Homogeneous Slowpoke reactor for the production of radio-isotope: a feasibility study

Energy Technology Data Exchange (ETDEWEB)

Busetta, P.; Bonin, H.W. [Royal Military College of Canada, Kingston, Ontario (Canada)

2006-09-15

The purpose of this research is to study the feasibility of replacing the actual heterogeneous fuel core of the present SLOWPOKE-2 by a reservoir containing a homogeneous fuel for the production of Mo-99. The study looked at three items: by using the MCNP Monte Carlo reactor calculation code, develop a series of parameters required for an homogeneous fuel and evaluate the uranyl sulfate concentration of the aqueous solution fuel in order to keep a similar excess reactivity; verify if the homogeneous react will retain its inherent safety attributes; and with the new dimensions and geometry of the fuel core, observe whether natural convection can still effectively cool the reactor using the modeling software FEMLAB(r). It was found that it is needed feasible to modify the SLOWPOKE-2 reactor for a homogeneous reactor using a solution of uranyl sulfate and water. (author)

Homogeneous slowpoke reactor for the production of radio-isotope. A feasibility study

International Nuclear Information System (INIS)

Busatta, P.; Bonin, H.

2005-01-01

The purpose of this research is to study the feasibility of replacing the actual heterogeneous fuel core of the present SLOWPOKE-2 by a reservoir containing a homogeneous fuel for the production of Mo-99. The study looked at three items: by using the MCNP 5 simulation code, develop a series of parameters required for an homogeneous fuel and evaluate the uranyl sulfate concentration of the aqueous solution fuel in order to keep a similar excess reactivity; verify if the homogeneous reactor will retain its inherent safety attributes; and with the new dimensions and geometry of the fuel core, observe whether the natural convection will still effectively cool the reactor using the modeling software FEMLAB. The MCNP 5 simulation code was validated by using a simulation with WIMS-AECL code. It was found that it is indeed feasible to modify the SLOWPOKE-2 reactor for a homogeneous reactor using a solution of uranyl sulfate and water. (author)

Homogeneous slowpoke reactor for the production of radio-isotope. A feasibility study

Energy Technology Data Exchange (ETDEWEB)

Busatta, P.; Bonin, H. [Royal Military College of Canada, Kingston, Ontario (Canada)]. E-mail: paul.busatta@rmc.ca; bonin-h@rmc.ca

2005-07-01

The purpose of this research is to study the feasibility of replacing the actual heterogeneous fuel core of the present SLOWPOKE-2 by a reservoir containing a homogeneous fuel for the production of Mo-99. The study looked at three items: by using the MCNP 5 simulation code, develop a series of parameters required for an homogeneous fuel and evaluate the uranyl sulfate concentration of the aqueous solution fuel in order to keep a similar excess reactivity; verify if the homogeneous reactor will retain its inherent safety attributes; and with the new dimensions and geometry of the fuel core, observe whether the natural convection will still effectively cool the reactor using the modeling software FEMLAB. The MCNP 5 simulation code was validated by using a simulation with WIMS-AECL code. It was found that it is indeed feasible to modify the SLOWPOKE-2 reactor for a homogeneous reactor using a solution of uranyl sulfate and water. (author)

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

Mathematical models in Slowpoke reactor internal irradiation site

International Nuclear Information System (INIS)

Raza, J.

2007-01-01

The main objective is to build representative mathematical models of neutron activation analysis in a Slowpoke internal irradiation site. Another significant objective is to correct various elements neutron activation analysis measured mass using these models. The neutron flux perturbation is responsible for the measured under-estimation of real masses. We supposed that neutron flux perturbation measurements taken during the Ecole Polytechnique de Montreal Slowpoke reactor first fuel loading were still valid after the second fuelling. .We also supposed that the thermal neutrons spatial and kinetic energies distributions as well as the absorption microscopic cross section dependence on the neutrons kinetic energies were important factors to satisfactorily represent neutron activation analysis results. In addition, we assumed that the neutron flux is isotropic in the laboratory system. We used experimental results from the Slowpoke reactor internal irradiation sites, in order to validate our mathematical models. Our models results are in close agreement with these experimental results..We established an accurate global mathematical correlation of the neutron flux perturbation in function of samples volumes and macroscopic neutron absorption cross sections. It is applicable to sample volumes ranging from 0,1 to 1,3 ml and macroscopic neutron absorption cross section up to 5 moles-b for seven (7) elements with atomic numbers (Z) ranging from 5 to 79. We first came up with a heuristic neutron transport mathematical semi-analytical model, in order to better understand neutrons behaviour in presence of one of several different nuclei samples volumes and mass. In order to well represent the neutron flux perturbation, we combined a neutron transport solution obtained from the spherical harmonics method of a finite cylinder and a mathematical expression combining two cylindrical harmonic functions..With the help of this model and the least squares method, we made extensive

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

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

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

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

Iodine behaviour in the SLOWPOKE nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Bekeris, P A; Evans, G J [Toronto Univ., ON (Canada). Dept. of Chemical Engineering and Applied Chemistry

1994-12-31

The purpose of this project is to measure and attempt to explain the presence and volatility of iodine isotopes present as fission products in the SLOWPOKE-2 reactor. Liquid sampling and extraction procedures developed indicated that approximately 40% of the reactor iodine is in the form of iodate (IO{sub 3}{sup -}), and 60% is in the form of iodide (I{sup -}). No appreciable amount in non-polar forms such as molecular iodine (I{sub 2}) or organic iodides (RI) were detected. This goes contrary to past expectations that all of the iodine in the liquid phase would be in the form of I{sup -}. In addition partition coefficients for I-131 were determined as 2-6x10{sup 6} at a neutral pH. Kr-88 is suspected as a possible interfering isotope in the measurement of I-131 in the liquid and gas phases. (author). 9 refs., 2 tabs., 2 figs.

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.

Use of a SLOWPOKE-2 reactor for nuclear forensics applications

Energy Technology Data Exchange (ETDEWEB)

Andrews, M.T.; Beames-Canivet, T.L.; Elliott, R.S.; Kelly, D.G.; Corcoran, E.C., E-mail: Emily.Corcoran@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada)

2014-07-01

A low enriched uranium SLOWPOKE-2 reactor is used as a neutron interrogation source in support of the identification and characterization of Special Nuclear Materials (SNM) at the Royal Military College of Canada (RMCC). Small amounts of fissile uranium and plutonium are sent into a SLOWPOKE-2 irradiation site before their transport to RMCC’s delayed neutron and gamma counting (DNGC) system. The counting arrangement of the DNGC consists of an array of six {sup 3}He and a high purity germanium detector. These detectors record the delayed neutron and photon emissions as a function of count time, to verify MCNP6 simulations of delayed particle emissions, and to detect and quantify trace amounts of fissile content. This paper discusses MCNP analyses done in preparation for an upcoming nuclear forensics exercise in the fall of 2014. MCNP6 simulations of the DNGC system focussed on the identification of characteristic gamma lines from prominent fission products. The relative intensities of these gamma lines are dependent on the SNM content in the sample. Gamma line pairs useful for SNM identification in RMCC's DNGC system are presented. (author)

DRAGON and SERPENT 2-D modelling of the SLOWPOKE-2 reactor at Ecole Polytechnique Montreal

International Nuclear Information System (INIS)

Raouafi, H.; Marleau, G.

2012-01-01

DRAGON is a deterministic code that can be used to perform lattice cell calculations based on numerical solutions of neutron transport equation. DRAGON can also be used for full core 2-D and 3-D simulations in transport. One alternative to the use of such a deterministic code consist in following the history of neutrons in the core based on statistical Monte Carlo simulation with codes like MCNP and SERPENT. This second calculation approach has been used successfully for SLOWPOKE-2 simulation in the past. Here we present a comparison between DRAGON and SERPENT calculations for the SLOWPOKE-2 reactor. We also compare the flux distribution obtained using both codes for a copper sample placed inside a small irradiation site. (author)

Various applications using the SLOWPOKE-2 facility at RMC

Energy Technology Data Exchange (ETDEWEB)

Bennett, L.G.I.; Nielsen, K.S. [Royal Military College of Canada, Kingston, ON (Canada)

2011-07-01

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.

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.

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

Keeping research reactors relevant: a pro-active approach for SLOWPOKE-2 at RMC

International Nuclear Information System (INIS)

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

2011-01-01

In 2001, the Royal Military College of Canada replaced its aging analogue SLOWPOKE-2 reactor control system with a digital control system. The system was successfully commissioned and has provided a renewed platform for student learning and research. An upgrade to the digital control and instrumentation system has been completed and will be installed in October 2010. The upgrade includes new computer hardware, updated software and a simulation and training system that will enhance training, education and research by licensed operators, students and researchers.

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

The multi-role nature of the SLOWPOKE-2 facility at the Royal Military College of Canada

International Nuclear Information System (INIS)

Bennett, L.G.I.; Beeley, P.A.

1994-01-01

After up to a decade of successful operation of seven SLOWPOKE-2 reactors within Canada and in Jamaica, an eighth SLOWPOKE-2 research reactor was installed at the Royal Military College of Canada in 1985. Its open pool was one factor that allowed the authors to develop a variety of research capabilities beyond those being established for NAA. A description of the research projects to date will serve to indicate the diversity of this facility. (author) 14 refs.; 4 figs.; 1 tab

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)

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.)

Performance of small reactors at universities for teaching, research, training and service (TRTS): thirty five years' experience with the Dalhousie University SLOWPOKE-2 reactor

Energy Technology Data Exchange (ETDEWEB)

Chatt, A., E-mail: a.chatt@dal.ca [Dalhousie Univ., Trace Analysis Research Centre, Dept. of Chemistry, Halifax, Nova Scotia (Canada)

2013-07-01

The Dalhousie University SLOWPOKE-2 Reactor (DUSR) facility, operated during 1976-2011, was the only research reactor in Atlantic Canada as well as the only one associated with a chemistry department in a Canadian university. The most outstanding features of the facility included: a rapid (100 ms) cyclic pneumatic sample transfer system, a permanently installed Cd-site, and a Compton-suppression gamma-ray spectrometer. The usage encompassed fundamental as well as applied studies in various fields using neutron activation analysis (NAA). The facility was used for training undergraduate/graduate students, postdoctoral fellows, technicians, and visiting scientists, and for cooperative projects with other universities, research organizations and industries. (author)

The SLOWPOKE licensing model

Energy Technology Data Exchange (ETDEWEB)

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

1989-08-15

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.

The status of HEU and LEU core conversion activities at the Jamaica SLOWPOKE

Energy Technology Data Exchange (ETDEWEB)

Preston, J.; Grant, C., E-mail: john.preston@uwimona.edu.jm [Univ. of the West Indies, Mona Campus, International Centre for Environmental and Nuclear Sciences, Kingston (Jamaica)

2013-07-01

The SLOWPOKE reactor in Jamaica has been operated by the International Centre for Environmental and Nuclear Sciences, University of the West Indies since 1984, mainly for the purpose of Neutron Activation Analysis. The HEU core with current utilization has another 14 years of operation, before the addition of a large beryllium annulus would be required to further extend the life-time by 15 years. However, in keeping with the spirit of the Reduced Enrichment for Research and Test Reactors (RERTR) program, the decision was taken in 2003 to convert the core from HEU to LEU, inline with those at the Ecole Polytechnic and RMC SLOWPOKE facilities. This paper reports on the current status of the conversion activities, including key fuel manufacture and regulatory issues, which have seen substantial progress during the last year. A timetable for the complete process is given, and provided that the fuel fabrication can be completed in the estimated 18 months, the core conversion should be accomplished by the end of 2014. (author)

Homogeneous SLOWPOKE reactors for Mo-99/Tc-99m production in North America

Energy Technology Data Exchange (ETDEWEB)

Hilborn, J.W., E-mail: hilbovanw@sympatico.ca [Deep River, Ontario (Canada); Bonin, H.W. [Royal Military College of Canada, Kingston, Ontario (Canada)

2014-07-01

The 15 month shutdown of NRU in 2009 - 2010 caused an overall isotope shortage of approximately 30%; and in North America, the annual Tc-99m demand decreased from an estimated 20 million unit doses to about 15 million unit doses. Mo-99/Tc-99m is produced from HEU targets, irradiated in NRU for 11 days, and after chemical removal of uranium it is shipped to Nordion in Kanata, Ontario. Nordion further purifies the material and sends it to Lantheus Medical Imaging in the USA for manufacture of Mo-99 generators, which are then distributed to hundreds of hospital radiopharmacies throughout North America. One other American company, Covidien, manufactures and distributes Mo-99 generators like Lantheus, but they import bulk Mo-99 from Europe or South Africa. At the hospitals, Tc-99m is chemically extracted daily from the Mo-99 generators and loaded into syringes for immediate clinical use. Fortuitously, the 66 hour half-life of Mo-99 allows the replenishment of Tc-99m in the generator over a growth period of about 20 hours; and a generator can be 'milked' daily for up to two weeks. A more efficient model is the direct production and distribution of Tc-99m unit doses to regional hospitals from 10 'industrial' radiopharmacies located at existing licensed reactor sites in North America. A 20 kW homogeneous SLOWPOKE reactor at each site would deliver 15 litres of irradiated uranyl sulphate fuel solution daily to industrial-scale hot cells for extraction of Mo-99, which would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and the Low Enriched Uranium (LEU) would be recycled. Each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily, for courier delivery to all of the Nuclear Medicine hospitals within a 3 hour average range by road transport. Typically, the delivered doses would be in the range 10 to 30 mCi. Assuming an average unit dose of 25 mCi at the hospital and 5 x 52

The status of HEU to LEU core conversion activities at the Jamaica SLOWPOKE

Energy Technology Data Exchange (ETDEWEB)

Preston, J.; Grant, C., E-mail: john.preston@uwimona.edu.jm [Univ. of the West Indies, Mona Campus, International Centre for Environmental and Nuclear Sciences, Mona (Jamaica)

2012-12-15

The SLOWPOKE reactor in Jamaica has been operated by the International Centre for Environmental and Nuclear Sciences, University of the West Indies since 1984, mainly for the purpose of Neutron Activation Analysis. The HEU core with current utilization has another 14 years of operation, before the addition of a large beryllium annulus would be required to further extend the life-time by 15 years. However, in keeping with the spirit of the Reduced Enrichment for Research and Test Reactors (RERTR) program, the decision was taken in 2003 to convert the core from HEU to LEU, in line with those at the Ecole Polytechnic and RMC SLOWPOKE facilities. This paper reports on the current status of the conversion activities, including key fuel manufacture and regulatory issues, which have seen substantial progress during the last year. A timetable for the complete process is given, and provided that the fuel fabrication can be completed in the estimated 18 months, the core conversion should be accomplished by the end of 2014. (author)

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

The keys to success in marketing small heating reactors

International Nuclear Information System (INIS)

McDougall, D.S.; Lynch, G.F.

1988-01-01

The success of the SLOWPOKE Energy System requires acceptance of the SLOWPOKE reactor within the community where the reactor's energy is to be used. Public acceptance will be obtained once the public is convinced that this nuclear heat source is needed, safe and of economic benefit to the community. The need for a new application of nuclear energy is described and the ability of small reactors used for district heating to play that role is shown. The safety of the reactor is being demonstrated with the establishment of the SLOWPOKE Demonstration Reactor by Atomic Energy of Canada Limited and with open, candid discussion with the involved community. Economic arguments are reviewed and include discussion of quantitative and qualitative issues. (orig.)

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

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)

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)

Medical isotope shortage 2009-2010 and future options NRU, SLOWPOKE and MAPLE

Energy Technology Data Exchange (ETDEWEB)

Hilborn, J. [Deep River, Ontario (Canada)

2013-07-01

The 15 month shutdown of NRU and the unexpected termination of the AECL/Nordion MAPLE project caused a world-wide shortage of medical isotopes. After the recent repair of NRU, AECL is confident that it could continue operating safely and reliably as a multi-purpose reactor until 2021 or longer. There is convincing evidence that the restoration of the MAPLE reactors is technically feasible, but it is highly improbable that a 10 MW MAPLE production reactor can ever be cost-effective. However, conversion of the present 10 MW reactors to 3 MW, without major changes to the structural hardware, warrants serious consideration. Finally, even the 20 kW SLOWPOKE reactor could produce useful quantities of Mo-99. If the present fuel rods were replaced with a small tank containing a solution of low-enriched uranyl sulphate in water, three of these liquid core reactors could supply all of Canada. (author)

Medical isotope shortage 2009-2010 and future options NRU, SLOWPOKE and MAPLE

International Nuclear Information System (INIS)

Hilborn, J.

2013-01-01

The 15 month shutdown of NRU and the unexpected termination of the AECL/Nordion MAPLE project caused a world-wide shortage of medical isotopes. After the recent repair of NRU, AECL is confident that it could continue operating safely and reliably as a multi-purpose reactor until 2021 or longer. There is convincing evidence that the restoration of the MAPLE reactors is technically feasible, but it is highly improbable that a 10 MW MAPLE production reactor can ever be cost-effective. However, conversion of the present 10 MW reactors to 3 MW, without major changes to the structural hardware, warrants serious consideration. Finally, even the 20 kW SLOWPOKE reactor could produce useful quantities of Mo-99. If the present fuel rods were replaced with a small tank containing a solution of low-enriched uranyl sulphate in water, three of these liquid core reactors could supply all of Canada. (author)

Proceedings

International Nuclear Information System (INIS)

Jury, J.W. ed.

1990-01-01

These fifteen papers were presented by students in nuclear engineering from the Universities of Toronto and Manitoba, the Royal Military College, Ecole Polytechnique, McMaster University, and Trent University. They cover the areas of CANDU, SLOWPOKE and MAPLE reactor systems and fuel, applied nucleonics, and simulation theory and thermalhydraulics. (L.L.)

Use of the Slowpoke-2 nuclear reactor at the Royal Military College of Canada for book conservation

Energy Technology Data Exchange (ETDEWEB)

Shaheen, K.; Welland, M.; Allen, F.; Corcoran, E.; Deschenes, M.; Bonin, H. [Royal Military College of Canada, Kingston, Ontario (Canada)

2005-07-01

The present project investigated the use of the mixed radiation field produced by the SLOWPOKE-2 reactor to prolong the life of biodeteriorated books. Research into past studies of radiation treatment indicated that the primary biodeteriorating agents, insects and moulds, can be reduced enough to return books to the 'natural' level of infestation with a dose of 2-3kGy where they will age in a manner consistent with a 'normal' book. Based on research of the potential negative effects of irradiation on paper, including depolymerization, loss of paper strength and durability, discoloration, and harm to ink, it was found that at doses below 8kGy, at a dose rate of 2.4kGy, there is no serious harm to the paper. Based on a desired dose range of 2 to 8kGy, and the dimensions and flux mapping of the radiation field in the reactor pool, a 60cm x 58cm x 43.5cm vacuum-sealed box, with a Cadmium foil neutron shield, is proposed. A preliminary feasibility study suggests that the capital and operating costs of this irradiation procedure would be approximately C$15000 and C$600, respectively. (author)

Reactors set for mini market

International Nuclear Information System (INIS)

Knox, Richard.

1988-01-01

Commercial nuclear power generation on a large-scale has an uncertain future. However, it is hoped that a small nuclear reactor could form the basis for providing heating, cooling or electricity in large buildings. Based on the Slowpoke research reactor, the Slowpoke energy system concept is simple. The concept and the way in which the small-scale reactor would work are discussed. The system consists of a stainless steel tank surrounded by reinforced concrete and let into the ground. The tank is full of light water which is heated to about 90 deg C by a central core of 2.4 percent enriched uranium fuel. The resulting natural circulation causes the water to pass through a heat exchanger. The water from the heat exchanger can be used for building or district heating, to operate air-conditioners or to generate small quantities of electricity. It is hoped to automate the operation of the reactor so that continuous supervision by a team of engineers would be unnecessary. A single operator on call in the building would be able to take control actions if the reactor's safety system failed. (UK)

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.)

Co-operation between Canada and Hungary on the application of the SLOWPOKE energy system to district heating in eastern Europe

Energy Technology Data Exchange (ETDEWEB)

Kay, R. E.; Halzl, J.; Sigmond, G.; Takats, F.; Bakacs, I.

1989-06-15

The SLOWPOKE Energy System is a nuclear energy source designed to provide up to 10 MWt of heat energy in the form of hot water to medium- and large- size district heating systems. An appropriate grouping of Canadian and Hungarian companies with the support of the Hungarian Ministry of Industry is studying the technical, economic, commercial, and nuclear licensability aspects of the application of the SLOWPOKE Energy System to district heating in Hungary. Results of these studies indicate that there is a significant potential market for SLOWPOKE Energy Systems in existing district heating systems, that the SLOWPOKE Energy System can be readily integrated into such systems, that high capacity factors can be achieved, and that it will be relatively easy to localize the supply of most components and systems.

Co-operation between Canada and Hungary on the application of the SLOWPOKE energy system to district heating in eastern Europe

International Nuclear Information System (INIS)

Kay, R.E.; Halzl, J.; Sigmond, G.; Takats, F.; Bakacs, I.

1989-06-01

The SLOWPOKE Energy System is a nuclear energy source designed to provide up to 10 MWt of heat energy in the form of hot water to medium- and large- size district heating systems. An appropriate grouping of Canadian and Hungarian companies with the support of the Hungarian Ministry of Industry is studying the technical, economic, commercial, and nuclear licensability aspects of the application of the SLOWPOKE Energy System to district heating in Hungary. Results of these studies indicate that there is a significant potential market for SLOWPOKE Energy Systems in existing district heating systems, that the SLOWPOKE Energy System can be readily integrated into such systems, that high capacity factors can be achieved, and that it will be relatively easy to localize the supply of most components and systems

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)

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.

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

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

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)

Concentrations and distributions of trace and minor elements in Chinese and Canadian coals and ashes

International Nuclear Information System (INIS)

Sun Jingxin; Jervis, R.E.

1987-01-01

A total of 35 trace and minor elements including some of environmental significance were determined in each of a selection of 15 Chinese and 6 Canadian thermal coals and their ashes by using the SLOWPOKE-2 nuclear reactor facility of the University of Toronto. The concentrations and distributions of these constituents among the coals and their combustion products (viz. ash and volatile matter) are presented. The detailed results showed wide variations in trace impurity concentrations (up to a factor of 100 and more) among the coals studied. Values for elemental enrichment factors (EF) relative to normal crustal abundances indicated that only As(EF=13), Br(5.7), I(16), S(230), Sb(11) and Se(320) were appreciably enriched in coal. (author) 14 refs.; 5 tabs

Women Plan Toronto (1985 - 2000) and Toronto Women’s City Alliance (2004 - and struggling on): Experiences and Lessons

OpenAIRE

Modlich, Regula

2012-01-01

This article presents the history, analysis and prospects for women’s capacity to engender the planning process in Toronto. It recounts the origins and actions of Women Plan Toronto in the early 1980s to the Toronto Women’s City Alliance campaigns, setting this pioneering work against today’s cut-backs of transit, child care, and social housing and efforts to establish a Women’s Equalities Office. The two women's groups have been struggling to eliminate ongoing silencing, discrimination, i...

The development of a small inherently safe homogeneous reactor for the production of medical isotopes

Energy Technology Data Exchange (ETDEWEB)

Carlin, G.E.; Bonin, H.W., E-mail: george.carlin@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada)

2013-07-01

The use of radioisotopes for various procedures in the health care industry has become one of the most important practices in medicine. New interest has been found in the use of liquid fueled nuclear reactors to produce these isotopes due to the ease of fuel processing and ability to efficiently use LEU as the fuel source. A version of this reactor is being developed at the Royal Military College of Canada to act as a successor to the SLOWPOKE-2 platform. The thermal hydraulic and transient characteristics of a 20 kWt version are being studied to verify inherent safety abilities. (author)

Toronto green roof construction standard

International Nuclear Information System (INIS)

Aster, D.

2007-01-01

Toronto City Council adopted a green roof strategy in February 2006. This paper reviewed the by-law governing the strategy as well as the work in progress to develop minimum standards for the design and construction of green roofs in Toronto. The strategy included a series of recommendations regarding the installation of green roofs on city buildings; a pilot grant program; using the development process to encourage green roofs; and, public education and promotion. It was noted that compared to Europe, the development of standards for green roofs in North America is in its early stages. As an emerging sustainable technology, there currently are no standards incorporated into Ontario's Building Code against which Toronto can measure the design and construction of green roofs. Therefore this paper included an analysis detailing how the recommended design requirements were able to support the City's green roof policy objectives and integrate the performance criteria for green roofs previously established and supported by Toronto City Council. The key policy objectives of the City's green roof strategy were to reduce the urban heat island effect; to address stormwater management implications in terms of quality and quantity; to improve the energy budgets of individual buildings; and, to improve air quality

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.

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.

REFINED METALLICITY INDICES FOR M DWARFS USING THE SLoWPoKES CATALOG OF WIDE, LOW-MASS BINARIES

International Nuclear Information System (INIS)

Dhital, Saurav; Stassun, Keivan G.; Bastien, Fabienne A.; West, Andrew A.; Massey, Angela P.; Bochanski, John J.

2012-01-01

We report the results from spectroscopic observations of 113 ultra-wide, low-mass binary systems, largely composed of M0-M3 dwarfs, from the SLoWPoKES catalog of common proper motion pairs identified in the Sloan Digital Sky Survey. Radial velocities of each binary member were used to confirm that they are comoving and, consequently, to further validate the high fidelity of the SLoWPoKES catalog. Ten stars appear to be spectroscopic binaries based on broad or split spectral features, supporting previous findings that wide binaries are likely to be hierarchical systems. We measured the Hα equivalent width of the stars in our sample and found that components of 81% of the observed pairs have similar Hα levels. The difference in Hα equivalent width among components with similar masses was smaller than the range of Hα variability for individual objects. We confirm that the Lépine et al. ζ-index traces iso-metallicity loci for most of our sample of M dwarfs. However, we find a small systematic bias in ζ, especially in the early-type M dwarfs. We use our sample to recalibrate the definition of ζ. While representing a small change in the definition, the new ζ is a significantly better predictor of iso-metallicity for the higher-mass M dwarfs.

Toronto Smog Summit Report Card

International Nuclear Information System (INIS)

2001-01-01

This 'report card' provides a summary of actions taken, and progress achieved by the federal government, the provincial government and the City of Toronto, respectively, in response to various previous commitments regarding air quality, sustainable transportation, climate and atmospheric research, investing in green infrastructure (federal government), environmental assessment regulations, transboundary air pollution, improved monitoring and reporting regulations. Ratings also cover efforts in imposing emissions caps on the electric industry, emissions reduction trading system, toll-free public air pollution hotline, regulation of ozone depleting substances (provincial government), public education campaign on smog reduction, energy efficiency initiatives, corporate smog alert response plan, and a number of other environmental issues (City of Toronto)

In vivo neutron activation at Toronto 1967-1981

International Nuclear Information System (INIS)

Harrison, J.E.; McNeill, K.G.

1986-01-01

Since the inception of work on in vivo neutron activation analysis at Toronto in 1967, the project has grown until these procedures are in routine diagnostic use at the Toronto General Hospital. Approximately 300 calcium tests and 600 nitrogen tests are carried out each year. Cadmium tests are also available. (author)

Toronto air quality index health links analysis

Energy Technology Data Exchange (ETDEWEB)

Pengelly, D [McMaster Inst. of Environment and Health, Hamilton, ON (Canada); Campbell, M; Macfarlane, R; Li-Muller, A [Toronto Public Health, ON (Canada)

2001-10-01

Based on data acquired in the year 1995, Toronto Public Health published a report called Air Pollution Burden of Illness in Toronto. In that report, it was estimated that up to 1000 Toronto residents die prematurely each year while another 5500 are admitted to hospitals due to six smog-related air pollutants. In the present document, the authors examined the air quality classifications of the Ontario Air Quality Index (AQI) in an attempt to determine whether the values adequately reflect the state of air quality and the associated burden of illness in Toronto. After careful examination of the results, it became apparent that 92 per cent of the premature mortality and hospitalization took place at times when the Air Quality Index was in the very good or good range. At times when the Air Quality Index was in the moderate or poor-very poor range, an estimated 8 per cent of the burden of illness occurred. These results indicate that the concentration range of a pollutant used to classify the good and very good categories is not always in agreement with the pollutant levels responsible for the adverse health effects. As demonstrated by this study, the air quality associated with the very good or good range described by the AQI is responsible for negative health effects in Toronto, and are lower than the provincial criteria of Ontario. The air quality conditions that may have an impact on health are not always correctly identified by the current AQI system. The authors are recommending a review of the provincial criteria for several air pollutants, and the current AQI system needs to be modified. 16 refs., tabs., figs.

Toronto 2001 Inter-governmental Declaration on Clean Air

International Nuclear Information System (INIS)

2001-01-01

This formal declaration commits the municipalities in the Greater Toronto Area, the provincial government of Ontario, and the federal government in Ottawa to undertake certain specific actions to improve air quality in their respective areas of jurisdiction, recognizing the validity of claims made by experts in numerous studies, linking air pollution to premature deaths, illnesses and hospitalization in major Canadian cities. The declaration also recognizes the validity of scientific claims as to the relationship between solar radiation, ambient heat, ground level ozone and global climate change, and the role played in air pollution by fossil fuel combustion. The Declaration calls for cooperation of all governments operating in the Greater Toronto Area to take inter-governmental actions to improve air quality by following up on key issues identified at annual Summits and by supporting the planning of future Summits, by working together with the Toronto Organizing Committee for the Olympic Games to ensure that the 2008 Olympic Games will contribute to a legacy of clean air for the Toronto region, and by implementing a social marketing campaign to help householders reduce both home energy use and vehicle kilometres travelled by 20 per cent. Beyond these inter-governmental commitments, special commitments of individual municipalities, and the provincial and federal governments also form part of the Declaration

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.)

Eesti Kunstnike Koondis Torontos...

Index Scriptorium Estoniae

2008-01-01

Eesti Kunstnike Koondis Torontos andis 2008. a. seitsmendat korda välja Margaret Kevendi nimelise stipendiumi, mille Eesti Kunstiakadeemiast pälvisid maalikunsti magistrant Saskia Järve ning maali- ja fotokunsti magistrant Flo Kasearu, Tartu Kõrgemast Kunstikoolist mööbli ja mööbli restaureerimise tudeng Karl Annus ning meedia- ja reklaamikunsti tudeng Kristjan Nagla

TORONTO HARBOUR COMMISSIONERS (THC) SOIL RECYCLE TREATMENT TRAIN - APPLICATIONS ANALYSIS REPORT

Science.gov (United States)

The Toronto Harbour Commissioners (THC) have developed a soil treatment train designed to treat inorganic and organic contaminants in soils. THC has conducted a large-scale demonstration of these technologies in an attempt to establish that contaminated soils at the Toronto Port ...

2005 Toronto smog report card : final grade C-

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-10-01

This annual Smog Report Card for Toronto evaluates the progress made by the City toward reducing the environmental and health impacts of smog. The final grade for the City in 2005 was a C-, a decrease over the B+ issued in 2004. The report card evaluates City Council actions based on their clean air commitments. In particular, the performance on initiatives in the following six major areas were graded: energy; transit; walking and biking; fleets and fuels; intergovernmental action; and new air quality strategies. Although Toronto had a record number of smog days due to high-temperatures and high pollution levels, it had a better record on smog and climate change than either the provincial or federal levels. Greenhouse gas emissions in Toronto are actually going down, but they are up 12 and 24 per cent at the federal and provincial levels respectively. In 2005, the City of Toronto developed a new Air Quality Management Strategy to replace the Smog Plan. Future evaluations will depend on whether the strategy is effective. The report recommends that efforts should be made to reduce greenhouse gas emissions which cause global warming, as well measures to reduce the urban heat island effect by planting trees, improving energy efficiency and using lighter-coloured materials for roads, parking lots and roofs. The report card criticized that there has been no green power purchased for the City and that the transit ridership growth strategy is behind schedule. It also noted that the City is not pedestrian or bike friendly. refs., tabs., figs.

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

The False Panacea of City Charters? A Political Perspective on the Case of Toronto

Directory of Open Access Journals (Sweden)

Andrew Sancton

2016-01-01

Full Text Available Toronto is unlike any other city, as its local boosters will not hesitate to point out. That was the basis, after all, of the “charter movement” that demanded special rights for a mega-city that the movement’s backers insisted was so vital that it even warranted a status similar to that of an entire province. Their efforts culminated in the province’s passage in 2006 of the City of Toronto Act, which appeared on its face to grant the metropolis the power it believed it required and merited. In reality, the Ontario government may have actually set Toronto back, leaving it more at the mercy of provincial power than other smaller municipalities. The few additional taxation powers that were granted by the ostensible Toronto “charter” — the City of Toronto Act — are, in reality, still overseen by the province, which retains the right to limit those revenue tools if it considers it “desirable in the provincial interest to do so.” But while Toronto may have been given just a small number of revenue tools, which it has used only sparingly, and the use of those tools is ultimately decided by Queen’s Park, their very existence has given the province licence to sidestep the city’s calls for more funding. The provincial Liberals have, in the past, insisted that Toronto make use of its own taxes before it demands more provincial funds. Meanwhile, the City of Toronto Act did nothing to curtail the power of the Ontario Municipal Board (OMB. Because municipal zoning decisions made in Toronto can be appealed to the OMB, which can substitute its own idea of “good planning” for elected local government, the City of Toronto is ultimately left with limited control over its planning decisions. In sum, virtually none of the desires that Toronto expected would be served by a city charter have been fulfilled. Quite the opposite, it would appear that the dreams once imagined by charter-city proponents have been snuffed out, and there is no

Welcome to Toronto. Welcome to the CIHR

Directory of Open Access Journals (Sweden)

Malcolm King

2000-01-01

Full Text Available May 6 to 10, 2000 is a great time for the Canadian respiratory community. It is the 100th anniversary of our Lung Association, and it is our chance to host the respiratory world at the American Lung Association, American Thoracic Society International Conference and the Canadian Thoracic Society Annual Meeting. The name Toronto comes from a Mohawk word meaning 'meeting place'. The rivers that run into Lake Ontario were traditional gathering places for the aboriginal peoples that lived in this area before the coming of the European settlers. My ancestors include both Mohawks and the Mississaugas of the Credit, the native tribe that occupied the Toronto area as its traditional territory until the late 18th century.

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)

Pigmentation and temporal effects on trace elements in hair

International Nuclear Information System (INIS)

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

1990-01-01

Variations in trace element concentration in the head and facial hair of five individuals with ever-increasing amounts of white hair were examined. Hair was collected from the scalp, cheeks, and chin from one donor on a regular basis since 1984. Samples were separated into white and pigmented fractions, and analyzed at SLOWPOKE-Toronto by INAA for the short-lived, isotope-producing elements Br, Ca, Cl, Cu, I, Mg, Mn, Na, S, and Zn. Temporal concentration variations of these elements over time, and variations of the elemental concentrations in pigmented and white hair were established

Toronto Hydro annual report, 1992

International Nuclear Information System (INIS)

1993-01-01

Toronto Hydro is the electric utility serving about 219,000 customers in Toronto, Ontario. In 1992, the utility purchased 9.6 billion kWh of electricity from Ontario Hydro, down 3.6% from 1990. Energy sales totalled 9.2 billion kWh, down 4.1% from 1990. Retail electricity rates increased an average of 6.7% in 1992, in spite of an increase in Ontario Hydro's wholesale rate by 8.2%, due to better than anticipated financial results and cost-control measures. The decline in electricity purchases and sales are attributed to economic factors, which also contributed to an increase in the utility's provision for bad debts. The third year of a 13.8-kV conversion project was completed in 1992; this project is converting the existing 4 kV distribution system to the higher voltage since maintenance and repair of the existing system is costly and the equipment is becoming less reliable. New construction, refurbishing, and modernization of equipment were performed at a number of substations. Other improvements in 1992 are reported in the areas of management and engineering systems, personnel policies, work safety, and energy management. Financial statements are included. 11 figs., 4 tabs

Toronto area ozone: Long-term measurements and modeled sources of poor air quality events

Science.gov (United States)

Whaley, C. H.; Strong, K.; Jones, D. B. A.; Walker, T. W.; Jiang, Z.; Henze, D. K.; Cooke, M. A.; McLinden, C. A.; Mittermeier, R. L.; Pommier, M.; Fogal, P. F.

2015-11-01

The University of Toronto Atmospheric Observatory and Environment Canada's Centre for Atmospheric Research Experiments each has over a decade of ground-based Fourier transform infrared (FTIR) spectroscopy measurements in southern Ontario. We present the Toronto area FTIR time series from 2002 to 2013 of two tropospheric trace gases—ozone and carbon monoxide—along with surface in situ measurements taken by government monitoring programs. We interpret their variability with the GEOS-Chem chemical transport model and determine the atmospheric conditions that cause pollution events in the time series. Our analysis includes a regionally tagged O3 model of the 2004-2007 time period, which quantifies the geographical contributions to Toronto area O3. The important emission types for 15 pollution events are then determined with a high-resolution adjoint model. Toronto O3, during pollution events, is most sensitive to southern Ontario and U.S. fossil fuel NOx emissions and natural isoprene emissions. The sources of Toronto pollution events are found to be highly variable, and this is demonstrated in four case studies representing local, short-, middle-, and long-range transport scenarios. This suggests that continental-scale emission reductions could improve air quality in the Toronto region. We also find that abnormally high temperatures and high-pressure systems are common to all pollution events studied, suggesting that climate change may impact Toronto O3. Finally, we quantitatively compare the sensitivity of the surface and column measurements to anthropogenic NOx emissions and show that they are remarkably similar. This work thus demonstrates the usefulness of FTIR measurements in an urban area to assess air quality.

Review of nuclear power in Canada

International Nuclear Information System (INIS)

Anon.

1982-01-01

Among the topics mentioned are the performance of Canadian nuclear generating stations; construction of new Candu reactors at home and abroad; uranium mining ventures and closures, research programs such as development of the Slowpoke III space-heating reactor; developments in nuclear medicine such as the Therac 25 accelerator, marketing of reactors, and waste management

TECHNOLOGY EVALUATION REPORT: TORONTO HARBOUR COMMISSIONERS (THC) SOIL RECYCLE TREATMENT TRAIN. Project Summary

Science.gov (United States)

A demonstration of the Toronto Harbour Commissioners' (THC) Soil Recycle Treatment Train was performed under the Superfund Innovative Technology Evaluation (SITE) Program at a pilot plant facility in Toronto, Ontario, Canada. The Soil Recycle Treatment Train, which consists of s...

Transactions: student conference, 1982

International Nuclear Information System (INIS)

1982-01-01

Papers presented at this conference covered the topics of CANDU reactor physics, control systems and steam generators; imaging in neutron radiography; cooling systems for a SLOWPOKE reactor; accelerator breeders; the investigation of point defects using positrons; neutron and gamma detectors; fusion reaction kinetics; and heavy ion fusion

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

Eesti filmi "Jade Warrior" esilinastus Torontos / Andres Laasik

Index Scriptorium Estoniae

Laasik, Andres, 1960-2016

2006-01-01

Soome ja Hiina mütoloogiat ühendav fantaasiafilm "Igavese armastuse sõdalane - Jade Warrior" (Soome, Hiina ja Eesti ühistöö) esilinastus eile Toronto filmifestivalil. Andmed filmi tootmise ja levitamise kohta

Faulting in unconsolidated sediments and bedrock east of Toronto - phase 1

International Nuclear Information System (INIS)

Rogojina, C.; Mohajer, A.A.; Eyles, N.

1995-10-01

Increasing concern with the potential earthquake hazard in southern Ontario has focused attention on neotectonic structures affecting bedrock. Within the boundaries of the metropolitan Toronto area (632 km 2 ), about 2500 fracture orientations have been measured in more than 70 bedrock outcrops. An east-northeast systematic fracture set constitute the most commonly-oriented fundamental fracture system in the study area. The east-northeast systematic fracture set may be the product of the current compressive stress field combined with regional uplift, but this should be confirmed by further field investigation. Anomalous fracture patterns were identified at the periphery of Metropolitan Toronto, specifically along the West Humber and Rouge rivers. Four post-glacial pop-ups were identified within Metro Toronto. Careful mapping and description of these pop-ups show a possible relationship with the contemporary principal stresses in the area and the local fracture pattern. (author). 41 refs., 8 figs

Smart meter status report from Toronto

International Nuclear Information System (INIS)

O'Brien, D.

2006-01-01

An update of Toronto Hydro's smart metering program was presented. Electricity demand is expected to keep increasing, and there is presently insufficient generation to match supply needs in Ontario. The smart metering program was introduced to aid in the Ontario government's energy conservation strategy, as well as to address peak supply problems that have led to power outages. It is expected that the smart metering program will reduce provincial peak supply by 5 per cent, as the meters support both time-of-use rates and critical peak pricing. Over 800,000 smart meters will be supplied to customers by 2007, and all 4.3 million homes in Toronto will have a smart meter by 2010. In order to meet targets for 2010, the utility will continue to install more 15,000 meters each month for the next 4 years. While the Ontario government has planned and coordinated the rollout and developed smart metering specifications and standards, Toronto Hydro is responsible for the purchase, installation, operation and maintenance of the meters. Advance testing of each meter is needed to ensure billing accuracy, and customer education on meter use is also. The complexity of the metering program has led the utility to establish a rigid project management process. Customer education pilot program are currently being conducted. Experience gained during the earlier phases of the program have enabled the utility to select appropriate metering systems based on density, topography and physical conditions. Project expenditures have been within budget due to improved project estimating and planning. The metering program has been conducted in tandem with the utility's peakSAVER program, a residential and small commercial load control program that has been successful in reducing summer peak demand by cycling air conditioners without causing discomfort. It was concluded that the utility will continue with its mass deployment of smart meters, and is currently preparing its call center to handled

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

Working with Spanish-Speaking Latin American Students in Toronto

Science.gov (United States)

Duran, Marcela S.

