with a change in the environment of deposition from subtidal to peritidal. The peritidal facies is characterized by laminated algal mat deposits, intraclast conglomerates, and dissolution breccia. The lower part of the Costigan member is sharply and erosionally overlain by fossiliferous limestones of the upper part, which contain an open marine fauna. It is possible that the erosional contact between the upper and lower parts coincides with a significant hiatus in the sedimentary record. In the subsurface, the Morro and the lower Costigan members correlate with the Stettler Formation and the upper Costigan correlates with the Big Valley Formation. It is postulated that the fossiliferous carbonates of the Big Valley and the upper Costigan represent the same basal transgressive deposit. 65 refs., 23 figs.

  1. Experience with embankment dam safety evaluation in Alberta

    International Nuclear Information System (INIS)

    Houston, M.; Morgenstern, N.R.

    1989-01-01

    Following a rash of dam failures in the 1970s, many jurisdictions responded with the implementation of both legislation and regulations mandating dam safety evaluations. Almost all dams in Alberta are embankment dams, of which failures are mainly caused by: overtopping during flood discharge due to inadequate spillway capacity or non-functioning floodgates; internal erosion along the dam foundation interface; non-homogeneity in the foundation or dam, leading to foundation failure or erosion; large settlements in the foundation; cracks following settlement, with resultant piping; and liquefaction. Summaries are presented of a series of case histories of dam safety evaluations conducted in Alberta where the outcome was not routine. The case histories describe evaluations carried out at the following dams. The Bighorn hydroelectric development was completed in 1972, and measured seepage was found to be ten times greater than a recommended alert level. Dam safety evaluations concluded that the performance of the dam and concrete cutoff wall is satisfactory, but the owner reads all monitoring instrumentation on a regular basis and seeks on-going review from consultants. The Three Sisters Dam is a 21 m high homogeneous embankment hydroelectric dam. Very large seepage flows were found, and although remedial measures have been effective, extreme vigilence with an intensive inspection and monitoring program is required. Other case studies detail seepage monitoring at the St. Mary Dam, complex seepage patterns at Waterton Dam and Tavers Dam, and material durability studies at Hartung Dam and Murray Dam. The importance of good records and construction and performance histories is emphasized. 12 figs., 10 refs

  2. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Nagatomi, Shozo.

    1976-01-01

    Object: To provide a jet and missile protective wall of a configuration being inflated toward the center of a reactor container on the inside of a body of the reactor container disposed within a biological shield wall to thereby increase safety of the reactor container. Structure: A jet and missile protective wall comprised of curved surfaces internally formed with a plurality of arch inflations filled with concrete between inner and outer iron plates and shape steel beam is provided between a reactor container surrounded by a biological shield wall and a thermal shield wall surrounding the reactor pressure vessel, and an adiabatic heat insulating material is filled in space therebetween. (Yoshino, Y.)

  3. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  4. Canadian Library Human Resources Short‐Term Supply and Demand Crisis Is Averted, But a Significant Long‐Term Crisis Must Be Addressed. A review of: 8Rs Research Team. The Future of Human Resources in Canadian Libraries February 2005. Edmonton, AB: University of Alberta. 21 February 2007 .

    Directory of Open Access Journals (Sweden)

    Julie McKenna

    2007-03-01

    Full Text Available Objective – To examine the human resources environment in Canadian libraries in order to assess readiness to accommodate change and to identify opportunities for human resources planning. The “8Rs” of the study were defined as recruitment, retirement, retention, remuneration, repatriation, rejuvenation, re‐accreditation, and restructuring.Design – This study was undertaken in three phases over nearly three years through the use a variety of methods including literature review, analyses of existing data (Statistics Canada and library school graduate data, telephone interviews (with senior library administrators, focus groups (with representatives from Canadian Association of Research Libraries, Canadian Urban Libraries Council and Alberta Association of Library Technicians, print surveys (library institutions and web‐based surveys (of professional librarians and paraprofessional library staff.Setting – Canadian libraries that are not component branches of a system, and that employ professional librarians.Subjects – Stage I: 17 senior library administrators participated in telephone interviews and three focus groups were conducted. Stage II: Surveyed library administrators representing institutions. A multi‐stage stratified random sampling technique was used to ensure geographical representation from each of Canada’s provinces and territories. Full census participation was conducted for members of the Canadian Association of Research Libraries and the Canadian Urban Libraries Council. The print survey instrument was distributed to 1,357 subjects; 461 completed surveys were returned (response rate of 34% with results for the total sample accurate within plus or minus 3.8 per centage points, 95 times out of 100. Stage III: Surveyed professional librarians and paraprofessional staff. Multi‐stage random sampling was used to ensure representation of library staff from all library sectors and sufficient sub‐sample sizes. Of the

  5. Alberta Oil Sands Equity annual report, 1991-92. Partnership and progress in Alberta's oil sands development

    International Nuclear Information System (INIS)

    1992-01-01

    Alberta Oil Sands Equity (AOSE) manages the Alberta government's equity investments in oil sands and heavy oil projects. AOSE is a 16.74% participant in the Syncrude Project, a 10% participant in the OSLO (Other Six Leases Operation) Commercial Project and the OSLO New Ventures project, and a 24.17% participant in the Lloydminster Bi-Provincial Upgrader. Syncrude produces over 11% of Canadian crude oil requirements, and AOSE's share yielded $43.3 million profit for 1991/92, down significantly from the $82.1 million the previous year due to lower oil prices. The OSLO Commercial Project is a proposed commercial oil sands plant with a mine site and extraction plant to be located north of Fort McMurray, and an upgrading facility to be situated north of Edmonton. Work on this project was suspended in early 1992. The OSLO New Ventures project will handle the exploration and development of the remaining five oil sands leases plus the southern portion of Lease 31. As of March 31, 1992, the project owners were considering a commercial demonstration project utilizing dredging and cold-water extraction processes. Two of the owners are unable to provide funding and discussions are under way to resolve the matter and move the program forward. The Lloydminster Bi-Provincial Upgrader was nearly 90% complete in March 1992 and full startup is expected in November 1992; engineering work was completed in March 1991. The upgrader will increase the value of heavy crude oil and thereby increase its demand. 4 figs., 4 tabs

  6. Erosion of the Alberta badlands produces highly variable and elevated heavy metal concentrations in the Red Deer River, Alberta.

    Science.gov (United States)

    Kerr, Jason G; Cooke, Colin A

    2017-10-15

    Erosion is important in the transport of heavy metals from terrestrial to fluvial environments. In this study, we investigated riverine heavy metal (Cd, Cu, Hg and Pb) dynamics in the Red Deer River (RDR) watershed at sites upstream (n=2) and downstream (n=7) of the Alberta badlands, an area of naturally high erosion. At sites draining the badlands, total water column Cd, Cu, Hg and Pb concentrations frequently exceeded guidelines for the protection of freshwater biota. Furthermore, peak concentrations of total Cd (9.8μgL -1 ), Cu (212μgL -1 ), Hg (649ngL -1 ) and Pb (361μgL -1 ) were higher than, or comparable to, values reported for rivers and streams heavily impacted by anthropogenic activities. Total suspended solids (TSS) explained a large proportion (r 2 =0.34-0.83) of the variation in total metal concentrations in the RDR and tributaries and metal fluxes were dominated by the particulate fraction (60-98%). Suspended sediment concentrations (C sed ) and metal to aluminum ratios were generally not indicative of substantial sediment enrichment. Rather, the highly variable and elevated metal concentrations in the RDR watershed were a function of the high and variable suspended sediment fluxes which characterize the river system. While the impact of this on aquatic biota requires further investigation, we suggest erosion in the Alberta badlands may be contributing to Hg-based fish consumption advisories in the RDR. Importantly, this highlights a broader need for information on contaminant dynamics in watersheds subject to elevated rates of erosion. Copyright © 2017 The Authors. Published by Elsevier B.V. All rights reserved.

  7. The Epidemiology of Childhood Asthma in Red Deer and Medicine Hat, Alberta

    Directory of Open Access Journals (Sweden)

    Patrick A Hessel

    2001-01-01

    Full Text Available OBJECTIVES: To document the prevalence of asthma among school-aged children in two Alberta communities, to understand host and indoor environmental factors associated with asthma, and to compare these factors between the two communities.