1978-01-01

The problems affecting the reception, adjustment, and placement of Spanish-speaking students into the Toronto school system are discussed, and include immigration patterns, Spanish values, and the Latin American school. (Author/HP)

University of Toronto mathematics competition (2001–2015)

CERN Document Server

Barbeau, Edward J

2016-01-01

This text records the problems given for the first 15 annual undergraduate mathematics competitions, held in March each year since 2001 at the University of Toronto. Problems cover areas of single-variable differential and integral calculus, linear algebra, advanced algebra, analytic geometry, combinatorics, basic group theory, and number theory. The problems of the competitions are given in chronological order as presented to the students. The solutions appear in subsequent chapters according to subject matter. Appendices recall some background material and list the names of students who did well. The University of Toronto Undergraduate Competition was founded to provide additional competition experience for undergraduates preparing for the Putnam competition, and is particularly useful for the freshman or sophomore undergraduate. Lecturers, instructors, and coaches for mathematics competitions will find this presentation useful. Many of the problems are of intermediate difficulty and relate to the first two...

Air pollution burden of illness from traffic in Toronto

International Nuclear Information System (INIS)

McKeown, D.; Campbell, M.; Bassil, K.; Morgan, C.; Lalani, M.; Macfarlane, R.; Bienefeld, M.

2007-11-01

This paper examined the health impacts of air pollution from traffic in Toronto. The paper provided a review of scientific studies on the health effects of vehicle pollution as well as a quantitative assessment of the economic costs and the burden of illness attributed to traffic pollution in Toronto. The report also assessed air pollution and traffic trends in the city, and outlined initiatives being conducted to reduce vehicle-related pollution. The study used the new air quality benefits tool (AQBAT) which determines the burden of illness and the economic impacts of traffic-related air pollution. Air modelling specialists were consulted in order to determine the contribution of traffic-related pollutants to overall pollution levels using data on traffic counts and vehicle emissions factors. The air model also considered dispersion, transport and and the transformation of compounds emitted from vehicles. Results of the study showed that traffic pollution caused approximately 440 premature deaths and 1700 hospitalizations per year. Children in the city experienced more than 1200 acute bronchitis episodes per year as a result of air pollution from traffic. Mortality-related costs associated with traffic pollution in Toronto were estimated at $2.2 billion. It was concluded that the city must pursue the implementation of sustainable transportation policies and programs which foster and enable the expansion and use of public transport. 47 refs., 8 tabs., 9 figs

Torontos peeti eesti dokfilmifestivali "Estdoc's" / Olev Remsu

Index Scriptorium Estoniae

Remsu, Olev, 1947-

2006-01-01

Toronto eesti dokumentaalfilmide festival "Estdoc's". Demonstreeriti filme: "Sinimäed" (Raimo Jõerand), "Tiim" (Peep Puks), "Mikk" (Rein Raamat, Peeter Brambat), "6 tundi" (Rein Kotov), "Erna retk" (Vaado Sarapuu), "Tõrjutud mälestused" (Imbi Paju), "Middendorfi jälgedes" (Riho Västrik), "Mehed unustatud armeest" (Indrek Treufeldt), "Nagu noor jumal" ja "Orjus Eestis" (mõlema autor Olev Remsu)

Toronto: A New Global City of Learning

Science.gov (United States)

Hamlin, Daniel; Davies, Scott

2016-01-01

Toronto, Canada, is emblematic of a new stratum of global cities. Unlike many world capitals, the city has gained stature only over the past half century, having successfully post-industrialized into a new economy and become a major world centre for immigration. Paradoxically, education has emerged as both a major driver of change and a divider of…

Eesti Vabariigi Presidendi Toomas Hendrik Ilvese kõned Toronto eestlastele / Toomas Hendrik Ilves ; foto: Vaado Sarapuu

Index Scriptorium Estoniae

Ilves, Toomas Hendrik, 1953-

2008-01-01

Vabariigi Presidendi kõned Toronto Eesti Majas pidulikul õhtusöögil 27. mail 2008 ja Toronto Eesti koolis lõputunnistuste kätteandmisel 26. mail 2008. Vabariigi President töövisiidil Kanadas 26.-30.05.2008

Toronto smog report card 2003 : final grade C -

International Nuclear Information System (INIS)

2003-10-01

An annual Smog Report Card for Toronto has been published annually by the Toronto Environmental Alliance since 1997, evaluating the progress made by the City toward reducing the environmental and health impacts of smog. The final grade for the City in 2003 was a C -, an improvement over last year's D +. The evaluation examined the performance on 33 initiatives in six major areas: leadership, transit, electricity, fleets and fuels, bikes and pedestrians, and public education. Issues that stood out were: a $30 million increase in funding to the Toronto Transit Commission (TTC), and the release of the TTC's Ridership Growth Strategy depicting how transit ridership can be increased through improved service and lower fares. The drive-through and pesticide by-laws were passed by Council, which should result in smog reduction from unnecessary activities. Leadership was found to be lacking at City Hall in the area of clean air, in view of its decision to proceed with the expansion of Island Airport. The decision to move forward on only 20 per cent of planned green power and energy efficiency measures was a low point in 2002. The City's budget process, which effectively screened out most environmental initiatives was in part responsible for the lack of progress. The following grades were awarded: transit and trip reduction (B), energy efficiency and green power received (D), fleets and fuels (C), bikes and pedestrians (C), public education (B). Recommendations for next year included: implementation of the TTC's Ridership Growth Strategy; creation of a Smog Plan Implementation Fund of $20 million per year to invest in energy efficiency, green fleets, green power and other related measures; and stop the expansion of Island Airport

History of Cardiovascular Surgery at Toronto General Hospital.

Science.gov (United States)

Lee, Myunghyun M; Alvarez, Juglans; Rao, Vivek

2016-01-01

The Division of Cardiovascular Surgery at Toronto General Hospital has enjoyed an enviable history of academic achievement and clinical success. The foundations of this success are innovation, creativity and excellence in patient care, which continue to influence the current members of the division. Copyright © 2016 Elsevier Inc. All rights reserved.

University of Toronto Instructors' Experiences with Developing MOOCs

Science.gov (United States)

Najafi, Hedieh; Rolheiser, Carol; Harrison, Laurie; Håklev, Stian

2015-01-01

We interviewed eight University of Toronto (U of T) instructors who have offered MOOCs on Coursera or EdX between 2012 and 2014 to understand their motivation for MOOC instruction, their experience developing and teaching MOOCs, and their perceptions of the implications of MOOC instruction on their teaching and research practices. Through…

Resilience and housing choices among Filipino immigrants in Toronto

NARCIS (Netherlands)

Thomas, R.

2013-01-01

In Canada, where immigration plays a major role in population growth, immigrants’ housing choices and settlement patterns have been extensively researched. Using a case study of Filipino immigrants in the Toronto Census Metropolitan Area, this paper demonstrates that choices such as affordable

2006 Toronto smog report card : final grade C-

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

This annual report card evaluated the progress made by the City of Toronto toward reducing the environmental and health impacts of smog. The final grade for 2006 was a C-, the same as for 2005. The highest grade of B+ was issued in 2004. The report card evaluated City Council actions based on their clean air commitments. Although the summer of 2006 was one of the best on record, with only 11 smog days, the grade of C- was issued because the performance of the City's Air Quality Improvement record was poor. Toronto Environmental Alliance strongly recommended that important changes be made to improve air quality, transit and waste disposal. It recommended that the City should address the real causes of unclean air, which are motor vehicle exhaust and toxic pollution. This report card graded the performance on initiatives in the following six major areas: energy; transit; air quality plan; walking and biking; fleets and fuels; and, intergovernmental action. The report recommended that efforts should be made to reduce greenhouse gas emissions which cause global warming. refs., tabs., figs.

Laboratory neutrons - a breakthrough in non-nuclear disciplines

International Nuclear Information System (INIS)

Jervis, R.E.

1983-01-01

The availability of laboratory neutrons at SLOWPOKE Nuclear reactor facility, has greatly facilitated interdisciplinary applied research there. Examples of the uses of the laboratory neutrons include those involved with environmental dispersal of inorganic pollutants, and those associated with public health investigations. (UK)

Centre for nuclear engineering University of Toronto annual report 1984

International Nuclear Information System (INIS)

1984-12-01

The annual report of the Centre for Nuclear Engineering, University of Toronto covers the following subjects: message from the Dean; Chairman's message; origins of the centre; formation of the centre; new nuclear appointments; and activities of the centre, 1984

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)

Proceedings of the Toronto TEAM/ACES workshop

International Nuclear Information System (INIS)

Turner, L.R.

1991-03-01

The third TEAM Workshop of the third round was held at Ontario Hydro in Toronto 25--26 October 1990, immediately following the Conference on Electromagnetic Field Computation. This was the first Joint Workshop with ACES (Applied Computational Electromagnetics Society), whose goals are similar to TEAM, but who tend to work at higher frequencies (Antennas, Propagation, and Scattering). A fusion problem, the eddy current heating of the case of the Euratom Large Coil Project Coil, was adapted as Problem 14 at the Oxford Workshop, and a solution to that problem was presented at Toronto by Oskar Biro of the Graz (Austria) University of Technology. Individual solutions were also presented for Problems 8 (Flaw in a Plate) and 9 (Moving Coil inside a Pipe). Five new solutions were presented to Problem 13 (DC Coil in a Ferromagnetic Yoke), and Koji Fujiwara of Okayama University summarized these solutions along with the similar number presented at Oxford. The solutions agreed well in the air but disagreed in the steel. Codes with a formulation in magnetic field strength or scalar potential underestimated the flux density in the steel, and codes based on flux density or vector potential overestimated it. Codes with edge elements appeared to do better than codes with nodal elements. These results stimulated considerable discussions; in my view that was the most valuable result of the workshop

Consulting Whom? Lessons from the Toronto Urban Aboriginal Strategy

Directory of Open Access Journals (Sweden)

Mai T. Nguyen

2014-04-01

Full Text Available The research conducted here looks at the current Urban Aboriginal Strategy (UAS in Toronto. The purpose of this Strategy is to provide long-term investments to support Aboriginal communities in urban settings by focusing on three priority areas: improving life skills; promoting job training, skills, and entrepreneurship; and supporting Aboriginal women, children, and families. This article seeks to answer the following question: Does the UAS provide Aboriginal participants with the ability to effectively participant in the consultation process? It argues that the UAS process of consulting with the urban Aboriginal community does not allow for the effective participation of Aboriginal peoples because of problematics related to consulting in an urban setting and despite the language of partnership, the federal government still reserves the right to make final decisions. These problems diminish the ability to build renewed Aboriginal-State relations based on mutual respect and trust, which has been absent within the Aboriginal-State apparatus and resulted in the political exclusion of Aboriginals in Canada. Though consultation can be a vehicle for empowering participants with decision-making authority, this is not the case in Toronto. The lack of a common vision, political buy-in, and the aura of secrecy leads to a political relationship built on mistrust. Mistrust between members and government renders the consultation process ineffective. This article combines the literature on public consultations with official government documents to identify critical components that must be evident for consultations to be fruitful and participation effective. These criteria are the benchmarks upon which to measure effectiveness. Based on interviews with the Steering Committee, this article finds that the UAS process of consulting with the Toronto Aboriginal community does not enable Aboriginal participants to effectively participate in the democratic process.

Energy solutions, neo-liberalism, and social diversity in Toronto, Canada.

Science.gov (United States)

Teelucksingh, Cheryl; Poland, Blake

2011-01-01

In response to the dominance of green capitalist discourses in Canada's environmental movement, in this paper, we argue that strategies to improve energy policy must also provide mechanisms to address social conflicts and social disparities. Environmental justice is proposed as an alternative to mainstream environmentalism, one that seeks to address systemic social and spatial exclusion encountered by many racialized immigrants in Toronto as a result of neo-liberal and green capitalist municipal policy and that seeks to position marginalized communities as valued contributors to energy solutions. We examine Toronto-based municipal state initiatives aimed at reducing energy use while concurrently stimulating growth (specifically, green economy/green jobs and 'smart growth'). By treating these as instruments of green capitalism, we illustrate the utility of environmental justice applied to energy-related problems and as a means to analyze stakeholders' positions in the context of neo-liberalism and green capitalism, and as opening possibilities for resistance.

Active tuberculosis among homeless persons, Toronto, Ontario, Canada, 1998-2007.

Science.gov (United States)

Khan, Kamran; Rea, Elizabeth; McDermaid, Cameron; Stuart, Rebecca; Chambers, Catharine; Wang, Jun; Chan, Angie; Gardam, Michael; Jamieson, Frances; Yang, Jae; Hwang, Stephen W

2011-03-01

While tuberculosis (TB) in Canadian cities is increasingly affecting foreign-born persons, homeless persons remain at high risk. To assess trends in TB, we studied all homeless persons in Toronto who had a diagnosis of active TB during 1998-2007. We compared Canada-born and foreign-born homeless persons and assessed changes over time. We identified 91 homeless persons with active TB; they typically had highly contagious, advanced disease, and 19% died within 12 months of diagnosis. The proportion of homeless persons who were foreign-born increased from 24% in 1998-2002 to 39% in 2003-2007. Among foreign-born homeless persons with TB, 56% of infections were caused by strains not known to circulate among homeless persons in Toronto. Only 2% of infections were resistant to first-line TB medications. The rise in foreign-born homeless persons with TB strains likely acquired overseas suggests that the risk for drug-resistant strains entering the homeless shelter system may be escalating.

Energy Solutions, Neo-Liberalism, and Social Diversity in Toronto, Canada

Science.gov (United States)

Teelucksingh, Cheryl; Poland, Blake

2011-01-01

In response to the dominance of green capitalist discourses in Canada’s environmental movement, in this paper, we argue that strategies to improve energy policy must also provide mechanisms to address social conflicts and social disparities. Environmental justice is proposed as an alternative to mainstream environmentalism, one that seeks to address systemic social and spatial exclusion encountered by many racialized immigrants in Toronto as a result of neo-liberal and green capitalist municipal policy and that seeks to position marginalized communities as valued contributors to energy solutions. We examine Toronto-based municipal state initiatives aimed at reducing energy use while concurrently stimulating growth (specifically, green economy/green jobs and ‘smart growth’). By treating these as instruments of green capitalism, we illustrate the utility of environmental justice applied to energy-related problems and as a means to analyze stakeholders’ positions in the context of neo-liberalism and green capitalism, and as opening possibilities for resistance. PMID:21318023

Potential for occupational and environmental exposure to ten carcinogens in Toronto

Energy Technology Data Exchange (ETDEWEB)

Muller, P. [ToxProbe Inc., Toronto, ON (Canada)

2002-03-01

A study was conducted in which several contaminants were assessed for their toxicological properties, potencies and occupational and environmental exposures in the city of Toronto. The contaminants included 1,3-butadiene, asbestos, benzene, cadmium, chromium, dioxins, formaldehyde, polycyclic aromatic hydrocarbons (PAHs), tetrachloroethylene, and trichloroethylene. The International Agency for Research on Cancer, the United States Environmental Protection Agency, and Health Canada have classified 9 of the 10 substances as human carcinogens. Tetrachloroethylene was classified as a probable human carcinogen. It was noted that there is no level of exposure for these chemicals that is without some risk. The information on the levels of selected contaminants in the workplace were obtained from existing literature. The sectors with the highest number of potentially exposed workers to these contaminants include the textiles industry, footwear manufacturing, wood products manufacturing, rubber products manufacturing, non-metallic mineral products manufacturing, fabricated metal products manufacturing, construction, land transport, and household services. The report discussed sources of emissions, routes and pathways of exposures and environmental levels, including outdoor air levels water concentrations, soil concentrations, and food concentrations. The report does not estimate the actual risk to Toronto residents due to environmental exposure to these carcinogens because data are insufficient to conduct such an assessment. However, some previous studies have indicated that exposure from ambient and indoor air has the greatest impact on human health. It is recommended that the city of Toronto remain up to date on the regulatory status of these chemicals. refs., tabs., figs., appendices.

The prospects for nuclear heating in Hungary

International Nuclear Information System (INIS)

Papp, I.; Lynch, G.F.

1989-09-01

In assessing alternative nuclear heat sources, a joint study was undertaken between Canada and Hungary to determine the feasibility of using the SLOWPOKE Energy System that has recently been developed. The SLOWPOKE Energy System is 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. It uses a combination of inherent safety features, including natural convection circulation and negative reactivity coefficients, and engineered features to ensure an extremely safe system. A SLOWPOKE demonstration heating reactor has been constructed in Canada. The unit started operation in July 1987 and is currently undergoing an extensive test program. Since the nuclear heat source is small, operates at atmospheric pressure, and produces hot water below 100 deg. C, the complex high-pressure, and high-temperature systems essential for electricity production are eliminated. As a result, the nuclear heat source can be located close to the load and will require a minimum of operator attention. In this way, a SLOWPOKE Energy System can be considered much like the oil- or natural gas fired furnace it is designed to replace. The extensive use of hot water district heating systems in Hungary offers the opportunity to exploit such simple nuclear systems as base load heat sources without an extensive retrofit of the existing systems. In addition, the studies have concluded that there are many economically attractive sites for 10 MW SLOWPOKE Energy Systems within the existing networks. The low capital investment requirements, coupled with a high degree of localization, even for the first unit, are seen as additional factors that facilitate the transfer of the technology to Hungary. Simple nuclear heat sources, such as the SLOWPOKE Energy System, when applied to the Hungarian district heating systems, offer the prospects of a significant reduction in the dependence on imported fossil fuels in the

Effects of neutrons and gamma radiation on high polymer epoxy adhesives

Energy Technology Data Exchange (ETDEWEB)

Bonin, H W; Bui, V T; Poirier, P E [Royal Military Coll. of Canada, Kingston, ON (Canada)

1996-12-31

The effect of irradiation in a SLOWPOKE-2 reactor on the adhesive strength of epoxy resins was studied using the ASTM D897 standard testing procedure. Initial weakening, up to 50%, ascribed to chain-scission, is followed by strengthening, ascribed to radiation-induced crosslinking. 7 refs., 1 tab., 14 figs.

Effects of neutrons and gamma radiation on high polymer epoxy adhesives

International Nuclear Information System (INIS)

Bonin, H.W.; Bui, V.T.; Poirier, P.E.

1995-01-01

The effect of irradiation in a SLOWPOKE-2 reactor on the adhesive strength of epoxy resins was studied using the ASTM D897 standard testing procedure. Initial weakening, up to 50%, ascribed to chain-scission, is followed by strengthening, ascribed to radiation-induced crosslinking. 7 refs., 1 tab., 14 figs

Undergraduate otolaryngology education at the University of Toronto: a review using a curriculum mapping system.

Science.gov (United States)

Oyewumi, Modupe; Isaac, Kathryn; Schreiber, Martin; Campisi, Paolo

2012-02-01

The aim of Canadian medical school curricula is to provide educational experiences that satisfy the specific objectives set out by the Medical Council of Canada. However, for specialties such as otolaryngology, there is considerable variability in student exposure to didactic and clinical teaching across Canadian medical schools, making it unclear whether students receive sufficient teaching of core otolaryngology content and clinical skills. The goal of this review was to assess the exposure to otolaryngology instruction in the undergraduate medical curriculum at the University of Toronto. Otolaryngology objectives were derived from objectives created by the Medical Council of Canada and the University of Toronto. The University of Toronto's recently developed Curriculum Mapping System (CMap) was used to perform a keyword search of otolaryngology objectives to establish when and to what extent essential topics were being taught. All (10 of 10) major topics and skills identified were covered in the undergraduate medical curriculum. Although no major gaps were identified, an uneven distribution of teaching time exists. The majority (> 90%) of otolaryngology education occurs during year 1 of clerkship. The amount of preclerkship education was extremely limited. Essential otolaryngology topics and skills are taught within the University of Toronto curriculum. The CMap was an effective tool to assess the otolaryngology curriculum and was able to identify gaps in otolaryngology education during the preclerkship years of medical school. As a result, modifications to the undergraduate curriculum have been implemented to provide additional teaching during the preclerkship years.

Assessing urban forest effects and values: Toronto's urban forest

Science.gov (United States)

David J. Nowak; Robert E. III Hoehn; Allison R. Bodine; Eric J. Greenfield; Alexis Ellis; Theodore A. Endreny; Yang Yang; Tian Zhou; Ruthanne. Henry

2013-01-01

An analysis of trees in Toronto, Ontario, reveals that this city has about 10.2 million trees with a tree and shrub canopy that covers approximately 26.6 percent of the city. The most common tree species are eastern white-cedar, sugar maple, and Norway maple. The urban forest currently stores an estimated 1.1 million metric tons of carbon valued at CAD$25.0 million. In...

Radiation damage on high polymer epoxies

Energy Technology Data Exchange (ETDEWEB)

Pak, H M [Royal Military Coll. of Canada, Kingston, ON (Canada)

1994-12-31

The effect of irradiation in a SLOWPOKE-2 reactor on the adhesive strength of epoxy resins was studied using the ASTM D897 standard testing procedure. Although the results were variable, indicating the doses were not well defined, nevertheless, there was evidence of strengthening associated with radiation-induced crosslinking. 2 figs., 1 tab.

Workforce challenges and opportunities in the solar photovoltaic industry in Toronto

International Nuclear Information System (INIS)

Saneinejad, Sheyda

2011-01-01

In December 2009, the city of Toronto adopted principles and targets for the city's sustainable energy future. The city plans to install 2 MW of solar photovoltaic panels in its facilities. The aim of this study is to assess the impact of such a project, as well as further expansion of solar photovoltaic energy generation, from the economic development perspective. A literature review, online surveys and interviews with solar industries were carried out and a job estimation model was developed. Results showed that the 2 MW installation would create 53 person years of employment locally while expansion of the technology throughout the city could generate 100,000 local jobs. However this research also pointed out a lack of suitably qualified and experienced personnel Canada-wide. This study demonstrated that the solar photovoltaic industry has the potential to provide significant economic benefits in Toronto but that certification programs must be put in place to address the lack of qualified personnel.

Inventorying Toronto's single detached housing stocks to examine the availability of clay brick for urban mining.

Science.gov (United States)

Ergun, Deniz; Gorgolewski, Mark

2015-11-01

This study examines the stocks of clay brick in Toronto's single detached housing, to provide parameters for city scale material reuse and recycling. Based on consensus from the literature and statistics on Toronto's single detached housing stocks, city scale reusable and recyclable stocks were estimated to provide an understanding of what volume could be saved from landfill and reintroduced into the urban fabric. On average 2523-4542 m(3) of brick was determined to be available annually for reuse, which would account for 20-36% of the volume of virgin brick consumed in new house construction in 2012. A higher volume, 6187 m(3) of brick, was determined to be available annually for recycling because more of the prevalence of cement-based mortar, which creates challenges for brick reuse in Toronto. The results demonstrated that older housing containing reusable brick were being mostly landfilled and replaced with housing that contained only recyclable brick. Copyright © 2015 Elsevier Ltd. All rights reserved.

Unattended nuclear systems for local energy supply

International Nuclear Information System (INIS)

Lynch, G.F.; Bancroft, A.R.; Hilborn, J.W.; McDougall, D.S.; Ohta, M.M.

1988-02-01

This paper describes recent developments in a small nuclear heat and electricity production system - the SLOWPOKE Energy System - that make it possible to locate the system close to the load, and that could have a major impact on local energy supply. The most important unique features arising from these developments are walk-away safety and the ability to operate in an unattended mode. Walk-away safety means that radiological protection is provided by intrinsic characteristics and does not depend on either engineered safety systems or operator intervention. This, in our view, is essential to public acceptance. The capability for unattended operation results from self-regulation; however, the performance can be remotely monitored. The SLOWPOKE Energy System consists of a water-filled pool, operating at atmospheric pressure, which cools and moderates a beryllium-reflected thermal reactor that is fuelled with 100 to 400 kg of low-enriched uranium. The pool water also provides shielding from radioactive materials trapped in the fuel. Heat is drawn from the pool and transferred either to a building hot-water distribution system or to an organic liquid which is converted to vapour to drive a turbine-generator unit. Heating loads between 2 qnd 10 MWt, and electrical loads up to 1 MWe can be satisfied. SLOWPOKE is a dramatic departure from conventional nuclear power reactors. Its nuclear heat source is intrinsically simple, having only one moving part: a solid neutron absorber which is slowly withdrawn from the reactor to balance the fuel burnup. Its power is self-regulated and excessive heat production cannot occur, even for the most severe combinations of system failure. Cooling of the fuel is assured by natural physical processes that do not depend on mechanical components such as pumps. These intrinsic characteristics assure public safety and ultra high reliability

Unattended nuclear systems for local energy supply

International Nuclear Information System (INIS)

Lynch, G.F.; Bancroft, A.R.; Hilborn, J.W.; McDougall, D.S.; Ohta, M.M.

1986-10-01

This paper describes recent developments in a small nuclear heat and electricity production system - the SLOWPOKE energy system - that make it possible to locate the system close to the load, and that could have a major impact on local energy supply. The most important unique features arising from these developments are walk-away safety and the ability to operate in an unattended mode. Walk-away safety means that radiological protection is provided by intrinsic characteristics and does not depend on either engineered safety systems or operator intervention. This, in our view, is essential to public acceptance. The capability for unattended operation results from self-regulation, however the performance can be remotely monitored. The SLOWPOKE energy system consists of a water-filled pool, operating at atmospheric pressure, which cools and moderates a beryllium-reflected thermal reactor that is fuelled with 100 to 400 kg of low enriched uranium. The pool water also provides shielding from radioactive materials trapped in the fuel. Heat is drawn from the pool and transferred either to a building hot-water distribution system or to an organic liquid which is converted to vapour to drive a turbine-generator unit. Heating loads between 2 and 10 MWt, and electrical loads up to 1 MWe can be satisfied. SLOWPOKE is a dramatic departure from conventional nuclear power reactors. Its nuclear heat source is intrinsically simple, having only one moving part: a solid neutron absorber which is slowly withdrawn from the reactor to balance the fuel burnup. Its power is self-regulated and excessive heat production cannot occur, even for the most severe combinations of system failure. Cooling of the fuel is assured by natural physical processes that do not depend on mechanical components such as pumps. These intrinsic characteristics assure public safety and ultra high reliability. (author)

Toronto hybrid taxi pilot

International Nuclear Information System (INIS)

Stevens, M.; Marans, B.

2009-10-01

This paper provided details of a hybrid taxi pilot program conducted to compare the on-road performance of Toyota Camry hybrid vehicles against conventional vehicles over a 1-year period in order to determine the business case and air emission reductions associated with the use of hybrid taxi cabs. Over 750,000 km worth of fuel consumption was captured from 10 Toyota Camry hybrids, a Toyota Prius, and 5 non-hybrid Camry vehicles over an 18-month period. The average real world fuel consumption for the taxis demonstrated that the Toyota Prius has the lowest cost of ownership, while the non-hybrid Camry has the highest cost of ownership. Carbon dioxide (CO 2 ) reductions associated with the 10 Camry hybrid taxis were calculated at 236 tonnes over a 7-year taxi service life. Results suggested that the conversion of Toronto's 5680 taxis would yield annual CO 2 emission reductions of over 19,000 tonnes. All hybrid purchasers identified themselves as highly likely to purchase a hybrid again. 5 tabs., 9 figs.

Toronto hybrid taxi pilot

Energy Technology Data Exchange (ETDEWEB)

Stevens, M. [CrossChasm Technologies, Cambridge, ON (Canada); Marans, B. [Toronto Atmospheric Fund, ON (Canada)

2009-10-15

This paper provided details of a hybrid taxi pilot program conducted to compare the on-road performance of Toyota Camry hybrid vehicles against conventional vehicles over a 1-year period in order to determine the business case and air emission reductions associated with the use of hybrid taxi cabs. Over 750,000 km worth of fuel consumption was captured from 10 Toyota Camry hybrids, a Toyota Prius, and 5 non-hybrid Camry vehicles over an 18-month period. The average real world fuel consumption for the taxis demonstrated that the Toyota Prius has the lowest cost of ownership, while the non-hybrid Camry has the highest cost of ownership. Carbon dioxide (CO{sub 2}) reductions associated with the 10 Camry hybrid taxis were calculated at 236 tonnes over a 7-year taxi service life. Results suggested that the conversion of Toronto's 5680 taxis would yield annual CO{sub 2} emission reductions of over 19,000 tonnes. All hybrid purchasers identified themselves as highly likely to purchase a hybrid again. 5 tabs., 9 figs.

Radon survey in Metropolitan Toronto schools

International Nuclear Information System (INIS)

Becker, E.; Moridi, R.

1992-01-01

The radon testing survey in Metropolitan Toronto public schools was the most intensive project of its kind ever undertaken in Canadian schools. It also included an extensive public education program on radiation and radon-in-schools. The radon levels at 632 schools were measured using the CAIRS Radon Monitors. Ninety percent of the locations measured were found to have a radon level equal to or less than 2 mWL. Two locations in two different schools were found to have a radon level at or above the Action Level (20 mWL). The remaining results were between the two extremes. Follow-up testing in those schools where more than 10 mWL of radon was found is in progress. (author)

Moving towards cleaner air: a progress report on the air quality strategy for the City of Toronto

International Nuclear Information System (INIS)

2001-06-01

The City of Toronto Environmental Plan was adapted in principle by City Council in April 2000. The Plan contains 66 recommendations on land, air, water, governance, sustainability, energy, transportation, green economic development and monitoring. As part of the actions on air, the Plan recommended that the City develop a comprehensive strategy to make Toronto's air clean and free of harmful levels of pollutants. This document reports on progress in the development of this comprehensive air quality standard. Work on the standards was undertaken by an Air Quality Strategy Interdepartmental Working Group (AQSI Working Group) consisting of city departmental representatives, which is one of several working groups reporting to the Toronto Interdepartmental Environmental Team (TIE). While the AQSI Working Group has not yet concluded its work, it is able to report a number of preliminary conclusions. Among them are: implementation of several successful city-wide programs. In this context preliminary indications are that program effectiveness will be limited by the availability of staff and appropriate funding. Policy and legal studies that will provide essential information relating to the legal/jurisdictional context are well underway. Modelling and monitoring of Toronto's air quality are in progress, and will be relied upon for information to guide policy development. Final strategy will have to be formulated in a regional context, in concert with the provincial and federal governments, and will have to take into account trans-boundary (inter-regional, inter-provincial and international) issues

Grannies, elders, and friends: aging Aboriginal women in Toronto.

Science.gov (United States)

Baskin, Cyndy; Davey, Caitlin J

2015-01-01

Based on a research project in Toronto, Canada, this article highlights the strengths and resiliency of 12 female Aboriginal Elders and seniors as they age together. For these women, being actively involved in their families and the Aboriginal community gives them a solid grounding in who they are, what their roles are and how they contribute to the whole. Of particular significance is the support and friendship the women offer each other through their commonalities, activities, and sense of humor.

Status report - FoodReach Toronto: lowering food costs for social agencies and community groups

Directory of Open Access Journals (Sweden)

Paul Coleman

2018-01-01

Full Text Available Toronto has the largest absolute number of food insecure households for any metropolitan census area in Canada: of its 2.1 million households, roughly 252 000 households (or 12% experience some level of food insecurity. Community organizations (including social agencies, school programs, and child care centres serve millions of meals per year to the city’s most vulnerable citizens, but often face challenges accessing fresh produce at affordable prices. Therefore in 2015, Toronto Public Health, in collaboration with public- and private-sector partners, launched the FoodReach program to improve the efficiency of food procurement among community organizations by consolidating their purchasing power. Since being launched, FoodReach has been used by more than 50 community organizations to provide many of Toronto’s most marginalised groups with regular access to healthy produce.

dyschronic, a Drosophila homolog of a deaf-blindness gene, regulates circadian output and Slowpoke channels.

Directory of Open Access Journals (Sweden)

James E C Jepson

Full Text Available Many aspects of behavior and physiology are under circadian control. In Drosophila, the molecular clock that regulates rhythmic patterns of behavior has been extensively characterized. In contrast, genetic loci involved in linking the clock to alterations in motor activity have remained elusive. In a forward-genetic screen, we uncovered a new component of the circadian output pathway, which we have termed dyschronic (dysc. dysc mutants exhibit arrhythmic locomotor behavior, yet their eclosion rhythms are normal and clock protein cycling remains intact. Intriguingly, dysc is the closest Drosophila homolog of whirlin, a gene linked to type II Usher syndrome, the leading cause of deaf-blindness in humans. Whirlin and other Usher proteins are expressed in the mammalian central nervous system, yet their function in the CNS has not been investigated. We show that DYSC is expressed in major neuronal tracts and regulates expression of the calcium-activated potassium channel SLOWPOKE (SLO, an ion channel also required in the circadian output pathway. SLO and DYSC are co-localized in the brain and control each other's expression post-transcriptionally. Co-immunoprecipitation experiments demonstrate they form a complex, suggesting they regulate each other through protein-protein interaction. Furthermore, electrophysiological recordings of neurons in the adult brain show that SLO-dependent currents are greatly reduced in dysc mutants. Our work identifies a Drosophila homolog of a deaf-blindness gene as a new component of the circadian output pathway and an important regulator of ion channel expression, and suggests novel roles for Usher proteins in the mammalian nervous system.

The impact of gentrification on ethnic neighbourhoods in Toronto: a case study of little Portugal.

Science.gov (United States)

Murdie, Robert; Teixeira, Carlos

2011-01-01

Despite extensive literature on the nature and impact of gentrification, there has been little consideration of the effects of gentrification on ethnic neighbourhoods. This study evaluates the negative and positive effects of gentrification on the Portuguese in west central Toronto. Details concerning the settlement patterns of the Portuguese, the characteristics of Portuguese residents and patterns of gentrification in inner-city Toronto were obtained from census data. Evaluations of neighbourhood change and attitudes of the residents towards gentrification were obtained from key informant and focus group interviews. The results suggest considerable ambivalence among the respondents, but most agreed that the long-term viability of Little Portugal as an immigrant reception area with a good supply of low-cost housing is in doubt.

Replacing the nation in the age of migration: negotiating South Asian identities in Toronto

Directory of Open Access Journals (Sweden)

Ishan Ashutosh

2015-08-01

Full Text Available This essay examines the role of the national in shaping the geo-political divides and connections of the South Asian diaspora in Toronto. South Asian diaspora identities are explored through two contrasting political projects that reveal the ambivalent role of the nation in producing diasporic subjectivities and their shifting borders. First, by discussing the perceptions of South Asians in Toronto, it is contended that national and religious divides are reproduced in the diaspora as a means of national belonging to the society of settlement. Diasporic geo-political divides are not merely transposed from societies of origin to settlement, but rather lie at the intersection of transnational and multicultural politics that encompass societies of origin and settlement. The reproduction of national divides in the South Asian diaspora is situated in the neighbourhoods of immigrant settlement that are positioned as the objects of multicultural efficacy. The second political project reconstitutes the national through cross-national solidarities. Through a discussion of South Asian organizations and political initiatives in Toronto and other cities in North America, this section illuminates diasporic politics predicated on new understandings of history and connection that rejuvenate and politicize multicultural politics. The argument presented finds that national boundaries are re-inscribed in the diaspora at the intersection of the multiple claims of membership. Simultaneously, experiences and interactions in the diaspora provide the grounds for transforming and questioning the limits of national belonging.

Organizing Capacities and Union Priorities in the Hotelsector in Oslo, Dublin, and Toronto

Directory of Open Access Journals (Sweden)

Ann Cecilie Bergene

2014-09-01

Full Text Available In this article, we draw international comparisons between industrial relations regimes in the hotel sector and compare relevant trade union experiences in the selected metropolitan areas of Oslo, Dublin, and Toronto. We ask how union strategies differ in these different hotel markets, and how strategic choices at a local level relate to industrial relations models, regulatory change, and corporate restructuring in the hotel market. The study is based on interviews with union representatives and key informants in Norway, Ireland, and Canada. The main argument we make is that the reorientation of union priorities and the willingness to engage in innovative strategies that has characterized hotel unionism in Toronto and Dublin is not detectable in the case of Oslo. This might be a result of the relatively strong position Norwegian trade unions have in national industrial relations, but can at the same time leave local hotel unions vulnerable as they are facing low unionization levels and corporate restructuring which they are unable to tackle effectively.

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

Unlocking the electric mobility potential of Toronto: moving toward an electric mobility master plan for the city

International Nuclear Information System (INIS)

Gleeson, A.; Scratch, K.

2010-10-01

This report is an analysis of the current state of electric transportation and its potential integration in the transportation system of the city of Toronto. In this document, electric vehicles include every mode of transport involving the use of energy drawn from the electricity grid, such as plug-in hybrid electric vehicles (PHEV), extended range electric vehicles (EREV), battery electric vehicles (BEV), grid connected transit vehicles and electrified locomotives. An overview of the movement of people and goods, including the consideration of patterns of commuting and modes of transportation, is provided in the first section of this document. It has been demonstrated that most of the trips taking place in the city correspond to the predicted operating range of many EVs. Section one also provides a description of the local electricity grid system serving Toronto neighbourhoods and of the sources and movements of air contaminants. It gives a evaluation of the state of EV technologies and analyzes the economic and social factors that have an impact on the public perceptions regarding these technologies. Current policies and programs designed to promote market adoption of EVs around the world are outlined in the conclusion of this section. A simulation work was performed through a collaborative work with Toronto Hydro Electric System Limited in order to analyze the consequences of different EV charging scenarios on the electricity grid system. The results of this simulation are described in section two of the report. The document also presents the outcomes of the workshop on the implementation of an electric mobility master plan held in Toronto in April, 2010. 176 refs.

Scoping Study on DRDC Toronto Future Research Regarding Naval Mine Countermeasures

Science.gov (United States)

2012-06-01

complete assigned missions. The exercise involved all of the NRF rotation 17: Belgium, France, Germany, Italy, Netherlands, Norway , Poland, Portugal...Toronto TR 2011-178 17 DARE is labour intensive to set up, populate with results and update. It can only produce results once enough MCM effort...operation (Scott, 2010). Since then, more than 10 Navies worldwide have acquired REMUS 100, creating a niche market for the UUVs. The use of UUVs

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

International Nuclear Information System (INIS)

Stratton, D.; Butt, C.

1982-04-01

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

Introducing Darwinism to Toronto's post-1887 reconstituted medical school.

Science.gov (United States)

Court, John P M

2011-01-01

Charles Darwin's scientific paradigm was largely welcomed in Canadian academic biology and medicine, while reaction among other faculty and laypeople ranged from interest to outrage. In 1874, Ramsay Wright, a Darwinian-era biologist from Edinburgh, was appointed to the University of Toronto's Chair of Natural History. Over his 38-year career Wright integrated the evolutionary perspective into medical and biology teaching without accentuating its controversial source. He also applied the emerging German experimental research model and laboratory technology. This study identifies five categories of scientific and personal influences upon Wright through archival research on biographical sources and his writings.

Feasibility analysis for a SolarShare co-operative in the City of Toronto

International Nuclear Information System (INIS)

Brigham, M.; Gipe, P.

2007-01-01

This report provided details of a feasibility study conducted to assess a business model for a solar electric co-operative within the City of Toronto. The study focused on the development of a rooftop array of solar photovoltaic (PV) panels. A portfolio of potential partners and projects representing approximately 4 MW was identified. Economic and financial models were used to determine the viability of the SolarShare rooftop design. Various tariffs and subsidies currently available for the development of renewable energy projects were reviewed. Despite growing environmental awareness and enthusiasm for solar energy projects amongst Toronto inhabitants, the analysis demonstrated that rooftop PV projects in Ontario are not profitable without a reduction in the costs of $3,500 to $5000 kW, subsidies, or an increase in tariff payments under the province's standard offer contract program. Revenues derived from energy sales under the SolarShare program were approximately half of what was required to undertake a profitable investment in solar PV. Recommendations for building profitable PV systems using a staged approach were included. 27 refs., 16 tabs., 1 fig

The prevalence and risks of early childhood caries (ECC) in Toronto, Canada.

Science.gov (United States)

Al-Jewair, Thikriat S; Leake, James L

2010-10-14

To determine the prevalence and risks of early childhood caries (ECC) among children less than 71 months of age in Toronto, Canada, and to evaluate the association between parental/caregiver depression and ECC. A secondary analysis of data previously collected by the Toronto Public Health as part of the 2003 Toronto Perinatal and Child Health Survey was performed. The 90-item survey was conducted over the telephone to 1,000 families with children from zero years (birth) to six years of age. Parents/caregivers were asked about factors related to the development and health of their children. For this study, only children younger than six years of age (less than 71 months) were included (n=833). The primary outcome of interest was self-reported and measured by the response to the question of whether a physician/dentist had ever told the parent/caregiver his/her child had ECC. The prevalence of ECC was 4.7 percent (37 of 791 children). The child's age, his/her history of dental visits, teeth brushing, the use of fluoridated toothpaste, the parent's/caregiver's depressive tendencies, the language spoken at home, and the household annual income were all significant in the bivariate analysis. Multiple logistic regression identified four factors associated with ECC: the child's age (being three years of age or older), having at least one parent/caregiver with depression, not speaking English at home, and having an annual household income less than $40,000 in Canadian dollars (CAD). While a child's age, home language, and household income are known risks for ECC, the finding that parental/caregiver depression may be related to ECC is new. Multiple risk factors are involved in the development of early childhood caries. Of particular importance are demographic (e.g., child's age), social (e.g., annual household income), and psychosocial factors (e.g., parental/caregiver depression) that are indirectly linked to ECC. More attention needs to be placed on understanding the role

Did the suicide barrier work after all? Revisiting the Bloor Viaduct natural experiment and its impact on suicide rates in Toronto.