  8. Preferences of Residents in Four Northern Alberta Communities Regarding Local Post-Secondary Programming

    Directory of Open Access Journals (Sweden)

    Patrick J. Fahy

    2009-06-01

    Full Text Available The western Canadian province of Alberta has used some of the proceeds from exploitation of its extraordinary natural resources to make available a range of post-secondary training and education opportunities to residents. While these provisions appear comprehensive, this study examined how well they actually suit the express needs of the residents of remote, Northern areas of the province, many of them Aboriginal. The literature shows that while Aboriginal people are underrepresented in Canada in university enrollments, they are no longer underrepresented in college or other institutions, suggesting that gains have been made for some residents of rural and remote parts of Canada. Further, when Northern residents (especially Aboriginal males complete advanced training, Statistics Canada reports they are highly successful in employment and income. Access is the pivotal issue, however: leaving the local community to attend training programs elsewhere is often disruptive and unsuccessful. As will be seen, the issue of access arose in this study’s findings with direct implications for distance delivery and support.This study was conducted as part of Athabasca University’s Learning Communities Project (LCP, which sought information about the views and experiences of a broad range of northern Alberta residents concerning their present post-secondary training and education opportunities. The study addresses an acknowledged gap in such information in relation to Canada in comparison with other OECD countries.Results are based on input from 165 individuals, obtained through written surveys (some completed by the researchers in face-to-face exchanges with the respondents, interviews, discussions, and observations, conducted with full-time or part-time residents of the study communities during 2007 and 2008. The four northern Alberta communities studied were Wabasca, Fox Lake, Ft. McKay (sometimes MacKay, and Ft. Chipewyan, totaling just over 6

  9. Competing in a deregulated market : what are we learning from the Alberta experience?

    International Nuclear Information System (INIS)

    Farrell, D.

    2002-01-01

    A history of the deregulation schedule in Alberta was presented. The spot market in the province opened in January 1996. What Albertans wanted from deregulation was a competitive power generation market, a liquid spot market, a liquid forward market, competitive retail market, a clear transmission policy, transparent pricing, and innovation. They got a competitive power generation market and a liquid spot market, but with few buyers and an unclear transmission policy with only medium transparency in prices. Innovation was seen in the form of small power and distributed generation such as wind energy. In 2001, the Alberta government stepped in to subsidize consumers because wholesale prices were trading at record highs. In 2002 wholesale prices collapsed. It was shown that prices have declined in Alberta as supply and demand came into balance. The Keephills Generating Plants 3 and 4 will have a large impact on the market in 2005. It was emphasized that new transmission would unlock additional potential market for Alberta generation. The paper presented viewgraphs showing existing generation capacity and the high Alberta prices following deregulation. It was noted that commodity cycles dominate growth plans in the electric power industry. The four generation markets in Alberta were identified. The lesson learned from past experience is that price signals will attract new generators to the market and that government leadership must be consistent. 4 tabs., 6 figs

  10. Successful and unsuccessful attempts to resolve caribou management and timber harvesting issues in west central Alberta

    Directory of Open Access Journals (Sweden)

    David Hervieux

    1996-01-01

    Full Text Available Research studies of woodland caribou in west central Alberta began in 1979 in response to proposed timber harvesting on their winter ranges. Using results from initial studies, timber harvest guidelines were developed. A recent review of these guidelines, and the assumptions on which they were based, has resulted in a renegotiation by government and industry of timber harvesting on caribou range in west central Alberta. Caribou range in west central Alberta overlaps many jurisdictional boundaries: federal and provincial lands, four Forest Management Agreement Areas, three Alberta Land and Forest Service Regions and two Alberta Fish and Wildlife Service Regions. This jurisdictional complexity in combination with other factors such as total allocation of the timber resources, high levels of petroleum, natural gas and coal extraction activities, a high level of concern by public groups for caribou conservation and recent understanding of woodland caribou needs for abundant space has made resolution of caribou/timber harvest conflicts exceedingly slow and often relatively unproductive. This paper reviews 10 years of trying to resolve conflicts between timber harvesting and caribou conservation through meetings, committees, integrated resource planning, policy papers and public consultation. We describe what might be learned by other jurisdictions that are trying to resolve similar caribou/timber harvesting issues. We conclude with an overview of recent timber harvest planning initiatives on caribou range in west central Alberta.

  11. A review of Alberta's environmental and emergency response capacity : learning the lessons and building change[Report of the Alberta Environmental Protection Commission

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-12-15

    Alberta's Environmental Commission was established in August 2005 following a train derailment and spill of Bunker C oil and pole treating oil into Lake Wabamun. Its role was to review and make recommendations on Alberta's ability to respond to environmental incidents. The Commission found that the problems and solutions to environmental protection go beyond the mandate of Alberta Environment. They lie within decisive and proactive emergency management and response systems. In light of growing industrial activity, as well as a growing population and economic base, the comprehensive response approach to an emergency must be world-class in order to minimize impacts on land, air, water, wildlife and people. The conclusions presented in this report refer to the overall system and the 5 frameworks that support it, including prevention and mitigation; preparedness; response; recovery; and research and knowledge. The Commission examined response systems in other provinces and jurisdiction and reviewed the current model in Alberta to assess its strength and weaknesses. Focus was on the following 6 objectives: recommend any changes needed to the Alberta government's capacity to respond to environmental incidents where industry cannot; review Alberta Environment's emergency response system in order to make recommendations to prevent, mitigate and respond to these incidents; review the provision of information needed in a report to Alberta Environment and the associated reporting process regarding the substances involved in spills; review potential high-risk situations affecting Alberta's lake and rivers as part of an overall risk management strategy; review best practices for preventing, mitigating and responding to incidents that can have a significant impact on the environment; and provide advice to the Ministries on safety and rail transportation issues to help them collaborate with the appropriate jurisdictions. It was concluded that action is

  12. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  13. Economic impact of switching rubella IgG methodologies to the prenatal public health program in Alberta.

    Science.gov (United States)

    Lai, Florence Y; Dover, Douglas C; Charlton, Carmen L

    2016-10-01

    Despite widespread use of a universal rubella standard, variability in rubella antibody titre can be observed between assays, particularly at the low end of the linear range. Here, we investigate the impact of a methodology change for rubella IgG from the Abbott AXSYM to the Abbott Architect in a comprehensive prenatal screening program in the Canadian province of Alberta. 51,815 specimens (21,399 tested by AxSYM and 30,416 tested by Architect) submitted for routine prenatal screening between January 2006 and December 2012 from women who lived in Alberta after the universal childhood immunization programme for rubella was implemented, and whose immunization records were available, were included in the study. Prenatal samples tested by AxSYM for rubella IgG were approximately 30% higher than those reported by Architect. Among individuals who had tests across multiple pregnancies, the change in test platform led to an additional 7% of women who initially tested positive, becoming non-positive (i.e. negative or indeterminate) in their subsequent tests. The tendency of the Architect IgG assay to report lower quantitative values was demonstrated across all birth cohorts and vaccination status, and resulted in an additional 2800 women requiring vaccination between 2010 and 2012 with an estimated cost of $38,500. The change in rubella IgG screening assay resulted in a significant increase in the number of women who required post partum vaccination and Public Health follow-up. Copyright © 2016 Elsevier B.V. All rights reserved.

  14. A continuing success - The United States Foreign Research Reactor Spent Nuclear Fuel Acceptance Program

    International Nuclear Information System (INIS)

    Mustin, Tracy P.; Clapper, Maureen; Reilly, Jill E.