Science.gov (United States)

Sinyor, Mark; Schaffer, Ayal; Redelmeier, Donald A; Kiss, Alex; Nishikawa, Yasunori; Cheung, Amy H; Levitt, Anthony J; Pirkis, Jane

2017-06-19

This research aims to determine the long-term impact of the Bloor Street Viaduct suicide barrier on rates of suicide in Toronto and whether media reporting had any impact on suicide rates. Natural experiment. City of Toronto, Canada; records at the chief coroner's office of Ontario 1993-2003 (11 years before the barrier) and 2004-2014 (11 years after the barrier). 5403 people who died by suicide in the city of Toronto. Changes in yearly rates of suicide by jumping at Bloor Street Viaduct, other bridges including nearest comparison bridge and walking distance bridges, and buildings, and by other means. Suicide rates at the Bloor Street Viaduct declined from 9.0 deaths/year before the barrier to 0.1 deaths/year after the barrier (incidence rate ratio (IRR) 0.005, 95% CI 0.0005 to 0.19, p=0.002). Suicide deaths from bridges in Toronto also declined significantly (IRR 0.53, 95% CI 0.40 to 0.71, psuicide at the Bloor Street Viaduct were associated with an increase in suicide-by-jumping from bridges the following year. The current study demonstrates that, over the long term, suicide-by-jumping declined in Toronto after the barrier with no associated increase in suicide by other means. That is, the barrier appears to have had its intended impact at preventing suicide despite a short-term rise in deaths at other bridges that was at least partially influenced by a media effect. Research examining barriers at other locations should interpret short-term results with caution. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

Assessing Greenhouse Gas emissions in the Greater Toronto Area using atmospheric observations (Invited)

Science.gov (United States)

Vogel, F. R.; Chan, E.; Huang, L.; Levin, I.; Worthy, D.

2013-12-01

Urban areas are said to be responsible for approximately 75% of anthropogenic Greenhouse Gases (GHGs) emissions while comprising only two percent of the land area [1]. This limited spatial expansion should facilitate a monitoring of anthropogenic GHGs from atmospheric observations. As major sources of emissions, cities also have a huge potential to drive emissions reductions. To effectively manage emissions, cities must however, first measure and report these publicly [2]. Modelling studies and measurements of CO2 from fossil fuel burning (FFCO2) in densely populated areas does, however, pose several challenges: Besides continuous in-situ observations, i.e. finding an adequate atmospheric transport model, a sufficiently fine-grained FFCO2 emission model and the proper background reference observations to distinguish the large-scale from the local/urban contributions to the observed FFCO2 concentration offsets ( ΔFFCO2) are required. Pilot studies which include the data from two 'sister sites*' in the vicinity of Toronto, Canada helped to derive flux estimates for Non-CO2 GHGs [3] and improve our understanding of urban FFCO2 emissions. Our 13CO2 observations reveal that the contribution of natural gas burning (mostly due to domestic heating) account for 80%×7% of FFCO2 emissions in the Greater Toronto Area (GTA) during winter. Our 14CO2 observations in the GTA, furthermore, show that the local offset of CO2 (ΔCO2) between our two sister sites can be largely attributed to urban FFCO2 emissions. The seasonal cycle of the observed ΔFFCO2 in Toronto, combined with high-resolution atmospheric modeling, helps to independently assess the contribution from different emission sectors (transportation, primary energy and industry, domestic heating) as predicted by a dedicated city-scale emission inventory, which deviates from a UNFCCC-based inventory. [1] D. Dodman. 2009. Blaming cities for climate change? An analysis of urban greenhouse gas emissions inventories

Teachers' Views of the Challenges of Teaching Grade 9 Applied Mathematics in Toronto Schools

Science.gov (United States)

Stoilescu, Dorian; McDougall, Douglas; Egodawatte, Gunawardena

2016-01-01

Mathematics teachers, mathematics department heads, curriculum leaders, and administrators from 11 schools in four school boards from Toronto, Ontario, Canada, participated in a project to improve the teaching and learning in grade 9 mathematics classrooms. In each of these schools, an implementation team was created, so that at least three…

Toronto's 2-1-1 healthcare services for immigrant populations.

Science.gov (United States)

Cortinois, Andrea A; Glazier, Richard H; Caidi, Nadia; Andrews, Gavin; Herbert-Copley, Mary; Jadad, Alejandro R

2012-12-01

Although access to information on health services is particularly important for recent immigrants, numerous studies have shown that their use of information and referral services is limited. This study explores the role played by 2-1-1 Toronto in supporting recent immigrants. The study objectives were to (1) understand whether 2-1-1 Toronto is reaching and supporting recent immigrants and (2) gain a better appreciation of the information needs of this population group. A phone survey was conducted in 2005-2006 to collect information on 2-1-1 users' characteristics and levels of satisfaction. Survey data were compared (in 2006) with census data to assess their representativeness. To achieve Objective 2, semistructured qualitative interviews were conducted and analyzed in 2006-2007, with a subset of Spanish-speaking callers. Recent immigrants were overrepresented among 2-1-1 callers. However, the survey population was substantially younger and had higher levels of formal education than the general population. Health-related queries represented almost one third of the total. The survey showed very high levels of satisfaction with the service. Many interviewees described their first experiences with the Canadian healthcare system negatively. Most of them had relied on disjointed, low-quality information sources. They trusted 2-1-1 but had discovered it late. Results are mixed in terms of 2-1-1's support to immigrants. A significant percentage of users do not take full advantage of the service. The service could become the information "entry point" for recent immigrants if it was able to reach them early in the resettlement process. Proactive, community-oriented work and a more creative use of technology could help. Copyright © 2012 American Journal of Preventive Medicine. All rights reserved.

Nuclear technologies for local energy systems

International Nuclear Information System (INIS)

McDonnell, F.N.; Lynch, G.F.

1990-03-01

If nuclear energy is to realize its full potential as a safe and cost-effective alternative to fossil fuels, applications beyond those that are currently being serviced by large, central nuclear power stations must be identified and appropriate reactors developed. The Canadian program on reactor systems for local energy supply is at the forefront of these developments. This program emphasizes design simplicity, low power density and fuel rating, reliance on natural processes, passive systems, and reduced reliance on operator action. The first product, the SLOWPOKE Energy System, is a 10 MW heat source specifically designed to provide hot water to satisfy the needs of local heating systems for building complexes, institutions and municipal district heating systems. A demonstration heating reactor has been constructed at the Whiteshell Nuclear Research Establishment in Manitoba and has been undergoing an extensive test program since first operation in 1987 July. Based on the knowledge learned from the design, construction, licensing and operational testing of this facility, the design of the 10 MW commercial-size unit is well advanced, and Atomic Energy of Canada Limited is prepared to commit the construction of the first commercial unit. Although the technical demonstration of the concept is important, it is recognized that another crucial element is the public and regulatory acceptance of small nuclear systems in urban areas. The decision by a community to commit the construction of a SLOWPOKE Energy System brings to a sharp focus the current public apprehension about nuclear technologies

Large scale replacement of fuel channels in the Pickering CANDU reactor using a man-in-the-loop remote control system

International Nuclear Information System (INIS)

Stratton, D.

1991-01-01

Spar Aerospace Limited of Toronto is presently under contract to Ontario Hydro to design a Remote Manipulation and Control System (RMCS) to be used during the large scale replacement of the fuel channels in the Pickering A Nuclear Generating Station. The system is designed to support the replacement of all 390 fuel channels in each of the four reactors at the Pickering A station in a safe manner that minimizes worker radiation exposure and unit outage time

Downsizing in the public sector: Metro-Toronto's hospitals.

Science.gov (United States)

Flint, Douglas H

2003-01-01

This study has two objectives. First, to predict the outcomes of a public sector downsizing; second to measure effects of downsizing at organizational and inter-organizational levels. Primary data to assess the organizational level effects was collected through interviews with senior executives at two of Metro-Toronto's hospitals. Secondary data, to assess the inter-organizational effects, was collected from government documents and media reports. Due to the exploratory nature of the study's objectives a case study method was employed. Most institutional downsizing practices aligned with successful outcomes. Procedures involved at the inter-organizational level aligned with unsuccessful outcomes and negated organizational initiatives. This resulted in an overall alignment with unsuccessful procedures. The implication, based on private sector downsizings, is that the post-downsized hospital system was more costly and less effective.

Nuclear reactor thermal hydraulics safety analysis and thoughts on FUKUSHIMA

International Nuclear Information System (INIS)

Ninokata, Hisashi

2012-01-01

The first part of this article is to show my thoughts on the accident at Fukushima Daiichi Nuclear Power Station. It is cited from a summary of my lecture talk in Indonesia, in the beginning of the last December, 2011. This talk was based on my previous lecture and seminar talks including those delivered at MIT, June 16, at the ANS Annual Meeting in Hollywood, Florida, June 28 at NURETH-13 in Toronto, September 27, and others. The content is based on the open and latest information available to date in Japan. It may contain some erroneous or uncertain information. I tried to minimize it to my best capability. Also I tried to eliminate any critical issues or opinions that may jeopardize some people who were involved in. The latter half of this article will be excerpts of my recent R and D activities related to the safety-by-design for sodium cooled fast reactors and light water reactors, thermal hydraulics analysis focusing on the simulation-based technology, in particular subchannel analysis and computational fluid dynamics. (J.P.N.)

Good practices in heavy water reactor operation

International Nuclear Information System (INIS)

2010-06-01

The value and importance of organizations in the nuclear industry engaged in the collection and analysis of operating experience and best practices has been clearly identified in various IAEA publications and exercises. Both facility safety and operational efficiency can benefit from such information sharing. Such sharing also benefits organizations engaged in the development of new nuclear power plants, as it provides information to assist in optimizing designs to deliver improved safety and power generation performance. In cooperation with Atomic Energy of Canada, Ltd, the IAEA organized the workshop on best practices in Heavy Water Reactor Operation in Toronto, Canada from 16 to 19 September 2008, to assist interested Member States in sharing best practices and to provide a forum for the exchange of information among participating nuclear professionals. This workshop was organized under Technical Cooperation Project INT/4/141, on Status and Prospects of Development for and Applications of Innovative Reactor Concepts for Developing Countries. The workshop participants were experts actively engaged in various aspects of heavy water reactor operation. Participants presented information on activities and practices deemed by them to be best practices in a particular area for consideration by the workshop participants. Presentations by the participants covered a broad range of operational practices, including regulatory aspects, the reduction of occupational dose, performance improvements, and reducing operating and maintenance costs. This publication summarizes the material presented at the workshop, and includes session summaries prepared by the chair of each session and papers submitted by the presenters

Reading the Urban Landscape: The Case of a Campus Tour at York University, Toronto, Ontario, Canada

Science.gov (United States)

Bardekjian, Adrina; Classens, Michael; Sandberg, L. Anders

2012-01-01

This paper presents a campus tour assignment in a first-year undergraduate environmental studies course at York University, Toronto, Canada. As a pedagogical tool, the assignment enables students to interrogate the dominant narratives of a university's immediate physical spaces and to apply broader theoretical and practical concepts to their…

Cycling to high school in Toronto, Ontario, Canada: Exploration of school travel patterns and attitudes by gender

NARCIS (Netherlands)

Wittmann, K.; Savan, B.; Ledsham, T.; Liu, G.; Lay, J.

2015-01-01

This study surveyed attitudes, behaviors, social norms, and perceived control among the populations of students at three high schools in downtown Toronto, Ontario, Canada. The results showed a pattern of hesitancy to cycle on the part of female high school students compared with their male

The hydrogen village in the Greater Toronto Area (GTA)

International Nuclear Information System (INIS)

Kimmel, T.B.; Smith, R.

2004-01-01

'Full text:' A Hydrogen Village (H2V) is a public/private partnership with an objective to accelerate the commercialization of hydrogen and fuel cell technology in Canada and firmly position Canada as the international leader in this sector. The first Hydrogen Village is planned for the Greater Toronto Area (GTA) and will make use of existing hydrogen and fuel cell deployments to assist in its creation. This five year GTA Hydrogen Village program is planned to begin operations in 2004. The Hydrogen Village will demonstrate and deploy various hydrogen production and delivery techniques as well as fuel cells for stationary, transportation (mobile) and portable applications. This paper will provide an overview of the Hydrogen Village and identify the missions, objectives, members and progress within the H2V. (author)

Behind the web store: the organisational and spatial evolution of multichannel retailing in Toronto

OpenAIRE

Andrew Currah

2002-01-01

In this paper I address two issues of general relevance to contemporary debates in economic geography: first, the organisational and spatial implications of new information technologies for the economic landscape; and, second, the enduring role of place to digital capitalism. Specifically, I examine the organisational evolution of multichannel retailing in Toronto from a geographical perspective. Bricks-and-mortar retailers are increasingly pursuing a multichannel strategy by operating an Int...

Urban flood perceptions and mitigative behaviours: Peterborough, Edmonton, and Toronto

International Nuclear Information System (INIS)

Sandink, D.

2009-01-01

This abstract presents research from two studies investigating urban flood perceptions and mitigative behaviours of private individuals in Canada. The first study, completed in July, 2006, investigated perceptions of overland flooding and sewer backup resulting from extreme rainfall events in Peterborough, Ontario. The second, completed in November, 2007, investigated sewer backup perceptions of homeowners in Edmonton, Alberta and Toronto, Ontario. The research studies sought to explore: Hazard and risk perceptions of individuals affected by overland flooding and sewer backup; Knowledge of mitigative options, and mitigative actions taken by individual residents to reduce the risk of basement flood damage; Attributions of responsibility for urban flood damages; Awareness of municipal actions designed to reduce urban flood risk; Satisfaction with the cost sharing tools of insurance and government relief.

Boundary Spanners and Advocacy Leaders: Black Educators and Race Equality Work in Toronto and London, 1968-1995

Science.gov (United States)

Johnson, Lauri

2016-01-01

This comparative study examines the historical development of race equality efforts during the 1970s and 1980s in two global cities--Toronto and London--and the role of African Canadian and Black British educators in longstanding school-community partnerships. I characterize the leadership stance of Black educators as boundary spanners and…

Ready for policy? Stakeholder attitudes toward menu labelling in Toronto, Canada.

Science.gov (United States)

Mah, Catherine L; Vanderlinden, Loren; Mamatis, Dia; Ansara, Donna L; Levy, Jennifer; Swimmer, Lisa

2013-04-18

The purpose of this research was to assess key stakeholder attitudes regarding menu labelling in Toronto, the largest municipality in Canada. Menu labelling is a population health intervention where food-labelling principles are applied to the eating-out environment through disclosure of nutrient content of food items on restaurant menus at the point of sale. Menu-labelling legislation has been implemented in the United States, but has yet to be adopted in Canada. As provincial voluntary programs and federal analyses progress, municipal jurisdictions will need to assess the feasibility of moving forward with parallel interventions. Data were collected and analyzed in late 2011 to early 2012, including: a consumer eating-out module incorporated into a public health surveillance telephone survey (n=1,699); an online survey of independent restaurant operators (n=256); in-depth key informant interviews with executives and decision makers at chain restaurants (n=9); and a policy consultation with local restaurant associations. Toronto residents, particularly men, younger adults, and those with higher income or education, frequently eat out. A majority indicated that nutrition information is important to them; 69% note that they currently use it and 78% reported they would use it if it were readily available. Resistance to menu-labelling requirements at the municipal level was articulated by franchise/chain restaurant executives and industry associations. Despite overall low interest among independent restaurant operators, 57% reported feeling some responsibility to provide nutrition information and 50% believed it could be good for business. This research supports earlier literature that indicates strong public support for menu labelling alongside perceived barriers among the restaurant and foodservices sector. Leverage points for effective operator engagement for menu-labelling adoption were identified, nonetheless, highlighting the need for public health support.

Man and radiation

International Nuclear Information System (INIS)

1981-01-01

The film reviews production aspects and application of various radiation sources that were developed in Canada for use in medicine (gamma cells, x-ray treatment facilities, electron linear accelerator) and in industry (mobile and static Co-60 gamma irradiation units for sterilisation purposes, SLOWPOKE nuclear reactor for uranium analysis). In addition, facilities for irradiation of blood and equipment for mapping blood flow in the human brain with the Kr-85 method are shown. Manufacturing and transport of Co-60 sources are demonstrated as well

Prof. Tiina Kirsi raamatuesitlus Toronto Ülikoolis : uus ingliskeelne raamat eesti naiste elulugudest / Eda Sepp ; fotod: Eda Sepp

Index Scriptorium Estoniae

Sepp, Eda

2004-01-01

20. mail 2004 toimus Toronto Ülikooli Eesti Õppetooli juures Tiina Ann Kirsi toimetatud ja Tartu Ülikooli väljaandena 2004. a. ilmunud raamatu "She who remembers survives : interpreting Estonian women's post-soviet life stories" esitlus, kus toimetaja andis põhjaliku ülevaate teose olemusest ning eesmärkidest

Neutron Spectrum Parameters In Inner Irradiation Channel Of The Nigeria Research Reactor-1 (NIRR-1) For Use In Absolute And KO-NAA Methods

International Nuclear Information System (INIS)

Jonah, S.A; Balogun, G.I; Mayaki, M.C.

2004-01-01

parameters of other Miniature Source Reactor (MNSR) and Slowpoke facilities. Further investigations based on this method are in progress to determine the neutron spectrum parameters of the irradiation NIRR-1

Breaking the Myth of Flexible Work: Contingent Work in Toronto. A Study Conducted by the Contingent Workers Project.

Science.gov (United States)

de Wolff, Alice

A survey of 205 people, 4 group interviews with approximately 30 people, and 6 design and analysis meetings involving approximately 40 people were conducted in a 1999 participatory study of contingent workers in Toronto. (Contingent work was defined to be lower-waged forms of non-permanent work arrangements that include contracting, employment…

Concentrations in air of organobromine, organochlorine and organophosphate flame retardants in Toronto, Canada

Science.gov (United States)

Shoeib, Mahiba; Ahrens, Lutz; Jantunen, Liisa; Harner, Tom

2014-12-01

Concentrations of organobromine (BFRs), organochlorine (CFRs) and organophosphate esters flame retardants and plasticizers (PFRs) in air were monitored for over one year at an urban site in Toronto, Canada during 2010-2011. The mean value for polybrominated diphenyl ethers (BDEs) (gas + particle phase) was 38 pg/m3 with BDE-47 and BDE-99 as the dominant congeners. The mean concentrations in air for ∑non-BDE (BFRs and CFRs), was 9.6 pg/m3 - about four times lower than the BDEs. The brominated FRs: TBP-AE, BTBPE, EH-TBB, BEH-TEBP and the chlorinated syn- and anti-DP were detected frequently, ranging from 87% to 96%. Highest concentrations in air among all flame retardant classes were observed for the Σ-PFRs. The yearly mean concentration in air for ΣPFRs was 2643 pg/m3 with detection frequency higher than 80%. Except for TBP-AE and b- DBE-DBCH, non-BDEs (BFRs, CFRs and PFRs) were mainly associated with the particle phase. BDE concentrations in air were positively correlated with temperature indicating that volatilization from local sources was an important factor controlling levels in air. This correlation did not hold for most BFRs, CFRs and PFRs which were mainly on particles. For these compounds, air concentrations in Toronto are likely related to emissions from point sources and advective inputs. This study highlights the importance of urban air monitoring for FRs. Urban air can be considered a sentinel for detecting changes in the use and application of FRs in commercial products.

Integrating bioethics into postgraduate medical education: the University of Toronto model.

Science.gov (United States)

Howard, Frazer; McKneally, Martin F; Levin, Alex V

2010-06-01

Bioethics training is a vital component of postgraduate medical education and required by accreditation organizations in Canada and the United States. Residency program ethics curricula should ensure trainees develop core knowledge, skills, and competencies, and should encourage lifelong learning and teaching of bioethics. Many physician-teachers, however, feel unprepared to teach bioethics and face challenges in developing and implementing specialty-specific bioethics curricula. The authors present, as one model, the innovative strategies employed by the University of Toronto Joint Centre for Bioethics. They postulate that centralized support is a key component to ensure the success of specialty-specific bioethics teaching, to reinforce the importance of ethics in medical training, and to ensure it is not overshadowed by other educational concerns.

Edmonton fills vacuum left by Toronto firm

International Nuclear Information System (INIS)

Lunan, D.

2000-01-01

EPCOR Energy Services, the retail marketing arm of Edmonton's municipal utility company, holds 30,000 residential customer contracts that it purchased from Alberta Natural Gas Savings Corporation last fall. It is also selling natural gas to 10,000 commercial customers. EPCOR now is interested in acquiring the customer base from Apollo Gas Marketing, a Toronto-based marketer recently forced out of the Alberta market by rising gas prices. EPCOR is eager to learn from the mistakes made by Apollo and other natural gas marketers and is putting together a contract package that would ensure a reasonable profit on operations even in the face of rising gas prices. Customers are offered the opportunity to sign fixed term contracts for one -, three-, or five years. The one year contract has a price tag of $6.75/gigajoule; the three-year term is priced at $5.99/gigajoule, and the five-year contract at $5.35/gigajoule. While the one-year price is a little high, compared to contracts available from other marketers, EPCOR's five-year term is worth customers' attention. EPCOR is able to make this offer since it has sufficient gas under a variety of futures contracts to meet it contractual obligations without being forced to buy gas on the spot market

Research on Foreign Language Teaching in North America : The University of Toronto and Michigan State University

OpenAIRE

Lauer, Joe; Yamada, Jun

1998-01-01

Both the Modern Language Centre at the University of Toronto's Ontario Institute for Studies in Education (OISE/UT), and the English Language Center at Michigan State University, are acknowledged as being among the best centers for applied linguistics research and education in the world. The Modern Language Centre has published important findings in the areas of second language acquisition, psycholinguistics, sociolinguistics and language curricula. Meanwhile, the English Language Center has ...

Exploring spatial patterns of sudden cardiac arrests in the city of Toronto using Poisson kriging and Hot Spot analyses.

Science.gov (United States)

Przybysz, Raymond; Bunch, Martin

2017-01-01

Our study looked at out-of-hospital sudden cardiac arrest events in the City of Toronto. These are relatively rare events, yet present a serious global clinical and public health problem. We report on the application of spatial methods and tools that, although relatively well known to geographers and natural resource scientists, need to become better known and used more frequently by health care researchers. Our data came from the population-based Rescu Epistry cardiac arrest database. We limited it to the residents of the City of Toronto who experienced sudden arrest in 2010. The data was aggregated at the Dissemination Area level, and population rates were calculated. Poisson kriging was carried out on one year of data using three different spatial weights. Kriging estimates were then compared in Hot Spot analyses. Spatial analysis revealed that Poisson kriging can yield reliable rates using limited data of high quality. We observed the highest rates of sudden arrests in the north and central parts of Etobicoke, western parts of North York as well as the central and southwestern parts of Scarborough while the lowest rates were found in north and eastern parts of Scarborough, downtown Toronto, and East York as well as east central parts of North York. Influence of spatial neighbours on the results did not extend past two rings of adjacent units. Poisson kriging has the potential to be applied to a wide range of healthcare research, particularly on rare events. This approach can be successfully combined with other spatial methods. More applied research, is needed to establish a wider acceptance for this method, especially among healthcare researchers and epidemiologists.

[A comparative study of primary care health promotion practices in Florianópolis, Santa Catarina State, Brazil, and Toronto, Ontario, Canada].

Science.gov (United States)

Heidemann, Ivonete Teresinha Schulter Buss; Cypriano, Camilla da Costa; Gastaldo, Denise; Jackson, Suzanne; Rocha, Carolina Gabriele; Fagundes, Eloi

2018-01-01

The study aimed to compare the experiences with the organization of universal public healthcare systems in relation to health promotion in primary care units in Florianópolis, Santa Catarina State, Brazil, and Toronto, Ontario, Canada. This was a descriptive exploratory study with a qualitative approach in primary care units. Data were collected with semi-structured interviews containing questions on health promotion practices, with 25 health professionals in Florianópolis and 10 in Toronto. The data were discussed using thematic analysis, identifying the practices, difficulties, and facilities in health promotion. In the two cities, 60% of health professionals and health administrators had not received any specific knowledge on health promotion during their training. As for health promotion skills, health professionals in Toronto identified them with autonomy and social determinants, while in Florianópolis they were related to health education and community participation. In both cities, health promotion practices are targeted to individual and collective activities. The motivation to act comes from interdisciplinarity and the demands raised by the population. Health promotion is a relevant form of care and stimulus for individual and community autonomy, in light of social determinants. Such practices aim at comprehensive health for the community, but there are limits in the teams that still conduct disease-centered activities. Resources are limited, requiring inter-sector actions to improve quality of life. Healthcare centers on the hegemonic model, and progress is needed to achieve a positive approach to health and social determinants.

Qualitative cross-sectional study of the perceived causes of depression in South Asian origin women in Toronto

Science.gov (United States)

Ekanayake, Samanthika; Ahmad, Farah

2012-01-01

Objective To explore how South Asian origin women in Toronto, Canada, understand and explain the causes of their depression. Design Cross-sectional in-depth qualitative interviews. Setting Outpatient service in Toronto, Ontario. Participants Ten women with symptoms of depression aged between 22 and 65 years of age. Seven were from India, two from Sri Lanka and one from Pakistan. Four were Muslim, three Hindu and three Catholic. Two participants had university degrees, one a high school diploma and seven had completed less than a high school education. Eight were married, one was unmarried and one a widow. Results Three main factors emerged from the participant narratives as the causes of depression: family and relationships, culture and migration and socioeconomic. The majority of the participants identified domestic abuse, marital problems and interpersonal problems in the family as the cause of their depression. Culture and migration and socioeconomic factors were considered contributory. None of our study participants reported spiritual, supernatural or religious factors as causes of depression. Conclusion A personal–social–cultural model emerged as the aetiological paradigm for depression. Given the perceived causation, psycho-social treatment methods may be more acceptable for South Asian origin women. PMID:22337816

Human Brain Proteome Project - 12th HUPO BPP Workshop. 26 September 2009, Toronto, Canada.

Science.gov (United States)

Gröttrup, Bernd; Eisenacher, Martin; Stephan, Christian; Marcus, Katrin; Lee, Bonghee; Meyer, Helmut E; Park, Young Mok

2010-06-01

The HUPO Brain Proteome Project (HUPO BPP) held its 12th workshop in Toronto on 26 September 2009 prior to the HUPO VIII World Congress. The principal aim of this project is to obtain a better understanding of neurodiseases and ageing, with the ultimate objective of discovering prognostic and diagnostic biomarkers, in addition to the development of novel diagnostic techniques and new medications. The attendees came together to discuss progress in the human clinical neuroproteomics and to define the needs and guidelines required for more advanced proteomic approaches.

The prospects for nuclear heating in Hungary

International Nuclear Information System (INIS)

Lynch, G.F.; Papp, I.

1989-09-01

Hungary supplies only half of its energy requirements from domestic resources and is very dependent upon imports of oil, natural gas and electricity to meet the current demand. In planning to reduce the dependence on imports, nuclear technology is considered an important element in the long-term energy strategy. To this end, an aggressive nuclear electricity generation program is being implemented with four 440 MWe units now operating and two 1000 MWe units committed. However, nuclear technology must be used in other energy sectors if the goal of long-term energy independence is to be achieved. On the demand side, 30% of the primary energy is consumed in the public sector, the major component being residential heating. Of the 3.7 million apartments in Hungary, 500 000 benefit from being connected to municipal district heating systems that use natural gas or oil as the energy base. This is, therefore, another significant energy sector that is amenable to using nuclear technology to substitute for imported oil and natural gas. In assessing alternative nuclear heat sources, a joint study was undertaken between Canada and Hungary to determine the feasibility of using the SLOWPOKE Energy System that has recently been developed. The SLOWPOKE Energy System is 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. It uses a combination of inherent safety features, including natural convection circulation and negative reactivity coefficients, and engineered features to ensure an extremely safe system. A SLOWPOKE demonstration heating reactor has been constructed in Canada. The unit started operation in 1987 July and is currently undergoing an extensive test program

Segregation or "Thinking Black"?: Community Activism and the Development Of Black-Focused Schools in Toronto and London, 1968-2008

Science.gov (United States)

Johnson, Lauri

2013-01-01

Background/Context: On January 29, 2008 the Toronto District School Board (TDSB) approved a city-wide Africentric elementary school under their Alternative School policy, sparking a contentious debate. Calls for Black-focused schools also arose in 2008 in London in response to the disengagement of African Caribbean youth. The historical record…

Production of medical short-lived radionuclides in Canada

International Nuclear Information System (INIS)

Wiebe, L.I.

1985-01-01

The production of radionuclides for medical and biomedical research in Canada has been reviewed with respect to the national geographic and demographic characteristics which influence their use. The types of facilities available for the production of short-lived radionuclides have been summarized, and a tabulation of the radionuclides that are produced has been presented. In broad terms production facilities can be classified as belonging to one of two groups, nuclear reactor or charged-particle accelerators. The charged-particle accelerators produce the more neutron-deficient and (because of the resultant decay properties) the more useful radionuclides for medical application. The nuclear reactor facilities for radionuclide production range in size and capacity from the high-flux research reactors of AECL to the six SLOWPOKE reactors, five of which are located on university campuses across the country. The McMaster University reactor is used to produce curie quantities of fluorine-18 weekly. Millicurie amounts of a large number of radionuclides, most of which have half-lives ranging from 2 to 50 hr, are produced in the low-flux reactors, in support of basic medical research

The Road to Responsive: University of Toronto Libraries’ Journey to a New Library Catalogue Interface

Directory of Open Access Journals (Sweden)

Lisa Gayhart

2014-01-01

Full Text Available With the recent surge in the mobile device market and an ever expanding patron base with increasingly divergent levels of technical ability, the University of Toronto Libraries embarked on the development of a new catalogue discovery layer to fit the needs of its diverse users. The result: a mobile-friendly, flexible and intuitive web application that brings the full power of a faceted library catalogue to users without compromising quality or performance, employing Responsive Web Design principles.

Homeworking: Home Office or Home Sweatshop? Report on Current Conditions of Homeworkers in Toronto's Garment Industry. NALL Working Paper.

Science.gov (United States)

Ng, Roxana; Wong, Renita Yuk-Lin; Choi, Angela

The current conditions of home workers in the garment industry in Toronto, Canada, were examined through in-depth telephone interviews with 30 Chinese-speaking immigrant women who were employed as home workers in 1999. The paper dicusses the formal training and informal learning experiences of immigrant woman who are garment workers. A comparison…

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)

Ending homelessness among people with mental illness: the At Home/Chez Soi randomized trial of a Housing First intervention in Toronto

Directory of Open Access Journals (Sweden)

Hwang Stephen W

2012-09-01

Full Text Available Abstract Background The At Home/Chez Soi (AH/CS Project is a randomized controlled trial of a Housing First intervention to meet the needs of homeless individuals with mental illness in five cities across Canada. The objectives of this paper are to examine the approach to participant recruitment and community engagement at the Toronto site of the AH/CS Project, and to describe the baseline demographics of participants in Toronto. Methods Homeless individuals (n = 575 with either high needs (n = 197 or moderate needs (n = 378 for mental health support were recruited through service providers in the city of Toronto. Participants were randomized to Housing First interventions or Treatment as Usual (control groups. Housing First interventions were offered at two different mental health service delivery levels: Assertive Community Treatment for high needs participants and Intensive Case Management for moderate needs participants. Demographic data were collected via quantitative questionnaires at baseline interviews. Results The effectiveness of the recruitment strategy was influenced by a carefully designed referral system, targeted recruitment of specific groups, and an extensive network of pre-existing services. Community members, potential participants, service providers, and other stakeholders were engaged through active outreach and information sessions. Challenges related to the need for different sectors to work together were resolved through team building strategies. Randomization produced similar demographic, mental health, cognitive and functional impairment characteristics in the intervention and control groups for both the high needs and moderate needs groups. The majority of participants were male (69%, aged >40 years (53%, single/never married (69%, without dependent children (71%, born in Canada (54%, and non-white (64%. Many participants had substance dependence (38%, psychotic disorder (37%, major depressive episode (36

Edmonton fills vacuum left by Toronto firm

Energy Technology Data Exchange (ETDEWEB)

Lunan, D.

2000-06-19

EPCOR Energy Services, the retail marketing arm of Edmonton's municipal utility company, holds 30,000 residential customer contracts that it purchased from Alberta Natural Gas Savings Corporation last fall. It is also selling natural gas to 10,000 commercial customers. EPCOR now is interested in acquiring the customer base from Apollo Gas Marketing, a Toronto-based marketer recently forced out of the Alberta market by rising gas prices. EPCOR is eager to learn from the mistakes made by Apollo and other natural gas marketers and is putting together a contract package that would ensure a reasonable profit on operations even in the face of rising gas prices. Customers are offered the opportunity to sign fixed term contracts for one -, three-, or five years. The one year contract has a price tag of $6.75/gigajoule; the three-year term is priced at $5.99/gigajoule, and the five-year contract at $5.35/gigajoule. While the one-year price is a little high, compared to contracts available from other marketers, EPCOR's five-year term is worth customers' attention. EPCOR is able to make this offer since it has sufficient gas under a variety of futures contracts to meet it contractual obligations without being forced to buy gas on the spot market.

Arsenic pollution in the Yellowknife area from gold smelter activities

International Nuclear Information System (INIS)

Hutchinson, T.C.; Aufreiter, S.; Hancock, R.G.V.

1982-01-01

Gold mined at Yelloknife in the North West Territories of Canada is associated with arsenopyrite ores which necessitates the oxidation of the arsenic and sulphur by roasting at two Yellowknife smelters. As 2 O 3 and SO 2 are emitted into the atmosphere, and despite improvements in emission control, significant emissions still occur. In order to asses the arsenic contamination in the local environment and the potential exposures to man, soil samples and samples of the native vegetation were collected in and around Yellowknife and the two smelters. Arsenic and antimony analyses were done by instrumental neutron activation analysis using the SLOWPOKE facility at University of Toronto. Zinc, copper, lead and cadmium analyses were done by atomic adsorption spectrophotometry. Arsenic was found to be accumulated in the soils in the vicinity of the two smelters to levels of several thousand ppm. Antimony levels were about 10% of arsenic and were highly correlated with arsenic. Zinc occured to 500 ppm around the smelters. Soil arsenic levels are sufficiently high to inhibit root growth in soils over a very extensive area. (author)

Interactive Online Modules and Videos for Learning Geological Concepts at the University of Toronto Department of Earth Sciences

Science.gov (United States)

Veglio, E.; Graves, L. W.; Bank, C. G.

2014-12-01

We designed various computer-based applications and videos as educational resources for undergraduate courses at the University of Toronto in the Earth Science Department. These resources were developed in effort to enhance students' self-learning of key concepts as identified by educators at the department. The interactive learning modules and videos were created using the programs MATLAB and Adobe Creative Suite 5 (Photoshop and Premiere) and range from optical mineralogy (extinction and Becke line), petrology (equilibrium melting in 2-phase systems), crystallography (crystal systems), geophysics (gravity anomaly), and geologic history (evolution of Canada). These resources will be made available for students on internal course websites as well as through the University of Toronto Earth Science's website (www.es.utoronto.ca) where appropriate; the video platform YouTube.com may be used to reach a wide audience and promote the material. Usage of the material will be monitored and feedback will be collected over the next academic year in order to gage the use of these interactive learning tools and to assess if these computer-based applications and videos foster student engagement and active learning, and thus offer an enriched learning experience.

Interculturalism and Physical Cultural Diversity in the Greater Toronto Area

Directory of Open Access Journals (Sweden)

Yuka Nakamura

2017-06-01

Full Text Available The Greater Toronto Area (GTA is one of the most multicultural communities in the world. Frequently, this description is based on ethnic, linguistic, and culinary diversity. Physical cultural diversity, such as different sports, martial arts, forms of dance, exercise systems, and other physical games and activities, remains ignored and understudied. Based on a living database of the GTA’s physical cultural diversity, this study identifies the trajectories of the lifecycle of activities that have been introduced into the GTA’s physical culture by immigrants. These pathways differ based on whether the activity is offered in a separate setting, where individuals may be participating with other immigrants of the same ethnocultural group, or mixed settings, where people are participating with people from outside of their ethnocultural group. We argue that the diversity and the lifecycle trajectories of physical cultural forms in the GTA serve as evidence of interculturalism and the contribution by immigrants to the social and cultural life of Canada.

Tapping into the ‘standing-reserve’: a comparative analysis of workers’ training programmes in Kolkata and Toronto

OpenAIRE

Maitra, Saikat; Maitra, Srabani

2015-01-01

This paper examines employment-related training programmes offered by state funded agencies and multinational corporations in Toronto (Canada) and Kolkata (India). In recent years both cities have witnessed a rise in the service sector industries aligned with global regimes of flexible work and the consequent reinvention of a worker subject that is no longer disciplined according to the needs of industrial production. A worker must now be self-regulated, competitive, flexible, with an ability...

"All Methods--and Wedded to None": The Deaf Education Methods Debate and Progressive Educational Reform in Toronto, Canada, 1922-1945

Science.gov (United States)

Ellis, Jason A.

2014-01-01

This article is about the deaf education methods debate in the public schools of Toronto, Canada. The author demonstrates how pure oralism (lip-reading and speech instruction to the complete exclusion of sign language) and day school classes for deaf schoolchildren were introduced as a progressive school reform in 1922. Plans for further oralist…

Generation X Leaders from London, New York and Toronto: Conceptions of Social Identity and the Influence of City-Based Context

Science.gov (United States)

Edge, Karen; Descours, Katherine; Oxley, Laura

2017-01-01

Inspired by scholarly calls to focus more intently on the influence of context on leaders' construction and negotiation of identity, this paper draws on evidence from our Economic and Social Research Council (ESRC) project in London, New York City and Toronto. Throughout the paper, we strive to illuminate how the city-based context influences how…

An automated microcomputer-controlled system for neutron activation and gamma-ray spectroscopy

International Nuclear Information System (INIS)

Edward, J.B.; Bennett, L.G.I.

1990-01-01

An automated instrumental neutron activation analysis (INAA) system has been constructed at the SLOWPOKE-2 reactor at the Royal Military College of Canada (RMC). Its pneumatic transfer system is controlled by an Apple IIe computer, linked in turn to an MS-DOS-compatible microcomputer which controls data acquisition. Custom software has been created for these computers and for off-line spectral analysis using programs that incorporate either peak boundary or Gaussian peak fitting methods of analysis. This system provides the gamut of INAA techniques for the analyst. The design and performance of the hardware and software are discussed. (orig.)

Public concern for air quality: explaining change in Toronto, Canada, 1967-1978

Energy Technology Data Exchange (ETDEWEB)

Dworkin, J M [Univ of Arizona, Tucson; Pijawka, K D

1982-01-01

The paper presents the results of an empirical study of the change in perception of air quality in Toronto, Canada from 1968-1978. The data show a shift in public concern with and awareness of air quality. Despite the fact that the 1978 population regarded air quality as degraded, air pollution declined as a public concern, requiring a less serious response by government than other societal problems. The results of the study were reviewed in the context of existing perception studies. In explaining change, the study found: (1) perception of ambient air quality was not related to air pollution levels; (2) air pollution declines as a public concern as other socioeconomic problems surface; and (3) the mass media has an important role in affecting public attitudes and behavior over environmental quality issues.

Towards an adaptation action plan : climate change and health in the Toronto-Niagara region : summary for policy makers

International Nuclear Information System (INIS)

Chiotti, Q.; Morton, I.; Maarouf, A.

2002-10-01

The current science regarding climate change and its potential health effects was assessed in an effort to provide information to decision-makers dealing with health infrastructure in the Toronto-Niagara region. This report also presents an assessment of how the health care system can adapt to handle the increased demand for services resulting from the projected negative human health effects of climate change. The first part of the report presents some background information on climate change and health issues and demonstrates how the current health care infrastructure cannot deal effectively with the full range of health effects that may occur in heavily populated areas such as the Toronto-Niagara region. The second part of the report summarizes the scientific knowledge about the expected impacts of climate change and associated health effects, such as heat stress, extreme weather events, poor air quality, vector-borne diseases, food and water-borne diseases, and increased exposure to ultra-violet radiation. It was noted that children and the elderly are most vulnerable. The final part of the report outlines an adaptation action plan to improve the health care infrastructure through public education and communication, surveillance and monitoring, ecosystem intervention, infrastructure development, technical engineering, and medical intervention. 100 refs., 1 fig

The role of air pollution in the relationship between a heat stress index and human mortality in Toronto

International Nuclear Information System (INIS)

Rainham, D.G.C.; Smoyer-Tomic, Karen E.

2003-01-01

In this study we considered confounding from air pollutants and chronological variables in the relation between humidex, a summer temperature and humidity index, and nonaccidental mortality, from 1980-1996 in Toronto, Canada. Changes in the risk of death by age group, gender, and combined cardiac-respiratory cause of death were estimated for both 1 deg. C and 50-95th percentile increases in humidex using a generalized additive linear model. With air pollution terms in the models, relative risk (RR) point estimates narrowly exceeded 1.0 for all groups. Humidex effects were most apparent for females (RR=1.006, 95% CI=1.004-1.008 per 1 deg. C humidex and RR=1.089, 95% CI=1.058-1.121 for 50th to 95th percentile humidex). When air pollution was omitted from the model, RR in the 50-95th percentile analysis increased less than 1.71% for all groups except females, for which RR decreased 1.42%. Differences in RR per 1 deg. C humidex were all less than 0.12%. Confidence intervals narrowed slightly for all groups investigated. Heat stress has a statistically significant, yet minimal impact on Toronto populations, and air pollution does appear to have a small, but consistent confounding effect on humidex effect estimates

Co-creating a psychiatric resident program with Ethiopians, for Ethiopians, in Ethiopia: the Toronto Addis Ababa Psychiatry Project (TAAPP).

Science.gov (United States)

Alem, Atalay; Pain, Clare; Araya, Mesfin; Hodges, Brian D

2010-01-01

Globalization in medical education often means a "brain drain" of desperately needed health professionals from low- to high-income countries. Despite the best intentions, partnerships that simply transport students to Western medical schools for training have shockingly low return rates. Ethiopia, for example, has sent hundreds of physicians abroad for specialty training over the past 30 years, the vast majority of whom have not returned. This represents a highly problematic net transfer of financial and human resources from the Ethiopian people to Western countries that have failed to develop their own adequate health human resource plans. With this background in mind, in 2003 Addis Ababa University invited the University of Toronto to collaborate on the first Ethiopian psychiatric residency program to be run entirely in Ethiopia. Called the Toronto Addis Ababa Psychiatry Project (TAAPP), it was established on the principle of supplementing the ability of the small Addis Ababa University Department of Psychiatry to teach, provide clinical supervision, and to help develop educational capacity. Over the last 6 years the model has involved a large number of University of Toronto faculty and residents who have spent blocks of 1 month each in Addis Ababa. This article describes the first three phases of TAAPP (I) Development of a model residency program; (II) Enhancing clinical, educational and leadership capacity; and (III) Sustainability, faculty development, and continuing education. Between 2003 and 2009, the number of psychiatrists in Ethiopia increased from 11 to 34; the Addis Ababa University Department of Psychiatry faculty increased members from three to nine. There are new departments of psychiatry established in four other university hospitals in Ethiopia outside the capital city. Mental health services are now being integrated within the national system of primary care. An important issue that underscores such a partnership is the risk of simply exporting

Safety and licensing of nuclear heating plants

International Nuclear Information System (INIS)

Snell, V.G.; Hilborn, J.W.; Lynch, G.F.; McAuley, S.J.

1989-09-01

World attention continues to focus on nuclear district heating, a low-cost energy from a non-polluting fuel. It offers long-term security for countries currently dependent on fossil fuels, and can reduce the burden of fossil fuel transportation on railways and roads. Current initiatives encompass large, centralized heating plants and small plants supplying individual institutions. The former are variants of their power reactor cousins but with enhanced safety features. The latter face the safety and licensing challenges of urban siting and remotely monitored operation, through use of intrinsic safety features such as passive decay heat removal, low stored energy and limited reactivity speed and depth in the control systems. Small heating reactor designs are compared, and the features of the SLOWPOKE Energy System, in the forefront of these designs, are summarized. The challenge of public perception must be met by clearly presenting the characteristics of small heating reactors in terms of scale and transparent safety in design and operation, and by explaining the local benefits

Bilingual Education Project: Evaluation of the 1973-74 French Immersion Program in Grades K-2 at Allenby Public School, Toronto.

Science.gov (United States)

Barik, Henri C.; And Others

The school performance of pupils in grades K-2 of the French immersion program in operation at Allenby Public School in Toronto is evaluated in comparison with that of pupils in the regular English program. The results indicate that by the end of kindergarten pupils in both programs are equally ready for beginning school work in grade 1. By the…

A cohort study of intra-urban variations in volatile organic compounds and mortality, Toronto, Canada

International Nuclear Information System (INIS)

Villeneuve, Paul J.; Jerrett, Michael; Su, Jason; Burnett, Richard T.; Chen, Hong; Brook, Jeffrey; Wheeler, Amanda J.; Cakmak, Sabit; Goldberg, Mark S.

2013-01-01

This study investigated associations between long-term exposure to ambient volatile organic compounds (VOCs) and mortality. 58,760 Toronto residents (≥35 years of age) were selected from tax filings and followed from 1982 to 2004. Death information was extracted using record linkage to national mortality data. Land-use regression surfaces for benzene, n-hexane, and total hydrocarbons were generated from sampling campaigns in 2002 and 2004 and assigned to residential addresses in 1982. Cox regression was used to estimate relationships between each VOC and non-accidental, cardiovascular, and cancer mortality. Positive associations were observed for each VOC. In multi-pollutant models the benzene and total hydrocarbon signals were strongest for cancer. The hazard ratio for cancer that corresponded to an increase in the interquartile range of benzene (0.13 μg/m 3 ) was 1.06 (95% CI = 1.02–1.11). Our findings suggest ambient concentrations of VOCs were associated with cancer mortality, and that these exposures did not confound our previously reported associations between NO 2 and cardiovascular mortality. -- Highlights: ► We studied associations between long-term exposure to volatile organic compounds and mortality. ► The study was a population-based cohort of Toronto adults followed for up to 22 years. ► We used land-use regression estimates of benzene, total hydrocarbons and n-hexane. ► Benzene and total hydrocarbons were positively associated with cancer mortality. ► VOCs did not confound associations between NO 2 and cardiovascular mortality. -- Long-term exposure to ambient benzene was associated with non-accidental and cancer causes of death, and did not attenuate associations between NO 2 and cardiovascular mortality

A Census of Midsize to Large Supermarkets in Toronto: A Cross-Sectional Analysis of the Consumer Nutrition Environment.

Science.gov (United States)

Camden, Andi; Levy, Jennifer; Bassil, Kate; Vanderlinden, Loren; Barnett, Olanna White; Minaker, Leia M; Mulligan, Kate; Campbell, Monica

2018-02-26

Assess the consumer nutrition environment in midsize to large supermarkets by supermarket type and area-level socioeconomic variables. Cross-sectional census of 257 supermarkets using the Toronto Nutrition Environment Measures Survey in Stores. Toronto, Canada. Availability; price and linear shelf space of fruits and vegetables vs energy-dense snack foods by supermarket type; after-tax, low-income measure; and neighborhood improvement area. Multivariate linear regression. There was a high availability of fruits (7.7 of 8) and vegetables (9.5 of 11). There was similar linear shelf space for fruits and vegetables vs energy-dense snack foods (ratio, 1.1 m). Adjusted fruit prices were lowest in quintiles 1 (β = -$1.30; P = .008), 2 (β = -$1.41; P = .005), and 3 (β = -$1.89; P discount stores (β = -$5.64; P discount (β = -$5.49; P discount (β = -$1.16; P < .001) and higher in other stores (β = + $0.67; P < .001) vs conventional. Findings do not indicate inequities in shelf space, availability, or price across diverse neighborhoods. Practitioners can use findings to help consumers navigate supermarkets to make healthy choices. Copyright © 2017 Society for Nutrition Education and Behavior. Published by Elsevier Inc. All rights reserved.

Upgrade plan for HANARO control computer system

International Nuclear Information System (INIS)

Kim, Min Jin; Kim, Young Ki; Jung, Hwan Sung; Choi, Young San; Woo, Jong Sub; Jun, Byung Jin

2001-01-01

A microprocessor based digital control system, the Multi-Loop Controller (MLC), which was chosen to control HANARO, was introduced to the market in early '80s and it had been used to control petrochemical plant, paper mill and Slowpoke reactor in Canada. Due to the development in computer technology, it has become so outdated model and the production of this model was discontinued a few years ago. Hence difficulty in acquiring the spare parts is expected. To achieve stable reactor control during its lifetime and to avoid possible technical dependency to the manufacturer, a long-term replacement plan for HANARO control computer system is on its way. The plan will include a few steps in its process. This paper briefly introduces the methods of implementation of the process and discusses the engineering activities of the plan

Cobalt-60 production in CANDU power reactors

International Nuclear Information System (INIS)

Slack, J.; Norton, J.L.; Malkoske, G.R.

2003-01-01

therapy machines. Today the majority of the cancer therapy cobalt-60 sources used in the world are manufactured using material from the NRU reactor in Chalk River. The same technology that was used for producing cobalt-60 in a research reactor was then adapted and transferred for use in a CANDU power reactor. In the early 1970s, in co-operation with Ontario Power Generation (formerly Ontario Hydro), bulk cobalt-60 production was initiated in the four Pickering A CANDU reactors located east of Toronto. This was the first full scale production of millions of curies of cobalt-60 per year. As the demand and acceptance of sterilization of medical products grew, MDS Nordion expanded its bulk supply by installing the proprietary Canadian technology in additional CANDUs. Over the years MDS Nordion has partnered with CANDU reactor owners to produce cobalt-60 at various sites. CANDU reactors that have, or are still producing cobalt-60, include Pickering A, Pickering B, Gentilly 2, Embalse in Argentina, and Bruce B. In conclusion, the technology for cobalt-60 production in CANDU reactors, designed and developed by MDS Nordion and Atomic Energy of Canada, has been safely, economically and successfully employed in CANDU reactors with over 195 reactor years of production. Today over forty percent of the world's disposable medical supplies are made safer through sterilization using cobalt-60 sources from MDS Nordion. Over the past 40 years, MDS Nordion with its CANDU reactor owner partners, has safely and reliably shipped more than 500 million curies of cobalt-60 sources to customers around the world. MDS Nordion is presently adding three more CANDU power reactors to its supply chain. These three additional cobalt producing CANDU's will help supplement the ability of the health care industry to provide safe, sterile, medical disposable products to people around the world. As new applications for cobalt-60 are identified, and the demand for bulk cobalt-60 increases, MDS Nordion and AECL

Mixed Field Modification of Thermally Cured Castor Oil Based Polyurethanes

International Nuclear Information System (INIS)

Mortley, A.

2006-01-01

Thermally cured polyurethanes were prepared from castor oil and hexamethylene diisocyanatee (HMDI). Due to the long aliphatic chain of the castor oil component of polyurethane, thermal curing of castor oil based polyurethane (COPU) is limited by increasing polymer viscosity. To enhance further crosslinking, COPUs were subjected to a range of accumulated doses (0.0-3.0 MGy) produced by the mixed ionizing field of the SLOWPOKE-2 research reactor. The physico-mechanical properties of COPU, unirradiated and irradiated, were characterized by mechanical tests. Increased bond formation resulting from radiation-induced crosslinking was confirmed by favorable increases in mechanical properties and by solid-state 13 C -NMR and FTIR spectra

New opportunities from nuclear R and D

International Nuclear Information System (INIS)

Hart, R.G.

1984-01-01

The author presents a new initiative within Atomic Energy of Canada Ltd. (AECL), the intention to look for spin-off business opportunities from main-line research and development. In 1982 AECL began encouraging ideas for spin-off applications. Some problems were encountered: the reluctance of staff to divert attention from the CANDU program; resource allocation; difficulties in getting market input; and difficulties in deciding what to license and what to retain as an in-house business opportunity. Successes have come in the areas of using CANDU technology in LWRs, SLOWPOKE reactors, industrial accelerators, stable isotope production, intelligent sensing systems, and deuterated lucite for fibre optics. (L.L.)

University of Toronto Instructors’ Experiences with Developing MOOCs

Directory of Open Access Journals (Sweden)

Hedieh Najafi

2015-06-01

Full Text Available We interviewed eight University of Toronto (U of T instructors who have offered MOOCs on Coursera or EdX between 2012 and 2014 to understand their motivation for MOOC instruction, their experience developing and teaching MOOCs, and their perceptions of the implications of MOOC instruction on their teaching and research practices. Through inductive analysis, we gleaned common motivations for MOOC development, including expanding public access to high quality learning resources, showcasing U of T teaching practices, and attempting to engage MOOC learners in application of concepts learned, even in the face of constraints that may inhibit active learning in MOOC contexts. MOOC design and delivery was a team effort with ample emphasis on planning and clarity. Instructors valued U of T instructional support in promoting systematic MOOC design and facilitating technical issues related to MOOC platforms. The evolution of MOOC support at U of T grew from a focus on addressing technical issues, to instructional design of MOOCs driven, first, by desired learning outcomes. Findings include changes in teaching practices of the MOOC instructors as they revised pedagogical practices in their credit courses by increasing opportunities for active learning and using MOOC resources to subsequently flip their classrooms. This study addresses the paucity of research on faculty experiences with developing MOOCs, which can subsequently inform the design of new forms of MOOC-like initiatives to increase public access to high quality learning resources, including those available through U of T.

Generation X School Leaders as Agents of Care: Leader and Teacher Perspectives from Toronto, New York City and London

OpenAIRE

Edge, K. E.; Descours, K.; Frayman, K.

2016-01-01

This paper draws on evidence from our three-year Economic and Social Research Council (ESRC)-funded research study of the lives, careers, experiences and aspirations of Generation X (under 40 years of age) principals and vice-principals in London, New York City, and Toronto. More specifically, the paper examines interview evidence from nine school-based studies in which nine leaders and 54 teachers discuss their perspectives on leaders’ care of their staff members. The evidence demonstrates t...

Toronto Civic Workers Bargaining Without a Base: The Significance of 2012

Directory of Open Access Journals (Sweden)

Carlo Fanelli

2014-05-01

Full Text Available This article explores how the politics and economics of austerity has influenced collective bargaining between the CUPE Locals 79/416 and the city of Toronto. I explore the relationship between neoliberalism and workplace precarity, drawing attention to the importance of the municipal public sector to trade unionism and the political potential of urbanized Left-labour radicalism. Following this, I provide an overview of the repeated attempts by City Council to extract concessions from unionized workers with a focus on the concession-filled 2012 round of bargaining and its relationship to earlier rounds. In what follows I discuss the implications of austerity bargaining for Locals 79 and 416 members, drawing attention to the repercussions this may have for other public sector workers. To conclude, I propose an alternative political strategy for municipal public sector unions, stressing the importance of a radicalized labour approach. It is my contention that this requires the development of both alternative policies and an alternative politics rooted in demands for workplace democracy and social justice.

Racial/ethnic variations in the main and buffering effects of ethnic and nonethnic supports on depressive symptoms among five ethnic immigrant groups in Toronto.

Science.gov (United States)

Kim, Il-Ho; Noh, Samuel

2016-01-01

This study examined variations in the main and buffering effects of ethnic and nonethnic social support on depressive symptoms associated with discrimination among five immigrant groups in Toronto. Data were taken from the Toronto Study of Settlement and Health, a cross-sectional survey of adult immigrants from five ethnic communities (Vietnamese, Ethiopian, Iranian, Korean, and Irish) in Toronto. A total of 900 surveys were collected through face-to-face interviews conducted between April and September 2001. Significant ethnic variations were observed in the effects of both ethnic and nonethnic social supports on discrimination-related depressive symptoms. Regarding the main effect, ethnic social support was significantly stronger for Iranian, Ethiopian, and Korean immigrants than for Irish immigrants. The benefits of nonethnic support were stronger for Iranian immigrants compared to the effect found in the Irish sample. With respect to stress-buffering or stress-moderating effects of social support, ethnic support was significant in all ethnic groups, except the Vietnamese group. Nonethnic support aggravated the negative impact of discrimination on depressive symptoms in the Irish group, but exerted a stress-buffering effect in the Iranian group. Overall, social supports received from fellow ethnic group members had significant main effects (suppressing depressive symptoms) and stress-buffering effects and were most pronounced in the minority ethnic immigrant groups of Ethiopians, Koreans, and Iranians. The effects were least evident among the Vietnamese and Irish. Evidence for the stress-suppressing and stress-buffering role of cross-ethnic group supports was unclear, and even inverted among Irish immigrants. Empirical evidence from the current study seems to support the sociocultural similarity hypothesis of social support.

Bringing hope and change: a study of youth probation officers in Toronto.

Science.gov (United States)

Umamaheswar, Janani

2013-09-01

Although youth probation (in some countries described as youth justice or youth offending work) has been widely discussed in older and more recent criminological literature, less attention has been paid to youth probation officers' accounts of their attitudes and strategies. In this study, the author uses in-depth interviews with 20 youth probation officers in Toronto, examining officers' attitudes toward the youth they work with and how these attitudes are reflected in the strategies that the officers use to achieve their professional goals. Findings reveal that the officers balance their authoritative and supportive roles not only to hold youth accountable, to encourage them to assert control over their lives, and to maintain optimism about the possibility of a nondeviant life, but also to assist the youth in attaining the means and resources necessary to make positive changes. These findings are interpreted within the framework of Canadian youth justice legislation as well as the broader desistance literature.

Characterizing the spatial distribution of ambient ultrafine particles in Toronto, Canada: A land use regression model.

Science.gov (United States)

Weichenthal, Scott; Van Ryswyk, Keith; Goldstein, Alon; Shekarrizfard, Maryam; Hatzopoulou, Marianne

2016-01-01

Exposure models are needed to evaluate the chronic health effects of ambient ultrafine particles (bus routes as well as variables for the number of on-street trees, parks, open space, and the length of bus routes within a 100 m buffer. There was no systematic difference between measured and predicted values when the model was evaluated in an external dataset, although the R(2) value decreased (R(2) = 50%). This model will be used to evaluate the chronic health effects of UFPs using population-based cohorts in the Toronto area. Crown Copyright © 2015. Published by Elsevier Ltd. All rights reserved.

The case of Iranian immigrants in the greater Toronto area: a qualitative study

Directory of Open Access Journals (Sweden)

Dastjerdi Mahdieh

2012-02-01

Full Text Available Abstract Introduction Iranians comprise an immigrant group that has a very different cultural background from that of the mainstream Canadian population and speaks a language other than English or French; in this case mainly Farsi (Persian. Although Iranian immigrants in Toronto receive a high proportion of care from Farsi-speaking family physicians and health care providers than physicians who cannot speak Farsi, they are still not satisfied with the provided services. The purpose of this study was to identify the obstacles and issues Iranian immigrants faced in accessing health care services as seen through the eyes of Iranian health care professionals/providers and social workers working in Greater Toronto Area, Canada. Methods Narrative inquiry was used to capture and understand the obstacles this immigrant population faces when accessing health care services, through the lens of fifty Iranian health care professionals/providers and social workers. Thirty three health care professionals and five social workers were interviewed. To capture the essence of issues, individual interviews were followed by three focus groups consisting of three health care professionals and one social worker in each group. Results Three major themes emerged from the study: language barrier and the lack of knowledge of Canadian health care services/systems; lack of trust in Canadian health care services due to financial limitations and fear of disclosure; and somatization and needs for psychological supports. Conclusion Iranians may not be satisfied with the Canadian health care services due to a lack of knowledge of the system, as well as cultural differences when seeking care, such as fear of disclosure, discrimination, and mistrust of primary care. To attain equitable, adequate, and effective access to health care services, immigrants need to be educated and informed about the Canadian health care system and services it provides. It would be of great benefit to

Psychometric Properties of the 20-Item Toronto Alexithymia Scale in the Chilean Population

Directory of Open Access Journals (Sweden)

Mauricio González-Arias

2018-06-01

Full Text Available Alexithymia can be defined as inability to identify and describe emotions in the self. Has shown to be related to several psychological and pathological processes that can result in unsatisfactory interpersonal relationships and decreased social adjustment. Advances in research of alexithymia require the development and validation of assessment instruments, and its application to different population. With this aim, we studied the psychometric properties of the Twenty-Item Toronto Alexithymia Scale (TAS-20 in Chilean population using various modeling procedures (e.g., CFA, ESEM in different structures (i.e., Correlated, Unidimensional, Hierarchical or Wording factors. Among the 10 models tested, the four-dimensional structure offered the best fit but with item-loading problems in the last factor (Pragmatic Thinking. We suggest that the studied version of the scale needs improvement (theoretical and empirical to ensure optimal indices of validation for Chilean population.

The gentle giants of healing

International Nuclear Information System (INIS)

Legault, B.

1989-01-01

Nuclear medicine, radiation therapy, and medical radioisotope production are explained at a popular level, for the non-specialist. Nuclear medicine in Canada uses either Positron emission tomography (PET), or single photon emission computerized tomography (SPECT). PET is used at the Montreal Neurological Institute to study epilepsy, brain tumours, stroke, or arterio-venous malformations. The much cheaper SPECT technique does many of the things that PET will do, and may eventually replace it to a considerable extent. This article features the manufacture of radioisotopes by Nordion Ltd., formerly known as AECL Radiochemical Co. Nordion supplies more than 20 isotopes, including about 80% of the world demand for 60 Co, and 70% of all reactor isotopes, including the medically important 99 Tc(m), 125 I and 201 Tl. Also featured is the intended acquisition (now cancelled) by Sherbrooke University of a 10-MW Slowpoke heating and isotope production reactor

``How am I going to work?'' Barriers to employment for immigrant Latinos and Latinas living with HIV in Toronto.

Science.gov (United States)

Serrano, Angel

2015-06-05

For individuals with HIV positive status, multiple barriers exist to accessing and re-entering employment. Studies on employment for people living with HIV lack a detailed consideration of race and ethnicity. This is the first article that focuses on barriers to employment for the HIV positive Latino community in the Canadian context. To document the barriers that a sample of HIV positive Latinos and Latinas encounter in finding and maintaining employment in Toronto. A non-probability sample of immigrant and refugee Latino men and women living with HIV/AIDS in Toronto participated in in-depth interviews concerning their experiences in the labor market, emphasizing the barriers that they have faced in access to employment. Interviews were audio recorded, transcribed and later analysed with NVivo 9. Two sets of barriers emerged from the analysis: structural barriers that immigrants encounter in access to employment, such as language difficulties, lack of Canadian work experience and anti-immigrant feelings and barriers to employment for HIV positive individuals, principally HIV related stigma and health related issues. Due to their intersectional identities as immigrants/refugees and HIV positive individuals, participants face compounded barriers to employment: Language difficulties, lack of migrant status and Canadian work experience, anti-immigrant sentiments in the labor market, ageism, HIV related stigma and side effects of medications among other barriers related with an HIV positive condition. Such barriers locate participants in a marginalized position in Canadian society.

MMRW-BOOKS, Legacy books on slowing down, thermalization, particle transport theory, random processes in reactors

International Nuclear Information System (INIS)

Williams, M.M.R.

2007-01-01

Description: Prof. M.M..R Williams has now released three of his legacy books for free distribution: 1 - M.M.R. Williams: The Slowing Down and Thermalization of Neutrons, North-Holland Publishing Company - Amsterdam, 582 pages, 1966. Content: Part I - The Thermal Energy Region: 1. Introduction and Historical Review, 2. The Scattering Kernel, 3. Neutron Thermalization in an Infinite Homogeneous Medium, 4. Neutron Thermalization in Finite Media, 5. The Spatial Dependence of the Energy Spectrum, 6. Reactor Cell Calculations, 7. Synthetic Scattering Kernels. Part II - The Slowing Down Region: 8. Scattering Kernels in the Slowing Down Region, 9. Neutron Slowing Down in an Infinite Homogeneous Medium, 10.Neutron Slowing Down and Diffusion. 2 - M.M.R. Williams: Mathematical Methods in Particle Transport Theory, Butterworths, London, 430 pages, 1971. Content: 1 The General Problem of Particle Transport, 2 The Boltzmann Equation for Gas Atoms and Neutrons, 3 Boundary Conditions, 4 Scattering Kernels, 5 Some Basic Problems in Neutron Transport and Rarefied Gas Dynamics, 6 The Integral Form of the Transport Equation in Plane, Spherical and Cylindrical Geometries, 7 Exact Solutions of Model Problems, 8 Eigenvalue Problems in Transport Theory, 9 Collision Probability Methods, 10 Variational Methods, 11 Polynomial Approximations. 3 - M.M.R. Williams: Random Processes in Nuclear Reactors, Pergamon Press Oxford New York Toronto Sydney, 243 pages, 1974. Content: 1. Historical Survey and General Discussion, 2. Introductory Mathematical Treatment, 3. Applications of the General Theory, 4. Practical Applications of the Probability Distribution, 5. The Langevin Technique, 6. Point Model Power Reactor Noise, 7. The Spatial Variation of Reactor Noise, 8. Random Phenomena in Heterogeneous Reactor Systems, 9. Associated Fluctuation Problems, Appendix: Noise Equivalent Sources. Note to the user: Prof. M.M.R Williams owns the copyright of these books and he authorises the OECD/NEA Data Bank

An examination of the time-dependent background counts of the delayed neutron counting system at the Royal Military College of Canada

International Nuclear Information System (INIS)

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

2011-01-01

A delayed neutron counting (DNC) system for the analysis of special nuclear materials (SNM) has been constructed and calibrated at the Royal Military College of Canada. The polyethylene vials used to transport SNM samples have been found to contribute a time-dependent count rate, B(t), far above the system background. B(t) has been found to be independent of polyethylene mass and shows a dependence on irradiation position in the SLOWPOKE-2 reactor and irradiation time. A comparison of B(t) and the theoretical delayed neutron production from the fission of small amounts of 235 U has indicated that trace amounts of uranium may be present in the DNC system tubing. (author)

Toronto Alexithymia Scale: Adaptation of the Brazilian Version to Low-Educated Adults

Directory of Open Access Journals (Sweden)

Tatiana Roccato Fortes

Full Text Available Abstract: For the purpose of studying Alexithymia in low-educated adults, we intend to adapt the Brazilian version of the Toronto Alexithymia Scale (TAS-26 and to verify its internal consistency. With that aim, we translated the original TAS-26 (English to Portuguese, adopting a colloquial language, without content distortion. An exploratory qualitative study interviewed 50 women (38-65 years, education <9 years and identified comprehension difficulties in 22 items, that needed adaptation. A professional translator performed the back-translation of the adapted TAS-26, that was applied to a new sample of women (90 with chronical pain and 90 without pain, 38-65 years, education <9 years to evaluate its internal consistency. Only four items (1/2/3/16 of the pre-existing Brazilian version (appropriate to university students did not require modification. The internal consistency (Cronbach’s alpha was satisfactory for total score (0.65 and elevated for factor 1 (0.87. The adapted Brazilian version of TAS-26 is appropriate to low-educated adults.

Risk factors for SARS transmission from patients requiring intubation: a multicentre investigation in Toronto, Canada.

Directory of Open Access Journals (Sweden)

Janet Raboud

Full Text Available BACKGROUND: In the 2003 Toronto SARS outbreak, SARS-CoV was transmitted in hospitals despite adherence to infection control procedures. Considerable controversy resulted regarding which procedures and behaviours were associated with the greatest risk of SARS-CoV transmission. METHODS: A retrospective cohort study was conducted to identify risk factors for transmission of SARS-CoV during intubation from laboratory confirmed SARS patients to HCWs involved in their care. All SARS patients requiring intubation during the Toronto outbreak were identified. All HCWs who provided care to intubated SARS patients during treatment or transportation and who entered a patient room or had direct patient contact from 24 hours before to 4 hours after intubation were eligible for this study. Data was collected on patients by chart review and on HCWs by interviewer-administered questionnaire. Generalized estimating equation (GEE logistic regression models and classification and regression trees (CART were used to identify risk factors for SARS transmission. RESULTS: 45 laboratory-confirmed intubated SARS patients were identified. Of the 697 HCWs involved in their care, 624 (90% participated in the study. SARS-CoV was transmitted to 26 HCWs from 7 patients; 21 HCWs were infected by 3 patients. In multivariate GEE logistic regression models, presence in the room during fiberoptic intubation (OR = 2.79, p = .004 or ECG (OR = 3.52, p = .002, unprotected eye contact with secretions (OR = 7.34, p = .001, patient APACHE II score > or = 20 (OR = 17.05, p = .009 and patient Pa0(2/Fi0(2 ratio < or = 59 (OR = 8.65, p = .001 were associated with increased risk of transmission of SARS-CoV. In CART analyses, the four covariates which explained the greatest amount of variation in SARS-CoV transmission were covariates representing individual patients. CONCLUSION: Close contact with the airway of severely ill patients and failure of infection control practices to prevent exposure

Toronto Hydro-Electric System Limited, 2010 asset condition assessment audit

Energy Technology Data Exchange (ETDEWEB)

Lotho, K.; Wang, F. [Kinectrics Inc., Toronto, ON (Canada)

2010-07-15

Toronto Hydro-Electric System Limited (THESL) has long been devoted to the enhancement of its asset management program. In 2006, Kinectrics Incorporated (Kinectrics) performed a full asset condition assessment (ACA) for important distribution assets. Subsequently, THESL made efforts to follow the recommendations given by the 2006 ACA and to enhance the quality of its asset condition data. THESL also created an application that measures the health indices of assets based on current and best available inspection data. In 2009, THESL performed a new ACA with this health index calculator. Kinectrics was requested to evaluate the improvement achieved by THESL between 2006 and 2009, and to compare the results obtained from the two ACA performed. An examination of the changes and ACA results between 2009 and 2010 has been conducted by Kinectrics. The Kinectrics findings were reported into the 2010 asset condition assessment audit report. The Health Index (HI) formulation and the results obtained between 2009 and 2010 were examined for twenty-one asset categories. The health index formulation including condition parameters, condition parameter weights and condition criteria, the granularity within the asset category, the percentage of the population presenting sufficient condition data and the health index classification distribution were compared for each one of the asset categories between 2009 and 2010. This report provides recommendations to facilitate future improvements.

The epidemiology of sexually transmitted co-infections in HIV-positive and HIV-negative African-Caribbean women in Toronto.

Science.gov (United States)

Remis, Robert S; Liu, Juan; Loutfy, Mona; Tharao, Wangari; Rebbapragada, Anuradha; Perusini, Stephen J; Chieza, Lisungu; Saunders, Megan; Green-Walker, LoriAnn; Kaul, Rupert

2013-11-17

HIV disproportionately affects African-Caribbean women in Canada but the frequency and distribution of sexually transmitted infections in this community have not been previously studied. We recruited women based on HIV status through a Toronto community health centre. Participants completed a socio-behavioural questionnaire using Audio Computer Assisted Self-Interview (ACASI) and provided blood for syphilis, HIV, hepatitis B and C, herpes simplex virus type 1 (HSV-1), herpes simplex virus type 2 (HSV-2), and human cytomegalovirus (CMV) serology, urine for chlamydia and gonorrhea molecular testing and vaginal secretions for bacterial vaginosis (BV) and human papillomavirus (HPV). Differences in prevalence were assessed for statistical significance using chi-square. We recruited 126 HIV-positive and 291 HIV-negative women, with a median age of 40 and 31 years, respectively (p history of HBV vaccination (66.1% vs. 44.0%, p = 0.0001). Classical STIs were rare in both groups; BV prevalence was low and did not vary by HIV status. HSV-2 infection was markedly more frequent in HIV-positive (86.3%) than HIV-negative (46.6%) women (p < 0.0001). Vaginal HPV infection was also more common in HIV-positive than in HIV-negative women (50.8% vs. 22.6%, p < 0.0001) as was infection with high-risk oncogenic HPV types (48.4% vs. 17.3%, p < 0.0001). Classical STIs were infrequent in this clinic-based population of African-Caribbean women in Toronto. However, HSV-2 prevalence was higher than that reported in previous studies in the general Canadian population and was strongly associated with HIV infection, as was infection with hepatitis B and HPV.

Weather sensitivity for zoo visitation in Toronto, Canada: a quantitative analysis of historical data

Science.gov (United States)

Hewer, Micah J.; Gough, William A.

2016-11-01

Based on a case study of the Toronto Zoo (Canada), multivariate regression analysis, involving both climatic and social variables, was employed to assess the relationship between daily weather and visitation. Zoo visitation was most sensitive to weather variability during the shoulder season, followed by the off-season and, then, the peak season. Temperature was the most influential weather variable in relation to zoo visitation, followed by precipitation and, then, wind speed. The intensity and direction of the social and climatic variables varied between seasons. Temperatures exceeding 26 °C during the shoulder season and 28 °C during the peak season suggested a behavioural threshold associated with zoo visitation, with conditions becoming too warm for certain segments of the zoo visitor market, causing visitor numbers to decline. Even light amounts of precipitation caused average visitor numbers to decline by nearly 50 %. Increasing wind speeds also demonstrated a negative influence on zoo visitation.

“We don't exist”: a qualitative study of marginalization experienced by HIV-positive lesbian, bisexual, queer and transgender women in Toronto, Canada

OpenAIRE

Logie, Carmen H; James, LLana; Tharao, Wangari; Loutfy, Mona R

2012-01-01

Background: Lesbian, bisexual, queer and transgender (LBQT) women living with HIV have been described as invisible and understudied. Yet, social and structural contexts of violence and discrimination exacerbate the risk of HIV infection among LBQT women. The study objective was to explore challenges in daily life and experiences of accessing HIV services among HIV-positive LBQT women in Toronto, Canada. Methods: We used a community-based qualitative approach guided by an intersectional theore...

Year in review: 1993

International Nuclear Information System (INIS)

Reid, J.M.

1994-01-01

This review of the year includes mention of the following subjects: The good performance of CANDU reactors worldwide (especially Point Lepreau and Wolsung-1); Permission granted to proceed with four new uranium projects in Saskatchewan; Failure of a suit brought by Energy Probe, the City of Toronto and Roslie Bertell claiming unconstitutionality of the Nuclear Liability Act; The International Nuclear Congress (INC93) in Toronto, and other conferences; Consultations with the Government of Canada regarding license fees to be charged by the AECB, and also consultations regarding the environment and other matters

Mental health of South Asian youth in Peel Region, Toronto, Canada: a qualitative study of determinants, coping strategies and service access

Science.gov (United States)

Multani, Amanpreet; Hynie, Michaela; Shakya, Yogendra; McKenzie, Kwame

2017-01-01

Objectives This qualitative study set out to understand the mental health challenges and service access barriers experienced by South Asian youth populations in the Peel Region of Toronto, Canada. Setting In-depth semistructured interviews were carried out with South Asian youth living in Peel Region (Mississauga, Brampton and Caledon), a suburb of Toronto, Canada, home to over 50% of Ontario’s South Asian population. Participants South Asian youth (n=10) engaged in thoughtful, candid dialogue about their mental health and service access barriers. Primary and secondary outcome measures Qualitative interview themes related to mental health stressors and mental health service access barriers experienced by youth living in Peel Region were assessed using thematic analysis. Results South Asian youth face many mental health stressors, from intergenerational and cultural conflict, academic pressure, relationship stress, financial stress and family difficulties. These stressors can contribute to mental health challenges, such as depression and anxiety and drug use, with marijuana, alcohol and cigarettes cited as the most popular substances. South Asian youth were only able to identify about a third (36%) of the mental health resources presented to them and did not feel well informed about mental health resources available in their neighbourhood. Conclusions They offered recommendations for improved youth support directed at parents, education system, South Asian community and mental health system. Institutions and bodies at all levels of the society have a role to play in ensuring the mental health of South Asian youth. PMID:29101148

Association between neighbourhood walkability and metabolic risk factors influenced by physical activity: a cross-sectional study of adults in Toronto, Canada.

Science.gov (United States)

Loo, C K Jennifer; Greiver, Michelle; Aliarzadeh, Babak; Lewis, Daniel

2017-04-08

To determine whether neighbourhood walkability is associated with clinical measures of obesity, hypertension, diabetes and dyslipidaemia in an urban adult population. Observational cross-sectional study. Urban primary care patients. 78 023 Toronto residents, aged 18 years and over, who were formally rostered or had at least 2 visits between 2012 and 2014 with a primary care physician participating in the University of Toronto Practice Based Research Network (UTOPIAN), within the Canadian Primary Care Sentinel Surveillance Network (CPCSSN). Differences in average body mass index (BMI), systolic and diastolic blood pressure, fasting blood glucose, haemoglobin A1c (HbA1C), total cholesterol, high-density lipoprotein (HDL), low-density lipoprotein and triglyceride between residents in the highest versus the lowest quartile of neighbourhood walkability, as estimated using multivariable linear regression models and stratified by age. Outcomes were objectively measured and were retrieved from primary care electronic medical records. Models adjusted for age, sex, smoking, medications, medical comorbidities and indices of neighbourhood safety and marginalisation. Compared with those in the lowest walkability quartile, individuals in the highest quartile had lower mean BMI (-2.64 kg/m 2 , 95% CI -2.98 to -2.30; pwalkable neighbourhoods and having lower BMI in adults of all ages. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

Inauguration of Cogen Plant ensures self-sustainability for Toronto Airport

International Nuclear Information System (INIS)

Anon.

2006-01-01

Details of a new cogeneration plant for Pearson International Airport were presented. The plant was installed to ensure that the airport will be self-sufficient with its own uninterrupted power supply, and will also provide steam for the airport's heating and cooling. The plant generated its first power onto the grid in August 2005. The 18,000 sq. foot cogeneration facility cost an estimated $140 million to build and is capable of supplying the airport with 117 MW of power. Power for the plant comes from 2 natural gas turbines, with an additional 33 MW generated by exhaust from the gas turbines passing through once-through steam generators producing steam for a third steam-driven generator. The remaining excess heat from the plant is used to heat and cool the airport buildings through a central utilities distribution system. Natural gas fueled cogeneration plants are considered to be clean energy, and it is anticipated that the plant will lessen the environmental impacts of the airport. Currently, the airport's peak electrical demand is approximately 38 MW of electricity, which is expected to peak at 65 to 70 MW in 2015. The surplus electricity produced at the cogeneration plant will be sold back into Ontario's power grid via the Clean Energy Supply contract. It was concluded that in addition to its environmental benefits, the plant will help to enhance electricity supply in the Greater Toronto Area (GTA)

Vanadium levels in marine organisms of Onagawa Bay in Japan

International Nuclear Information System (INIS)

Fukushima, M.; Suzuki, H.; Saito, K.; Chatt, A.

2009-01-01

Vanadium in marine organisms from Onagawa Bay in Miyagi, Japan, was determined by an instrumental neutron activation analysis (INAA) method using anticoincidence gamma-ray spectrometry at the Dalhousie University SLOWPOKE-2 Reactor (DUSR) facility in Canada. Seaweeds, cultivated oysters, plankton, and four different species of sea squirt were collected from Onagawa Bay during 2005-2008. Vanadium levels around 20 μg g -1 (dry weight) were found in Japanese tangle and hijiki seaweeds. One species of sea squirt (Ciona savignyi) contained 160-500 ppm of V and it was highest among the four species of sea squirts studied. Protein-bound V species were separated by gel permeation chromatography (GPC) and the element determined by inductively coupled plasma atomic emission spectrometry (ICP-AES). (author)

Investigation into the application of polyetherimide to nuclear waste storage containers

Energy Technology Data Exchange (ETDEWEB)

Saboui, Y.; Bonin, H.W.; Bui, V.T. [Royal Military College of Canada, Kingston, Ontario (Canada)

2009-07-01

The procedure of the analysis of the effects of irradiation on the mechanical and chemical properties of the polyetherimide (PEI) is outlined. Previous research in this field at the Royal Military College of Canada is presented. Samples of PEI will be exposed to a mixed radiation field, in the pool of a SLOWPOKE-2 nuclear reactor, then changes in mechanical properties, degradation product formation, and physical property changes will be assessed. Additionally, the heat transfer in the sample will be calculated in order to model the heat transfer rate and heat diffusion profile of PEI. The purpose of the proposed research is to determine the feasibility of using PEI for spent CANDU nuclear fuel and nuclear waste storage containers. (author)

Investigation into the application of polyetherimide to nuclear waste storage containers

Energy Technology Data Exchange (ETDEWEB)

Saboui, Y.; Bonin, H.W.; Bui, V.T. [Royal Military College, Kingston, Ontario (Canada)

2010-07-01

The procedure of the analysis of the effects of irradiation on the mechanical and chemical properties of the polyetherimide (PEI) is outlined. Previous research in this field at the Royal Military College of Canada is presented. Samples of PEI will be exposed to a mixed radiation field, in the pool of a SLOWPOKE-2 nuclear reactor, then changes in mechanical properties, degradation product formation, and physical property changes will be assessed. Additionally, the heat transfer in the sample will be calculated in order to model the heat transfer rate and heat diffusion profile of PEI. The purpose of the proposed research is to determine the feasibility of using PEI for spent CANDU nuclear fuel and nuclear waste storage containers. (author)

Investigation into the application of polyetherimide to nuclear waste storage containers

International Nuclear Information System (INIS)

Saboui, Y.; Bonin, H.W.; Bui, V.T.

2009-01-01

The procedure of the analysis of the effects of irradiation on the mechanical and chemical properties of the polyetherimide (PEI) is outlined. Previous research in this field at the Royal Military College of Canada is presented. Samples of PEI will be exposed to a mixed radiation field, in the pool of a SLOWPOKE-2 nuclear reactor, then changes in mechanical properties, degradation product formation, and physical property changes will be assessed. Additionally, the heat transfer in the sample will be calculated in order to model the heat transfer rate and heat diffusion profile of PEI. The purpose of the proposed research is to determine the feasibility of using PEI for spent CANDU nuclear fuel and nuclear waste storage containers. (author)

Race relations and racism in the LGBTQ community of Toronto: perceptions of gay and queer social service providers of color.

Science.gov (United States)

Giwa, Sulaimon; Greensmith, Cameron

2012-01-01

This article explores race relations and racism within the lesbian, gay, bisexual, transgender, and queer (LGBTQ) community of Toronto, Ontario, from the perspective of seven gay/queer social service providers of color. Social constructions of race, race relations, and racism were placed at the centre of analysis. Employing interpretive phenomenological analysis, findings indicated that intergroup and broader systemic racism infiltrates the LGBTQ community, rendering invisible the lived experiences of many LGBTQ people of color. The study contributes to a growing body of research concerning our understanding of factors underpinning social discrimination in a contemporary Canadian LGBTQ context.

Award of merit: transportable remediation unit -Jacques Whitford Environment Limited -Toronto

International Nuclear Information System (INIS)

Anon.

1995-01-01

A unique hybrid of remediation technologies was designed to deal with the problem of removing the gasoline and fuel-oil found in soils and groundwater as a result of spills or leakage at petroleum storage and dispensing facilities. Liquid petroleum hydrocarbons were found discharging into a creek in a residential and commercial neighborhood of Metropolitan Toronto. Numerous in-place soil and ground water remediation approaches were evaluated in the course of searching for a solution. A full-scale, transportable, in-situ bioslurping remediation unit was recommended. The unit was connected to 13 specially designed vertical bioslurping wells, and to a buried horizontal header network comprised of four separate zones that could be used to simultaneously extract and/or inject air and water flows. Cycling of various modes of operation was based on detailed monitoring and analysis, which allowed for optimal recovery and biological degradation of contaminants. After only four months of operation, over 4000 kg of petroleum hydrocarbon contaminants had been removed and treated, and all of the mobile liquid hydrocarbons at the water table had been removed. Treatment cost was estimated at $100 to $120 per tonne of contaminated soil, but assuming that the unit could be used at more than one site, the net treatment cost would decrease to $20 to $30 per tonne. 1 ill

Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

International Nuclear Information System (INIS)

Henry, A.F.

1980-01-01

Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

Reactor core in FBR type reactor

International Nuclear Information System (INIS)

Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

1989-01-01

In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

Developing a short version of the Toronto Structured Interview for Alexithymia using item response theory.