    2000-01-01

    The United States Department of Energy, in consultation with the Department of State, adopted the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel in May 1996. To date, the Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program, established under this policy, has completed 16 spent fuel shipments. 2,651 material test reactor (MTR) assemblies, one Slowpoke core containing less than 1 kilogram of U.S.-origin enriched uranium, 824 Training, Research, Isotope, General Atomic (TRIGA) rods, and 267 TRIGA pins from research reactors around the world have been shipped to the United States so far under this program. As the FRR SNF Acceptance Program progresses into the fifth year of implementation, a second U.S. cross country shipment has been completed, as well as a second overland truck shipment from Canada. Both the cross country shipment and the Canadian shipment were safely and successfully completed, increasing our knowledge and experience in these types of shipments. In addition, two other shipments were completed since last year's RERTR meeting. Other program activities since the last meeting included: taking pre-emptive steps to avoid license amendment pitfalls/showstoppers for spent fuel casks, publication of a revision to the Record of Decision allowing up to 16 casks per ocean going vessel, and the issuance of a cable to 16 of the 41 eligible countries reminding their governments and the reactor operators that the U.S.-origin uranium in their research reactors may be eligible for return to the United States under the Acceptance Program and urging them to begin discussions on shipping schedules. The FRR SNF program has also supported the Department's implementation of the competitive pricing policy for uranium and resumption of shipments of fresh uranium for fabrication into assemblies for research reactors. The United States Foreign Research Reactor Spent Nuclear Fuel Acceptance Program continues

  15. Heterogeneous reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

  16. Isotopic signatures of anthropogenic CH4 sources in Alberta, Canada

    Science.gov (United States)

    Lopez, M.; Sherwood, O. A.; Dlugokencky, E. J.; Kessler, R.; Giroux, L.; Worthy, D. E. J.

    2017-09-01

    A mobile system was used for continuous ambient measurements of stable CH4 isotopes (12CH4 and 13CH4) and ethane (C2H6). This system was used during a winter mobile campaign to investigate the CH4 isotopic signatures and the C2H6/CH4 ratios of the main anthropogenic sources of CH4 in the Canadian province of Alberta. Individual signatures were derived from δ13CH4 and C2H6 measurements in plumes arriving from identifiable single sources. Methane emissions from beef cattle feedlots (n = 2) and landfill (n = 1) had δ13CH4 signatures of -66.7 ± 2.4‰ and -55.3 ± 0.2‰, respectively. The CH4 emissions associated with the oil or gas industry had distinct δ13CH4 signatures, depending on the formation process. Emissions from oil storage tanks (n = 5) had δ13CH4 signatures ranging from -54.9 ± 2.9‰ to -60.6 ± 0.6‰ and non-detectable C2H6, characteristic of secondary microbial methanogenesis in oil-bearing reservoirs. In contrast, CH4 emissions associated with natural gas facilities (n = 8) had δ13CH4 signatures ranging from -41.7 ± 0.7‰ to -49.7 ± 0.7‰ and C2H6/CH4 molar ratios of 0.10 for raw natural gas to 0.04 for processed/refined natural gas, consistent with thermogenic origins. These isotopic signatures and C2H6/CH4 ratios have been used for source discrimination in the weekly atmospheric measurements of stable CH4 isotopes over a two-month winter period at the Lac La Biche (LLB) measurement station, located in Alberta, approximately 200 km northeast of Edmonton. The average signature of -59.5 ± 1.4‰ observed at LLB is likely associated with transport of air after passing over oil industry sources located south of the station.

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    Mysels, K.J.; Shenoy, A.S.

    1976-01-01

    A nuclear reactor is described in which the core consists of a number of fuel regions through each of which regulated coolant flows. The coolant from neighbouring fuel regions is combined in a manner which results in an averaging of the coolant temperature at the outlet of the core. By this method the presence of hot streaks in the reactor is reduced. (UK)

  18. Clean air strategy for Alberta: Report to the ministers

    International Nuclear Information System (INIS)

    1991-11-01

    As a response to continuing discussions on the impact of fossil fuels on global warming, acid deposition, and smog, a clean air strategy consultation program was announced by Alberta's Ministers of Energy and Environment to encourage public discussion on air emissions resulting from the production and use of energy. The consultation program had three objectives: to help identify and clarify the most important issues associated with energy production and use which need to be addressed in developing a clean air strategy; to outline practical and achievable actions which can be taken to reduce emissions; and to develop program and policy recommendations to the provincial government. The consultation program included workshops and regional sessions, as well as background research. The discussions, findings, and conclusions from the program are summarized. Several air quality management challenges were identified, including the need for a more comprehensive system for managing air quality; the priority of local air quality issues and problems; the need to address cumulative regional emissions and impacts; and scientific and economic uncertainties. A number of goals have been developed to address these challenges, such as implementation of a comprehensive air quality management system, identification of cost-effective energy conservation and efficiency opportunities, development of innovative and targeted solutions to manage cumulative emissions, and improvement of the gathering and application of scientific and technical knowledge regarding atmospheric processes and effects. A glossary of terms is included. 12 figs., 17 tabs

  19. Shell's Caroline gas project on track in southwest Alberta

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This paper reports that western Canada's biggest sour natural gas, sulfur, and natural gas liquids development project in 2 decades is on target to start up late this year. Shell Canada Ltd.'s $950 million (Canadian) Caroline project will produce 2 tcf of gas and associated products from the Swan Hills member of the middle Devonian Beaverhill Lake group. The price tag will reach about $1 billion, including some start-up costs. The project is designed to process an average 300 MMcfd of gas. It will produce 17,500 b/d of pentanes plus, 4,100 metric tons/day of sulfur, 90 MMcfd of sales gas, and 28,000 b/d of NGL-ethane, propane, and butane. A labor force that is peaking at about 2,400 workers is completing a network of processing plants, about 143 miles of pipeline, three field compressors, and other facilities covering an area of 161 sq miles. Dilcon Constructors Ltd., an arm of Delta Catalytic Corp., Calgary, is the main contractor for the project. About 85% of the services and equipment for Caroline are coming from Alberta suppliers, 7% from suppliers elsewhere in Canada, and only 8% from non-Canadian Sources

  20. Brazilian validation of the Alberta Infant Motor Scale.

    Science.gov (United States)

    Valentini, Nadia Cristina; Saccani, Raquel

    2012-03-01

    The Alberta Infant Motor Scale (AIMS) is a well-known motor assessment tool used to identify potential delays in infants' motor development. Although Brazilian researchers and practitioners have used the AIMS in laboratories and clinical settings, its translation to Portuguese and validation for the Brazilian population is yet to be investigated. This study aimed to translate and validate all AIMS items with respect to internal consistency and content, criterion, and construct validity. A cross-sectional and longitudinal design was used. A cross-cultural translation was used to generate a Brazilian-Portuguese version of the AIMS. In addition, a validation process was conducted involving 22 professionals and 766 Brazilian infants (aged 0-18 months). The results demonstrated language clarity and internal consistency for the motor criteria (motor development score, α=.90; prone, α=.85; supine, α=.92; sitting, α=.84; and standing, α=.86). The analysis also revealed high discriminative power to identify typical and atypical development (motor development score, P<.001; percentile, P=.04; classification criterion, χ(2)=6.03; P=.05). Temporal stability (P=.07) (rho=.85, P<.001) was observed, and predictive power (P<.001) was limited to the group of infants aged from 3 months to 9 months. Limited predictive validity was observed, which may have been due to the restricted time that the groups were followed longitudinally. In sum, the translated version of AIMS presented adequate validity and reliability.

  1. Fruit and vegetable preferences and intake among children in Alberta.

    Science.gov (United States)

    Chu, Yen Li; Farmer, Anna; Fung, Christina; Kuhle, Stefan; Veugelers, Paul

    2013-01-01

    The association between preference for and intake of fruits and vegetables was examined among Albertan children. Data used were collected as part of a provincial population-based survey among grade 5 children in Alberta. Intake of two fruits and five vegetables was assessed using the Harvard food frequency questionnaire, and preference for individual fruit and vegetable items was rated using a three-point Likert-type scale. Random effects models with children nested within schools were used to test for associations between fruit and vegetable preference and intake. A total of 3398 children aged 10 to 11 years returned completed surveys. Children who reported a greater liking for fruits and vegetables also reported significantly (p<0.001) higher intake. On average, children who liked a food a lot ate 0.5 to 2.7 more weekly servings of the food than did children who did not like the food. These findings suggest that focusing on interventions designed to increase taste preference may lead to increased fruit and vegetable intake among children. Introducing children to unfamiliar fruits and vegetables through taste testing may be an effective and practical health promotion approach for improving dietary habits.