Science.gov (United States)

Sekely, Angela; Taylor, Graeme J; Bagby, R Michael

2018-03-17

The Toronto Structured Interview for Alexithymia (TSIA) was developed to provide a structured interview method for assessing alexithymia. One drawback of this instrument is the amount of time it takes to administer and score. The current study used item response theory (IRT) methods to analyze data from a large heterogeneous multi-language sample (N = 842) to investigate whether a subset of items could be selected to create a short version of the instrument. Samejima's (1969) graded response model was used to fit the item responses. Items providing maximum information were retained in the short model, resulting in the elimination of 12-items from the original 24-items. Despite the 50% reduction in the number of items, 65.22% of the information was retained. Further studies are needed to validate the short version. A short version of the TSIA is potentially of practical value to clinicians and researchers with time constraints. Copyright © 2018. Published by Elsevier B.V.

Working with Toronto neighbourhoods toward developing indicators of community capacity.

Science.gov (United States)

Jackson, Suzanne F; Cleverly, Shelley; Poland, Blake; Burman, David; Edwards, Richard; Robertson, Ann

2003-12-01

Often the goal of health and social development agencies is to assess communities and work with them to improve community capacity. Particularly for health promoters working in community settings and to ensure consistency in the definition of health promotion, the evaluation of health promotion programmes should be based on strengths and assets, yet existing information for planning and evaluation purposes usually focuses on problems and deficits. A model and definition of community capacity, grounded in community experience and focusing on strengths and assets, was developed following a 4-year, multi-site, qualitative, action research project in four Toronto neighbourhoods. There was significant community involvement in the four Community Advisory Committees, one for each study site. Semi-structured, open-ended interviews and focus groups were conducted with 161 residents and agency workers identified by the Community Advisory Committees. The data were analyzed with the assistance of NUDIST software. Thematic analysis was undertaken in two stages: (i) within each site and (ii) across sites, with the latter serving as the basis for the development of indicators of community capacity. This paper presents a summary of the research, the model and the proposed indicators. The model locates talents and skills of community members in a larger context of socioenvironmental conditions, both inside and outside the community, which can act to enable or constrain the expression of these talents and skills. The significance of the indicators of community capacity proposed in the study is that they focus on identifying and measuring the facilitating and constraining socioenvironmental conditions.

UNMIX Methods Applied to Characterize Sources of Volatile Organic Compounds in Toronto, Ontario

Directory of Open Access Journals (Sweden)

Eugeniusz Porada

2016-06-01

Full Text Available UNMIX, a sensor modeling routine from the U.S. Environmental Protection Agency (EPA, was used to model volatile organic compound (VOC receptors in four urban sites in Toronto, Ontario. VOC ambient concentration data acquired in 2000–2009 for 175 VOC species in four air quality monitoring stations were analyzed. UNMIX, by performing multiple modeling attempts upon varying VOC menus—while rejecting the results that were not reliable—allowed for discriminating sources by their most consistent chemical characteristics. The method assessed occurrences of VOCs in sources typical of the urban environment (traffic, evaporative emissions of fuels, banks of fugitive inert gases, industrial point sources (plastic-, polymer-, and metalworking manufactures, and in secondary sources (releases from water, sediments, and contaminated urban soil. The remote sensing and robust modeling used here produces chemical profiles of putative VOC sources that, if combined with known environmental fates of VOCs, can be used to assign physical sources’ shares of VOCs emissions into the atmosphere. This in turn provides a means of assessing the impact of environmental policies on one hand, and industrial activities on the other hand, on VOC air pollution.

Low-level tritium research facility for the University of Toronto Institute for Aerospace Studies

International Nuclear Information System (INIS)

Kherani, N.P.; Shmayda, W.T.

1984-06-01

The objective of the Low-level Tritium Research Facility for the University of Toronto Institute for Aerospace Studies (UTIAS) is to investigate tritium-material interactions and how they differ with respect to protium and deuterium. The tritium laboratory will also be employed to study tritium retention, tritium imaging, and the effect of tritium on diagnostic devices. This report is a preliminary design document of the UTIAS Low-Level Tritium Research Facility including the fundamentals of tritium, a description of the facility, tritium laboratory requirements and the safety analysis of the laboratory. The facility is designed to handle a total elemental tritium inventory of 10 Ci, though it will initially commence operation with 1 Ci and later increased to the maximum value. In the event of an instantaneous emission of the total tritium inventory within the laboratory, the working personnel would be exposed to an airborne tritium concentration less than the maximum permissible. Moreover, with all the safety features included in this design the likelihood of such an accident is very remote. Thus, the tritium laboratory design is intrinsically safe

Reactor core and initially loaded reactor core of nuclear reactor

International Nuclear Information System (INIS)

Koyama, Jun-ichi; Aoyama, Motoo.

1989-01-01

In BWR type reactors, improvement for the reactor shutdown margin is an important characteristic condition togehter with power distribution flattening . However, in the reactor core at high burnup degree, the reactor shutdown margin is different depending on the radial position of the reactor core. That is , the reactor shutdown margin is smaller in the outer peripheral region than in the central region of the reactor core. In view of the above, the reactor core is divided radially into a central region and as outer region. The amount of fissionable material of first fuel assemblies newly loaded in the outer region is made less than the amount of the fissionable material of second fuel assemblies newly loaded in the central region, to thereby improve the reactor shutdown margin in the outer region. Further, the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower portion of the first fuel assemblies is made smaller than the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower region of the second fuel assemblies, to thereby obtain a sufficient thermal margin in the central region. (K.M.)

Exploring opportunities for healthy aging among older persons with a history of homelessness in Toronto, Canada.

Science.gov (United States)

Waldbrook, Natalie

2015-03-01

Within the areas of literature on both population aging and health and homelessness, little attention has been given to the opportunities and barriers to healthy aging among older persons with a history of homelessness. Set in the context of inner-city Toronto, Canada, this article reports on the findings from qualitative interviews with 29 formerly homeless older persons. The findings illustrate participants' experiences of positive health change since moving into a stable housing environment and the aspects of housing they perceive to have improved their health and wellbeing. The qualitative findings also draw attention to the ongoing barriers to healthy aging that can be experienced among older persons with a history of homelessness. Overall, this study draws on the lived experiences of formerly homeless older persons to offer a better understanding of the long-term effects of homelessness on health, wellbeing, and aging. Copyright © 2015 Elsevier Ltd. All rights reserved.

Neutron radiography of aircraft composite flight control surfaces

International Nuclear Information System (INIS)

Lewis, W.J.; Bennett, L.G.I.; Chalovich, T.R.; Francescone, O.

2001-01-01

A small (20 kWth), safe, pool-type nuclear research reactor called the SLOWPOKE-2 is located at the Royal Military College of Canada (RMC). The reactor was originally installed for teaching, training, research and semi-routine analysis, specifically, neutron activation analysis. It was envisioned that the neutrons from the SLOWPOKE-2 could also be used for neutron radiography, and so a research program was initiated to develop this technology. Over a period of approximately 15 years, and through a series of successive modifications, a neutron radiography system (NRS) was developed. Once completed, several applications of the technology have been demonstrated, including the nondestructive examination of the composite flight control surfaces from the Canadian Air Force's primary jet fighter, the CF18 Hornet aircraft. An initial trial was setup to investigate the flight control surfaces of 3 aircraft, to determine the parameters for a final licensed system, and to compare the results to other nondestructive methods. Over 500 neutron radiographs were made for these first 3 aircraft, and moisture and corrosion were discovered in the honeycomb structure and hydration was found in the composite and adhesive layers. In comparison with other NDT methods, neutron radiography was the only method that could detect the small areas of corrosion and moisture entrapment. However, before examining an additional 7 aircraft, the recommended modifications to the NRS were undertaken. These modifications were necessary to accommodate the larger flight control surfaces safely by incorporating flexible conformable shielding. As well, to expedite inspections so that all flight control surfaces from one aircraft could be completed in less than two weeks, there was a need to decrease the exposure time by both faster film/conversion screen combinations and by incorporating the capability of near realtime, digital radioscopy. Finally, as there are no inspection specific image quality

Nuclear reactor physics course for reactor operators

International Nuclear Information System (INIS)

Baeten, P.

2006-01-01

The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' 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 aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

Reactor core of FBR type reactor

International Nuclear Information System (INIS)

Hayashi, Hideyuki; Ichimiya, Masakazu.

1994-01-01

A reactor core is a homogeneous reactor core divided into two regions of an inner reactor core region at the center and an outer reactor core region surrounding the outside of the inner reactor core region. In this case, the inner reactor core region has a lower plutonium enrichment degree and less amount of neutron leakage in the radial direction, and the outer reactor core region has higher plutonium enrichment degree and greater amount of neutron leakage in the radial direction. Moderator materials containing hydrogen are added only to the inner reactor core fuels in the inner reactor core region. Pins loaded with the fuels with addition of the moderator materials are inserted at a ratio of from 3 to 10% of the total number of the fuel pins. The moderator materials containing hydrogen comprise zirconium hydride, titanium hydride, or calcium hydride. With such a constitution, fluctuation of the power distribution in the radial direction along with burning is suppressed. In addition, an absolute value of the Doppler coefficient can be increased, and a temperature coefficient of coolants can be reduced. (I.N.)

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

Inspection of CF188 composite flight control surfaces with neutron radiography

International Nuclear Information System (INIS)

Lewis, W.J.; Bennett, L.G.I.; Mullin, S.K.

1996-01-01

At the Royal Military College of Canada's SLOWPOKE-2 Facility, a neutron radiography facility has been designed and installed using a small (20kWth), pool-type research reactor called the SLOWPOKE-2 (Safe Low Power c(K)ritical Experiment) as the neutron source. Since then, the research has continued along two fronts: developing applications and improving the quality of the neutron beam. The most interesting applications investigated to date has been the inspection of various metal ceramic composites and the inspection of the composite flight control surfaces of some of the CF188 Hornet aircraft. As part of the determination of the integrity of the aircraft, it was decided to inspect an aircraft with the highest flight house using both X- and neutron radiography. The neutron radiography and, to a lesser extent, X-radiography inspections completed at McClellan AFB revealed 93 anomalies. After returning to Canada, the component with the greatest structural significance, namely the right hand rudder from the vertical stabilizer, was removed from the aircraft and put through a rigorous program of numerous NDT inspections, including X-radiography (film and real-time), eddy current, ultrasonics (through transmission and pitch-catch), infrared thermography, and neutron radiography. Therefore, of all the techniques investigated, only through transmission ultrasonics and neutron radiography were able to identify large areas of hydration. However, only neutron radiography could identify the small areas of moisture and hydration. Given the structural significance of the flight control surfaces in modern fighter aircraft, even the smallest amounts of hydration could potentially lead to catastrophic results

Determination of selected elements in red, brown and green seaweed species for monitoring pollution in the coastal environment of Ghana

International Nuclear Information System (INIS)

Serfor-Armah, Y.; Ghana Atomic Energy Commission, Legon-Accra; Ghana University, Legon-Accra; Carboo, D.; Akuamoah, R.K.; Chatt, A.

2006-01-01

The concentrations of 23 elements, namely Al, As, Br, Ca, Cd, Cl, Co, Cr, Cu, Fe, Hf, Hg, I, K, La, Mg, Mn, Na, Ni, Sc, Sm, V, and Zn, in seven Rhodophyta (red), three Phaeophyta (brown) and five Chlorophyta (green) seaweed species from different areas along the coast of Ghana were determined using instrumental neutron activation analysis (INAA). These species can be potentially used as biomonitors. The INAA method involved irradiations using thermal and epithermal neutrons at the Dalhousie University SLOWPOKE-2 Reactor (DUSR) facility followed by conventional and anti-coincidence γ-ray spectrometry. The precision in terms of relative standard deviation was within ±4%. The accuracy of the methods was evaluated by analyzing four reference materials. Our results were within ±3% of the certified or information values in all cases. (author)

Application of INAA in the characterisation and quantification of Dy-labeled ceramic spheres and their use as inert tracers in soil studies

International Nuclear Information System (INIS)

Duke, M.J.M.; Plante, A.F.; McGill, W.B.

2000-01-01

An inert, activated tracer method, using sized ceramic spheres custom labeled with ∼15% Dy 2 O 3 manufacture, has been developed to study soil aggregation. Instrumental neutron activation analysis (INAA) with a Slowpoke reactor, using 165m Dy (T 1/2 = 1.26 min), provides an extremely rapid means with which to characterise the Dy-content of the various size fractions of labeled spheres from different production runs. In contrast, the Dy-content (and hence number of spheres) of 5-8 g soil/sphere mixtures is determined using the longer-lived 165 Dy (T 1/2 = 2.33 hrs) following a ∼30-minute decay period during which the otherwise interfering 28 Al (T 1/2 = 2.24 min) preferentially decays. The method is expected to find many applications. (author)

Reactor core for LMFBR type reactors

International Nuclear Information System (INIS)

Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

1987-01-01

Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

Characterizing Suicide in Toronto: An Observational Study and Cluster Analysis

Science.gov (United States)

Sinyor, Mark; Schaffer, Ayal; Streiner, David L

2014-01-01

Objective: To determine whether people who have died from suicide in a large epidemiologic sample form clusters based on demographic, clinical, and psychosocial factors. Method: We conducted a coroner’s chart review for 2886 people who died in Toronto, Ontario, from 1998 to 2010, and whose death was ruled as suicide by the Office of the Chief Coroner of Ontario. A cluster analysis using known suicide risk factors was performed to determine whether suicide deaths separate into distinct groups. Clusters were compared according to person- and suicide-specific factors. Results: Five clusters emerged. Cluster 1 had the highest proportion of females and nonviolent methods, and all had depression and a past suicide attempt. Cluster 2 had the highest proportion of people with a recent stressor and violent suicide methods, and all were married. Cluster 3 had mostly males between the ages of 20 and 64, and all had either experienced recent stressors, suffered from mental illness, or had a history of substance abuse. Cluster 4 had the youngest people and the highest proportion of deaths by jumping from height, few were married, and nearly one-half had bipolar disorder or schizophrenia. Cluster 5 had all unmarried people with no prior suicide attempts, and were the least likely to have an identified mental illness and most likely to leave a suicide note. Conclusions: People who die from suicide assort into different patterns of demographic, clinical, and death-specific characteristics. Identifying and studying subgroups of suicides may advance our understanding of the heterogeneous nature of suicide and help to inform development of more targeted suicide prevention strategies. PMID:24444321

Left ventricular assist device exchange: the Toronto General Hospital experience.

Science.gov (United States)

Tsubota, Hideki; Ribeiro, Roberto V P; Billia, Filio; Cusimano, Robert J; Yau, Terrence M; Badiwala, Mitesh V; Stansfield, William E; Rao, Vivek

2017-08-01

As support times for left ventricular assist devices (LVADs) become longer, several complications requiring device exchange may occur. To our knowledge, this is the first Canadian report regarding implantable LVAD exchange. We retrospectively reviewed the cases of consecutive, unique patients implanted with an LVAD between June 2006 and October 2015 at Toronto General Hospital. In total, 122 patients were impanted with an LVAD during the study period. Eight patients required LVAD exchange, and 1 patient had 2 replacements (9 of 122, 7.3%). There were 7 HeartMate II (HMII), 1 HVAD and 1 DuraHeart pumps exchanged. Two of these exchanges occurred early at the time of initial implant, whereas 7 occurred late (range 8-623 d). Six exchanges were made owing to pump thrombosis. Of the 3 exchanges made for other causes, 1 HMII exchange was owing to a driveline fracture, 1 DuraHeart patient had early inflow obstruction requiring exchange to HMII at the initial implant, and the third had a suspected inflow obstruction with no evidence of thrombosis at the time of the procedure. The mean support time before exchange was 225 days, and time from exchange to transplant, death or ongoing support was 245 days. Three patients were successfully bridged to transplant, and at the time of data collection 2 were supported awaiting transplant. Three patients died after a mean duration of 394.3 days (range 78-673 d) of support postreplacement. Four cases were successfully performed using a subcostal approach. Pump thrombosis is the most common cause for LVAD exchange, which can be performed with acceptable morbidity and mortality. The subcostal approach may be the preferred procedure for an HMII exchange when indicated.

Climate change, energy and sustainability: lessons from the Toronto-Niagara region

International Nuclear Information System (INIS)

Chiotti, Q.

2001-01-01

(electricity and natural gas), and the demand for energy. Climate factors considered include changes in the mean, but more importantly variability in temperatures and changes in extreme weather events. This part of the discussion draws upon extensive research in the Toronto-Niagara Region, which has been supported through the Federal Interdepartmental Panel on Energy Research and Development (PERD). Emphasis is placed on identifying what aspects of current climate have had the greatest impact on the energy sector, and the adaptation options that will be necessary to reduce future vulnerability in face of inevitable climate variability and change. In section three, the emphasis shifts towards actions to reduce GHG plus related emissions, within the context of environmental and health benefits. The co-benefits of reducing GHG plus related emissions includes the implications for ecosystems and biodiversity, environmental health (managed (forestry) and unmanaged (agriculture) systems), social welfare and human health. This discussion is based on research conducted on co-benefits as part of the multi-stakeholder process to develop a national strategy on climate change. The paper concludes by providing a preliminary assessment of the various mitigation options currently being proposed to help reach emission targets set out in the Kyoto Protocol, as they apply to the Toronto-Niagara Region. The assessment, which will be undertaken in greater depth as part of Phases III through V of the PERD supported project, considers the vulnerability of an altered energy system to climate change impacts, and the potential co-benefits for environment and health This includes changes brought about by fossil fuel switching, the inter-provincial transmission of electricity, alternative technologies, and energy efficiency, amongst other mitigation actions. (author)

Psychosocial stressors contributing to emergency psychiatric service utilization in a sample of ethno-culturally diverse clients with psychosis in Toronto.

Science.gov (United States)

Rotenberg, Martin; Tuck, Andrew; McKenzie, Kwame

2017-09-02

Understanding the psychosocial stressors of people with psychoses from minority ethnic groups may help in the development of culturally appropriate services. This study aimed to compare psychosocial factors associated with attendance at an emergency department (ED) for six ethnic groups. Preventing crises or supporting people better in the community may decrease hospitalization and improve outcomes. A cohort was created by retrospective case note analysis of people of East-Asian, South-Asian, Black-African, Black-Caribbean, White-North American and White-European origin groups attending a specialized psychiatric ED in Toronto with a diagnosis of psychosis between 2009 and 2011. The psychological or social stressors which were linked to the presentation at the ED that were documented by the attending physicians were collected for this study. Logistic regression models were constructed to analyze the odds of presenting with specific stressors. Seven hundred sixty-five clients were included in this study. Forty-four percent of the sample did not have a psychiatrist, and 53% did not have a primary care provider. Social environmental stressors were the most frequent psychosocial stressor across all six groups, followed by issues in the primary support group, occupational and housing stressors. When compared to White-North American clients, East-Asian and White-European origin clients were less likely to present with a housing stressor, while Black-African clients had decreased odds of presenting with primary support group stressor. Having a primary care provider or psychiatrist were predominantly protective factors. In Toronto, moving people with chronic mental health conditions out of poverty, increasing the social safety net and improving access to primary care and community based mental health services may decrease many of the stressors which contribute to ED attendance.

Consolidation of existing solid waste management plans in the Greater Toronto Area

Energy Technology Data Exchange (ETDEWEB)

1989-08-01

The municipalities of the Greater Toronto Area (GTA) will be implementing initiatives in solid waste management, in view of the fact that current landfill capacity is nearly exhausted. A consolidation of information is provided on the solid waste management plans, programs, and facilities within the GTA. In response to environmental concerns coupled with difficulties encountered in developing new solid waste disposal facilities, waste reduction, reuse, and recycling efforts are developing rapidly. Some of the measures currently implemented and under investigation include: curbside recycling programs for newspapers, glass, metal, and plastic containers; expanding recycling efforts to apartment buildings; expanding the kinds of materials collected through the curbside programs; improving recycling services in rural areas; public education and promotional programs; promotion of home composting; household hazardous waste programs; recovery of cardboard from commercial and industrial sources, coupled with bans on cardboard at landfills; recovery of selected waste building materials such as wood and drywall, coupled with bans on these materials at landfills; recovery of paper from office buildings; and programs to assist industries in waste reduction, reuse, and recycling. The solid wastes generated in the GTA are managed in a number of facilities including recycling centers, transfer stations, and landfill sites. A 410 tonne/day energy-from-waste facility has recently been approved for Peel Region and is planned to be constructed in the coming year. 21 refs., 1 fig., 14 tabs.

Acid rain: reflections on energy and environment. [Summary of conference at Toronto, November 1-3, 1979

Energy Technology Data Exchange (ETDEWEB)

Passmore, J

1979-12-01

Citizens groups organized a well-attended conference in Toronto, where speakers were requested to give clear direction on the political and technical opportunities for eliminating acid rain. Major Ontario contributors to the problem are the international Nickel Company, coal-fired power plants, and automobiles. The matter has top priority for the Ontario government, but individuals must cooperate by changing their lifestyles and paying closer attention to the environmental impacts of energy consumption. Canada is prepared to take unilateral action if no agreement is reached with the US on how much oxide emissions must be reduced. Conservation is the key to reducing energy demand in the short term, while development and careful management of domestic renewable energy sources can provide long-term energy growth. Acid rain is blamed for the death of 150 Ontario lakes and a reduction in solar radiation. The conference called for national policies aimed at eliminating the causes of acid rain and challenged environmentalists to lobby accordingly. (DCK)

Nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

This patent describes an improved liquid metal nuclear reactor construction comprising: (a) a nuclear reactor core having a bottom platform support structure; (b) a reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core; (c) a containment structure surrounding the reactor vessel and having a sidewall spaced outwardly from the reactor vessel side wall and having a base mat spaced below the reactor vessel bottom end wall; (d) a central small diameter post anchored to the containment structure base mat and extending upwardly to the reactor vessel to axially fix the bottom end wall of the reactor vessel and provide a center column support for the lower end of the reactor core; (e) annular support structure disposed in the reactor vessel on the bottom end wall and extending about the lower end of the core; (f) structural support means disposed between the containment structure base mat and bottom end of the reactor vessel wall and cooperating for supporting the reactor vessel at its bottom end wall on the containment structure base mat to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event; (g) a bed of insulating material disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall; freely expand radially from the central post as it heats up while providing continuous support thereof; (h) a deck supported upon the wall of the containment vessel above the top open end of the reactor vessel; and (i) extendible and retractable coupling means extending between the deck and the top open end of the reactor vessel and flexibly and sealably interconnecting the reactor vessel at its top end to the deck

Evaluation of Multi-Year Continuous Measurements of Ultrafine Particles at Two Near-Road Stations in Toronto, Canada

Science.gov (United States)

Su, Y.; Sofowote, U.; Debosz, J.; Munoz, T.; Whitelaw, C.

2013-12-01

Particles with an aerodynamic diameter less than 100 nanometre (nm) are referred to as ultrafine particles (UFPs). Relative to fine and course particles, UFPs have greater potential to be suspended in air for a longer time and absorb toxic chemicals due to their larger surface areas per unit mass. UFPs could penetrate deep into the respiratory or cardiovascular systems and pose adverse health effects. In urban environments, primary sources of UFPs are from road traffic emissions and account for most of the total particle numbers. Controls on UPFs rely on better understanding of their emission sources and environmental behaviour. Ontario Ministry of the Environment have monitored UFPs since 2010 at two near-road stations in Toronto by using TSI 3031 UFP monitors. The two monitoring stations are approximately 20-30 meters adjacent to major arterial roads with over 20,000 vehicles per day. UFPs concentrations were monitored using six size channels: 20-30nm, 30-50nm, 50-70nm, 70-100nm, 100-200nm, and 200-450nm. Data are collected at time intervals of 11 or 15 minutes and averaged hourly. Concurrent measurements include wind speeds, wind directions, and concentrations of other air pollutants such as nitrogen oxides and black carbon. Data influenced by road-side traffic emissions were filtered by wind direction within 45° of normal to the road and wind speed greater than 1 m/s. Number concentrations were found higher for particles with sizes of 20-30nm and 30-50nm than for other sizes of UFPs. The observed particle number distributions are generally consistent with the theoretical understanding of particle nuclei mode and accumulation mode. During the day, for UFPs with sizes of 20-30nm and 30-50nm, elevated number concentrations were observed in morning traffic hours and to a less extent in the late afternoon. The elevated UFPs number concentrations coincided with nitrogen oxides and black carbon. Moreover, higher number concentrations were found on weekdays than

Fusion Canada issue 8

International Nuclear Information System (INIS)

1989-08-01

A short bulletin from the National Fusion Program. Included in this issue are Canada-ITER contributions, NET Fuel Processing Loop, Bilateral Meeting for Canada-Europe, report from Tokamak de Varennes and a report from the University of Toronto on materials research for Fusion Reactors. 3 figs

Fusion Canada issue 8

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-08-01

A short bulletin from the National Fusion Program. Included in this issue are Canada-ITER contributions, NET Fuel Processing Loop, Bilateral Meeting for Canada-Europe, report from Tokamak de Varennes and a report from the University of Toronto on materials research for Fusion Reactors. 3 figs.

An Observational Study of Suicide Death in Homeless and Precariously Housed People in Toronto.

Science.gov (United States)

Sinyor, Mark; Kozloff, Nicole; Reis, Catherine; Schaffer, Ayal

2017-07-01

Homelessness has been identified as an important risk factor for suicide death, but there is limited research characterising homeless people who die by suicide. The goal of this study is to identify personal, clinical, and suicide method-related factors that distinguish homeless and precariously housed people who die from suicide from those who are not homeless at the time of suicide. Coroner records were reviewed for all suicide deaths in Toronto from 1998 to 2012. Data abstracted included housing status as well as other demographics, clinical variables such as the presence of mental illness, and suicide method. Of 3319 suicide deaths, 60 (1.8%) were homeless and 230 (6.9%) were precariously housed. Homeless and precariously housed people were each younger than nonhomeless people ( P suicide note. Homeless people and precariously housed were more likely to have died by fall/jump than nonhomeless people (62%, 57%, and 29%, respectively). Homeless and precariously housed people are overrepresented among suicide deaths in a large urban center and differ demographically, clinically, and in their suicide method from nonhomeless people who die by suicide. Targeted suicide prevention strategies should aim to address factors specific to homeless people.

Analysis of newspaper coverage of active aging through the lens of the 2002 World Health Organization Active Ageing Report: A Policy Framework and the 2010 Toronto Charter for Physical Activity: A Global Call for Action.

Science.gov (United States)

Abdullah, Boushra; Wolbring, Gregor

2013-12-05

As populations continue to grow older, efforts to support the process of aging well are important goals. Various synonyms are used to cover aging well, such as active aging. The World Health Organization published in 2002 the report Active Ageing: A Policy Framework that according to the call for papers, has brought active ageing to the forefront of international public health awareness. The 2010 Toronto Charter for Physical Activity: A Global Call for Action was singled out in the call for papers as a key document promoting physical activity one goal of the 2002 WHO active aging policy framework. Media are to report to the public topics of importance to them. We investigated the newspaper coverage of aging well and synonymous terms such as active aging through the lens of the 2002 WHO active aging policy framework and the 2010 Toronto Charter for Physical Activity. As sources we used the following newspapers: China Daily, The Star (Malaysia), two UK newspapers (The Guardian, The Times), a database of 300 Canadian newspapers (Canadian Newsstand) and a US newspaper (The New York Times). The study generated data answering the following four research questions: (1) how often are the 2002 WHO active aging policy framework and the 2010 Toronto Charter for Physical Activity mentioned; (2) how often is the topic of active aging and terms conveying similar content (aging well, healthy aging, natural aging and successful aging) discussed; (3) which of the issues flagged as important in the 2002 WHO active aging policy framework and the 2010 Toronto Charter for Physical Activity are covered in the newspaper coverage of active aging and synonymous terms; (4) which social groups were mentioned in the newspapers covered. The study found a total absence of mentioning of the two key documents and a low level of coverage of "active aging" and terms conveying similar content. It found further a lack of engagement with the issues raised in the two key documents and a low level of

Generation IV reactors: reactor concepts

International Nuclear Information System (INIS)

Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

2003-01-01

Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

CNS proceedings of the 1997 CNA/CNS annual conference on powering Canada's future. Vol. 1, 2

International Nuclear Information System (INIS)

Donnelly, J.V.; Oliva, A.

1997-01-01

The Canadian Nuclear Society presents a Technical Program Proceedings, presented in Toronto June 1997. The papers are split into Volumes one and two. The topics being: nuclear design and engineering, instrumentation, new technology, health and biology, safety analysis methods, nuclear waste management, reactor physics and operator interface and plant monitoring. The second volume contains topics including plant simulators, computer code validation, reactor safety research and development, thermal hydraulics methods, safety assessment and analysis, radiation transport, and radionuclides, applied nuclear research and development, reactor performance assessment and life cycle management, system and component simulation and design, small reactor analysis and desktop nuclear plant simulator demonstration

CNS proceedings of the 1997 CNA/CNS annual conference on powering Canada`s future. Vol. 1, 2

Energy Technology Data Exchange (ETDEWEB)

Donnelly, J V [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Oliva, A [Ontario Hydro, Toronto, Ontario (Canada); eds.

1998-12-31

The Canadian Nuclear Society presents a Technical Program Proceedings, presented in Toronto June 1997. The papers are split into Volumes one and two. The topics being: nuclear design and engineering, instrumentation, new technology, health and biology, safety analysis methods, nuclear waste management, reactor physics and operator interface and plant monitoring. The second volume contains topics including plant simulators, computer code validation, reactor safety research and development, thermal hydraulics methods, safety assessment and analysis, radiation transport, and radionuclides, applied nuclear research and development, reactor performance assessment and life cycle management, system and component simulation and design, small reactor analysis and desktop nuclear plant simulator demonstration

Nuclear reactor

International Nuclear Information System (INIS)

Hattori, Sadao; Sato, Morihiko.

1994-01-01

Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

The CAREM reactor and present currents in reactor design

International Nuclear Information System (INIS)

Ordonez, J.P.

1990-01-01

INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author) [es

Feasibility of Rectangular Concrete Pressure Vessels for Human Occupancy

Science.gov (United States)

1990-07-01

incorporated: into the s 1.71 ! -1 rule-. 20 DISTRIBUTION/ AVAILABILIT ’- ,"r ABSTRACT 2’ ABSTRACT SECURITY CLASSIFICATION 7 JUNCLASSIFIED/UNLIMITED 0 SAME AS RPT...carried the end loads. Gas cooled reactors were never very popular in the US. Domestic utilities preferred boiling water reactors that operated at...Point Tower); 1975 - 9,000 psi in Chicago ( Water Tower Place); 1984 - 10,000 psi in Seattle (Century Square Bldg.); 1987 - 10,000 psi in Toronto

Neutron behavior, reactor control, and reactor heat transfer. Volume four

International Nuclear Information System (INIS)

Anon.

1986-01-01

Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant)

Reactor science and technology: operation and control of reactors

International Nuclear Information System (INIS)

Qiu Junlong

1994-01-01

This article is a collection of short reports on reactor operation and research in China in 1991. The operation of and research activities linked with the Heavy Water Research Reactor, Swimming Pool Reactor and Miniature Neutron Source Reactor are briefly surveyed. A number of papers then follow on the developing strategies in Chinese fast breeder reactor technology including the conceptual design of an experimental fast reactor (FFR), theoretical studies of FFR thermo-hydraulics and a design for an immersed sodium flowmeter. Reactor physics studies cover a range of topics including several related to work on zero power reactors. The section on reactor safety analysis is concerned largely with the assessment of established, and the presentation of new, computer codes for use in PWR safety calculations. Experimental and theoretical studies of fuels and reactor materials for FBRs, PWRs, BWRs and fusion reactors are described. A final miscellaneous section covers Mo-Tc isotope production in the swimming pool reactor, convective heat transfer in tubes and diffusion of tritium through plastic/aluminium composite films and Li 2 SiO 3 . (UK)

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.)

Aboriginal Knowledge Infusion in Initial Teacher Education at the Ontario Institute for Studies in Education at the University of Toronto

Directory of Open Access Journals (Sweden)

Angela Mashford-Pringle

2013-11-01

Full Text Available Knowledge of the Aboriginal socio-political history in Canada has historically been excluded from public education. In Ontario, public school children learn about Aboriginal people at specific times in the curriculum. However, teachers frequently only teach the bare essentials about Aboriginal people in Canada because they do not have adequate knowledge or feel that they lack the ability to teach about this subject. The Ontario Institute of Studies in Education at the University of Toronto has implemented the Deepening Knowledge Project to provide teacher candidates with an increased awareness and knowledge about Aboriginal history, culture, and worldview for their future teaching careers. This article will provide insight into the project and the curriculum developed for working with teacher candidates.

Programming Deep Brain Stimulation for Parkinson's Disease: The Toronto Western Hospital Algorithms.

Science.gov (United States)

Picillo, Marina; Lozano, Andres M; Kou, Nancy; Puppi Munhoz, Renato; Fasano, Alfonso

2016-01-01

Deep brain stimulation (DBS) is an established and effective treatment for Parkinson's disease (PD). After surgery, a number of extensive programming sessions are performed to define the most optimal stimulation parameters. Programming sessions mainly rely only on neurologist's experience. As a result, patients often undergo inconsistent and inefficient stimulation changes, as well as unnecessary visits. We reviewed the literature on initial and follow-up DBS programming procedures and integrated our current practice at Toronto Western Hospital (TWH) to develop standardized DBS programming protocols. We propose four algorithms including the initial programming and specific algorithms tailored to symptoms experienced by patients following DBS: speech disturbances, stimulation-induced dyskinesia and gait impairment. We conducted a literature search of PubMed from inception to July 2014 with the keywords "deep brain stimulation", "festination", "freezing", "initial programming", "Parkinson's disease", "postural instability", "speech disturbances", and "stimulation induced dyskinesia". Seventy papers were considered for this review. Based on the literature review and our experience at TWH, we refined four algorithms for: (1) the initial programming stage, and management of symptoms following DBS, particularly addressing (2) speech disturbances, (3) stimulation-induced dyskinesia, and (4) gait impairment. We propose four algorithms tailored to an individualized approach to managing symptoms associated with DBS and disease progression in patients with PD. We encourage established as well as new DBS centers to test the clinical usefulness of these algorithms in supplementing the current standards of care. Copyright © 2016 Elsevier Inc. All rights reserved.

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)

Roles of plasma neutron source reactor in development of fusion reactor engineering: Comparison with fission reactor engineering

International Nuclear Information System (INIS)

Hirayama, Shoichi; Kawabe, Takaya

1995-01-01

The history of development of fusion power reactor has come to a turning point, where the main research target is now shifting from the plasma heating and confinement physics toward the burning plasma physics and reactor engineering. Although the development of fusion reactor system is the first time for human beings, engineers have experience of development of fission power reactor. The common feature between them is that both are plants used for the generation of nuclear reactions for the production of energy, nucleon, and radiation on an industrial scale. By studying the history of the development of the fission reactor, one can find the existence of experimental neutron reactors including irradiation facilities for fission reactor materials. These research neutron reactors played very important roles in the development of fission power reactors. When one considers the strategy of development of fusion power reactors from the points of fusion reactor engineering, one finds that the fusion neutron source corresponds to the neutron reactor in fission reactor development. In this paper, the authors discuss the roles of the plasma-based neutron source reactors in the development of fusion reactor engineering, by comparing it with the neutron reactors in the history of fission power development, and make proposals for the strategy of the fusion reactor development. 21 refs., 6 figs

Estudos da Consistência Interna e Fatorial Confirmatórioda Escala Toronto de Alexitimia-20 (ETA-20

Directory of Open Access Journals (Sweden)

Daniela Wiethaeuper

2005-01-01

Full Text Available El objetivo de este estudio es verificar las cualidades métricas del ETA-20 (Escala Toronto de Alexitimia-20con una muestra de estudiantes universitarios brasileños e, comparar los resultados conseguidos aquí con los deotros países. Constituyó-se a muestra de 489 estudiantes de ambos los sexos y con edades de 16 a 51 años, dela educación superior, de la red privada. El índice Alpha de Cronbach (=0.765 para la escala total, con lamuestra fuera comparable con las otras muestras de estudiantes, de otros países (esos habían variado de 0.68los 0.84. Los resultados de la adecuación al modelo tridimensional, para la muestra brasileña (2/gl=3.67;GFI=0.881; AGFI=0.851; RMSEA=0,074, son perfectamente comparables a ésos presentados en estudios deotros países

Reactor physics aspects of CANDU reactors

International Nuclear Information System (INIS)

Critoph, E.

1980-01-01

These four lectures are being given at the Winter Course on Nuclear Physics at Trieste during 1978 February. They constitute part of the third week's lectures in Part II: Reactor Theory and Power Reactors. A physical description of CANDU reactors is given, followed by an overview of CANDU characteristics and some of the design options. Basic lattice physics is discussed in terms of zero energy lattice experiments, irradiation effects and analytical methods. Start-up and commissioning experiments in CANDU reactors are reviewed, and some of the more interesting aspects of operation discussed - fuel management, flux mapping and control of the power distribution. Finally, some of the characteristics of advanced fuel cycles that have been proposed for CANDU reactors are summarized. (author)

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

Comparison between TRU burning reactors and commercial fast reactor

International Nuclear Information System (INIS)

Fujimura, Koji; Sanda, Toshio; Ogawa, Takashi

2001-03-01

Research and development for stabilizing or shortening the radioactive wastes including in spent nuclear fuel are widely conducted in view point of reducing the environmental impact. Especially it is effective way to irradiate and transmute long-lived TRU by fast reactors. Two types of loading way were previously proposed. The former is loading relatively small amount of TRU in all commercial fast reactors and the latter is loading large amount of TRU in a few TRU burning reactors. This study has been intended to contribute to the feasibility studies on commercialized fast reactor cycle system. The transmutation and nuclear characteristics of TRU burning reactors were evaluated and compared with those of conventional transmutation system using commercial type fast reactor based upon the investigation of technical information about TRU burning reactors. Major results are summarized as follows. (1) Investigation of technical information about TRU burning reactors. Based on published reports and papers, technical information about TRU burning reactor concepts transmutation system using convectional commercial type fast reactors were investigated. Transmutation and nuclear characteristics or R and D issue were investigated based on these results. Homogeneously loading of about 5 wt% MAs on core fuels in the conventional commercial type fast reactor may not cause significant impact on the nuclear core characteristics. Transmutation of MAs being produced in about five fast reactors generating the same output is feasible. The helium cooled MA burning fast reactor core concept propose by JAERI attains criticality using particle type nitride fuels which contain more than 60 wt% MA. This reactor could transmute MAs being produced in more than ten 1000 MWe-LWRs. Ultra-long life core concepts attaining more than 30 years operation without refueling by utilizing MA's nuclear characteristics as burnable absorber and fertile nuclides were proposed. Those were pointed out that

Nuclear reactor types

International Nuclear Information System (INIS)

Jones, P.M.S.

1987-01-01

The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

The Relationship between Retail Merchandising in the Content Area and Its Effect on Comprehension and Reading Rate as Measured by Retail Merchandising Reading Tests Given to Selected Secondary School Students in Metropolitan Toronto.

Science.gov (United States)

Best, Jane

A total of 99 students from a Toronto secondary vocational school participated in a study to determine whether students who studied retail merchandising differed significantly in comprehension and reading rate from students who did not study retail merchandising. An experimental group composed of 50 merchandising students and a control group of 49…

Reactor containment and reactor safety in the United States

International Nuclear Information System (INIS)

Kouts, H.

1986-01-01

The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

Reactor Physics

International Nuclear Information System (INIS)

Ait Abderrahim, A.

2002-01-01

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

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.

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

Mixed field radiation modification of polyurethanes based on castor oil

Energy Technology Data Exchange (ETDEWEB)

Mortley, A.; Bonin, H.W.; Bui, V.T. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)]. E-mail: aba.mortley@rmc.ca

2006-07-01

Polyurethane is among the polymers and polymer-based composite materials being investigated at the Royal Military College of Canada for the fabrication of leak-tight containers for the long-term disposal of radioactive waste. Due to the long aliphatic chain of the castor oil component of polyurethane, thermal curing of castor oil based polyurethane (COPU) is limited by increasing polymer viscosity. To enhance further crosslinking, COPUs were subjected to a range of doses (0.0 - 3.0 MGy) produced by the mixed ionizing radiation field of a SLOWPOKE-2 research nuclear reactor. The tensile mechanical properties of castor oil based polyurethanes (COPU), unirradiated and irradiated, were characterized by mechanical tensile tests. Increases in mechanical strength due to radiation-induced crosslinking and limitations of thermal curing were confirmed by tensile tests and changing {sup 13}C-NMR and FTIR spectra. (author)

Mixed field radiation modification of polyurethanes based on castor oil

International Nuclear Information System (INIS)

Mortley, A.; Bonin, H.W.; Bui, V.T.

2006-01-01

Polyurethane is among the polymers and polymer-based composite materials being investigated at the Royal Military College of Canada for the fabrication of leak-tight containers for the long-term disposal of radioactive waste. Due to the long aliphatic chain of the castor oil component of polyurethane, thermal curing of castor oil based polyurethane (COPU) is limited by increasing polymer viscosity. To enhance further crosslinking, COPUs were subjected to a range of doses (0.0 - 3.0 MGy) produced by the mixed ionizing radiation field of a SLOWPOKE-2 research nuclear reactor. The tensile mechanical properties of castor oil based polyurethanes (COPU), unirradiated and irradiated, were characterized by mechanical tensile tests. Increases in mechanical strength due to radiation-induced crosslinking and limitations of thermal curing were confirmed by tensile tests and changing 13 C-NMR and FTIR spectra. (author)

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.)

Mental health and hospital chaplaincy: strategies of self-protection (case study: toronto, Canada).

Science.gov (United States)

Kianpour, Masoud

2013-01-01

This is a study about emotion management among a category of healthcare professional - hospital chaplains - who have hardly been the subject of sociological research about emotions. The aim of the study was to understand how chaplains manage their work-related emotions in order to protect their mental health, whilst also providing spiritual care. Using in-depth, semi structured interviews, the author spoke with 21 chaplains from five faith traditions (Christianity, Islam, Judaism, Buddhism and modern paganism) in different Toronto (Canada) Hospitals to see how they manage their emotion, and what resources they rely on in order to protect their mental health. Data analysis was perfumed according to Sandelowski's method of qualitative description. The average age and work experience of the subjects interviewed in this study are 52 and 9.6 respectively. 11 chaplains worked part-time and 10 chaplains worked full-time. 18 respondents were women and the sample incudes 3 male chaplains only. The findings are discussed, among others, according to the following themes: work-life balance, self-reflexivity, methods of self-care, and chaplains' emotional make-up. Emotion management per se is not a problem. However, if chaplains fail to maintain a proper work-life balance, job pressure can be harmful. As a strategy, many chaplains work part-time. As a supportive means, an overwhelming number of chaplains regularly benefit from psychotherapy and/or spiritual guidance. None.

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.

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

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

Acoustic assessment report for Toronto Hydro Energy Services Inc. Ashbridge's Bay power generation facility

International Nuclear Information System (INIS)

Bernard, F.; Shinbin, N.

2010-04-01

This acoustic assessment report was conducted to determine the potential noise impacts of a biogas cogeneration plant that will be located on a street in a primarily industrial area of Toronto, Ontario. The facility will be comprised of seven 1.416 MW biogas-fired reciprocating engine generators and a single flare. The report presented results obtained from noise level calculations and noise modelling studies of the on-site equipment at the planned facility. The cogeneration plant will utilize biogas produced in existing digesters to generate electricity and hot water. The biogas will be produced by anaerobic digestion from municipal sewage waste at an adjacent facility. It is expected that the facility will generate 9.912 MW of electricity from the generators. Heat resulting from the biogas combustion process is recovered from engine and exhaust flue gases by heat exchangers. The facility will operate continuously. Significant noise sources at the facility include generator exhaust gas stacks; air intake points; building ventilation fans; and roof-top heat dump radiators. Sound power levels determined for each of the noise sources were based upon worst-case operating scenarios. Results of the assessment indicated that the facility is in compliance with all Ministry of the Environment (MOE) requirements. 5 refs., 10 tabs., 4 figs.

Improved nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding liquid metal coolant and housing the core within the pool. A generally cylindrical concrete containment structure surrounds the reactor vessel and a central support pedestal is anchored to the containment structure base mat and supports the bottom wall of the reactor vessel and the reactor core. The periphery of the reactor vessel bore is supported by an annular structure which allows thermal expansion but not seismic motion of the vessel, and a bed of thermally insulating material uniformly supports the vessel base whilst allowing expansion thereof. A guard ring prevents lateral seismic motion of the upper end of the reactor vessel. The periphery of the core is supported by an annular structure supported by the vessel base and keyed to the vessel wall so as to be able to expand but not undergo seismic motion. A deck is supported on the containment structure above the reactor vessel open top by annular bellows, the deck carrying the reactor control rods such that heating of the reactor vessel results in upward expansion against the control rods. (author)

Reactor as furnace and reactor as lamp

International Nuclear Information System (INIS)

Goldanskii, V.I.

1992-01-01

There are presented general characteristics of the following ways of transforming of nuclear energy released in reactors into chemical : ordinary way (i.e. trough the heat, mechanical energy and electricity); chemonuclear synthesis ; use of high-temperature fuel elements (reactor as furnace); use of the mixed nγ-radiation of reactors; use of the radiation loops; radiation - photochemical synthesis (reactor as lamp). Advantage and disadvantages of all above variants are compared. The yield of the primary product of fixation of nitrogen (nitric oxide NO) in reactor with the high-temperature (above ca. 1900degC) fuel elements (reactor-furnace) can exceed W ∼ 200 kg per gram of burned uranium. For the latter variant (reactor-lamp) the yield of chemical products can reach W ∼ 60 kg. per gram of uranium. Such values of W are close to or even strongly exceed the yields of chemical products for other abovementioned variants and - what is particularly important - are not connected to the necessity of archscrupulous removal of radioactive contamination of products. (author)

Development of Reactor Console Simulator for PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Mohd Idris Taib; Izhar Abu Hussin; Mohd Khairulezwan Abdul Manan; Nufarhana Ayuni Joha; Mohd Sabri Minhat

2012-01-01

The Reactor Console Simulator will be an interactive tool for operator training and teaching of PUSPATI TRIGA Reactor. Behaviour and characteristic for reactor console and reactor itself can be evaluated and understand. This Simulator will be used as complement for actual present reactor console. Implementation of man-machine interface is using computer screens, keyboard and mouse. Multiple screens are used to match the physical of present reactor console. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate the estimated reactor console parameters. (author)

Spatial Assessment of Road Traffic Injuries in the Greater Toronto Area (GTA: Spatial Analysis Framework

Directory of Open Access Journals (Sweden)

Sina Tehranchi

2017-03-01

Full Text Available This research presents a Geographic Information Systems (GIS and spatial analysis approach based on the global spatial autocorrelation of road traffic injuries for identifying spatial patterns. A locational spatial autocorrelation was also used for identifying traffic injury at spatial level. Data for this research study were acquired from Canadian Institute for Health Information (CIHI based on 2004 and 2011. Moran’s I statistics were used to examine spatial patterns of road traffic injuries in the Greater Toronto Area (GTA. An assessment of Getis-Ord Gi* statistic was followed as to identify hot spots and cold spots within the study area. The results revealed that Peel and Durham have the highest collision rate for other motor vehicle with motor vehicle. Geographic weighted regression (GWR technique was conducted to test the relationships between the dependent variable, number of road traffic injury incidents and independent variables such as number of seniors, low education, unemployed, vulnerable groups, people smoking and drinking, urban density and average median income. The result of this model suggested that number of seniors and low education have a very strong correlation with the number of road traffic injury incidents.

A cohort study of intra-urban variations in volatile organic compounds and mortality, Toronto, Canada.

Science.gov (United States)

Villeneuve, Paul J; Jerrett, Michael; Su, Jason; Burnett, Richard T; Chen, Hong; Brook, Jeffrey; Wheeler, Amanda J; Cakmak, Sabit; Goldberg, Mark S

2013-12-01

This study investigated associations between long-term exposure to ambient volatile organic compounds (VOCs) and mortality. 58,760 Toronto residents (≥35 years of age) were selected from tax filings and followed from 1982 to 2004. Death information was extracted using record linkage to national mortality data. Land-use regression surfaces for benzene, n-hexane, and total hydrocarbons were generated from sampling campaigns in 2002 and 2004 and assigned to residential addresses in 1982. Cox regression was used to estimate relationships between each VOC and non-accidental, cardiovascular, and cancer mortality. Positive associations were observed for each VOC. In multi-pollutant models the benzene and total hydrocarbon signals were strongest for cancer. The hazard ratio for cancer that corresponded to an increase in the interquartile range of benzene (0.13 μg/m(3)) was 1.06 (95% CI = 1.02-1.11). Our findings suggest ambient concentrations of VOCs were associated with cancer mortality, and that these exposures did not confound our previously reported associations between NO2 and cardiovascular mortality. Crown Copyright © 2013. Published by Elsevier Ltd. All rights reserved.

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

Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

International Nuclear Information System (INIS)

Greneche, D.

2014-01-01

This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

3. Annual conference 1982, June 9, Royal Hotel, Toronto, Canada. Proceedings

International Nuclear Information System (INIS)

Oberth, R.C.

1982-01-01

Papers presented at this conference cover the fields of thermalhydraulics, system design and analysis, system operation, environmental and radiation protection, reactor and fuel physics, fuel cycles and mining, safety systems and reliability, public and regulatory aspects, and nuclear power plant operators

Prevalence of Sexually Transmitted Viral and Bacterial Infections in HIV-Positive and HIV-Negative Men Who Have Sex with Men in Toronto.

Directory of Open Access Journals (Sweden)

Robert S Remis

Full Text Available Hepatitis B (HBV, hepatitis C (HCV and other sexually transmitted infections (STIs have been associated with HIV transmission risk and disease progression among gay men and other men who have sex with men (MSM, but the frequency and distribution of STIs in this community in Canada has not been extensively studied.We recruited MSM living with and without HIV from a large primary care clinic in Toronto. Participants completed a detailed socio-behavioural questionnaire using ACASI and provided blood for syphilis, HIV, HBV and HCV, herpes simplex virus type 1 (HSV-1 and type 2 (HSV-2, and human cytomegalovirus (CMV serology, urine for chlamydia and gonorrhea, and a self-collected anal swab for human papillomavirus (HPV molecular diagnostics. Prevalences were expressed as a proportion and compared using chi-square.442 MSM were recruited, 294 living with HIV and 148 without. Active syphilis (11.0% vs. 3.4%, ever HBV (49.4% vs. 19.1%, HCV (10.4% vs. 3.4%, HSV-2 (55.9% vs. 38.2%, CMV (98.3% vs. 80.3% and high-risk (HR anal HPV (67.6% vs. 51.7% infections were significantly more common in men living with HIV. Chlamydia and gonorrhea were infrequent in both groups. Regardless of HIV infection status, age and number of lifetime male sexual partners were associated with HBV infection and lifetime injection drug use with HCV infection.Syphilis and viral infections, including HBV, HCV, HSV-2, CMV, and HR-HPV, were common in this clinic-based population of MSM in Toronto and more frequent among MSM living with HIV. This argues for the implementation of routine screening, vaccine-based prevention, and education programs in this high-risk population.

Control of reactor coolant flow path during reactor decay heat removal

International Nuclear Information System (INIS)

Hunsbedt, A.N.

1988-01-01

This patent describes a sodium cooled reactor of the type having a reactor hot pool, a slightly lower pressure reactor cold pool and a reactor vessel liner defining a reactor vessel liner flow gap separating the hot pool and the cold pool along the reactor vessel sidewalls and wherein the normal sodium circuit in the reactor includes main sodium reactor coolant pumps having a suction on the lower pressure sodium cold pool and an outlet to a reactor core; the reactor core for heating the sodium and discharging the sodium to the reactor hot pool; a heat exchanger for receiving sodium from the hot pool, and removing heat from the sodium and discharging the sodium to the lower pressure cold pool; the improvement across the reactor vessel liner comprising: a jet pump having a venturi installed across the reactor vessel liner, the jet pump having a lower inlet from the reactor vessel cold pool across the reactor vessel liner and an upper outlet to the reactor vessel hot pool

The research reactors their contribution to the reactors physics

International Nuclear Information System (INIS)

Barral, J.C.; Zaetta, A.; Johner, J.; Mathoniere, G.

2000-01-01

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

Reactor noise analysis of experimental fast reactor 'JOYO'

International Nuclear Information System (INIS)

Ohtani, Hideji; Yamamoto, Hisashi

1980-01-01

As a part of dynamics tests in experimental fast reactor ''JOYO'', reactor noise tests were carried out. The reactor noise analysis techniques are effective for study of plant characteristics by determining fluctuations of process signals (neutron signal, reactor inlet temperature signals, etc.), which are able to be measured without disturbances for reactor operations. The aims of reactor noise tests were to confirm that no unstable phenomenon exists in ''JOYO'' and to gain initial data of the plant for reference of the future data. Data for the reactor noise tests treated in this paper were obtained at 50 MW power level. Fluctuations of process signals were amplified and recorded on analogue tapes. The analysis was performed using noise code (NOISA) of digital computer, with which statistical values of ASPD (auto power spectral density), CPSD (cross power spectral density), and CF (coherence function) were calculated. The primary points of the results are as follows. 1. RMS value of neutron signal at 50 MW power level is about 0.03 MW. This neutron fluctuation is not disturbing reactor operations. 2. The fluctuations of A loop reactor inlet temperatures (T sub(AI)) are larger than the fluctuations of B loop reactor inlet temperature (T sub(BI)). For this reason, the major driving force of neutron fluctuations seems to be the fluctuations of T sub(AI). 3. Core and blanket subassemblies can be divided into two halves (A and B region), with respect to the spacial motion of temperature in the reactor core. A or B region means the region in which sodium temperature fluctuations in subassembly are significantly affected by T sub(AI) or T sub(BI), respectively. This phenomenon seems to be due to the lack of mixing of A and B loop sodium in lower plenum of reactor vessel. (author)

INC '93 overview

International Nuclear Information System (INIS)

Howe, Bruce

1993-01-01

At the close of the International Nuclear Congress, INC '93, held in Toronto in October 1993, Bruce Howe, then president of AECL, presented a 'Review and Conclusions' under the following headings: Introduction, Future Energy Requirements, Economics of electricity generation, Radioactive waste management, Reactor safety, Public acceptance, Technology developments, Future energy strategies, Conclusion

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

Reactor water spontaneous circulation structure in reactor pressure vessel

International Nuclear Information System (INIS)

Takahashi, Kazumi

1998-01-01

The gap between the inner wall of a reactor pressure vessel of a BWR type reactor and a reactor core shroud forms a down comer in which reactor water flows downwardly. A feedwater jacket to which feedwater at low temperature is supplied is disposed at the outer circumference of the pressure vessel just below a gas/water separator. The reactor water at the outer circumferential portion just below the air/water separator is cooled by the feedwater jacket, and the feedwater after cooling is supplied to the feedwater entrance disposed below the feedwater jacket by way of a feedwater introduction line to supply the feedwater to the lower portion of the down comer. This can cool the reactor water in the down comer to increase the reactor water density in the down comer thereby forming strong downward flows and promote the recycling of the reactor water as a whole. With such procedures, the reactor water can be recycled stably only by the difference of the specific gravity of the reactor water without using an internal pump. In addition, the increase of the height of the pressure vessel can be suppressed. (I.N.)

Pathways between under/unemployment and health among racialized immigrant women in Toronto.

Science.gov (United States)

Premji, Stephanie; Shakya, Yogendra

2017-02-01

We sought to document pathways between under/unemployment and health among racialized immigrant women in Toronto while exploring the ways in which gender, class, migration and racialization, as interlocking systems of social relations, structure these relationships. We conducted 30 interviews with racialized immigrant women who were struggling to get stable employment that matched their education and/or experience. Participants were recruited through flyers, partner agencies and peer researcher networks. Most interviews (21) were conducted in a language other than English. Interviews were transcribed, translated as appropriate and analyzed using NVivo software. The project followed a community-based participatory action research model. Under/unemployment negatively impacted the physical and mental health of participants and their families. It did so directly, for example through social isolation, as well as indirectly through representation in poor quality jobs. Under/unemployment additionally led to the intensification of job search strategies and of the household/caregiving workload which also negatively impacted health. Health problems, in turn, contributed to pushing participants into long-term substandard employment trajectories. Participants' experiences were heavily structured by their social location as low income racialized immigrant women. Our study provides needed qualitative evidence on the gendered and racialized dimensions of under/unemployment, and adverse health impacts resulting from this. Drawing on intersectional analysis, we unpack the role that social location plays in creating highly uneven patterns of under/unemployment and negative health pathways for racialized immigrant women. We discuss equity informed strategies to help racialized immigrant women overcome barriers to stable work that match their education and/or experience.

Energy impacts of heat island reduction strategies in the Greater Toronto Area, Canada; FINAL

International Nuclear Information System (INIS)

Konopacki, Steven; Akbari, Hashem

2001-01-01

In 2000, the Toronto Atmospheric Fund (TAF) embarked on an initiative to quantify the potential benefits of Heat Island Reduction (HIR) strategies (shade trees, reflective roofs and pavements) in reducing cooling energy use in buildings, lowering the ambient air temperature and improve air quality. This report summarizes the efforts of Lawrence Berkeley National Laboratory (LBNL) to assess the impacts of HIR measures on building cooling- and heating-energy use. We discuss our efforts to calculate annual energy savings and peak-power avoidance of HIR strategies in the building sector of the Greater Toronto Area. The analysis is focused on three major building types that offer most saving potentials: residence, office and retail store. Using an hourly building energy simulation model, we quantify the energy saving potentials of (1) using cool roofs on individual buildings[direct effect], (2) planting deciduous shade trees near south and west walls of building[direct effect], (3) planting coniferous wind-shielding vegetation near building[direct effect], (4) ambient cooling by a large-scale program of urban reforestation with reflective building roofs and pavements[indirect effect], (5) and the combined direct and indirect effects. Results show potential annual energy savings of over$11M (with uniform residential and commercial electricity and gas prices of$0.084/kWh and$5.54/GJ) could be realized by ratepayers from the combined direct and indirect effects of HIR strategies. Of that total, about 88 percent was from the direct impact roughly divided equally among reflective roofs, shade trees and wind-shielding, and the remainder (12 percent) from the indirect impact of the cooler ambient air temperature. The residential sector accounts for over half (59 percent) of the total, offices 13 percent and retail stores 28 percent. Savings from cool roofs were about 20 percent, shade trees 30 percent, wind shielding of tree 37 percent, and indirect effect 12 percent. These

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.)

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

Effect of air quality alerts on human health: a regression discontinuity analysis in Toronto, Canada.

Science.gov (United States)

Chen, Hong; Li, Qiongsi; Kaufman, Jay S; Wang, Jun; Copes, Ray; Su, Yushan; Benmarhnia, Tarik

2018-01-01

Ambient air pollution is a major health risk globally. To reduce adverse health effects on days when air pollution is high, government agencies worldwide have implemented air quality alert programmes. Despite their widespread use, little is known about whether these programmes produce any observable public-health benefits. We assessed the effectiveness of such programmes using a quasi-experimental approach. We assembled a population-based cohort comprising all individuals who resided in the city of Toronto (Ontario, Canada) from 2003 to 2012 (about 2·6 million people). We ascertained seven health outcomes known to be affected by short-term elevation of air pollution, using provincial health administrative databases. These health outcomes were cardiovascular-related mortality, respiratory-related mortality, and hospital admissions or emergency-department visits for acute myocardial infarction, heart failure, stroke, asthma, and chronic obstructive pulmonary disease (COPD). We applied a regression discontinuity design to assess the effectiveness of an intervention (ie, the air quality alert programme). To quantify the effect of the air quality alert programme, we estimated for each outcome both the absolute rate difference and the rate ratio attributable to programme eligibility (by intention-to-treat analysis) and the alerts themselves (by two-stage regression approach), respectively. Between Jan 1, 2003, and Dec 31, 2012, on average between three and 27 daily cardiovascular or respiratory events were reported in Toronto (depending on the outcome). Alert announcements reduced asthma-related emergency-department visits by 4·73 cases per 1 000 000 people per day (95% CI 0·55-9·38), or in relative terms by 25% (95% CI 1-47). Programme eligibility also led to 2·05 (95% CI 0·07-4·00) fewer daily emergency-department visits for asthma. We did not detect a significant reduction in any other health outcome as a result of alert announcements or programme

FBR type reactor

International Nuclear Information System (INIS)

Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

1994-01-01

In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

RB Research nuclear reactor RB reactor, Annual report for 2000

International Nuclear Information System (INIS)

Milosevic, M.

2000-12-01

Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

Reactor container

International Nuclear Information System (INIS)

Kato, Masami; Nishio, Masahide.

1987-01-01

Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

Reactor Physics Programme

Energy Technology Data Exchange (ETDEWEB)

De Raedt, C

2000-07-01

The Reactor Physics and 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 on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research 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. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

Reactor Physics Programme

International Nuclear Information System (INIS)

De Raedt, C.

2000-01-01

The Reactor Physics and 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 on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research 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. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

Some physics problems in the design of thorium-fuelled CANDU reactors

International Nuclear Information System (INIS)

Milgram, M.S.; Walker, W.H.

1976-08-01

This paper is the text of a presentation to the American Nuclear Society Conference, Toronto, 14-1 8 June, 1976. The contents deal with the adequacy of fission product representations in U 233 -Th cycles, the sensitivity of burnup predictions to cross-section data, and the flux dependence phenomenon associated with Pa 233

Mismatched racial identities, colourism, and health in Toronto and Vancouver.

Science.gov (United States)

Veenstra, Gerry

2011-10-01

Using original telephone survey data collected from adult residents of Toronto (n = 685) and Vancouver (n = 814) in 2009, I investigate associations between mental and physical health and variously conceived racial identities. An 'expressed racial identity' is a self-identification with a racial grouping that a person will readily express to others when asked to fit into official racial classifications presented by Census forms, survey researchers, insurance forms, and the like. Distinguishing between Asian, Black, South Asian, and White expressed racial identities, I find that survey respondents expressing Black identity are the most likely to report high blood pressure or hypertension, a risk that is slightly attenuated by socioeconomic status, and that respondents expressing Asian identity are the most likely to report poorer self-rated mental health and self-rated overall health, risks that are not explained by socioeconomic status. I also find that darker-skinned Black respondents are more likely than lighter-skinned Black respondents to report poor health outcomes, indicating that colourism, processes of discrimination which privilege lighter-skinned people of colour over their darker-skinned counterparts, exists and has implications for well-being in Canada as it does in the United States. Finally, 'reflected racial identity' refers to the racial identity that a person believes that others tend to perceive him or her to be. I find that expressed and reflected racial identities differ from one another for large proportions of self-expressed Black and South Asian respondents and relatively few self-expressed White and Asian respondents. I also find that mismatched racial identities correspond with relatively high risks of various poor health outcomes, especially for respondents who consider themselves White but believe that others tend to think they are something else. I conclude by presenting a framework for conceptualizing multifaceted suites of racial

Local seismic monitoring east and north of Toronto - Volume 1

International Nuclear Information System (INIS)

Mohajer, A.A.; Doughty, M.

1996-08-01

Monitoring of small magnitude ('micro') earthquakes in a dense local network is one of the techniques used to delineate currently active faults and seismic sources. The conventional wisdom is that smaller, but more frequent, seismic events normally occur on active fault planes and a log linear empirical relation between frequency and magnitude can be used to estimate the magnitude and recurrence (frequency) of the larger events. A program of site-specific seismic monitoring has been supported by the AECB since 1991, to investigate the feasibility of microearthquake detection in suburban areas of east Toronto in order to assess the rate activity of local events in the vicinity of the nuclear power plants at Pickering and Darlington. For deployment of the seismic stations at the most favorable locations an extensive background noise survey was carried out. This survey involved measuring and comparing the amplitude response of the ambient vibration caused by natural phenomena (e.g. wind blow, water flow, wave action) or human activities such as farming, mining and industrial work at 25 test sites. Subsequently, a five-station seismic network, with a 30 km aperture, was selected between the Pickering and Darlington nuclear power plants on Lake Ontario, to the south, and Lake Scugog to the north. The detection threshold obtained for two of the stations allows recording of local events M L =0-2, a magnitude range which is usually not detected by regional seismic networks. An analysis of several thousand triggered signals resulted in the identification of about 120 local events, which can not be assigned to any source other than the natural release of crustal stresses. The recurrence frequency of these microearthquakes shows a linear relationship which matches that of larger events in the last two centuries in this region. The preliminary results indicate that the stress is currently accumulating and is being released within clusters of small earthquakes

A pilot study to measure levels of selected elements in Thai foods by instrumental neutron activation analysis

International Nuclear Information System (INIS)

Laoharojanaphand, S.; Busamongkol, A.; Permnamtip, V.; Judprasong, K.; Chatt, A.

2012-01-01

A pilot study was carried out to evaluate the scope of instrumental neutron activation analysis (INAA) for measuring the levels of selected elements in a few commonly consumed food items in Thailand. Several varieties of rice, beans, aquatic food items, vegetables and soybean products were bought from major distribution centers in Bangkok, Thailand. Samples were prepared according to the protocols prescribed by the nutritionist for food compositional analysis. Levels of As, Br, Ca, Cd, Cl, Cr, Cu, Fe, K, Mg, Mn, and Zn were measured by INAA using the irradiation and counting facilities available at the Thai Research Reactor with the maximum in-core thermal neutron flux of 3 x 10 13 cm -2 s -1 of the Thailand Institute of Nuclear Technology in Bangkok. Selenium was determined by cyclic INAA using the Dalhousie University SLOWPOKE-2 Reactor facilities in Halifax, Canada at a thermal neutron flux of 2.5 x 10 11 cm -2 s -1 . Both cooked and uncooked foods were analyzed. The elemental composition of food products was found to depend significantly on the raw material as well as the preparation technique. (author)

Nuclear reactors. Introduction

International Nuclear Information System (INIS)

Boiron, P.

1997-01-01

This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

Nuclear reactor, reactor core thereof, and device for constituting the reactor

International Nuclear Information System (INIS)

Takiyama, Masashi.

1994-01-01

A reactor core is constituted by charging coolants (light water) in a reactor pressure vessel and distributing fuel assemblies, reflecting material sealing pipes, moderator (heavy water and helium gas) sealing pipes, and gas sealing pipes therein. A fuel guide tube is surrounded by a cap and the gap therebetween is made hollow and filled with coolant steams. The cap is supported by a baffle plate. The moderator sealing pipe is disposed in a flow channel of coolants in adjacent with the cap. The position of the moderator sealing tube in the reactor core is controlled by water stream from a hydraulic pump with a guide tube extending below the baffle plate being as a guide. Then, the position of the moderator sealing tube is varied to conduct power control, burnup degree compensation, and reactor shut down. With such procedures, moderator cooling facility is no more necessary to simplify the structure. Further, heat generated from the moderator is transferred to the coolants thereby improving heat efficiency of the reactor. (I.N.)

Slurry reactors

Energy Technology Data Exchange (ETDEWEB)

Kuerten, H; Zehner, P [BASF A.G., Ludwigshafen am Rhein (Germany, F.R.)

1979-08-01

Slurry reactors are designed on the basis of empirical data and model investigations. It is as yet not possible to calculate the flow behavior of such reactors. The swarm of gas bubbles and cluster formations of solid particles and their interaction in industrial reactors are not known. These effects control to a large extent the gas hold-up, the gas-liquid interface and, similarly as in bubble columns, the back-mixing of liquids and solids. These hydrodynamic problems are illustrated in slurry reactors which constructionally may be bubble columns, stirred tanks or jet loop reactors. The expected effects are predicted by means of tests with model systems modified to represent the conditions in industrial hydrogenation reactors. In his book 'Mass Transfer in Heterogeneous Catalysis' (1970) Satterfield complained of the lack of knowledge about the design of slurry reactors and hence of the impossible task of the engineer who has to design a plant according to accepted rules. There have been no fundamental changes since then. This paper presents the problems facing the engineer in designing slurry reactors, and shows new development trends.

Optimal reactor strategy for commercializing fast breeder reactors

International Nuclear Information System (INIS)

Yamaji, Kenji; Nagano, Koji

1988-01-01

In this paper, a fuel cycle optimization model developed for analyzing the condition of selecting fast breeder reactors in the optimal reactor strategy is described. By dividing the period of planning, 1966-2055, into nine ten-year periods, the model was formulated as a compact linear programming model. With the model, the best mix of reactor types as well as the optimal timing of reprocessing spent fuel from LWRs to minimize the total cost were found. The results of the analysis are summarized as follows. Fast breeder reactors could be introduced in the optimal strategy when they can economically compete with LWRs with 30 year storage of spent fuel. In order that fast breeder reactors monopolize the new reactor market after the achievement of their technical availability, their capital cost should be less than 0.9 times as much as that of LWRs. When a certain amount of reprocessing commitment is assumed, the condition of employing fast breeder reactors in the optimal strategy is mitigated. In the optimal strategy, reprocessing is done just to meet plutonium demand, and the storage of spent fuel is selected to adjust the mismatch of plutonium production and utilization. The price hike of uranium ore facilitates the commercial adoption of fast breeder reactors. (Kako, I.)

Computerized reactor monitor and control for nuclear reactors

International Nuclear Information System (INIS)

Buerger, L.

1982-01-01

The analysis of a computerized process control system developed by Transelektro-KFKI-Videoton (Hangary) for a twenty-year-old research reactor in Budapest and or a new one in Tajura (Libya) is given. The paper describes the computer hardware (R-10) and the implemented software (PROCESS-24K) as well as their applications at nuclear reactors. The computer program provides for man-machine communication, data acquisition and processing, trend and alarm analysis, the control of the reactor power, reactor physical calculations and additional operational functions. The reliability and the possible further development of the computerized systems which are suitable for application at reactors of different design are also discussed. (Sz.J.)

Safeguarding research reactors

International Nuclear Information System (INIS)

Powers, J.A.

1983-03-01

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

Control of reactor coolant flow path during reactor decay heat removal

Science.gov (United States)

Hunsbedt, Anstein N.

1988-01-01

An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

Challenging homophobia and heterosexism through storytelling and critical dialogue among Hong Kong Chinese immigrant parents in Toronto.

Science.gov (United States)

Wong, Josephine Pui-Hing; Poon, Maurice Kwong-Lai

2013-01-01

Homophobia and heterosexism are ubiquitous in Canadian society. They contribute to significant health and mental health disparities for lesbian, gay and bisexual youth and their families. Anti-homophobia efforts tend to focus on students and teachers at school. While these efforts are important, they do not reach parents, who play an important role in shaping young people's attitudes towards gender and sexuality. To eliminate bullying and victimisation associated with homophobia at school and in the community, concerted efforts are urgently needed to mobilise parents to become champions against homophobia and heterosexism. In this paper, we report on our use of storytelling and critical dialogue to engage a group of Hong Kong Chinese immigrant parents in Toronto to interrogate their values and assumptions about homosexuality. In particular, we illustrate how we use storytelling to create a liminal space whereby the narrators and listeners collaborate to create counter-discourses that challenge social domination and exclusion. We then discuss the implications of using a critical dialogical approach to integrate anti-homophobia efforts in community parenting programmes.

Reactor operations Brookhaven medical research reactor, Brookhaven high flux beam reactor informal monthly report

International Nuclear Information System (INIS)

Hauptman, H.M.; Petro, J.N.; Jacobi, O.

1995-04-01

This document is the April 1995 summary report on reactor operations at the Brookhaven Medical Research Reactor and the Brookhaven High Flux Beam Reactor. Ongoing experiments/irradiations in each are listed, and other significant operations functions are also noted. The HFBR surveillance testing schedule is also listed

Special design issues related to the G. Ross Lord Dam constructed in Metropolitan Toronto

Energy Technology Data Exchange (ETDEWEB)

Sowa, V.A. [Jacques Whitford and Associates Ltd., Vancouver, BC (Canada); Tawil, A.H. [Acres International Ltd., Niagara Falls, ON (Canada); Haley, D.R. [Toronto Region and Conservation Authority, Downsview, ON (Canada)

2002-07-01

This paper describes the special considerations required to build a flood control dam in a metropolitan area that holds major city infrastructures such as power transmission towers, pipelines, sanitary sewers and graveyards. The paper refers to the G. Ross Lord Dam, a 20 m high earth fill flood control dam which was constructed in 1973 on the West Branch of the Don River in Toronto. It was built following recommendations after Hurricane Hazel caused widespread flooding and the death of 81 people in 1954. The dam includes a concrete chute spillway and stilling basin. The geotechnical design of the dam was described along with the dam structures and the methods used to flood proof the infrastructure. The dam has a sloping impervious core and an upstream blanket to reduce seepage. Seepage control is provided by a drainage blanket and a chimney drain. A main overflow spillway was constructed on the south abutment, and a low level outlet was constructed at the base of the dam to accommodate normal river flows through the dam. Most of the water level control during a flood event is provided by the main overflow spillway. Spillway slab anchor keys prevent down slope creep of the slabs. The dam, the spillway and the reservoir structure have performed well since construction. 6 refs., 10 figs.

Reactor core for FBR type reactor

International Nuclear Information System (INIS)

Fujita, Tomoko; Watanabe, Hisao; Kasai, Shigeo; Yokoyama, Tsugio; Matsumoto, Hiroshi.

1996-01-01

In a gas-sealed assembly for a FBR type reactor, two or more kinds of assemblies having different eigen frequency and a structure for suppressing oscillation of liquid surface are disposed in a reactor core. Coolant introduction channels for introducing coolants from inside and outside are disposed in the inside of structural members of an upper shielding member to form a shielding member-cooling structure in the reactor core. A structure for promoting heat conduction between a sealed gas in the assembly and coolants at the inner side or the outside of the assembly is disposed in the reactor core. A material which generates heat by neutron irradiation is disposed in the assembly to heat the sealed gases positively by radiation heat from the heat generation member also upon occurrence of power elevation-type event to cause temperature expansion. Namely, the coolants flown out from or into the gas sealed-assemblies cause differential fluctuation on the liquid surface, and the change of the capacity of a gas region is also different on every gas-sealed assemblies thereby enabling to suppress fluctuation of the reactor power. Pressure loss is increased by a baffle plate or the like to lower the liquid surface of the sodium coolants or decrease the elevating speed thereof thereby suppressing fluctuation of the reactor power. (N.H.)

Space-time reactor kinetics for heterogeneous reactor structure

Energy Technology Data Exchange (ETDEWEB)

Raisic, N [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

1969-11-15

An attempt is made to formulate time dependent diffusion equation based on Feinberg-Galanin theory in the from analogue to the classical reactor kinetic equation. Parameters of these equations could be calculated using the existing codes for static reactor calculation based on the heterogeneous reactor theory. The obtained kinetic equation could be analogues in form to the nodal kinetic equation. Space-time distribution of neutron flux in the reactor can be obtained by solving these equations using standard methods.

Nuclear Reactor RA Safety Report, Vol. 4, Reactor

International Nuclear Information System (INIS)

1986-11-01

RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices [sr

Feasible reactor power cutback logic development for an integral reactor

International Nuclear Information System (INIS)

Han, Soon-Kyoo; Lee, Chung-Chan; Choi, Suhn; Kang, Han-Ok

2013-01-01

Major features of integral reactors that have been developed around the world recently are simplified operating systems and passive safety systems. Even though highly simplified control system and very reliable components are utilized in the integral reactor, the possibility of major component malfunction cannot be ruled out. So, feasible reactor power cutback logic is required to cope with the malfunction of components without inducing reactor trip. Simplified reactor power cutback logic has been developed on the basis of the real component data and operational parameters of plant in this study. Due to the relatively high rod worth of the integral reactor the control rod assembly drop method which had been adapted for large nuclear power plants was not desirable for reactor power cutback of the integral reactor. Instead another method, the control rod assembly control logic of reactor regulating system controls the control rod assembly movements, was chosen as an alternative. Sensitivity analyses and feasibility evaluations were performed for the selected method by varying the control rod assembly driving speed. In the results, sensitivity study showed that the performance goal of reactor power cutback system could be achieved with the limited range of control rod assembly driving speed. (orig.)

What Internet services would patients like from hospitals during an epidemic? Lessons from the SARS outbreak in Toronto.

Science.gov (United States)

Rizo, Carlos A; Lupea, Doina; Baybourdy, Homayoun; Anderson, Matthew; Closson, Tom; Jadad, Alejandro R

2005-08-03

International health organizations and officials are bracing for a pandemic. Although the 2003 severe acute respiratory syndrome (SARS) outbreak in Toronto did not reach such a level, it created a unique opportunity to identify the optimal use of the Internet to promote communication with the public and to preserve health services during an epidemic. The aim of the study was to explore patients' attitudes regarding the health services that might be provided through the Internet to supplement those traditionally available in the event of a future mass emergency situation. We conducted "mask-to-mask" surveys of patients at three major teaching hospitals in Toronto during the second outbreak of SARS. Patients were surveyed at the hospital entrances and selected clinics. Descriptive statistics and logistic regression models were used for the analysis. In total, 1019 of 1130 patients responded to the survey (90% overall response rate). With respect to Internet use, 70% (711/1019) used the Internet by themselves and 57% (578/1019) with the help of a friend or family member. Of the Internet users, 68% (485/711) had already searched the World Wide Web for health information, and 75% (533/711) were interested in communicating with health professionals using the Internet as part of their ongoing care. Internet users expressed interest in using the Web for the following reasons: to learn about their health condition through patient education materials (84%), to obtain information about the status of their clinic appointments (83%), to send feedback to the hospital about how to improve its services (77%), to access screening tools to help determine if they were potentially affected by the infectious agent responsible for the outbreak (77%), to renew prescriptions (75%), to consult with their health professional about nonurgent matters (75%), and to access laboratory test results (75%). Regression results showed that younger age, higher education, and English as a first

Toward a joint health and disease management program. Toronto hospitals partner to provide system leadership.

Science.gov (United States)

Macleod, Anne Marie; Gollish, Jeffrey; Kennedy, Deborah; McGlasson, Rhona; Waddell, James

2009-01-01

The Joint Health and Disease Management Program in the Toronto Central Local Health Integration Network (TC LHIN) is envisioned as a comprehensive model of care for patients with hip and knee arthritis. It includes access to assessment services, education, self-management programs and other treatment programs, including specialist care as needed. As the first phase of this program, the hospitals in TC LHIN implemented a Hip and Knee Replacement Program to focus on improving access and quality of care, coordinating services and measuring wait times for patients waiting for hip or knee replacement surgery. The program involves healthcare providers, consumers and constituent hospitals within TC LHIN. The approach used for this program involved a definition of governance structure, broad stakeholder engagement to design program elements and plans for implementation and communication to ensure sustainability. The program and approach were designed to provide a model that is transferrable in its elements or its entirety to other patient populations and programs. Success has been achieved in creating a single wait list, developing technology to support referral management and wait time reporting, contributing to significant reductions in waits for timely assessment and treatment, building human resource capacity and improving patient and referring physician satisfaction with coordination of care.

Darlington NGD valve packing program

International Nuclear Information System (INIS)

Spence, C.G.

1995-01-01

Darlington NGD is a four unit CANDU 1000 nuclear generation station, located on the shores of Lake Ontario, approximately 45 miles east of Toronto. The CANDU design is a Pressurized Heavy Water Reactor (PHWR), each unit at Darlington is designed to produce 940MWe. The commissioning phase of the station was completed in the spring of 1993. (author)

GENOMICS, BIOTECHNOLOGY AND GLOBALHEALTH: THE WORK OF THE UNIVERSITY OF TORONTO JOINT CENTRE FOR BIOETHICS GENÓMICA, BIOTECNOLOGÍA Y SALUD MUNDIAL: EL TRABAJO DEL CENTRO ASOCIADO DE BIOÉTICA DE LA UNIVERSIDAD DE TORONTO GENÓMICA, BIOTECNOLOGIA E SAÚDE MUNDIAL: O TRABALHO DO CENTRO ASSOCIADO DE BIOÉTICA DA UNIVERSIDADE DE TORONTO

Directory of Open Access Journals (Sweden)

Abdallah S Daar

2004-01-01

Full Text Available The new and rapidly advancing field of genomics and related biotechnologies has the ability to either improve or worsen global health inequities. In general, developing countries are left behind in the development of new technologies and advances in genomic medicine. In this view, the University of Toronto Joint Centre for Bioethics (JCB through the Canadian Program on Genomics and Global Health has developed 25 research projects on capacity enhancement for developing countries for improving global health equity, including public health via genomics and related biotechnologies. One project with a great impact was the “Top Ten Biotechnologies for Improving Health in Developing Countries” for its influence in the “Grand Challenges in Global Health Initiative” foster by the Melinda Gates Foundation. Additionally, the UN Millennium Development Project has asked JCB to become the genomics working group for improving global health through genomics biotechnology and JCB has started by studying applications of genomics/biotechnologies in seven developing countries: Brazil, China, Cuba, Egypt, India, South Africa and South Korea, which may set examples for other developing nationsEl nuevo campo de la genómica y sus biotecnologías relacionadas, de rápido desarrollo, tiene la habilidad tanto de mejorar como de empeorar las desigualdades globales en salud. En general, los países en desarrollo quedan atrás en el desarrollo de nuevas tecnologías y avances en la medicina genómica. En vista de esta situación, el Centro Asociado de Bioética de la Universidad de Toronto (JCB a través del Programa Canadiense sobre Genómica y Salud Global ha desarrollado 25 proyectos de investigación sobre desarrollo de capacidades en países en desarrollo para mejorar la equidad en salud global, incluyendo la salud pública a través de la genómica y sus biotecnologías relacionadas. Entre estos, un proyecto de gran impacto fue “Diez Biotecnologías de Mayor

RA Reactor

International Nuclear Information System (INIS)

1978-02-01

In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation [sr

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...

Reactor container

International Nuclear Information System (INIS)

Naruse, Yoshihiro.

1990-01-01

The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

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

Nuclear research reactors

International Nuclear Information System (INIS)

1985-01-01

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

Using nudges to reduce waste? The case of Toronto's plastic bag levy.

Science.gov (United States)

Rivers, Nicholas; Shenstone-Harris, Sarah; Young, Nathan

2017-03-01

The overuse of disposable plastic bags is a major environmental problem across the globe. In recent years, numerous jurisdictions have sought to curb disposable bag use by implementing a levy or fee at the point of purchase. These levies are typically small and symbolic (around $0.05 per bag), but serve as a highly-visible and continuous reminder to consumers. As such, they are consistent with nudging policies that seek to encourage broad changes in behaviour through small, non-coercive measures that influence people's thinking about an issue. While existing empirical evidence suggests that nudges are highly effective in reducing disposable bag use, we argue that many of these studies are flawed because they lack adequate temporal and geographic controls. We use longitudinal data from four waves of a major Canadian survey to analyze the effect of a disposable bag levy in the City of Toronto. Controlling for demographics and changes in social norms over time, we find that the levy increased the use of reusable shopping bags by 3.4 percentage points. Moreover, we find that the impact of the policy was highly variable across behavioural and demographic groups. The levy was highly effective in encouraging people who already used reusable bags to use them more frequently, while having no effect on infrequent users. We also find that the effects are limited to households with high socio-economic status (as measured by income, educational attainment, and housing situation). This suggests important limitations for nudging policy more generally, as people with lower socio-economic status appear to have been unaffected by this behavioural prompt. Copyright © 2016 Elsevier Ltd. All rights reserved.