  2. Adoption of the Healthy Heart Kit by Alberta family physicians.

    Science.gov (United States)

    Bize, Raphaël; Plotnikoff, Ronald C; Scott, Shannon D; Karunamuni, Nandini; Rodgers, Wendy

    2009-01-01

    The Healthy Heart Kit (HHK) is a risk management and patient education kit for the prevention of cardiovascular disease (CVD) and the promotion of CV health. There are currently no published data examining predictors of HHK use by physicians. The main objective of this study was to examine the association between physicians' characteristics (socio-demographic, cognitive, and behavioural) and the use of the HHK. All registered family physicians in Alberta (n=3068) were invited to participate in the "Healthy Heart Kit" Study. Consenting physicians (n=153) received the Kit and were requested to use it for two months. At the end of this period, a questionnaire collected data on the frequency of Kit use by physicians, as well as socio-demographic, cognitive, and behavioural variables pertaining to the physicians. The questionnaire was returned by 115 physicians (follow-up rate = 75%). On a scale ranging from 0 to 100, the mean score of Kit use was 61 [SD=26]. A multiple linear regression showed that "agreement with the Kit" and the degree of "confidence in using the Kit" was strongly associated with Kit use, explaining 46% of the variability for Kit use. Time since graduation was inversely associated with Kit use, and a trend was observed for smaller practices to be associated with lower use. Given these findings, future research and practice should explore innovative strategies to gain initial agreement among physicians to employ such clinical tools. Participation of older physicians and solo-practitioners in this process should be emphasized.

  3. Workplace violence in Alberta and British Columbia hospitals.

    Science.gov (United States)

    Hesketh, Kathryn L; Duncan, Susan M; Estabrooks, Carole A; Reimer, Marlene A; Giovannetti, Phyllis; Hyndman, Kathryn; Acorn, Sonia

    2003-03-01

    Workplace violence is a significant and widespread public health concern among health care workers, including nurses. With growing awareness of how practice environments influence patient outcomes and the retention of health professionals, it is timely to consider the impact of workplace violence in hospitals. Registered nurses in Alberta and British Columbia, Canada were surveyed on their experiences of violence in the workplace over the last five shifts. Our results suggest that nurses are experiencing many incidences of violence in a given work week, particularly in the emergency, psychiatric, and medical-surgical settings. Most violent acts are perpetrated by patients, but there is also a significant portion of violence and abuse committed by hospital co-workers, particularly emotional abuse and sexual harassment. Our results also indicate that the majority of workplace violence is not reported. We suggest that using the Broken Windows theory might be a useful tool to conceptualize why workplace violence occurs, and that this framework be used to begin to develop new violence prevention policies and strategies.

  4. Controls on Mannville coalbed methane production in Fort Assiniboine, Alberta

    Energy Technology Data Exchange (ETDEWEB)

    Bearinger, D.; Majcher, M. [Nexen Inc., Calgary, AB (Canada)

    2010-07-01

    A horizontal well exploitation scheme is being used in the Fort Assiniboine field in central Alberta to produce coalbed methane (CBM) from the under-saturated coals of the Mannville Formation. The Mannville coal seams in this region are under-saturated. In order to improve permeability to gas within the fracture system and achieve economic gas production rates, the reservoir's ability to dewater the coal through the fracture fabric to establish a gas phase is key. Across the field, a wide range of production rates can be found. A study was conducted to collect field wide data from core, wells, geological and geophysical mapping and production data in order to determine the major controls on gas production rates. The paper discussed the compilation of wellbore parameters, including borehole orientation and length; wellbore configuration; and production data. It also discussed the characterization of reservoir parameters such as reservoir thickness; structure; stress; and reservoir quality. It was concluded that the main controls on Mannville CBM production in the Fort Assiniboine field are coal seam thickness, effective stress, coal quality and face cleat exposure. 5 refs., 14 figs.

  5. Pesticide Use and Asthma in Alberta Grain Farmers.

    Science.gov (United States)

    Cherry, Nicola; Beach, Jeremy; Senthilselvan, Ambikaipakan; Burstyn, Igor

    2018-03-15

    A study of the respiratory health of grain farmers in Alberta, Canada was carried out in March 2002. Two populations were identified: members, in 1983, of a province-wide farm organisation, and grain farmers registered with the provincial agriculture department. A telephone interview addressed pesticide use (using pre-circulated trade names), chronic disease and respiratory symptoms. Pesticide ingredients were identified from provincial crop protection guides. Total years of use were calculated for seven chemical groups. Consent for linkage to administrative health records was obtained in 2009. A likelihood score (Lscore) is computed, relating symptoms to asthma diagnosis. Self-reported asthma and the Lscore are examined against duration of pesticide exposures. Of the 10,767 farmers listed, 2426 were still living, had farmed grain and were interviewed; 1371 were re-contacted and matched to health records. After allowance for confounders, years of exposure to phenoxy compounds are related to self-reported asthma and Lscore. Compared to no exposure, the adjusted odds ratios (95% Confidence Intervals for self-reported asthma for short, medium and long exposure to phenoxy compounds are 1.29 (0.66-2.52), 2.52 (1.25-5.09), and 3.18 (1.54-6.58), and for Lscore are 1.19 (0.91-1.55), 1.50 (1.13-1.99), and 1.58 (1.18-2.12). We conclude that lifetime exposure to phenoxy herbicides is associated with an increased risk of asthma.

  6. Review of Alberta Crown Crude Oil Marketing Program

    International Nuclear Information System (INIS)

    Crandall, G. R.; Kromm, R. B.

    1999-01-01

    This report contains an independent evaluation of the operations of the private marketing agents that are currently marketing the Alberta Crown's share of royalty crude oil. The evaluation includes a review of pricing performance, working relationship, current issues and the overall performance of the marketing arrangements during the fiscal years of 1997 and 1998. Overall, the outsourcing of sales of Crown production to agents is judged to be successful. For example, it has been noted that agents are becoming more aggressive in maintaining and increasing their margins. On the other hand, the increased level of aggressiveness in marketing, while tending to maximize Crown revenues, is also creating a potential conflict on how margins should be shared between the Crown and its agents. Also, there has been evidence of some management issues between the agents and the Crown concerning the extent to which the Crown should share in any increased value which the agent generates by increased third party marketing activities. These differences need to be addressed in order to maintain the strong performance of the marketing program. The consultants also recommend additional guidelines on risk management issues that more clearly define the Crown's risk tolerance. 2 tabs., 4 figs

  7. Electricity market reform failures: UK, Norway, Alberta and California

    International Nuclear Information System (INIS)

    Chikeung Woo; Lloyd, Debra; Tishler, Asher

    2003-01-01

    An analysis of electricity market reforms already taken place in the UK, Norway, Alberta (Canada) and California (USA) leads to our overall conclusion that the introduction of a competitive generation market, of itself, has failed to deliver reliable service at low and stable prices. The market reform failures are attributed to market power abuse by few dominant sellers (especially at times of transmission congestion), poor market design that invites strategic bidding by suppliers, the lack of customer response to price spikes, capacity shortage caused by demand growth not matched by new capacity, and thin trading of forward and futures contracts that are critical for price discovery and risk management. The paper then explains why an electricity market reform can easily fail to deliver the promised gains of better service at lower and more stable prices. The policy implication is that an electric market reform can be extremely risky, and may lead to a disastrous outcome. Thus, it is imprudent to implement such a reform in countries with limited sites for new generation and no indigenous fuels (e.g., Israel and Hong Kong). These countries should therefore consider introducing performance-based regulation that can immediately benefit electricity consumers in terms of lower prices, more stable prices, improved reliability, more choices, while encouraging the electric sector to pursue efficient operation and investment. (Author)

  8. Environmental issues and creditor's rights in Alberta and Saskatchewan

    International Nuclear Information System (INIS)

    McCarthy, P.T.; Lee, S.; Milani, M.W.

    1996-01-01

    A clarification of the ranking of environmentally related claims in bankruptcy and receivership proceedings, was presented. Also, the liability that a creditor assumes when taking control of a debtor's business or assets, particularly where environmental contaminants are concerned, was explained. The way that environmental law operates and the sorts of liability it imposes and upon whom, was also explained. Generally, environmental legislation imposes liability upon the owner of a contaminated property, whether or not the owner caused or created the problem. However, legislation also exists which imposes liability on the party in control and on the party which caused the contamination. A review of cases which deal with environmental legislation and their impact upon receivers in Saskatchewan and Alberta, was presented. Ways in which secured creditors can assess liability and minimize risks, were also described. The proposed amendments to the Bankruptcy and Insolvency Act (BIA) expand the current limited protection from personal liability for trustees in bankruptcy and extend it to receivers, trustees, monitors and agents

  9. Fusion reactor materials

    International Nuclear Information System (INIS)

    Rowcliffe, A.F.; Burn, G.L.; Knee', S.S.; Dowker, C.L.

    1994-02-01

    This is the fifteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; Special purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the U.S. Department of Energy. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

  10. The power of Alberta business : the impact of electricity deregulation on Alberta small and medium-sized business

    International Nuclear Information System (INIS)

    Pohlmann, C.; Kelly, D.

    2001-07-01

    Deregulation of the electricity market came into effect on January 1, 2001 in Alberta. This deregulation affects the retail and generation fields of electricity. The intention was to introduce competition and apply downward pressure on electricity prices, but the reverse effect was witnessed: power prices increased. It resulted in a period of anxiety on the part of businesses, caused by the volatility of electricity prices. A survey of Canadian Federation of Independent Business (CFIB) members was conducted in May and June 2001 to better understand the impacts of electricity deregulation on small and medium-sized businesses. A broad range of businesses provided responses (951 responses) covering all sectors of industry and regions in Alberta. A large proportion of respondents were dissatisfied with deregulation, caused in part by the confusion created by the flurry of rebate and credit announcements designed to ease the transition. Small firms were faced with significant increases in electricity prices, and several could not estimate the size of the increase as it was too difficult to measure. Responses varied from a low of 5 per cent increase to a high of 400 per cent in power rates. Most respondents also indicated that the increases had an impact on their business. The impact of power rate increases by sector was examined. Another consequence of deregulation was the fact that billing moved from a single invoice received to the requirement to actively manage energy usage. It was discovered that a lack of information on electricity cost and consumption management impeded the the ability to make business decisions. The CFIB asked respondents to indicate the measures being considered to address management of electricity costs. Incorporating energy-saving devices and/or methods had been considered by slightly more than 40 per cent of respondents. Negotiating with power retailers represented another option under consideration by some. It was felt that government must

  11. Chemical and physical hydrogeology of coal, mixed coal-sandstone and sandstone aquifers from coal-bearing formations in the Alberta Plains region, Alberta

    International Nuclear Information System (INIS)

    Lemay, T.G.

    2003-09-01

    With the decline of conventional oil and gas reserves, natural gas from coal (NGC) is an unconventional gas resource that is receiving much attention from petroleum exploration and development companies in Alberta. Although the volume of the NGC resource is large, there are many challenges facing NGC development in Alberta, including technical and economic issues, land access, water disposal, water diversion and access to information. Exploration and development of NGC in Alberta is relatively new, therefore there is little baseline data on which to base regulatory strategies. Some important information gaps have been filled through water well sampling in coal, mixed coal-sandstone and sandstone aquifers throughout Alberta. Analyses focused on the chemical and physical characteristics aquifers in use for domestic or agricultural purposes. Aquifer depths were generally less than 100 metres. Samples collected from Paskapoo-Scollard Formation, Horseshoe Canyon Formation and Belly River Group aquifers exceed Canadian water quality guideline values with respect to pH, sodium, manganese, chloride, chromium, sulphate, phenols and total dissolved solids. Pump tests conducted within the aquifers indicate that the groundwater flow is complicated. Water quality will have to be carefully managed to ensure responsible disposal practices are followed. Future studies will focus on understanding the chemical and biological process that occur within the aquifers and the possible link between these processes and gas generation. Mitigation and disposal strategies for produced water will also be developed along with exploration strategies using information obtained from hydrogeologic studies. 254 refs., 182 tabs., 100 figs., 3 appendices

  12. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

    A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

  13. Alberta's current market structure and future vision : transmission, critical infrastructure

    Energy Technology Data Exchange (ETDEWEB)

    McMaster, D. [Alberta Electric System Operator, Calgary, AB (Canada)

    2006-07-01

    Alberta's ongoing economic growth depends on reliable electricity, particularly as the province becomes the supplier of energy for North America. This paper addressed issues regarding Alberta's need for a robust power transmission system to ensure a quality electricity supply and to facilitate competitive market and investment in new supply. The Alberta Electric System Operator (AESO) facilitates a fair and open competitive and sustainable market for electricity and provides for the economic operation of the Alberta Interconnected Electric System. The AESO suggested that more than $3 billion may be needed in new transmission in the next 10 to 15 years. A first 500 kV line from Edmonton to Calgary is critical for ongoing reliability and to connect new supply in the Wabamun Lake area. The importance of strengthening interties with neighbouring jurisdictions was also discussed. A review of Alberta's electricity load and supply revealed that more than 3,000 MW of new generation have been added since 2001. A 10-year outlook (2007 to 2016) revealed an expected 3 per cent average annual growth rate in energy and peak demand, with a need for 3,800 MW of new generation by 2016. Since Alberta depends on a competitive market to provide a sufficient supply of electricity, confidence in market structure and operation is crucial. The AESO is working on developing and implementing a set of market and regulatory stability objectives in consultation with stakeholders in order to guide the evolution of the electricity market. The AESO has plans to interface Alberta's framework with the Electric Reliability Organization and to implement mandatory reliability standards. It also has plans to harmonize the AESO's tariff, market rules, and participant contracts to ensure consistency. tabs., figs.

  14. Future uses of research reactors

    International Nuclear Information System (INIS)

    Fleming, R.F.

    1990-01-01

    The use of research reactors in the next decade will be driven by two key forces: the retirement of obsolete facilities and the development of new capabilities, both in the United States and worldwide. Most research reactors in use in the United States began operation in the period from the late 1950s to the middle of the 1960s, both at universities and at the national laboratories. New design concepts include the 10-MW MAPLE by Atomic Energy of Canada Limited intended to provide an order-of-magnitude upgrade for the 2-MW university swimming-pool facilities and the advanced neutron source by the U.S. Department of Energy intended as the ultimate steady-state neutron facility. A rational program for U.S. research reactors might include the following components: (1) an inexpensive and very reliable reactor to replace the underutilized or underfunded university facilities of 2 MW or less; (2) a simple design in the 10- to 20-MW range to provide full research capability for some universities and other laboratories (the MAPLE design is a step in this direction); and (3) one or more of a high-end reactor with a power level up to 250 MW. Recent experience has shown that an important design criterion for any such facilities must be reliability of operation. All of these reactors would provide high-quality neutron beams as well as a variety of irradiation facilities

  15. Where's the water : with an ambitious program underway to map Alberta's water resources, researchers hope to ensure there's enough to meet increasing industrial, agricultural, and municipal demands

    International Nuclear Information System (INIS)

    Collison, M.

    2007-01-01

    Researchers at Natural Resources Canada's Earth Sciences Sector are currently studying the impact of climate change on water resources and groundwater in relation to energy development in Alberta, as well as to assess whether there is sufficient supply to aid in the production of oil sands. The project includes mapping of major regional aquifers to improve an understanding of groundwater resources. The aim of the project is to characterize formations, and understand natural controls of quality, availability and sustainability for long-term use. The project aims to characterize the physical makeup of rocks that form the aquifer, as well as to develop hydrological models of how water moves through systems. The University of Calgary is leading a project to analyze the chemical, isotopic state and composition of shallow groundwater in order to establish a baseline of its chemical makeup. The aim of the project is to provide an overview of groundwater as compared to produced water that occurs as a result of coalbed methane (CBM) drilling activities. Methane produced from CBM has a different isotopic signature than naturally occurring methane in groundwater. Researchers at the university are analyzing water from more than 75 production wells, as well as an additional 300 monitoring wells. It is hoped that all of the groundwater projects will help to improve Alberta's water preservation record. The intense energy production in the province means that no other location contributes as significantly as Alberta to global warming. It was concluded that improvements in energy technologies and environmental protection in the province will benefit people around the world. 4 figs

  16. Independent assessment team report to the Alberta Energy and Utilities Board on implementing deregulation of electricity generation in Alberta

    International Nuclear Information System (INIS)