Strategic planning for research reactors. Guidance for reactor managers

International Nuclear Information System (INIS)

2001-04-01

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

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1991-04-01

The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

Research reactors - an overview

International Nuclear Information System (INIS)

West, C.D.

1997-01-01

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

Multiregion reactors

International Nuclear Information System (INIS)

Moura Neto, C. de; Nair, R.P.K.

1979-08-01

The study of reflected reactors can be done employing the multigroup diffusion method. The neutron conservation equations, inside the intervals, can be written by fluxes and group constants. A reflected reactor (one and two groups) for a slab geometry is studied, aplying the continuity of flux and current in the interface. At the end, the appropriated solutions for a infinite cylindrical reactor and for a spherical reactor are presented. (Author) [pt

Reactor building

International Nuclear Information System (INIS)

Maruyama, Toru; Murata, Ritsuko.

1996-01-01

In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

Nuclear reactor

International Nuclear Information System (INIS)

Garabedian, G.

1988-01-01

A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

Reactor physics challenges in GEN-IV reactor design

Energy Technology Data Exchange (ETDEWEB)

Driscoll, Michael K.; Hejzlar, Pavel [Massachusetts Institute of Technology, MA (United States)

2005-02-15

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources.

Reactor physics challenges in GEN-IV reactor design

International Nuclear Information System (INIS)

Driscoll, Michael K.; Hejzlar, Pavel

2005-01-01

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources

Reactor Vessel Surveillance Program for Advanced Reactor

Energy Technology Data Exchange (ETDEWEB)

Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

2008-10-15

This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

What does it mean to ‘eat Jewishly?’: authorizing discourse in the Jewish food movement in Toronto, Canada

Directory of Open Access Journals (Sweden)

Aldea Mulhern

2015-01-01

Full Text Available This article examines the development of ‘eating Jewishly’ among participants at Shoresh Jewish Environmental Programs in Toronto, Canada. Participants at Shoresh construct and draw upon Jewish tradition in order to resolve gaps between the is and the ought of the conventional food system, and to a lesser extent, the narrower food system of kashrut. ‘Eating Jewishly’ re-positions religious orthodoxy as one in a set of authorizing discourses, subsuming all Jewish eating acts under one rubric. ‘Eating Jewishly’ thus departs from standard narratives of Jewish eating as either eating kosher, or eating traditional Jewish foods. I use a theory of authorizing discourse to show the conditions of possibility through which Shoresh develops their intervention as Jewish. I conclude that such authorization practices are a key form of productive constraint in the formation of Shoresh’s lived religion, and in the formation of religion as a framework for social good.

The nuclear reactor strategy between fast breeder reactors and advanced pressurized water reactors

International Nuclear Information System (INIS)

Seifritz, W.

1983-01-01

A nuclear reactor strategy between fast breeder reactors (FBRs) and advanced pressurized water reactors (APWRs) is being studied. The principal idea of this strategy is that the discharged plutonium from light water reactors (LWRs) provides the inventories of the FBRs and the high-converter APWRs, whereby the LWRs are installed according to the derivative of a logistical S curve. Special emphasis is given to the dynamics of reaching an asymptotic symbiosis between FBRs and APWRs. The main conclusion is that if a symbiotic APWR-FBR family with an asymptotic total power level in the terawatt range is to exist in about half a century from now, we need a large number of FBRs already in an early phase

Increased SRP reactor power

International Nuclear Information System (INIS)

MacAfee, I.M.

1983-01-01

Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

Latent segmentation based count models: Analysis of bicycle safety in Montreal and Toronto.

Science.gov (United States)

Yasmin, Shamsunnahar; Eluru, Naveen

2016-10-01

The study contributes to literature on bicycle safety by building on the traditional count regression models to investigate factors affecting bicycle crashes at the Traffic Analysis Zone (TAZ) level. TAZ is a traffic related geographic entity which is most frequently used as spatial unit for macroscopic crash risk analysis. In conventional count models, the impact of exogenous factors is restricted to be the same across the entire region. However, it is possible that the influence of exogenous factors might vary across different TAZs. To accommodate for the potential variation in the impact of exogenous factors we formulate latent segmentation based count models. Specifically, we formulate and estimate latent segmentation based Poisson (LP) and latent segmentation based Negative Binomial (LNB) models to study bicycle crash counts. In our latent segmentation approach, we allow for more than two segments and also consider a large set of variables in segmentation and segment specific models. The formulated models are estimated using bicycle-motor vehicle crash data from the Island of Montreal and City of Toronto for the years 2006 through 2010. The TAZ level variables considered in our analysis include accessibility measures, exposure measures, sociodemographic characteristics, socioeconomic characteristics, road network characteristics and built environment. A policy analysis is also conducted to illustrate the applicability of the proposed model for planning purposes. This macro-level research would assist decision makers, transportation officials and community planners to make informed decisions to proactively improve bicycle safety - a prerequisite to promoting a culture of active transportation. Copyright © 2016 Elsevier Ltd. All rights reserved.

Health status of newly arrived refugees in Toronto, Ont: Part 1: infectious diseases.

Science.gov (United States)

Redditt, Vanessa J; Janakiram, Praseedha; Graziano, Daniela; Rashid, Meb

2015-07-01

To determine the prevalence of selected infectious diseases among newly arrived refugee patients and whether there is variation by key demographic factors. Retrospective chart review. Primary care clinic for refugee patients in Toronto, Ont. A total of 1063 refugee patients rostered at the clinic from December 2011 to June 2014. Demographic information (age, sex, and region of birth); prevalence of HIV, hepatitis B, hepatitis C, Strongyloides, Schistosoma, intestinal parasites, gonorrhea, chlamydia, and syphilis infections; and varicella immune status. The median age of patients was 29 years and 56% were female. Refugees were born in 87 different countries. Approximately 33% of patients were from Africa, 28% were from Europe, 14% were from the Eastern Mediterranean Region, 14% were from Asia, and 8% were from the Americas (excluding 4% born in Canada or the United States). The overall rate of HIV infection was 2%. The prevalence of hepatitis B infection was 4%, with a higher rate among refugees from Asia (12%, P refugees (64%, P refugees from Africa (6%, P = .003). Schistosoma infection was identified in 15% of patients from Africa. Intestinal parasites were identified in 16% of patients who submitted stool samples. Approximately 8% of patients were varicella nonimmune, with higher rates in patients from the Americas (21%, P refugee patients to provide timely preventive and curative care. Our data also point to possible policy and clinical implications, such as targeted screening approaches and improved access to vaccinations and therapeutics. Copyright© the College of Family Physicians of Canada.

Source, concentration, and distribution of elemental mercury in the atmosphere in Toronto, Canada

International Nuclear Information System (INIS)

Cairns, Elaine; Tharumakulasingam, Kavitharan; Athar, Makshoof; Yousaf, Muhammad; Cheng, Irene; Huang, Y.; Lu, Julia; Yap, Dave

2011-01-01

Atmospheric gaseous elemental mercury [GEM] at 1.8, 4, and 59 m above ground, in parking lots, and in indoor and outdoor air was measured in Toronto City, Canada from May 2008-July 2009. The average GEM value at 1.8 m was 1.89 ± 0.62 ng m -3 . The GEM values increased with elevation. The average GEM in underground parking lots ranged from 1.37 to 7.86 ng m -3 and was higher than those observed from the surface parking lots. The GEM in the indoor air ranged from 1.21 to 28.50 ng m -3 , was higher in the laboratories than in the offices, and was much higher than that in the outdoor air. All these indicate that buildings serve as sources of mercury to the urban atmosphere. More studies are needed to estimate the contribution of urban areas to the atmospheric mercury budget and the impact of indoor air on outdoor air quality and human health. - Highlights: → Buildings served as mercury sources to urban atmosphere. → Atmospheric mercury level increased with increasing height in the street canyon. → Emission from vehicles and ground surfaces was not the major sources of Hg to urban air. → Mercury levels were higher in indoor than outdoor air and in laboratories than in offices. → Mercury levels were higher in the outdoor air near building walls. - Buildings serve as sources of gaseous elemental mercury and research is needed to quantify the emission and to assess the impact of indoor air on outdoor air quality and human health.

Tokamak reactor studies

International Nuclear Information System (INIS)

Baker, C.C.

1981-01-01

This paper presents an overview of tokamak reactor studies with particular attention to commercial reactor concepts developed within the last three years. Emphasis is placed on DT fueled reactors for electricity production. A brief history of tokamak reactor studies is presented. The STARFIRE, NUWMAK, and HFCTR studies are highlighted. Recent developments that have increased the commercial attractiveness of tokamak reactor designs are discussed. These developments include smaller plant sizes, higher first wall loadings, improved maintenance concepts, steady-state operation, non-divertor particle control, and improved reactor safety features

Computerized reactor monitor and control for research reactors

International Nuclear Information System (INIS)

Buerger, L.; Vegh, E.

1981-09-01

The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

Calculation of low-energy reactor neutrino spectra reactor for reactor neutrino experiments

Energy Technology Data Exchange (ETDEWEB)

Riyana, Eka Sapta; Suda, Shoya; Ishibashi, Kenji; Matsuura, Hideaki [Dept. of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Kyushu (Japan); Katakura, Junichi [Dept. of Nuclear System Safety Engineering, Nagaoka University of Technology, Nagaoka (Japan)

2016-06-15

Nuclear reactors produce a great number of antielectron neutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may take part in special weak interactions. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectrum from a typical pressurized water reactor (PWR) reactor core. To calculate neutrino spectra, we need information about all generated nuclides that emit neutrinos. They are mainly fission fragments, reaction products and trans-uranium nuclides that undergo negative beta decay. Information in relation to trans-uranium nuclide compositions and its evolution in time (burn-up process) were provided by a reactor code MVP-BURN. We used typical PWR parameter input for MVP-BURN code and assumed the reactor to be operated continuously for 1 year (12 months) in a steady thermal power (3.4 GWth). The PWR has three fuel compositions of 2.0, 3.5 and 4.1 wt% {sup 235}U contents. For preliminary calculation we adopted a standard burn-up chain model provided by MVP-BURN. The chain model treated 21 heavy nuclides and 50 fission products. The MVB-BURN code utilized JENDL 3.3 as nuclear data library. We confirm that the antielectron neutrino flux in the low energy region increases with burn-up of nuclear fuel. The antielectron-neutrino spectrum in low energy region is influenced by beta emitter nuclides with low Q value in beta decay (e.g. {sup 241}Pu) which is influenced by burp-up level: Low energy antielectron-neutrino spectra or emission rates increase when beta emitters with low Q value in beta decay accumulate. Our result shows the flux of low energy reactor neutrinos increases with burn-up of nuclear fuel.

Nuclear Reactor Physics

Science.gov (United States)

Stacey, Weston M.

2001-02-01

An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

Reactor. Mind picture of the future Jules-Horowitz Reactor (RHJ)

International Nuclear Information System (INIS)

Eustache, S.

1999-01-01

This paper gives information about the future research reactor, named Reactor Jules-Horowitz (RJH). This irradiation reactor will be placed at industrialists disposal, for research concerning the competitiveness and the safety french electro-nuclear park. Principles and innovations are detailed. This reactor will respect the ALARA principle (as low as reasonably achievable). (A.L.B.)

The analysis for inventory of experimental reactor high temperature gas reactor type

International Nuclear Information System (INIS)

Sri Kuntjoro; Pande Made Udiyani

2016-01-01

Relating to the plan of the National Nuclear Energy Agency (BATAN) to operate an experimental reactor of High Temperature Gas Reactors type (RGTT), it is necessary to reactor safety analysis, especially with regard to environmental issues. Analysis of the distribution of radionuclides from the reactor into the environment in normal or abnormal operating conditions starting with the estimated reactor inventory based on the type, power, and operation of the reactor. The purpose of research is to analyze inventory terrace for Experimental Power Reactor design (RDE) high temperature gas reactor type power 10 MWt, 20 MWt and 30 MWt. Analyses were performed using ORIGEN2 computer code with high temperatures cross-section library. Calculation begins with making modifications to some parameter of cross-section library based on the core average temperature of 570 °C and continued with calculations of reactor inventory due to RDE 10 MWt reactor power. The main parameters of the reactor 10 MWt RDE used in the calculation of the main parameters of the reactor similar to the HTR-10 reactor. After the reactor inventory 10 MWt RDE obtained, a comparison with the results of previous researchers. Based upon the suitability of the results, it make the design for the reactor RDE 20MWEt and 30 MWt to obtain the main parameters of the reactor in the form of the amount of fuel in the pebble bed reactor core, height and diameter of the terrace. Based on the main parameter or reactor obtained perform of calculation to get reactor inventory for RDE 20 MWT and 30 MWT with the same methods as the method of the RDE 10 MWt calculation. The results obtained are the largest inventory of reactor RDE 10 MWt, 20 MWt and 30 MWt sequentially are to Kr group are about 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq, for group I are 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq and for groups Cs are 2,20E+16 Bq, 2,40E+16 Bq, 2,60E+16 Bq. Reactor inventory will then be used to calculate the reactor source term and it

FBR type reactors

International Nuclear Information System (INIS)

Suzuoki, Akira; Yamakawa, Masanori.

1985-01-01

Purpose: To enable safety and reliable after-heat removal from a reactor core. Constitution: During ordinary operation of a FBR type reactor, sodium coolants heated to a high temperature in a reactor core are exhausted therefrom, collide against the reactor core upper mechanisms to radially change the flowing direction and then enter between each of the guide vanes. In the case if a main recycling pump is failed and stopped during reactor operation and the recycling force is eliminated, the swirling stream of sodium that has been resulted by the flow guide mechanism during normal reactor operation is continuously maintained within a plenum at a high temperature. Accordingly, the sodium recycling force in the coolant flow channels within the reactor vessel can surely be maintained for a long period of time due to the centrifugal force of the sodium swirling stream. In this way, since the reactor core recycling flow rate can be secured even after the stopping of the main recycling pump, after-heat from the reactor core can safely and surely be removed. (Seki, T.)

FBR type reactor

International Nuclear Information System (INIS)

Hayase, Tamotsu.

1991-01-01

The present invention concerns an FBR type reactor in which transuranium elements are eliminated by nuclear conversion. There are loaded reactor core fuels being charged with mixed oxides of plutonium and uranium, and blanket fuels mainly comprising depleted uranium. Further, liquid sodium is used as coolants. As transuranium elements, isotope elements of neptunium, americium and curium contained in wastes taken out from light water reactors or the composition thereof are used. The reactor core comprises a region with a greater mixing ratio and a region with a less mixing ratio of the transuranium elements. The mixing ratio of the transuranium elements is made greater for the fuels in the reactor core region at the boundary with the blanket of great neutron leakage. With such a constitution, since the positive reactivity value at the reactor core central portion is small in the Na void reactivity distribution in the reactor core, the positive reactivity is small upon Na boiling in the reactor core central region upon occurrence of imaginable accident, to attain reactor safety. (I.N.)

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

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-07-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

International Nuclear Information System (INIS)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

Thai research reactor

International Nuclear Information System (INIS)

Aramrattana, M.

1987-01-01

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

Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

Energy Technology Data Exchange (ETDEWEB)

Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Poore, III, Willis P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Moe, Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-03-01

This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

Nuclear reactor instrumentation at research reactor renewal

International Nuclear Information System (INIS)

Baers, B.; Pellionisz, P.

1981-10-01

The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

Reactor System Design

International Nuclear Information System (INIS)

Chi, S. K.; Kim, G. K.; Yeo, J. W.

2006-08-01

SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

BWR type reactor

International Nuclear Information System (INIS)

Watanabe, Shoichi

1983-01-01

Purpose : To flatten the radial power distribution in the reactor core thereby improve the thermal performance of the reactor core by making the moderator-fuel ratio of fuel assemblies different depending on their position in the reactor core. Constitution : The volume of fuels disposed in the peripheral area of the reactor core is decreased by the increase of the volume of moderators in fuel assemblies disposed in the peripheral area of the reactor core to thereby make the moderator-fuel volume greater in the peripheral area than that in the central area. The moderator-fuel ratio adjustment is attained by making the number of water rods greater, decreasing the diameter of fuel pellets or decreasing the number of fuel pins in fuel assemblies disposed at the peripheral area of the reactor core as compared with fuel assemblies disposed at the central area of the reactor core. In this way, the infinite multiplication factors of fuels can be increased to thereby improve the reactor core performance. (Aizawa, K.)

Prevention device for rapid reactor core shutdown in BWR type reactors

International Nuclear Information System (INIS)

Koshi, Yuji; Karatsu, Hiroyuki.

1986-01-01

Purpose: To surely prevent rapid shutdown of a nuclear reactor upon partial load interruption due to rapid increase in the system frequency. Constitution: If a partial load interruption greater than the sum of the turbine by-pass valve capacity and the load setting bias portion is applied in a BWR type power plant, the amount of main steams issued from the reactor is decreased, the thermal input/output balance of the reactor is lost, the reactor pressure is increased, the void is collapsed, the neutron fluxes are increased and the reactor power rises to generate rapid reactor shutdown. In view of the above, the turbine speed signal is compared with a speed setting value in a recycling flowrate control device and the recycling pump is controlled to decrease the recycling flowrate in order to compensate the increase in the neutron fluxes accompanying the reactor power up. In this way, transient changes in the reactor core pressure and the neutron fluxes are kept within a setting point for the rapid reactor shutdown operation thereby enabling to continue the plant operation. (Horiuchi, T.)

The Toronto Obsessive-Compulsive Scale: Psychometrics of a Dimensional Measure of Obsessive-Compulsive Traits.

Science.gov (United States)

Park, Laura S; Burton, Christie L; Dupuis, Annie; Shan, Janet; Storch, Eric A; Crosbie, Jennifer; Schachar, Russell J; Arnold, Paul D

2016-04-01

To describe the Toronto Obsessive-Compulsive Scale (TOCS), a novel 21-item parent- or self-report questionnaire that covers wide variation in obsessive-compulsive (OC) traits, and to evaluate its psychometric properties in a community-based pediatric sample. The TOCS was completed for 16,718 children and adolescents between the ages of 6 and 17 years in a community setting. Internal consistency, convergent validity with the Obsessive-Compulsive Scale of the Child Behaviour Checklist (CBCL-OCS), divergent validity with the Strengths and Weaknesses of ADHD (Attention-Deficit/Hyperactivity Disorder) Symptoms and Normal Behaviour Rating Scale (SWAN), interrater reliability, as well as sensitivity and specificity of the TOCS were assessed. The internal consistency of the 21 TOCS items was excellent (Cronbach's α = 0.94). TOCS was moderately correlated with the CBCL-OCS (Spearman correlation = 0.51) and poorly correlated with the SWAN (Pearson correlation = 0.02). Sensitivity and specificity analyses indicated that a TOCS total score of greater than 0 successfully discriminated community-reported obsessive-compulsive disorder (OCD) cases from noncases. OC traits were continuously distributed both at the total score and dimensional level in our pediatric community sample. TOCS is a multidimensional measure of OC traits in children and adolescents with sound psychometric properties. TOCS reveals that OC traits are common and continuously distributed in a community sample. TOCS may be a useful measure for studies of the characteristics and etiology of OC traits. Copyright © 2016. Published by Elsevier Inc.

An observational study of bullying as a contributing factor in youth suicide in Toronto.

Science.gov (United States)

Sinyor, Mark; Schaffer, Ayal; Cheung, Amy H

2014-12-01

Bullying has been identified as a potential contributing factor in youth suicide. This issue has been highlighted in recent widely publicized media reports, worldwide, in which deceased youth were bullied. We report on an observational study conducted to determine the frequency of bullying as a contributing factor to youth suicide. Coroner records were reviewed for all suicide deaths in youth aged between 10 and 19 in the city of Toronto from 1998 to 2011. Data abstracted were recent stressors (including bullying), clinical variables, such as the presence of mental illness, demographics, and methods of suicide. Ninety-four youth suicides were included in the study. The mean age was 16.8 years, and 70.2% were male. Bullying was present in 6 deaths (6.4%), and there were no deaths where online or cyberbullying was detected. Bullying was the only identified contributing factor in fewer than 5 deaths. The most common stressors identified were conflict with parents (21.3%), romantic partner problems (17.0%), academic problems (10.6%), and criminal and (or) legal problems (10.6%). Any stressor or mental and (or) physical illness was detected in 78.7% of cases. Depression was detected in 40.4% of cases. Our study highlights the need to view suicide in youth as arising from a complex interplay of various biological, psychological, and social factors of which bullying is only one. It challenges simple cause-and-effect models that may suggest that suicide arises from anyone factor, such as bullying.

Reactor core of nuclear reactor

International Nuclear Information System (INIS)

Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

1994-01-01

In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

Proceedings of the fourth international conference on CANDU maintenance

International Nuclear Information System (INIS)

1997-01-01

These proceedings record the information presented at the 4th International Conference on CANDU Maintenance held November 16-18,1997 in Toronto, Canada. The papers for these proceedings were prepared on component maintenance, human performance, steam generator leak detection, fuel channel inspections, rotating equipment maintenance, surveillance programs, inspection techniques, valve maintenance, steam generator repairs and performance, reactor aging management and preventative maintenance

Proceedings of the fourth international conference on CANDU maintenance

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

These proceedings record the information presented at the 4th International Conference on CANDU Maintenance held November 16-18,1997 in Toronto, Canada. The papers for these proceedings were prepared on component maintenance, human performance, steam generator leak detection, fuel channel inspections, rotating equipment maintenance, surveillance programs, inspection techniques, valve maintenance, steam generator repairs and performance, reactor aging management and preventative maintenance.

High-temperature and breeder reactors - economic nuclear reactors of the future

International Nuclear Information System (INIS)

Djalilzadeh, A.M.

1977-01-01

The thesis begins with a review of the theory of nuclear fission and sections on the basic technology of nuclear reactors and the development of the first generation of gas-cooled reactors applied to electricity generation. It then deals in some detail with currently available and suggested types of high temperature reactor and with some related subsidiary issues such as the coupling of different reactor systems and various schemes for combining nuclear reactors with chemical processes (hydrogenation, hydrogen production, etc.), going on to discuss breeder reactors and their application. Further sections deal with questions of cost, comparison of nuclear with coal- and oil-fired stations, system analysis of reactor systems and the effect of nuclear generation on electricity supply. (C.J.O.G.)

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

Observations of Lake-Breeze Events During the Toronto 2015 Pan-American Games

Science.gov (United States)

Mariani, Zen; Dehghan, Armin; Joe, Paul; Sills, David

2018-01-01

Enhanced meteorological observations were made during the 2015 Pan and Parapan American Games in Toronto in order to measure the vertical and horizontal structure of lake-breeze events. Two scanning Doppler lidars (one fixed and one mobile), a C-band radar, and a network including 53 surface meteorological stations (mesonet) provided pressure, temperature, humidity, and wind speed and direction measurements over Lake Ontario and urban areas. These observations captured the full evolution (prior, during, and after) of 27 lake-breeze events (73% of observation days) in order to characterize the convective and dynamic processes driving lake breezes at the local scale and mesoscale. The dominant signal of a passing lake-breeze front (LBF) was an increase in dew-point temperature of 2.3 ± 0.3°C, coinciding with a 180° shift in wind direction and a decrease in air temperature of 2.1 ± 0.2°C. Doppler lidar observations over the lake detected lake breezes 1 hour (on average) before detection by radar and mesonet. On days with the synoptic flow in the offshore direction, the lidars observed wedge-shaped LBFs with shallow depths, which inhibited the radar's ability to detect the lake breeze. The LBF's ground speed and inland penetration distance were found to be well-correlated (r = 0.78), with larger inland penetration distances occurring on days with non-opposing (non-offshore) synoptic flow. The observed enhanced vertical motion ({>} 1 m s^{-1}) at the LBF, observed by the lidar on 54% of lake-breeze days, was greater (at times {>} 2.5 m s^{-1}) than that observed in previous studies and longer-lasting over the lake than over land. The weaker and less pronounced lake-breeze structure over land is illustrated in two case studies highlighting the lifetime of the lake-breeze circulation and the impact of propagation distance on lake-breeze intensity.

Nuclear reactor neutron shielding

Science.gov (United States)

Speaker, Daniel P; Neeley, Gary W; Inman, James B

2017-09-12

A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

Fast breeder reactors

International Nuclear Information System (INIS)

Heinzel, V.

1975-01-01

The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

Reactor container

International Nuclear Information System (INIS)

Shibata, Satoru; Kawashima, Hiroaki

1984-01-01

Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

Reactor technology: power conversion systems and reactor operation and maintenance

International Nuclear Information System (INIS)

Powell, J.R.

1977-01-01

The use of advanced fuels permits the use of coolants (organic, high pressure helium) that result in power conversion systems with good thermal efficiency and relatively low cost. Water coolant would significantly reduce thermal efficiency, while lithium and salt coolants, which have been proposed for DT reactors, will have comparable power conversion efficiencies, but will probably be significantly more expensive. Helium cooled blankets with direct gas turbine power conversion cycles can also be used with DT reactors, but activation problems will be more severe, and the portion of blanket power in the metallic structure will probably not be available for the direct cycle, because of temperature limitations. A very important potential advantage of advanced fuel reactors over DT fusion reactors is the possibility of easier blanket maintenance and reduced down time for replacement. If unexpected leaks occur, in most cases the leaking circuit can be shut off and a redundant cooling curcuit will take over the thermal load. With the D-He 3 reactor, it appears practical to do this while the reactor is operating, as long as the leak is small enough not to shut down the reactor. Redundancy for Cat-D reactors has not been explored in detail, but appears feasible in principle. The idea of mobile units operating in the reactor chamber for service and maintenance of radioactive elements is explored

Fusion-fission hybrid reactors

International Nuclear Information System (INIS)

Greenspan, E.

1984-01-01

This chapter discusses the range of characteristics attainable from hybrid reactor blankets; blanket design considerations; hybrid reactor designs; alternative fuel hybrid reactors; multi-purpose hybrid reactors; and hybrid reactors and the energy economy. Hybrid reactors are driven by a fusion neutron source and include fertile and/or fissile material. The fusion component provides a copious source of fusion neutrons which interact with a subcritical fission component located adjacent to the plasma or pellet chamber. Fissile fuel and/or energy are the main products of hybrid reactors. Topics include high F/M blankets, the fissile (and tritium) breeding ratio, effects of composition on blanket properties, geometrical considerations, power density and first wall loading, variations of blanket properties with irradiation, thermal-hydraulic and mechanical design considerations, safety considerations, tokamak hybrid reactors, tandem-mirror hybrid reactors, inertial confinement hybrid reactors, fusion neutron sources, fissile-fuel and energy production ability, simultaneous production of combustible and fissile fuels, fusion reactors for waste transmutation and fissile breeding, nuclear pumped laser hybrid reactors, Hybrid Fuel Factories (HFFs), and scenarios for hybrid contribution. The appendix offers hybrid reactor fundamentals. Numerous references are provided

Academic performance and educational pathways of young allophones: A comparative multivariate analysis of Montreal, Toronto, and Vancouver

Directory of Open Access Journals (Sweden)

Jacques Ledent

2013-05-01

Full Text Available Using several local and provincial data banks enabling one to follow the school progression of the cohort of students who, in Canada’s three main immigration-destination cities, were expected to graduate secondary school in 2004, this article examines the academic performance and educational pathways of those students who at home use a language other the main language of schooling: non-French speakers in Montreal and non-English speakers in Toronto and Vancouver. First, after accounting for differences in characteristics, those students (target group are shown to succeed better than the remaining students (comparison group, especially in Vancouver. However, within the target group, there appear to be substantial differences in performance between linguistic subgroups, which are far from being similar in all three cities. Second, the individual and contextual factors that influence the academic performance of the students in the target group appear to be similar for some and different for others in the three cities, while presenting some more-or-less large discrepancies with the corresponding factors pertaining to the comparison group. The article concludes with a few policy implications.

Reactor protection systems for the Replacement Research Reactor, ANSTO

International Nuclear Information System (INIS)

Morris, C.R.

2003-01-01

The 20-MW Replacement Research Reactor Project which is currently under construction at ANSTO will have a combination of a state of the art triplicated computer based reactor protection system, and a fully independent, and diverse, triplicated analogue reactor protection system, that has been in use in the nuclear industry, for many decades. The First Reactor Protection System (FRPS) consists of a Triconex triplicated modular redundant system that has recently been approved by the USNRC for use in the USA?s power reactor program. The Second Reactor Protection System is a hardwired analogue system supplied by Foxboro, the Spec 200 system, which is also Class1E qualified. The FRPS is used to drop the control rods when its safety parameter setpoints have been reached. The SRPS is used to drain the reflector tank and since this operation would result in a reactor poison out due to the time it would take to refill the tank the FRPS trip setpoints are more limiting. The FRPS and SRPS have limited hardwired indications on the control panels in the main control room (MCR) and emergency control centre (ECC), however all FRPS and SRPS parameters are capable of being displayed on the reactor control and monitoring system (RCMS) video display units. The RCMS is a Foxboro Series I/A control system which is used for plant control and monitoring and as a protection system for the cold neutron source. This paper will provide technical information on both systems, their trip logics, their interconnections with each other, and their integration into the reactor control and monitoring system and control panels. (author)

Reactor container

International Nuclear Information System (INIS)

Fukazawa, Masanori.

1991-01-01

A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

Air quality plans unveiled at Toronto's first Smog Summit

Energy Technology Data Exchange (ETDEWEB)

Anon.

2000-06-23

New federal and provincial initiatives to improve air quality were announced at the recent first-ever Toronto Smog Summit. An initial one million dollars have been pledged by the federal Minister of the Environment to support a framework for extending daily air quality forecasting across Canada, to begin within the next year. The funding will be used to increase the information base of existing air quality advisory programs in Ontario, and to create a daily air quality index immediately in other areas of the country most affected by smog. Existing air quality assessment programs will be expanded to include air quality models incorporating measurement and reporting of particulate matter levels. A second federal initiative also announced at the is meeting will be a corporate smog action plan, led by the Ontario regional offices of the federal departments of the Environment, Health Canada, and Public Works and Government Services. This program will include rapid response by federal government departments during Smog Alerts Days and measures to reduce the federal government's contribution to causing smog through encouragement of low or no emission options for employees, educational programs on best practices at home and at the office, reduction of employee travel through flextime and telecommuting, conversion of government vehicles to natural gas and other alternatives, and retrofitting government buildings for greater energy and water efficiency. A federal commitment of at least $200,000 was also announced by the Minister of Transport to support six sustainable transportation projects. The provincial Minister of the Environment announced the membership of the province's Anti-Smog Action Plan, which involves some 50 partners from industry associations, companies, government agencies and non-government organizations to help Ontario to meet its commitment to reduces nitrogen oxides and volatile organic compounds emissions by 45 per cent by 2015. A strategy for

A multi-purpose reactor

International Nuclear Information System (INIS)

Changwen Ma

2000-01-01

An integrated natural circulation self pressurized reactor can be used for sea water desalination, electrogeneration, ship propulsion and district or process heating. The reactor can be used for ship propulsion because it has following advantages: it is a integrated reactor. Whole primary loop is included in a size limited pressure vessel. For a 200 MW reactor the diameter of the pressure vessel is about 5 m. It is convenient to arranged on a ship. Hydraulic driving facility of control rods is used on the reactor. It notably decreases the height of the reactor. For ship propulsion, smaller diameter and smaller height are important. Besides these, the operation reliability of the reactor is high enough, because there is no rotational machine (for example, circulating pump) in safety systems. Reactor systems are simple. There are no emergency water injection system and boron concentration regulating system. These features for ship propulsion reactor are valuable. Design of the reactor is based on existing demonstration district heating reactor design. The mechanic design principles are the same. But boiling is introduced in the reactor core. Several variants to use the reactor as a movable seawater desalination plant are presented in the paper. When the sea water desalination plant is working to produce fresh water, the reactor can supply electricity at the same time to the local electricity network. Some analyses for comprehensive application of the reactor have been done. Main features and parameters of the small (Thermopower 200 MW) reactor are given in the paper. (author)

TU Electric reactor physics model verification: Power reactor benchmark

International Nuclear Information System (INIS)

Willingham, C.E.; Killgore, M.R.

1988-01-01

Power reactor benchmark calculations using the advanced code package CASMO-3/SIMULATE-3 have been performed for six cycles of Prairie Island Unit 1. The reload fuel designs for the selected cycles included gadolinia as a burnable absorber, natural uranium axial blankets and increased water-to-fuel ratio. The calculated results for both startup reactor physics tests (boron endpoints, control rod worths, and isothermal temperature coefficients) and full power depletion results were compared to measured plant data. These comparisons show that the TU Electric reactor physics models accurately predict important measured parameters for power reactors

Supercritical Water Reactors

International Nuclear Information System (INIS)

Bouchter, J.C.; Dufour, P.; Guidez, J.; Latge, C.; Renault, C.; Rimpault, G.

2014-01-01

The supercritical water reactor (SCWR) is one of the 6 concepts selected for the 4. generation of nuclear reactors. SCWR is a new concept, it is an attempt to optimize boiling water reactors by using the main advantages of supercritical water: only liquid phase and a high calorific capacity. The SCWR requires very high temperatures (over 375 C degrees) and very high pressures (over 22.1 MPa) to operate which allows a high conversion yield (44% instead of 33% for a PWR). Low volumes of coolant are necessary which makes the neutron spectrum shift towards higher energies and it is then possible to consider fast reactors operating with supercritical water. The main drawbacks of supercritical water is the necessity to use very high pressures which has important constraints on the reactor design, its physical properties (density, calorific capacity) that vary strongly with temperatures and pressures and its very high corrosiveness. The feasibility of the concept is not yet assured in terms of adequate materials that resist to corrosion, reactor stability, reactor safety, and reactor behaviour in accidental situations. (A.C.)

Tank type reactor

International Nuclear Information System (INIS)

Otsuka, Fumio.

1989-01-01

The present invention concerns a tank type reactor capable of securing reactor core integrity by preventing incorporation of gases to an intermediate heat exchanger, thgereby improving the reliability. In a conventional tank type reactor, since vortex flows are easily caused near the inlet of an intermediate heat exchanger, there is a fear that cover gases are involved into the coolant main streams to induce fetal accidents. In the present invention, a reactor core is suspended by way of a suspending body to the inside of a reactor vessel and an intermediate heat exchanger and a pump are disposed between the suspending body and the reactor vessel, in which a vortex current preventive plate is attached at the outside near the coolant inlet on the primary circuit of the intermediate heat exchanger. In this way vortex or turbulence near the inlet of the intermediate heata exchanger or near the surface of coolants can be prevented. Accordingly, the cover gases are no more involved, to insure the reactor core integrity and obtain a tank type nuclear reactor of high reliability. (I.S.)

New about research reactors

International Nuclear Information System (INIS)

Egorenkov, P.M.

2001-01-01

The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

Evaluation of Pressure Changes in HANARO Reactor Hall after a Reactor Shutdown

International Nuclear Information System (INIS)

Han, Geeyang; Han, Jaesam; Ahn, Gukhoon; Jung, Hoansung

2013-01-01

The major objective of this work is intended to evaluate the characteristics of the thermal behavior regarding how the decay heat will be affected by the reactor hall pressure change and the increase of pool water temperature induced in the primary coolant after a reactor shutdown. The particular reactor pool water temperature at the surface where it is evaporated owing to the decay heat resulting in the local heat transfer rate is related to the pressure change response in the reactor hall associated with the primary cooling system because of the reduction of the heat exchanger to remove the heat. The increase in the pool water temperature is proportional to the heat transfer rate in the reactor pool. Consequently, any limit on the reactor pool water temperature imposes a corresponding limit on the reactor hall pressure. At HANARO, the decay heat after a reactor shutdown is mainly removed by the natural circulation cooling in the reactor pool. This paper is written for the safety feature of the pressure change related leakage rate from the reactor hall. The calculation results show that the increase of pressure in the reactor hall will not cause any serious problems to the safety limits although the reactor hall pressure is slightly increased. Therefore, it was concluded that the pool water temperature increase is not so rapid as to cause the pressure to vary significantly in the reactor hall. Furthermore, the mathematical model developed in this work can be a useful analytical tool for scoping and parametric studies in the area of thermal transient analysis, with its proper representation of the interaction between the temperature and pressure in the reactor hall

Design guide for Category III reactors: pool type reactors

International Nuclear Information System (INIS)

Brynda, W.J.; Lobner, P.R.; Powell, R.W.; Straker, E.A.

1978-11-01

The Department of Energy (DOE) in the ERDA Manual requires that all DOE-owned reactors be sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate consideration to health and safety factors. Specific guidance pertinent to the safety of DOE-owned reactors is found in Chapter 0540 of the ERDA Manual. The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC). This Design Guide deals principally with the design and functional requirement of Category III reactor structures, components, and systems

The computerized reactor period measurement system for China fast burst reactor-II

International Nuclear Information System (INIS)

Zhao Wuwen; Jiang Zhiguo

1996-01-01

The article simply introduces the hardware, principle, and software of the computerized reactor period measurement system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between fission yield and pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computerized measurement system makes the reactor period measurement into automatical and intelligent and also improves the speed and precision of period data on-line process

Computer measurement system of reactor period for China fast burst reactor-II

International Nuclear Information System (INIS)

Zhao Wuwen; Jiang Zhiguo

1997-01-01

The author simply introduces the hardware, principle, and software of the reactor period computer measure system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between Fission yield and Pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computer measure system makes the reactor period measurement into automation and intellectualization and also improves the speed and precision of period data process on-line

Reactor safety method

International Nuclear Information System (INIS)

Vachon, L.J.

1980-01-01

This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature

Small propulsion reactor design based on particle bed reactor concept

International Nuclear Information System (INIS)

Ludewig, H.; Lazareth, O.; Mughabghab, S.; Perkins, K.; Powell, J.R.

1989-01-01

In this paper Particle Bed Reactor (PBR) designs are discussed which use 233 U and /sup 242m/Am as fissile materials. A constant total power of 100MW is assumed for all reactors in this study. Three broad aspects of these reactors is discussed. First, possible reactor designs are developed, second physics calculations are outlined and discussed and third mass estimates of the various candidates reactors are made. It is concluded that reactors with a specific mass of 1 kg/MW can be envisioned of 233 U is used and approximately a quarter of this value can be achieved if /sup 242m/Am is used. If this power level is increased by increasing the power density lower specific mass values are achievable. The limit will be determined by uncertainties in the thermal-hydraulic analysis. 5 refs., 5 figs., 6 tabs

Physics of nuclear reactors

International Nuclear Information System (INIS)

Baeten, Peter

2006-01-01

This course gives an introduction to Nuclear Reactor Physics. The first chapter explains the most important parameters and concepts in nuclear reactor physics such as fission, cross sections and the effective multiplication factor. Further on, in the second chapter, the flux distributions in a stationary reactor are derived from the diffusion equation. Reactor kinetics, reactor control and reactor dynamics (feedback effects) are described in the following three chapters. The course concludes with a short description of the different types of existing and future reactors. (author)

Generation III+ Reactor Portfolio

International Nuclear Information System (INIS)

2010-03-01

While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

Guide to power reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-07-15

The IAEA's major first scientific publication is the Directory of Power Reactors now in operation or under construction in various parts of the world. The purpose of the directory is to present important details of various power projects in such a way as to provide a source of easy reference for anyone interested in the development of the peaceful uses of atomic energy, either at the technical or management level. Six pages have been devoted to each reactor the first of which contains general information, reactor physics data and information about the core. The second and third contain sketches of the fuel element or of the fuel element assembly, and of the horizontal and vertical sections of the reactor. On the fourth page information is grouped under the following heads: fuel element, core heat transfer, control, reactor vessel and over-all dimensions, and fluid flow. The fifth page shows a simplified flow diagram, while the sixth provides information on reflector and shielding, containment and turbo generator. Some information has also been given, when available, on cost estimates and operating staff requirements. Remarks and a bibliography constitute the last part of the description of each reactor. Reactor projects included in this directory are pressurized light water cooled power reactors. Boiling light water cooled power reactors, heavy water cooled power reactors, gas cooled power reactors, organic cooled power reactors liquid metal cooled power reactors and liquid metal cooled power reactors

Analysis of dynamic stability and safety of reactor system by reactor simulator

International Nuclear Information System (INIS)

Raisic, N.

1963-11-01

In order to enable qualitative analysis of dynamic properties of reactors RA and RB, mathematical models of these reactors were formulated and adapted for solution on analog computer. This report contains basic assessments for creating the model and complete equations for each reactor. Model was used to analyse three possible accidents at the RA reactor and possible hypothetical accidents at the RB reactor

Nuclear reactor physics

CERN Document Server

Stacey, Weston M

2010-01-01

Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

Sodium-cooled nuclear reactor

International Nuclear Information System (INIS)

Hammers, H.W.

1982-01-01

The invention concerns a sodium-cooled nuclear reactor, whose reactor tank contains the primary circuit, shielding surrounding the reactor core and a primary/secondary heat exchanger, particularly a fast breeder reactor on the module principle. In order to achieve this module principle it is proposed to have electromagnetic circulating pumps outside the reactor tank, where the heat exchanger is accomodated in an annular case above the pumps. This case has several openings at the top end to the space above the reactor core, some smaller openings in the middle to the same space and is connected at the bottom to an annular space between the tank wall and the reactor core. As a favoured variant, it is proposed that the annular electromagnetic pumps should be arranged concentrically to the reactor tank, where there is an annual duct on the inside of the reactor tank. In this way the sodium-cooled nuclear reactor is made suitable as a module with a large number of such elements. (orig.) [de

Atomic reactor thermal engineering

International Nuclear Information System (INIS)

Kim, Gwang Ryong

1983-02-01

This book starts the introduction of atomic reactor thermal engineering including atomic reaction, chemical reaction, nuclear reaction neutron energy and soon. It explains heat transfer, heat production in the atomic reactor, heat transfer of fuel element in atomic reactor, heat transfer and flow of cooler, thermal design of atomic reactor, design of thermodynamics of atomic reactor and various. This deals with the basic knowledge of thermal engineering for atomic reactor.