    1999-01-01

    The particular aspect of deregulation of electricity generation in Alberta discussed is the economics of power purchase agreements (PPAs). There are various parameters associated with the PPAs that are emphasized including: technical characteristics; unit availability, capital costs and O and M costs; coal costs; gas costs; payment for flexible operation; hydro obligation amounts; income tax; property tax; and working capital, insurance and other costs. Chapter one of the Independent Assessment Team (IAT) report covers the report scope, and chapter two describes certain main principles underlying determination of PPAs. Chapter three discusses the IAT's determination of the PPA's forms and their main terms and conditions. Chapter four describes the IAT's determination of the underlying parameter values of the PPAs. Chapter five describes the ITA's determination of the allowed rate of return on equity and the capital structure of PPAs. An appendix covers a detailed description of the consultations carried out by the IAT; a report by HESI on the results of Pool modelling carried out to date (the HESI work was done to assist the IAT in determining PPAs, not the auction design); summary outputs of the IAT's financial model with indicative financial statements for each unit and company under the PPAs; and a document on shared services, common facilities and new units

  17. Feasibility study of the university of Utah TRIGA reactor power upgrade - Part I: Neutronics-based study in respect to control rod system requirements and design

    Directory of Open Access Journals (Sweden)

    Ćutić Avdo

    2013-01-01

    Full Text Available We present a summary of extensive studies in determining the highest achievable power level of the current University of Utah TRIGA core configuration in respect to control rod requirements. Although the currently licensed University of Utah TRIGA power of 100 kW provides an excellent setting for a wide range of experiments, we investigate the possibility of increasing the power with the existing fuel elements and core structure. Thus, we have developed numerical models in combination with experimental procedures so as to assess the potential maximum University of Utah TRIGA power with the currently available control rod system and have created feasibility studies for assessing new core configurations that could provide higher core power levels. For the maximum determined power of a new University of Utah TRIGA core arrangement, a new control rod system was proposed.

  18. Do "Virtual" and "Outpatient" Public Health Tuberculosis Clinics Perform Equally Well? A Program-Wide Evaluation in Alberta, Canada.

    Directory of Open Access Journals (Sweden)

    Richard Long

    Full Text Available Meeting the challenge of tuberculosis (TB elimination will require adopting new models of delivering patient-centered care customized to diverse settings and contexts. In areas of low incidence with cases spread out across jurisdictions and large geographic areas, a "virtual" model is attractive. However, whether "virtual" clinics and telemedicine deliver the same outcomes as face-to-face encounters in general and within the sphere of public health in particular, is unknown. This evidence is generated here by analyzing outcomes between the "virtual" and "outpatient" public health TB clinics in Alberta, a province of Western Canada with a large geographic area and relatively small population.In response to the challenge of delivering equitable TB services over long distances and to hard to reach communities, Alberta established three public health clinics for the delivery of its program: two outpatient serving major metropolitan areas, and one virtual serving mainly rural areas. The virtual clinic receives paper-based or electronic referrals and generates directives which are acted upon by local providers. Clinics are staffed by dedicated public health nurses and university-based TB physicians. Performance of the two types of clinics is compared between the years 2008 and 2012 using 16 case management and treatment outcome indicators and 12 contact management indicators.In the outpatient and virtual clinics, respectively, 691 and 150 cases and their contacts were managed. Individually and together both types of clinics met most performance targets. Compared to outpatient clinics, virtual clinic performance was comparable, superior and inferior in 22, 3, and 3 indicators, respectively.Outpatient and virtual public health TB clinics perform equally well. In low incidence settings a combination of the two clinic types has the potential to address issues around equitable service delivery and declining expertise.

  19. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

    The reactor core of nuclear reactors usually is composed of individual elongated fuel elements that may be vertically arranged and through which coolant flows in axial direction, preferably from bottom to top. With their lower end the fuel elements gear in an opening of a lower support grid forming part of the core structure. According to the invention a locking is provided there, part of which is a control element that is movable along the fuel element axis. The corresponding locking element is engaged behind a lateral projection in the opening of the support grid. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  20. Review of the application of sulphur recovery guidelines in Alberta: discussion paper for stakeholder consultation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-09-01

    The Alberta Energy and Utilities Board in cooperation with Alberta Environment has initiated a review of the application of Alberta sulphur recovery guidelines as currently described in Informational Letter 88-13 and the related report ERCB-AE 88-AA. The aim of the review is to clarify how the guidelines apply to older sour gas plants and to other facilities where sour or acid gases are handled. Such clarification is necessary for fair and consistent application of the existing guidelines. The specific objectives of the review are to clarify and/or update the sulphur recovery requirements for grandfathered sour gas plants, the application of the sulphur recovery guidelines to other facilities, and the proliferation guidelines for small gas plants and other facilities. The paper was prepared as part of an ongoing commitment by the Board and Alberta Environment to multi-stakeholder consultation. The discussion paper provides background on the issues, as well as a discussion of alternatives that could be considered. It is intended to assist public and industry stakeholders in providing input and recommendations to the Board and Alberta government.

  1. An inventory and risk-based prioritization of Steep Creek Fans in Alberta, Canada

    Directory of Open Access Journals (Sweden)

    Holm Kris

    2016-01-01

    Full Text Available In June 2013, heavy rainfall caused flooding on most rivers in the province of Alberta, Canada, producing one of Canada’s most expensive natural disasters with about $6 billion (CDN in damage. Flooding inundated several municipalities including downtown Calgary, the fourth-largest city in Canada. Debris flows and debris floods caused extensive highway closures and damages to development on alluvial fans. Following these events, the Government of Alberta requested an inventory of all fans intersecting municipal development, major roads and highways in Alberta. Such fans may be subject to debris flow, debris flood (mud flows, and/or flood hazards. The study area spans the entirety of the Alberta Rocky Mountains, approximately 51,000 km2 (7% of Alberta. We characterize 710 fans in terms of hazard level and presence and types of elements at risk. We statistically analyse watershed attributes to predict the dominant fan hydrogeomorphic process types. All fans under provincial jurisdiction are assigned priority ratings based on hazard levels and the presence and value of elements at risk. The prioritization is risk-based as it considers both hazards and potential consequences. Of the fans prioritized, 13% intersected parcels containing land and residential developments with an assessed value of $2.4 billion (CDN, and the remainder were crossed by roads, pipelines or transmission lines. We present the study results on an interactive, searchable web application that can support ongoing hazard and risk assessments and risk reduction planning.

  2. Alberta biodiversity monitoring program - monitoring effectiveness of sustainable forest management planning.

    Science.gov (United States)

    Stadt, J John; Schieck, Jim; Stelfox, Harry A

    2006-10-01

    A conceptual model of sustainable forest management is described based on three connected and necessary components: Policy/Strategic Planning, Operational Planning, and Effectiveness Monitoring/Science. Alberta's proposed Forest Management Planning Standard is described as an example of operational planning. The standard utilizes coarse and fine filter approaches to conserving biodiversity and sets requirements for implementation monitoring. The Alberta Biodiversity Monitoring Program (ABMP) is described as an example of effectiveness monitoring supporting Operational Planning. The ABMP is a rigorous science-based initiative that is being developed to monitor and report on biodiversity status and trends throughout the province of Alberta, Canada. The basic survey design consists of 1656 sites, 20 km apart, evenly spaced on a grid pattern across Alberta. Sites will be sampled over a five-year period at a rate of 350 sites/year. Standardized sampling protocols will be used to cover a broad range of species and habitat elements within terrestrial and aquatic environments, as well as broader landscape-level features. Trends and associations detected by ABMP products will be validated through cause-effect research. ABMP focuses research on critical issues and informs both operational planning and the development of policy and strategic-level plans. The Alberta Forest Management Planning Standard and the ABMP are described as key components to implementing resource planning based on ecosystem management principles.

  3. Fertility in Alberta in a Context of Rapid Economic Growth, 1997-2007

    Directory of Open Access Journals (Sweden)

    Frank Trovato

    2010-12-01

    Full Text Available Historically, birth rates in Alberta have followed closely the trajectory of change experienced by the other Canadian provinces. Its total fertility rate fell during the low point of the 1930s; it increased during the post-War baby boom in the 1950s and sixties, and thereafter fell to subreplacement levels beginning in the mid 1970s. In recent years, especially since the early 2000s, the birth rate in Alberta has unexpectedly increased, such that by 2007, it had reached 1.90 children per woman - not far from the 2.1 level needed for generational replacement in the long term. During this same period both national and provincial fertility rates fluctuated at levels below those of Alberta (except Saskatchewan and Manitoba, whose rates have been higher. In this study, I examine the historical pattern of fertility change in Alberta, noting similarities and differences with the other provinces. I then look at the association of selected macro level factors (marriage, unemployment, wages, female labour force participation with change in total and parity-specific birth rates between 1997 and 2007, a period of unprecedented economic growth in Alberta. The statistical results show that although marriage is not significantly correlated with change in fertility rates, male and female wages and female labour force participation all show associations consistent with a procyclical interpretation of fertility change - that is, periods of economic growth are conducive to fertility increase whereas bad economic times are associated with reduced fertility.

  4. Present status and future prospect of research reactors

    International Nuclear Information System (INIS)

    Takemi, Hirokatsu

    1996-01-01

    The present status of research reactors more than MW class reactor in JAERI and the Kyoto University and the small reactors in the Musashi Institute of Technology, the Rikkyo University, the Tokyo University, the Kinki University and other countries are explained in the paper. The present status of researches are reported by the topics in each field. The future researches of the beam reactor and the irradiation reactor are reviewed. On various kinds of use of research reactor and demands of neutron field of a high order, new type research reactors under investigation are explained. Recently, the reactors are used in many fields such as the basic science: the basic physics, the material science, the nuclear physics, and the nuclear chemistry and the applied science; the earth and environmental science, the biology and the medical science. (S.Y.)

  5. Reactor use in nuclear engineering programs

    International Nuclear Information System (INIS)

    Murray, R.L.

    1975-01-01

    Nuclear reactors for dual use in training and research were established at about 50 universities in the period since 1950, with assistance by the U. S. Atomic Energy Commission and the National Science Foundation. Most of the reactors are in active use for a variety of educational functions--laboratory teaching of undergraduates and graduate students, graduate research, orientation of visitors, and nuclear power plant reactor operator training, along with service to the technical community. As expected, the higher power reactors enjoy a larger average weekly use. Among special programs are reactor sharing and high-school teachers' workshops

  6. NCSU reactor sharing program. Final technical report

    International Nuclear Information System (INIS)

    Perez, P.B.

    1997-01-01

    The Nuclear Reactor Program at North Carolina State University provides the PULSTAR Research Reactor and associated facilities to eligible institutions with support, in part, from the Department of Energy Reactor Sharing Program. Participation in the NCSU Reactor Sharing Program continues to increase steadily with visitors ranging from advance high school physics and chemistry students to Ph.D. level research from neighboring universities. This report is the Final Technical Report for the DOE award reference number DE-FG05-95NE38136 which covers the period September 30, 1995 through September 30, 1996

  7. A Case Study: Implementation of a Management System for the TRIGA Mark II Research Reactor at the Laboratory of Applied Nuclear Energy (LENA) of the University of Pavia, Italy. Annex I

    International Nuclear Information System (INIS)

    2013-01-01

    This annex provides an example for the implementation of a management system for operating organizations of research reactors, based on a case study in which the implementation of such a system has been completed. The case study relates the experience of the Applied Nuclear Energy Laboratory (hereafter referred to as LENA) of the University of Pavia, Italy. This example is used because of the recent completion of the implementation of an integrated management system, and also because of the specific characteristics of the organization (such as the limited number of staff, limited financial resources, etc.), which are often typical for organizations that operate smaller research reactors. Section I-1 gives a brief presentation of the organization, including the scope of work, the main activities performed, the organizational structure, the identification of interested parties and the applicable requirements and standards. Section I-2 describes the LENA Management System, the reasons for its implementation, the stages of its development and the processes involved. Some practical examples related to the development of the LENA Management System are discussed in Section I-3, indicating the choices made by the organization. In particular, Section I-3.12 shows the correlation between the LENA Management System processes and the processes considered in the main body of this publication.

  8. Sour-gas potential in Devonian of western Alberta, Canada

    Energy Technology Data Exchange (ETDEWEB)

    Podruski, J.A.

    1989-03-01

    The Geological Survey of Canada is presently conducting an assessment of the undiscovered gas resources of the Western Canada sedimentary basin using the exploration play analysis technique. The first system being examined is the Devonian, which as been divided into four exploration districts based on differences in depositional and tectonic histories, hydrocarbon compositions, and exploration practices. The western Alberta sour gas district contains most of the Devonian gas reserves (10 trillion ft/sup 3/ of marketable gas) and potential in 12 exploration plays. Production in the Upper Devonian Swan Hills, Leduc, and Nisku formations is from the updip (northeast), basinward termination of carbonate shelves or large reef complexes and their associated patch and pinnacle reefs. Mapping the reef or shelf carbonate transition to basinal shale and carbonate delineates the play areas in these formations. Production in the Upper Devonian Wabamun Formation is from stratigraphic traps at shelf carbonate/shelf evaporite transitions and in structural-stratigraphic traps in dolomitized shelf carbonate. Pools in these plays typically contain from 50 to 500 billion ft/sup 3/ of marketable gas, have 10-30% H/sub 2/S, and occur at depths from 8000 to 15,000 ft. Potential in most plays is large, considering that between 90 and 99% of the play areas are unexplored. Present exploration is still concentrating on the conventional shelf margin or reef traps, such as in the area of the recent Caroline discovery. Subtle intrashelf traps are only beginning to be explored and could constitute a major resource target of the future, provided that economic conditions and improvements in seismic technology and geologic understanding will sustain the exploration effort in this district.

  9. Epidemiology of pertussis in Alberta, Canada 2004–2015

    Directory of Open Access Journals (Sweden)

    Xianfang C. Liu

    2017-06-01

    Full Text Available Abstract Background We describe the epidemiology of pertussis in Alberta, Canada by person, place, and time between 2004 and 2015, identify outbreak years, and examine vaccination coverage and vaccination timeliness. Methods We used health data from Alberta’s Communicable Disease Registry System for the period of January 1, 2004 through August 31, 2015 to identify unique cases of pertussis. Unique cases were deterministically linked to data in Alberta’s immunization repository and health care insurance plan registry. Population estimates and vaccination coverage were extracted from Alberta’s online Interactive Health Data Application. We estimated pertussis incidence rates per 100,000 persons by year, age group, gender, and health zone. Outbreak years were identified using a one-sided cumulative sum (CUSUM analysis by comparing annual incidence rates to baseline rates. Results Over the period, 3510 cases of pertussis were confirmed by laboratory testing or epidemiological linkage. Incidence rates per 100,000 persons were highest in 2004 (20.5, 2005 (13.6, and 2015 (10.4 for all age groups. Incidence rates were highest among the youngest age groups and decreased as age groups increased. Based on CUSUM analysis, 2008 and 2012 met the criteria for outbreak years. Vaccination coverage was over 90% among the general population, however only 61% of cases received at least one dose. About 60% of cases were diagnosed 5+ years after receiving the vaccine. Approximately 87–91% of vaccinated cases did not receive the first three vaccine doses in a timely manner. Conclusion Pertussis incidence rates fluctuated over the period across all age groups. The majority of cases had no record of vaccination or were delayed in receiving vaccines. CUSUM analysis was an effective method for identifying outbreaks.

  10. Pesticide Use and Asthma in Alberta Grain Farmers

    Directory of Open Access Journals (Sweden)

    Nicola Cherry

    2018-03-01

    Full Text Available A study of the respiratory health of grain farmers in Alberta, Canada was carried out in March 2002. Two populations were identified: members, in 1983, of a province-wide farm organisation, and grain farmers registered with the provincial agriculture department. A telephone interview addressed pesticide use (using pre-circulated trade names, chronic disease and respiratory symptoms. Pesticide ingredients were identified from provincial crop protection guides. Total years of use were calculated for seven chemical groups. Consent for linkage to administrative health records was obtained in 2009. A likelihood score (Lscore is computed, relating symptoms to asthma diagnosis. Self-reported asthma and the Lscore are examined against duration of pesticide exposures. Of the 10,767 farmers listed, 2426 were still living, had farmed grain and were interviewed; 1371 were re-contacted and matched to health records. After allowance for confounders, years of exposure to phenoxy compounds are related to self-reported asthma and Lscore. Compared to no exposure, the adjusted odds ratios (95% Confidence Intervals for self-reported asthma for short, medium and long exposure to phenoxy compounds are 1.29 (0.66–2.52, 2.52 (1.25–5.09, and 3.18 (1.54–6.58, and for Lscore are 1.19 (0.91–1.55, 1.50 (1.13–1.99, and 1.58 (1.18–2.12. We conclude that lifetime exposure to phenoxy herbicides is associated with an increased risk of asthma.