Argentinean integrated small reactor design and scale economy analysis of integrated reactor

International Nuclear Information System (INIS)

Florido, P. C.; Bergallo, J. E.; Ishida, M. V.

2000-01-01

This paper describes the design of CAREM, which is Argentinean integrated small reactor project and the scale economy analysis results of integrated reactor. CAREM project consists on the development, design and construction of a small nuclear power plant. CAREM is an advanced reactor conceived with new generation design solutions and standing on the large experience accumulated in the safe operation of Light Water Reactors. The CAREM is an indirect cycle reactor with some distinctive and characteristic features that greatly simplify the reactor and also contribute to a highly level of safety: integrated primary cooling system, self pressurized, primary cooling by natural circulation and safety system relying on passive features. For a fully doupled economic evaluation of integrated reactors done by IREP (Integrated Reactor Evaluation Program) code transferred to IAEA, CAREM have been used as a reference point. The results shows that integrated reactors become competitive with power larger than 200MWe with Argentinean cheapest electricity option. Due to reactor pressure vessel construction limit, low pressure drop steam generator are used to reach power output of 200MWe for natural circulation. For forced circulation, 300MWe can be achieved. (author)

Programming Deep Brain Stimulation for Tremor and Dystonia: The Toronto Western Hospital Algorithms.

Science.gov (United States)

Picillo, Marina; Lozano, Andres M; Kou, Nancy; Munhoz, Renato Puppi; Fasano, Alfonso

2016-01-01

Deep brain stimulation (DBS) is an effective treatment for essential tremor (ET) and dystonia. After surgery, a number of extensive programming sessions are performed, mainly relying on neurologist's personal experience as no programming guidelines have been provided so far, with the exception of recommendations provided by groups of experts. Finally, fewer information is available for the management of DBS in ET and dystonia compared with Parkinson's disease. Our aim is to review the literature on initial and follow-up DBS programming procedures for ET and dystonia and integrate the results with our current practice at Toronto Western Hospital (TWH) to develop standardized DBS programming protocols. We conducted a literature search of PubMed from inception to July 2014 with the keywords "balance", "bradykinesia", "deep brain stimulation", "dysarthria", "dystonia", "gait disturbances", "initial programming", "loss of benefit", "micrographia", "speech", "speech difficulties" and "tremor". Seventy-six papers were considered for this review. Based on the literature review and our experience at TWH, we refined three algorithms for management of ET, including: (1) initial programming, (2) management of balance and speech issues and (3) loss of stimulation benefit. We also depicted algorithms for the management of dystonia, including: (1) initial programming and (2) management of stimulation-induced hypokinesia (shuffling gait, micrographia and speech impairment). We propose five algorithms tailored to an individualized approach to managing ET and dystonia patients with DBS. We encourage the application of these algorithms to supplement current standards of care in established as well as new DBS centers to test the clinical usefulness of these algorithms in supplementing the current standards of care. Copyright © 2016 Elsevier Inc. All rights reserved.

Radiation effects on polymers for coatings on copper canisters used for the containment of radioactive materials

Energy Technology Data Exchange (ETDEWEB)

Mortley, Aba [Department of Chemistry and Chemical Engineering, Royal Military College of Canada, P.O. Box 17000 Station Force, Kingston, ON, K7K 7B4 (Canada)], E-mail: aba.mortley@rmc.ca; Bonin, H.W.; Bui, V.T. [Department of Chemistry and Chemical Engineering, Royal Military College of Canada, P.O. Box 17000 Station Force, Kingston, ON, K7K 7B4 (Canada)

2008-05-31

The present work proposes applying polyurethane coatings as an additional barrier in the design of Canadian nuclear waste disposal containers. The goal of the present research is to investigate the physico-mechanical integrity of a natural castor oil-based polyurethane (COPU) to be used as a coating material in pH-radiation-temperature environments. As the first part to these inquiries, the present paper investigates the effect of a mixed radiation field supplied by a SLOWPOKE-2 nuclear research reactor on COPUs that differ only by their isocyanate structure. FTIR, DSC, DMA, WAXS, and MALDI are used to characterize the changes that occur as a result of radiation and to relate these changes to polymer structure and composition. The COPUs used in the present work have demonstrated sustained physico-mechanical properties up to accumulated doses of 2.0 MGy and are therefore suitable for end-uses in radiation environments such as those expected in the deep geological repository.

Fast reactors

International Nuclear Information System (INIS)

Vasile, A.

2001-01-01

Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

Reactor power measuring device

International Nuclear Information System (INIS)

Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

1993-01-01

The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

Reactor container

International Nuclear Information System (INIS)

Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

1997-01-01

In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

Study on Reactor Performance of Online Power Monitoring in PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

2014-01-01

The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on reactor performance of online power monitoring based on various parameter of reactor such as log power, linear power, period, Fuel and coolant temperature and reactivity parameter with using neutronic and other instrumentation system of reactor. Methodology of online power estimation and monitoring is to evaluate and analysis of reactor power which is important of reactor safety and control. Neutronic instrumentation system will use to estimate power measurement, differential of log and linear power and period during reactor operation .This study also focus on noise fluctuation from fission chamber during reactor operation .This work will present result of online power monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that optimization of online power monitoring will improved the reactor control and safety parameter of reactor during operation. (author)

Proceedings of the 2009 Annual Meeting of the Canadian Mathematics Education Study Group = Actes de la Rencontre Annuelle 2009 du Groupe Canadien d'Etude en Didactique des Mathematiques (33rd, Toronto, Ontario, Canada, June 5-June 9, 2009)

Science.gov (United States)

Liljedahl, Peter, Ed.; Oesterle, Susan, Ed.; Abu-Bakare, Veda, Ed.

2010-01-01

This submission contains the Proceedings of the 2009 Annual Meeting of the Canadian Mathematics Education Study Group (CMESG), held at York University in Toronto, Ontario. 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 Study Group…

Nuclear power reactors: reactor safety and military and civil defence

International Nuclear Information System (INIS)

Hvinden, T.

1976-01-01

The formation of fission products and plutonium in reactors is briefly described, followed by a short general discussion of reactor safety. The interaction of reactor safety and radioactive release considerations with military and civil defence is thereafter discussed. Reactors and other nuclear plants are factors which must be taken into account in the defence of the district around the site, and as potential targets of both conventional and guerilla attacks and sabotage, requiring special defence. The radiological hazards arising from serious damage to a power reactor by conventional weapons are briefly discussed, and the benefits of underground siting evaluated. Finally the author discusses the significance of the IAEA safeguards work as a preventive factor. (JIW)

Research reactors in Argentina

International Nuclear Information System (INIS)

Carlos Ruben Calabrese

1999-01-01

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

To the analysis of reactor noise in boiling water reactors

International Nuclear Information System (INIS)

Seifritz, W.

1972-01-01

The paper contains some basic thoughts on the problem of neutron flux oscillations in power reactors. The advantages of self-powered detectors and their function are explained. In addition, noise measurements of the boiling water reactors at Lingen and Holden are described, and the possibilities of an employment of vanadium detectors for the analysis of reactor noise are discussed. The final pages of the paper contain a complete list of the author's publications in the field of reactor noise analysis. (RW/AK) [de

The CEA research reactors

International Nuclear Information System (INIS)

Schwartz, J.P.

1993-01-01

Two main research reactors, specifically designed, PEGASE reactor and Laue-Langevin high flux reactor, are presented. The PEGASE reactor was designed at the end of the 50s for the study of the gas cooled reactor fuel element behaviour under irradiation; the HFR reactor, was designed in the late 60s to serve as a high yield and high level neutron source. Historical backgrounds, core and fuel characteristics and design, flux characteristics, etc., are presented. 5 figs

State space modeling of reactor core in a pressurized water reactor

Energy Technology Data Exchange (ETDEWEB)

Ashaari, A.; Ahmad, T.; M, Wan Munirah W. [Department of Mathematical Science, Faculty of Science, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Shamsuddin, Mustaffa [Institute of Ibnu Sina, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Abdullah, M. Adib [Swinburne University of Technology, Faculty of Engineering, Computing and Science, Jalan Simpang Tiga, 93350 Kuching, Sarawak (Malaysia)

2014-07-10

The power control system of a nuclear reactor is the key system that ensures a safe operation for a nuclear power plant. However, a mathematical model of a nuclear power plant is in the form of nonlinear process and time dependent that give very hard to be described. One of the important components of a Pressurized Water Reactor is the Reactor core. The aim of this study is to analyze the performance of power produced from a reactor core using temperature of the moderator as an input. Mathematical representation of the state space model of the reactor core control system is presented and analyzed in this paper. The data and parameters are taken from a real time VVER-type Pressurized Water Reactor and will be verified using Matlab and Simulink. Based on the simulation conducted, the results show that the temperature of the moderator plays an important role in determining the power of reactor core.

Virtual nuclear reactor for education of nuclear reactor physics

International Nuclear Information System (INIS)

Tsuji, Masashi; Narabayashi, Takashi; Shimazu, Youichiro

2008-01-01

As one of projects that were programmed in the cultivation program for human resources in nuclear engineering sponsored by the Ministry of Economy, Trade and Industry, the development of a virtual reactor for education of nuclear reactor physics started in 2007. The purpose of the virtual nuclear reactor is to make nuclear reactor physics easily understood with aid of visualization. In the first year of this project, the neutron slowing down process was visualized. The data needed for visualization are provided by Monte Carlo calculations; The flights of the respective neutrons generated by nuclear fissions are traced through a reactor core until they disappear by neutron absorption or slow down to a thermal energy. With this visualization and an attached supplement textbook, it is expected that the learners can learn more clearly the physical implication of neutron slowing process that is mathematically described by the Boltzmann neutron transport equation. (author)

Generation X School Leaders as Agents of Care: Leader and Teacher Perspectives from Toronto, New York City and London

Directory of Open Access Journals (Sweden)

Karen Edge

2016-03-01

Full Text Available This paper draws on evidence from our three-year Economic and Social Research Council (ESRC-funded research study of the lives, careers, experiences and aspirations of Generation X (under 40 years of age principals and vice-principals in London, New York City, and Toronto. More specifically, the paper examines interview evidence from nine school-based studies in which nine leaders and 54 teachers discuss their perspectives on leaders’ care of their staff members. The evidence demonstrates that leaders and teachers both place a high level of importance on leaders’ ability and willingness to be supportive, understanding, and approachable. Teachers also expect leaders to serve as advocates for and role models of good work/life balance. While the school-level studies take place in radically different city-based contexts, the expectation of leaders’ care for teachers transcends different accountability and policy structures. Both groups focus their discussion on work/life balance and, more specifically, the need for leaders to understand that teachers are people with lives beyond school. The paper highlights implications for policy, practice, and future research.

Reactor physics and reactor strategy investigations into the fissionable material economy of the thorium and uranium cycle in fast breeder reactors and high temperature reactors

International Nuclear Information System (INIS)

Schikorr, W.M.

In this work the properties governing the fissionable material economy of the uranium and thorium cycles are investigated for the advanced reactor types currently under development - the fast breeder reactor (FBR) and the high temperature reactor (HTR) - from the point of view of the optimum utilization of the available nuclear fuel reserves and the continuance of supply of these reserves. For this purpose, the two reactor types are first of all considered individually and are subsequently discussed as a complementary overall system

Reactor core

International Nuclear Information System (INIS)

Azekura, Kazuo; Kurihara, Kunitoshi.

1992-01-01

In a BWR type reactor, a great number of pipes (spectral shift pipes) are disposed in the reactor core. Moderators having a small moderating cross section (heavy water) are circulated in the spectral shift pipes to suppress the excess reactivity while increasing the conversion ratio at an initial stage of the operation cycle. After the intermediate stage of the operation cycle in which the reactor core reactivity is lowered, reactivity is increased by circulating moderators having a great moderating cross section (light water) to extend the taken up burnup degree. Further, neutron absorbers such as boron are mixed to the moderator in the spectral shift pipe to control the concentration thereof. With such a constitution, control rods and driving mechanisms are no more necessary, to simplify the structure of the reactor core. This can increase the fuel conversion ratio and control great excess reactivity. Accordingly, a nuclear reactor core of high conversion and high burnup degree can be attained. (I.N.)

Nuclear reactor

International Nuclear Information System (INIS)

Batheja, P.; Huber, R.; Rau, P.

1985-01-01

Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

Performance improvement of the Annular Core Pulse Reactor for reactor safety experiments

International Nuclear Information System (INIS)

Reuscher, J.A.; Pickard, P.S.

1976-01-01

The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past several years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. The new features of the improvements are described

Identification of nuclear reactor characteristics by the reactor noise analysis

International Nuclear Information System (INIS)

Yashima, Hideyuki

1980-01-01

Reactor noise analysis method was applied to TRIGA II Research Reactor (Atomic Research Laboratory, Musashi Institute of Technology) and computed power spectral density (PSD) from the CIC current record. PSD has provided many valuable informations regarding to the reactor kinetics, including the effect of control rods vibration. Another information of neutron physics parameters were obtained and this result was compared with the parameter which was formerly measured by the Feynman-α experiment. Through these experiments we could find overall frequency characteristics of TRIGA II Reactor. (author)

Research on the reactor physics and reactor safety of VVER reactors. AER Symposium 2016

Energy Technology Data Exchange (ETDEWEB)

Kliem, S.

2017-09-15

The selected paperscan be attributed to the following main subjects: Reactor start-up tests and use of corresponding data for code validation, code development and application, approaches for safety analyses, closure of nuclear fuel cycle, prospective reactor concepts.

The fast breeder reactor

International Nuclear Information System (INIS)

Collier, J.

1990-01-01

The arguments for and against the fast breeder reactor are debated. The case for the fast reactor is that the world energy demand will increase due to increasing population over the next forty years and that the damage to the global environment from burning fossil fuels which contribute to the greenhouse effect. Nuclear fission is the only large scale energy source which can achieve a cut in the use of carbon based fuels although energy conservation and renewable sources will also be important. Fast reactors produce more energy from uranium than other types of (thermal) reactors such as AGRs and PWRs. Fast reactors would be important from about 2020 onwards especially as by then many thermal reactors will need to be replaced. Fast reactors are also safer than normal reactors. The arguments against fast reactors are largely economic. The cost, especially the capital cost is very high. The viability of the technology is also questioned. (UK)

Reactor feedwater system

International Nuclear Information System (INIS)

Kagaya, Hiroyuki; Tominaga, Kenji.

1993-01-01

In a simplified water type reactor using a gravitationally dropping emergency core cooling system (ECCS), the present invention effectively prevents remaining high temperature water in feedwater pipelines from flowing into the reactor upon occurrence of abnormal events. That is, (1) upon LOCA, if a feedwater pipeline injection valve is closed, boiling under reduced pressure of the remaining high temperature water occurs in the feedwater pipelines, generated steams prevent the remaining high temperature water from flowing into the reactor. Accordingly, the reactor is depressurized rapidly. (2) The feedwater pipeline injection valve is closed and a bypassing valve is opened. Steams generated by boiling under reduced pressure of the remaining high temperature water in the feedwater pipelines are released to a condensator or a suppression pool passing through bypass pipelines. As a result, the remaining high temperature water is prevented from flowing into the reactor. Accordingly, the reactor is rapidly depressurized and cooled. It is possible to accelerate the depressurization of the reactor by the method described above. Further, load on the depressurization valve disposed to a main steam pipe can be reduced. (I.S.)

Neutron transport. Physics and calculation of nuclear reactors with applications to pressurized water reactors and fast neutron reactors. 2 ed.

International Nuclear Information System (INIS)

Bussac, J.; Reuss, P.

1985-01-01

This book presents the main physical bases of neutron theory and nuclear reactor calculation. 1) Interactions of neutrons with matter and basic principles of neutron transport; 2) Neutron transport in homogeneous medium and the neutron field: kinetic behaviour, slowing-down, resonance absorption, diffusion equation, processing methods; 3) Theory of a reactor constituted with homogeneous zones: critical condition, kinetics, separation of variables, calculation and neutron balance of the fundamental mode, one-group and multigroup theories; 4) Study of heterogeneous cell lattices: fast fission factor, resonance absorption, thermal output factor, diffusion coefficient, computer codes; 5) Operation and control of reactors: perturbation theory, reactivity, fuel properties evolution, poisoning by fission products, calculation of a reactor and fuel management; 6) Study of some types of reactors: PWR and fast breeder reactors, the main reactor types of the present French program [fr

Ulysse, mentor reactor

International Nuclear Information System (INIS)

Bouquin, B.; Rio, I.; Safieh, J.

1997-01-01

On July 23, 1961, the ULYSSE reactor began its first power rise. Designed at that time to train nuclear engineering students and reactor operators, this reactor still remains an indispensable tool for nuclear teaching and a choice instrument for scientists. (author)

Siting of research reactors

International Nuclear Information System (INIS)

1987-01-01

The purpose of this document is to develop criteria for siting and the site-related design basis for research reactors. The concepts presented in this document are intended as recommendations for new reactors and are not suggested for backfitting purposes for facilities already in existence. In siting research reactors serious consideration is given to minimizing the effects of the site on the reactor and the reactor on the site and the potential impact of the reactor on the environment. In this document guidance is first provided on the evaluation of the radiological impact of the installation under normal reactor operation and accident conditions. A classification of research reactors in groups is then proposed, together with a different approach for each group, to take into account the relevant safety problems associated with facilities of different characteristics. Guidance is also provided for both extreme natural events and for man-induced external events which could affect the safe operation of the reactor. Extreme natural events include earthquakes, flooding for river or coastal sites and extreme meteorological phenomena. The feasibility of emergency planning is finally considered for each group of reactors

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

International Nuclear Information System (INIS)

Blotcky, A.J.; Arsenaut, L.J.

1972-01-01

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

Reactor transients tests for SNR fuel elements in HFR reactor

International Nuclear Information System (INIS)

Plitz, H.

1989-01-01

In HFR reactor, fuel pins of LMFBR reactors are putted in irradiation specimen capsules cooled with sodium for reactor transients tests. These irradiation capsules are instrumented and the experiences realized until this day give results on: - Fuel pins subjected at a continual variation of power - melting fuel - axial differential elongation of fuel pins

Nuclear reactor coolant channels

International Nuclear Information System (INIS)

Macbeth, R.V.

1978-01-01

A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

Training reactor deployment. Advanced experimental course on designing new reactor cores

International Nuclear Information System (INIS)

Skoda, Radek

2009-01-01

Czech Technical University in Prague (CTU) operating its training nuclear reactor VR1, in cooperation with the North West University of South Africa (NWU), is applying for accreditation of the experimental training course ''Advanced experimental course on designing the new reactor core'' that will guide the students, young nuclear engineering professionals, through designing, calculating, approval, and assembling a new nuclear reactor core. Students, young professionals from the South African nuclear industry, face the situation when a new nuclear reactor core is to be build from scratch. Several reactor core design options are pre-calculated. The selected design is re-calculated by the students, the result is then scrutinized by the regulator and, once all the analysis is approved, physical dismantling of the current core and assembling of the new core is done by the students, under a close supervision of the CTU staff. Finally the reactor is made critical with the new core. The presentation focuses on practical issues of such a course, desired reactor features and namely pedagogical and safety aspects. (orig.)

Three-dimensional reactor dynamics code for VVER type nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Kyrki-Rajamaeki, R. [VTT Energy, Espoo (Finland)

1995-10-01

A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.).

Three-dimensional reactor dynamics code for VVER type nuclear reactors

International Nuclear Information System (INIS)

Kyrki-Rajamaeki, R.

1995-10-01

A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.)

Reactor performances and microbial communities of biogas reactors: effects of inoculum sources.

Science.gov (United States)

Han, Sheng; Liu, Yafeng; Zhang, Shicheng; Luo, Gang

2016-01-01

Anaerobic digestion is a very complex process that is mediated by various microorganisms, and the understanding of the microbial community assembly and its corresponding function is critical in order to better control the anaerobic process. The present study investigated the effect of different inocula on the microbial community assembly in biogas reactors treating cellulose with various inocula, and three parallel biogas reactors with the same inoculum were also operated in order to reveal the reproducibility of both microbial communities and functions of the biogas reactors. The results showed that the biogas production, volatile fatty acid (VFA) concentrations, and pH were different for the biogas reactors with different inocula, and different steady-state microbial community patterns were also obtained in different biogas reactors as reflected by Bray-Curtis similarity matrices and taxonomic classification. It indicated that inoculum played an important role in shaping the microbial communities of biogas reactor in the present study, and the microbial community assembly in biogas reactor did not follow the niche-based ecology theory. Furthermore, it was found that the microbial communities and reactor performances of parallel biogas reactors with the same inoculum were different, which could be explained by the neutral-based ecology theory and stochastic factors should played important roles in the microbial community assembly in the biogas reactors. The Bray-Curtis similarity matrices analysis suggested that inoculum affected more on the microbial community assembly compared to stochastic factors, since the samples with different inocula had lower similarity (10-20 %) compared to the samples from the parallel biogas reactors (30 %).

The fast reactor

International Nuclear Information System (INIS)

1980-02-01

The subject is discussed as follows: brief description of fast reactors; advantage in conserving uranium resources; experience, in UK and elsewhere, in fast reactor design, construction and operation; safety; production of plutonium, security aspects; consideration of future UK fast reactor programme. (U.K.)

PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Masood, Z.

2016-01-01

The PUSPATI TRIGA Reactor is the only research reactor in Malaysia. This 1 MW TRIGA Mk II reactor first reached criticality on 28 June 1982 and is located at the Malaysian Nuclear Agency premise in Bangi, Malaysia. This reactor has been mainly utilised for research, training and education and isotope production. Over the years several systems have been refurbished or modernised to overcome ageing and obsolescence problems. Major achievements and milestones will also be elaborated in this paper. (author)

Fast Spectrum Reactors

CERN Document Server

Todd, Donald; Tsvetkov, Pavel

2012-01-01

Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

Reactor Engineering Department annual report

International Nuclear Information System (INIS)

1985-08-01

Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

Matsuura, Shojiro; Nakahara, Yasuaki; Takano, Hideki

1982-09-01

Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

Opportunities for reducing greenhouse gas, energy use, and electricity use in the Greater Toronto area

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-02-16

The Clean Air Partnership (CAP) was interested in scanning and prioritizing energy efficiency opportunities to reduce energy use and the associated greenhouse gas emissions in the greater Toronto area (GTA). A study was conducted to scope out the most promising program directions for the GTA should government funding become available to launch the initiative, based on the relative technical potential of energy efficiency (and some fuel substitution) measures in the targeted sectors. A report to the Ontario Power Authority (OPA) focused on the residential and institutional sectors. These included new and existing residential buildings, condominiums and single-family homes, with special detail provided on appliances and central air conditioning; as well as municipal, university, school, and hospital buildings, with special attention towards measures to make street and traffic signal lighting more energy efficient. This letter provided a summary of findings. Next steps were also presented. It was recommended that three market transformation initiatives be designed and implemented to realize the technical potential for reductions in peak electricity and carbon dioxide emissions reductions. These three programs were discussed with reference to the energy efficient lighting collaborative; a green loan program for new homes and condominiums; and a community residential CDM program. A market transformation framework was also presented. It addressed the five key steps in the movement of a product from the manufacturer to the end user, namely availability; awareness; accessibility; affordability; and acceptance. 1 tab., 3 figs.

Request for Naval Reactors Comment on Proposed PROMETHEUS Space Flight Nuclear Reactor High Tier Reactor Safety Requirements and for Naval Reactors Approval to Transmit These Requirements to Jet Propulsion Laboratory

International Nuclear Information System (INIS)

D. Kokkinos

2005-01-01

The purpose of this letter is to request Naval Reactors comments on the nuclear reactor high tier requirements for the PROMETHEUS space flight reactor design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval Reactors approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the reactor safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear reactor high tier safety requirements are consistent with the long standing safety culture of the Naval Reactors Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophy on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear Reactors (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory

Status of neutron activation analysis in developing countries

International Nuclear Information System (INIS)

Chatt, A.

1996-01-01

The 60th anniversary of the discovery of neutron activation analysis (NAA) by Hevesy and Levi is being celebrated in 1996. With the availability of nuclear reactors capable of producing fluxes of the order of 10 12 to 10 14 n/cm 2 s, the development of high-resolution and high-efficiency conventional and anticoincidence gamma-ray detectors, multichannel pulse-height analyzers, and personal computer-based softwares, NAA has become an extremely valuable analytical technique, especially for the simultaneous determinations of multielement concentrations. This technique can be used in a number of ways, depending on the nature of the matrix, the major elements in the sample, and on the elements of interest. In most cases, several elements can be determined without any chemical pretreatment of the sample; the technique is then called instrumental NAA (INAA). In other cases, an element can be concentrated from an interfering matrix prior to irradiation; the technique is then termed preconcentration NAA (PNAA). In opposite instances, the irradiation is followed by a chemical separation of the desired element; the technique is then called radiochemical NAA (RNAA). All three forms of NAA can provide elemental concentrations of high accuracy and precision with excellent sensitivity. The number of research reactors in developing countries has increased steadily from 17 in 1955 through 71 in 1975 to 89 in 1995. Low flux reactors such as SLOWPOKE and the Chinese MNSR are primarily used for NAA

Multi-purpose reactor

International Nuclear Information System (INIS)

1991-05-01

The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MW t h, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co 60 ) production capacity is 50000 Ci/yr, 200 Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N 16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

Mirror reactor studies

International Nuclear Information System (INIS)

Moir, R.W.; Barr, W.L.; Bender, D.J.

1977-01-01

Design studies of a fusion mirror reactor, a fusion-fission mirror reactor, and two small mirror reactors are summarized. The fusion reactor uses 150-keV neutral-beam injectors based on the acceleration of negative ions. The injectors provide over 1 GW of continuous power at an efficiency greater than 80%. The fusion reactor has three-stage, modularized, Venetian blind, plasma direct converter with a predicted efficiency of 59% and a new concept for removal of the lune-shaped blanket: a crane is brought between the two halves of the Yin-Yang magnet, which are separated by a float. The design has desirable features such as steady-state operation, minimal impurity problems, and low first-wall thermal stress. The major disadvantage is low Q resulting in high re-circulating power and hence high cost of electrical power. However, the direct capital cost per unit of gross electrical power is reasonable [$1000/kW(e)]. By contrast, the fusion-fission reactor design is not penalized by re-circulating power and uses relatively near-term fusion technology being developed for the fusion power program. New results are presented on the Th- 233 U and the U- 239 Pu fuel cycles. The purpose of this hybrid is fuel production, with projected costs at $55/g of Pu or $127/g of 233 U. Blanket and cooling system designs, including an emergency cooling system, by General Atomic Company, lead us to the opinion that the reactor can meet expected safety standards for licensing. The smallest mirror reactor having only a shield between the plasma and the coil is the 4.2-m long fusion engineering research facility (FERF) designed for material irradiation. The smallest mirror reactor having both a blanket and shield is the 7.5-m long experimental power reactor (EPR), which has both a fusion and a fusion-fission version. (author)

Reactor Simulations for Safeguards with the MCNP Utility for Reactor Evolution Code

International Nuclear Information System (INIS)

Shiba, T.; Fallot, M.

2015-01-01

To tackle nuclear material proliferation, we conducted several proliferation scenarios using the MURE (MCNP Utility for Reactor Evolution) code. The MURE code, developed by CNRS laboratories, is a precision, open-source code written in C++ that automates the preparation and computation of successive MCNP (Monte Carlo N-Particle) calculations and solves the Bateman equations in between, for burnup or thermal-hydraulics purposes. In addition, MURE has been completed recently with a module for the CHaracterization of Radioactive Sources, called CHARS, which computes the emitted gamma, beta and alpha rays associated to any fuel composition. Reactor simulations could allow knowing how plutonium or other material generation evolves inside reactors in terms of time and amount. The MURE code is appropriate for this purpose and can also provide knowledge on associated particle emissions. Using MURE, we have both developed a cell simulation of a typical CANDU reactor and a detailed model of light water PWR core, which could be used to analyze the composition of fuel assemblies as a function of time or burnup. MURE is also able to provide, thanks to its extension MURE-CHARTS, the emitted gamma rays from fuel assemblies unloaded from the core at any burnup. Diversion cases of Generation IV reactors have been also developed; a design of Very High Temperature Reactor (a Pebble Bed Reactor (PBR), loaded with UOx, PuOx and ThUOx fuels), and a Na-cooled Fast Breeder Reactor (FBR) (with depleted Uranium or Minor Actinides in the blanket). The loading of Protected Plutonium Production (P3) in the FBR was simulated. The simulations of various reactor designs taking into account reactor physics constraints may bring valuable information to inspectors. At this symposium, we propose to show the results of these reactor simulations as examples of the potentiality of reactor simulations for safeguards. (author)

Reactor Sharing Program

International Nuclear Information System (INIS)

Tehan, Terry

2002-01-01

Support utilization of the RINSC reactor for student and faculty instructions and research. The Department of Energy award has provided financial assistance during the period 9/29/1995 to 5/31/2001 to support the utilization of the Rhode Island Nuclear Science Center (RINSC) reactor for student and faculty instruction and research by non-reactor owning educational institutions within approximately 300 miles of Narragansett, Rhode Island. Through the reactor sharing program, the RINSC (including the reactor and analytical laboratories) provided reactor services and laboratory space that were not available to the other universities and colleges in the region. As an example of services provided to the users: Counting equipment, laboratory space, pneumatic and in-pool irradiations, demonstrations of sample counting and analysis, reactor tours and lectures. Funding from the Reactor Sharing Program has provided the RINSC to expand student tours and demonstration programs that emphasized our long history of providing these types of services to the universities and colleges in the area. The funding have also helped defray the cost of the technical assistance that the staff has routinely provided to schools, individuals and researchers who have called on the RINSC for resolution of problems relating to nuclear science. The reactor has been featured in a Public Broadcasting System documentary on Pollution in the Arctic and how a University of Rhode Island Professor used Neutron Activation Analysis conducted at the RINSC to discover the sources of the ''Arctic Haze''. The RINSC was also featured by local television on Earth Day for its role in environmental monitoring

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.

Technological status of reactor coolant pumps in generation III+ pressurized nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Brecht, Bernhard; Bross, Stephan [KSB Aktiengesellschaft, Frankenthal (Germany)

2016-05-15

KSB has been developing and producing pumps for thermal power plants for nearly 90 years. Consequently, KSB also started to develop and manufacture pumps for all kinds of nuclear power plants from the very beginning of the civil use of nuclear energy. This is especially true for reactor coolant pumps for pressurized water reactors. For the generation of advanced evolutionary reactors (Generation III+ reactors), KSB developed an advanced shaft seal system which is also able to fulfill the requirements of station blackout conditions. The tests in the KSB test rigs, which were successfully completed in December 2015, proved the full functionality of the new design. For generation III+ passive plant reactors KSB developed a new reactor coolant pump type called RUV, which is based on the experience of classic reactor coolant pumps and reactor internal pumps. It is a very compact, hermetically sealed vertical pump-motor unit with a wet winding motor. A full scale prototype successfully passed the 1st stage qualification test program in October 2015.

Reactor control device

International Nuclear Information System (INIS)

Fukami, Haruo; Morimoto, Yoshinori.

1981-01-01

Purpose: To operate a reactor always with safety operation while eliminating the danger of tripping. Constitution: In a reactor control device adapted to detect the process variants of a reactor, control a control rod drive controlling system based on the detected signal to thereby control the driving the control rods, control the reactor power and control the electric power generated from an electric generator by the output from the reactor, detection means is provided for the detection of the electric power from said electric generator, and a compensation device is provided for outputting control rod driving compensation signals to the control rod driving controlling system in accordance with the amount of variation in the detected value. (Seki, T.)

Research reactor DHRUVA

International Nuclear Information System (INIS)

Veeraraghaven, N.

1990-01-01

DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 10 14 n/cm 2 /sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

Fully integrated analysis of reactor kinetics, thermalhydraulics and the reactor control system in the MAPLE-X10 research reactor

International Nuclear Information System (INIS)

Shim, S.Y.; Carlson, P.A.; Baxter, D.K.

1992-01-01

A prototype research reactor, designated MAPLE-X10 (Multipurpose Applied Physics Lattice Experimental - X 10MW), is currently being built at AECL's Chalk River Laboratories. The CATHENA (Canadian Algorithm for Thermalhydraulic Network Analysis) two-fluid code was used in the safety analysis of the reactor to determine the adequacy of core cooling during postulated reactivity and loss-of-forced-flow transients. The system responses to a postulated transient are predicted including the feedback between reactor kinetics, thermalhydrauilcs and the reactor control systems. This paper describes the MAPLE-X10 reactor and the modelling methodology used. Sample simulations of postulated loss-of-heat-sink and loss-of-regulation transients are presented. (author)

Power Trip Set-points of Reactor Protection System for New Research Reactor

International Nuclear Information System (INIS)

Lee, Byeonghee; Yang, Soohyung

2013-01-01

This paper deals with the trip set-point related to the reactor power considering the reactivity induced accident (RIA) of new research reactor. The possible scenarios of reactivity induced accidents were simulated and the effects of trip set-point on the critical heat flux ratio (CHFR) were calculated. The proper trip set-points which meet the acceptance criterion and guarantee sufficient margins from normal operation were then determined. The three different trip set-points related to the reactor power are determined based on the RIA of new research reactor during FP condition, over 0.1%FP and under 0.1%FP. Under various reactivity insertion rates, the CHFR are calculated and checked whether they meet the acceptance criterion. For RIA at FP condition, the acceptance criterion can be satisfied even if high power set-point is only used for reactor trip. Since the design of the reactor is still progressing and need a safety margin for possible design changes, 18 MW is recommended as a high power set-point. For RIA at 0.1%FP, high power setpoint of 18 MW and high log rate of 10%pp/s works well and acceptance criterion is satisfied. For under 0.1% FP operations, the application of high log rate is necessary for satisfying the acceptance criterion. Considering possible decrease of CHFR margin due to design changes, the high log rate is suggested to be 8%pp/s. Suggested trip set-points have been identified based on preliminary design data for new research reactor; therefore, these trip set-points will be re-established by considering design progress of the reactor. The reactor protection system (RPS) of new research reactor is designed for safe shutdown of the reactor and preventing the release of radioactive material to environment. The trip set point of RPS is essential for reactor safety, therefore should be determined to mitigate the consequences from accidents. At the same time, the trip set-point should secure margins from normal operational condition to avoid

Investigation of the basic reactor physics characteristics of the Dalat Nuclear Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Huy, Ngo Quang [Centre for Nuclear Technique Application, Ho Chi Minh City (Viet Nam); Thong, Ha Van; Khang, Ngo Phu [Nuclear Research Inst., Da Lat (Viet Nam)

1994-10-01

The Dalat nuclear research reactor was reconstructed from TRIGA MARK II reactor, built in 1963 with nominal power of 250 KW, and reached its planned nominal power of 500 kW for the first time in Feb. 1984. The Dalat reactor has some characteristics distinct from the former TRIGA reactor. Investigation of its characteristics is carried out by the determination of the reactor physics parameters. This paper represents the experimental results obtained for the effective fraction of the delayed photoneutrons, the extraneous neutron source left after the reactor is shut down, the lowest power levels of reactor critical states, the relative axial and radial distributions of thermal neutrons, the safe positive reactivity inserted into the reactor at deep subcritical state, the reactivity temperature coefficient of water, the temperature on the surface of the fuel elements, etc. (author). 10 refs., 10 figs., 2 tabs.

Reactor safety device

International Nuclear Information System (INIS)

Okada, Yasumasa.

1987-01-01

Purpose: To scram control rods by processing signals from a plurality of temperature detectors and generating abnormal temperature warning upon occurrence of abnormal temperature in a nuclear reactor. Constitution: A temperature sensor comprising a plurality of reactors each having a magnetic body as the magnetic core having a curie point different from each other and corresponding to the abnormal temperature against which reactor core fuels have to be protected is disposed in an identical instrumentation well near the reactor core fuel outlet/inlet of a reactor. A temperature detection device actuated upon detection of an abnormal temperature by the abrupt reduction of the reactance of each of the reactors is disposed. An OR circuit and an AND circuit for conducting OR and AND operations for each of the abnormal temperature detection signals from the temperature detection device are disposed. The output from the OR circuit is used as the abnormal temperature warning signal, while the output from the AND circuit is utilized as a signal for actuating the scram operation of control rod drive mechanisms. Accordingly, it is possible to improve the reliability of the reactor scram system, particularly, improve the reliability under a high temperature atmosphere. (Kamimura, M.)

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

1980-09-01

Research activities in the Division of Reactor Engineering in fiscal 1979 are described. The work of the Division is closely related to development of multi-purpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committees on Reactor Physics and on Decomissioning of Nuclear Facilities. (author)

Reactor scram device for FBR type reactor

International Nuclear Information System (INIS)

Kumasaka, Katsuyuki; Arashida, Genji; Itooka, Satoshi.

1991-01-01

In a control rod attaching structure in a reactor scram device of an FBR type reactor, an anti-rising mechanism proposed so far against external upward force upon occurrence of earthquakes relies on the engagement of a mechanical structure but temperature condition is not taken into consideration. Then, in the present invention, a material having curie temperature characteristics and which exhibits ferromagnetism only under low temperature condition and a magnet device are disposed to one of a movable control rod and a portion secured to the reactor. Alternatively, a bimetal member or a shape memory alloy which actuates to fix to the mating member only under low temperature condition is secured. The fixing device is adapted to operate so as to secure the control rods when the low temperature state is caused depending on the temperature condition. With such a constitution, when the control rods are separated from a driving device, they are prevented from rising even if they undergo external upward force due to earthquakes and so on, which can improve the reactor safety. (N.H.)

Nuclear reactor engineering: Reactor systems engineering. Fourth edition, Volume Two

International Nuclear Information System (INIS)

Glasstone, S.; Sesonske, A.

1994-01-01

This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Extensively updated, the fourth edition includes new materials on reactor safety and risk analysis, regulation, fuel management, waste management and operational aspects of nuclear power. This volume contains the following: the systems concept, design decisions, and information tools; energy transport; reactor fuel management and energy cost considerations; environmental effects of nuclear power and waste management; nuclear reactor safety and regulation; power reactor systems; plant operations; and advanced plants and the future

Refuelling nuclear reactors

International Nuclear Information System (INIS)

Stacey, J.; Webb, J.; White, W.P.; McLaren, N.H.

1981-01-01

An improved nuclear reactor refuelling machine is described which can be left in the reactor vault to reduce the off-load refuelling time for the reactor. The system comprises a gripper device rangeable within a tubular chute, the gripper device being movable by a pantograph. (U.K.)

Compilation of reactor physics data of the year 1984, AVR reactor

International Nuclear Information System (INIS)

Werner, H.; Bergerfurth, A.; Thomas, F.; Geskes, B.

1985-12-01

The 'AVR reactor physics data' is a documentation published once a year, the data presented being obtained by a simulation of reactor operation using the AVR-80 numerical model. This model is constantly updated and improved in response to new results and developments in the field of reactor theory and thermohydraulics, and in response to theoretical or practical modifications of reactor operation or in the computer system. The large variety of measured data available in the AVR reactor simulation system also makes it an ideal testing system for verification of the computing programs presented in the compilation. A survey of the history of operations in 1984 and a short explanation of the computerized simulation methods are followed by tables and graphs that serve as a source of topical data for readers interested in the physics of high-temperature pebble-bed reactors. (orig./HP) [de

Compilation of reactor physics data of the year 1983, AVR reactor

International Nuclear Information System (INIS)

Werner, H.; Bergerfurth, A.; Thomas, F.; Geskes, B.

1985-06-01

The 'AVR reactor physics data' is a documentation published once a year, the data presented being obtained by a simulation of reactor operation using the AVR-80 numerical model. This model is constantly updated and improved in response to new results and developments in the field of reactor theory and thermohydraulics, and in response to theoretical or practical modifications of reactor operation or in the computer system. The large variety of measured data available in the AVR reactor simulation system also makes it an ideal testing system for verification of the computing programs presented in the compilation. A survey of the history of operations in 1983 and a short explanation of the computerized simulation methods are followed by tables and graphs that serve as a source of topical data for readers interested in the physics of high-temperature pebble-bed reactors. (orig./HP) [de

Reactor containment

International Nuclear Information System (INIS)

Kawabe, Ryuhei; Yamaki, Rika.

1990-01-01

A water vessel is disposed and the gas phase portion of the water vessel is connected to a reactor container by a pipeline having a valve disposed at the midway thereof. A pipe in communication with external air is extended upwardly from the liquid phase portion to a considerable height so as to resist against the back pressure by a waterhead in the pipeline. Accordingly, when the pressure in the container is reduced to a negative level, air passes through the pipeline and uprises through the liquid phase portion in the water vessel in the form of bubbles and then flows into the reactor container. When the pressure inside of the reactor goes higher, since the liquid surface in the water vessel is forced down, water is pushed up into the pipeline. Since the waterhead pressure of a column of water in the pipeline and the pressure of the reactor container are well-balanced, gases in the reactor container are not leaked to the outside. Further, in a case if a great positive pressure is formed in the reactor container, the inner pressure overcomes the waterhead of the column of water, so that the gases containing radioactive aerosol uprise in the pipeline. Since water and the gases flow being in contact with each other, this can provide the effect of removing aerosol. (T.M.)

Multipurpose research reactors

International Nuclear Information System (INIS)

1988-01-01

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

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

1978-10-01

Research activities in the Division of Reactor Engineering in fiscal 1977 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committee on Reactor Physics. (Author)

An internally illuminated monolith reactor: Pros and cons relative to a slurry reactor

NARCIS (Netherlands)

Carneiro, Joana T.; Carneiro, J.T.; Berger, Rob; Moulijn, Jacob A.; Mul, Guido

2009-01-01

In the present study, kinetic models for the photo-oxidation of cyclohexane in two different photoreactor systems are discussed: a top illumination reactor (TIR) representative of a slurry reactor, and the so-called internally illuminated monolith reactor (IIMR) representing a reactor containing

Undergraduate reactor control experiment

International Nuclear Information System (INIS)

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

1992-01-01