  11. Public health surveillance response following the southern Alberta floods, 2013.

    Science.gov (United States)

    Sahni, Vanita; Scott, Allison N; Beliveau, Marie; Varughese, Marie; Dover, Douglas C; Talbot, James

    2016-08-15

    In June of 2013, southern Alberta underwent flooding that affected approximately 100,000 people. We describe the process put in place for public health surveillance and assessment of the impacts on health. Public health surveillance was implemented for the six-week period after the flood to detect anticipated health events, including injuries, mental health problems and infectious diseases. Data sources were emergency departments (EDs) for presenting complaints, public health data on the post-exposure administration of tetanus vaccine/immunoglobulin, administrative data on prescription drugs, and reportable diseases. An increase in injuries was detected through ED visits among Calgary residents (rate ratio [RR] 1.28, 95% confidence interval [CI]: 1.14-1.43) and was supported by a 75% increase in the average weekly administration of post-exposure prophylaxis against tetanus. Mental health impacts in High River residents were observed among females through a 1.64-fold (95% CI: 1.11-2.43) and 2.32-fold (95% CI: 1.45-3.70) increase in new prescriptions for anti-anxiety medication and sleep aids respectively. An increase in sexual assaults presenting to EDs (RR 3.18, 95% CI: 1.29-7.84) was observed among Calgary residents. No increases in infectious gastrointestinal disease or respiratory illness were identified. Timely identification and communication of surveillance alerts allowed for messaging around the use of personal protective equipment and precautions for personal safety. Existing data sources were used for surveillance following an emergency situation. The information produced, though limited, was sufficiently timely to inform public health decision-making.

  12. Albedo of a hybrid poplar plantation in central Alberta, Canada

    Science.gov (United States)

    Price, D. T.; Bernier, P. Y.; Orchansky, A.; Thomas, B.

    2012-04-01

    Canada's boreal forest resources are coming under increasing pressure from competing land-uses, including establishment of protected areas, and losses of harvestable forest to mining and oil and gas exploration. In the prairie region, concerns about lack of wood supply for pulpmills and potential opportunities for bioenergy production and carbon sequestration for climate change mitigation, have spurred interest in afforestation of marginal agricultural land, notably with fast-growing hybrid poplars (HP). However, global modelling studies suggest that a shift from grassland or crops to forest cover in temperate and boreal regions could result in reduced surface albedo, particularly in winter, causing an increase in radiative forcing and reducing any climate mitigation benefits due to net GHG removal. We report on seven growing seasons of measurements of short-wave canopy albedo using tower-mounted instruments, along with eddy covariance measurements of carbon, water and energy balance, at a site in central Alberta planted with HP cuttings in spring 2005. The data show little systematic change in average albedo as vegetation has changed from bare ground to a plantation of 6 m trees. Reasons for this include very wide (3 m) spacing between the trees, and snow cover which often persists for 4-5 months and is highly visible below the bare canopies during winter. While measurements should continue as the trees grow larger, we postulate that extensive afforestation with HP is unlikely to have major effects on regional-scale surface albedo compared to the agricultural systems they replace. Normal rotation lengths are 15-20 years, hence even if older plantations have significantly lower winter albedo, their contribution to the regional average would be relatively small because they will cover only a small fraction of the landscape (e.g., compared to forests of boreal conifers or temperate broadleaved species).

  13. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  14. Reactor Neutrinos

    Directory of Open Access Journals (Sweden)

    Soo-Bong Kim

    2013-01-01

    Full Text Available We review the status and the results of reactor neutrino experiments. Short-baseline experiments have provided the measurement of the reactor neutrino spectrum, and their interest has been recently revived by the discovery of the reactor antineutrino anomaly, a discrepancy between the reactor neutrino flux state of the art prediction and the measurements at baselines shorter than one kilometer. Middle and long-baseline oscillation experiments at Daya Bay, Double Chooz, and RENO provided very recently the most precise determination of the neutrino mixing angle θ13. This paper provides an overview of the upcoming experiments and of the projects under development, including the determination of the neutrino mass hierarchy and the possible use of neutrinos for society, for nonproliferation of nuclear materials, and geophysics.

  15. REACTOR SHIELD

    Science.gov (United States)

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  16. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  17. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

    This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

  18. Health researchers in Alberta: an exploratory comparison of defining characteristics and knowledge translation activities

    Directory of Open Access Journals (Sweden)

    Birdsell Judy M

    2007-01-01

    Full Text Available Abstract Background Canadian funding agencies are no longer content to support research that solely advances scientific knowledge, and key directives are now in place to promote research transfer to policy- and decision-makers. Therefore, it is necessary to improve our understanding of how researchers are trained and supported to facilitate knowledge translation activities. In this study, we investigated differences in health researcher characteristics and knowledge translation activities. Methods Our sample consisted of 240 health researchers from three Alberta universities. Respondents were classified by research domain [basic (n = 72 or applied (n = 168] and faculty [medical school (n = 128 or other health science (n = 112]. We examined our findings using Mode I and Mode II archetypes of knowledge production, which allowed us to consider the scholarly and social contexts of knowledge production and translation. Results Differences among health researcher professional characteristics were not statistically significant. There was a significant gender difference in the applied researcher faculty group, which was predominantly female (p p p = .01; Mode II, p p = .025 and number of publications (medical school > other faculties; p = .004. There was an interaction effect for research domain and faculty group for number of publications (p = .01, in that applied researchers in medical faculties published more than their peers in other faculty groups. Conclusion Our findings illustrate important differences between health researchers and provide beginning insights into their professional characteristics and engagement in Mode I and Mode II activities. A future study designed to examine these dimensions in greater detail, including potential covariates across more varied institutions, would yield richer insights and enable an examination of relative influences, needs and costs of each mode of activity.

  19. The reactor Cabri

    International Nuclear Information System (INIS)

    Ailloud, J.; Millot, J.P.

    1964-01-01

    It has become necessary to construct in France a reactor which would permit the investigation of the conditions of functioning of future installations, the choice, the testing and the development of safety devices to be adopted. A water reactor of a type corresponding to the latest CEA constructions in the field of laboratory or university reactors was decided upon: it appeared important to be able to evaluate the risks entailed and to study the possibilities of increasing the power, always demanded by the users; on the other hand, it is particularly interesting to clarify the phenomena of power oscillation and the risks of burn out. The work programme for CABRI will be associated with the work carried out on the American Sperts of the same type, during its construction, very useful contacts were made with the American specialists who designed the se reactors. A brief description of the reactor is given in the communication as well as the work programme for the first years with respect to the objectives up to now envisaged. Rough description of the reactor. CABRI is an open core swimming-pool reactor without any lateral protection, housed in a reinforced building with controlled leakage, in the Centre d'Etudes Nucleaires de Cadarache. It lies alone in the middle of an area whose radius is 300 meters long. Control and measurements equipment stand out on the edge of that zone. It consumes MTR fuel elements. The control-safety rods are propelled by compressed air. The maximum flow rate of cooling circuit is 1500 m 3 /h. Transient measurements are recorded in a RW330 unit. Aims and work programme. CABRI is meant for: - studies on the safety of water reactors - for the definition of the safety margins under working conditions: research of maximum power at which a swimming-pool reactor may operate with respect to a cooling accident, of local boiling effect on the nuclear behaviour of the reactor, performances of the control and safety instruments under exceptional

  20. Propulsion reactors

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    A nuclear reactor equips the recently constructed French aircraft- carrier Charles-De-Gaulle, in a few months the second nuclear submarine (SNLE) of new generation will be operational. In last october the government launched the program Barracuda which consists of 6 submarines (SNA) whose series head will be operational in 2010. The main asset of nuclear propulsion is to allow an almost unlimited autonomy: soft water, air are produced inside the submarine and the maximum time spent underwater is only limited by human capacity to cope with confinement. CEA has 3 missions concerning country defence. First the designing, the fabrication and the maintenance of weapons, secondly the supplying of fissile materials and thirdly the nuclear propulsion. A new generation of propulsion reactors is being studied and a ground installation involving a test reactor equivalent to that on board is being built. This test reactor (RES) will simulate any type of on-board reactors by adjusting temperature, pressure, flowrate and even equipment such as steam generator. This reactor will validate the technological choices for the Barracuda program. (A.C.)