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

International Nuclear Information System (INIS)

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

1983-07-01

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

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

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

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

International Nuclear Information System (INIS)

Harnden, A.M.C.

1995-09-01

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

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.

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)

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

International Nuclear Information System (INIS)

Harnden, A.M.C.

1995-09-01

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

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

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)

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)

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

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

The metro area of Montreal.

Science.gov (United States)

1986-10-01

Montreal, one of the most civilized and cosmopolitan of North American cities, is the 2nd city in Canada in size and the largest French-speaking city. Of the 2.8 million people who lived there at census time in 1981, 45% chose both French and English as their official language, 41% chose French, and 1% used some other language. Fully 68% of Montreal residents said their mother tongue was French, and 68% also said they spoke French at home. The importance of bilingualism to the business culture of Montreal cannot be overemphasized. In the last decade, French-Canadians have taken an increasingly stronger role in business. Upper-middle-class suburbs that as little as 10 years ago had only 10% of their residents who were of French-Canadian descent now have as many as 50-60% of their residents who are French-Canadians. Most residents of Montreal willingly learn 2 languages. US firms should assume that all representatives who are sent to Montreal should be fluent in both French and English. Montreal's 2,828,349 people create a population density of 1004.9 persons per square kilometer. Montreal has 665 census tracts, which are described in the Metropolitan Atlas Series. Nearly 62% of Montreal's population fall between the ages of 20 and 64--the prime working ages. Although Montreal is 79% Catholic, it does not have the high fertility levels often associated with Catholic areas. There were 1,026,920 households in Montreal in 1981 with an average of 2.7 persons per household. 71% of these were census family households. Montreal had 1,026,895 occupied dwellings in 1985 with an average of 5 rooms each. About 71% of the population aged 15 and over that were not in school were in the labor force; 41% of the labor force was female. The largest employment category for men was manufacturing (16%) and the largest for women was clerical work (39%).

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)

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

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)

Montreal Modern: Retro Culture and the Modern Past in Montreal

Directory of Open Access Journals (Sweden)

Kristian Handberg

2015-03-01

Full Text Available Through analyses of the retro scenes in Montreal, Canada, the article discusses retro culture's role as cultural memory. It is shown how Montreal's cultural identity is formed by memories of modern culture such as the Red-light and Sin City reputation of the illicit nightlife of the 1940s and 1950s, and the space age modernism of the 1960s following the Expo 67 and Quebec's Quiet Revolution. This is reflected in the city's thriving retro culture through the study of two groups of retro shops. In circulating specific memories and objects in a specific context, retro is an important negotiation of the past in the present. Especially, it is stated that the retro culture displays "local accents" and a new focus on the specificities of modern culture giving a revaluation to a previously overlooked identity such as the Quebecit.

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.

1959 : Borden bails on Montreal question

International Nuclear Information System (INIS)

Anon.

2008-01-01

In 1959, following months of hearings, the Borden Royal Commission on Oil and Gas was unwilling to grant western producers the access to the Montreal refinery market. Rather than building a pipeline to Montreal, the Commission urged a national policy supporting the export of Canadian crude without license, and encouraging the use of Canadian crude in markets that already have pipeline access to it, including the west coast, Midwest and Ontario. The Commission recommended that the Canadian oil and gas industry take measures to enlarge its share of the United States market and asked that petroleum product retailers displace 50,000 barrels per day of products refined from imported crude in Montreal and sold in Ontario with a similar volume of products refined from Canadian crude. Proponents of the Commission's report stated that exports to the United States were essential to the Canadian oil industry and that a crude oil line to Montreal was not economic. Other key events in 1959 were listed in this article. Alberta and Southern sought approval to export 460 million cubic feet of gas per day to California. Dome Petroleum Limited suggested that the Arctic Islands could hold reserves of up to 100 billion barrels, and a planned nuclear explosion to free oil from the Athabasca oil sands was called off by the federal government for political reasons. 1 tab., 1 fig

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.

Hydrofluorocarbon (HFC) Scenarios, Climate Effects and the Montreal Protocol

Science.gov (United States)

Velders, G. J. M.; Fahey, D. W.; Daniel, J. S.

2016-12-01

The Montreal Protocol has reduced the use of ozone-depleting substances by more than 95% from its peak levels in the 1980s. As a direct result the use of hydrofluorocarbons (HFCs) as substitute compounds has increased significantly. National regulations to limit HFC use have been adopted recently in the European Union, Japan and USA, and four proposals have been submitted to amend the Montreal Protocol to substantially reduce growth in HFC use. The Parties of the Montreal Protocol have discussed these proposals during their meetings in 2016. The effects of the national regulations and Montreal Protocol amendment proposals on climate forcings and surface temperatures will be presented. Global scenarios of HFC emissions reach 4.0-5.3 GtCO2-eq yr-1 in 2050, which corresponds to a projected growth from 2015 to 2050 which is 9% to 29% of that for CO2 over the same time period. In 2050, in percent of global HFC emissions, China ( 30%), India and the rest of Asia ( 25%), Middle East and northern Africa ( 10%), and USA ( 10%) are the principal source regions; and refrigeration and stationary air conditioning are the major use sectors. Calculated baseline emissions are reduced by 90% in 2050 by implementing the North America Montreal Protocol amendment proposal. This corresponds to a reduction in surface temperature attributed to HFCs from 0.1 oC to 0.04 oC in 2050 and from 0.3-0.4 oC to 0.02 oC in 2100.

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.)

Montreal Protocol Benefits simulated with CCM SOCOL

Directory of Open Access Journals (Sweden)

T. Egorova

2013-04-01

Full Text Available Ozone depletion is caused by the anthropogenic increase of halogen-containing species in the atmosphere, which results in the enhancement of the concentration of reactive chlorine and bromine in the stratosphere. To reduce the influence of anthropogenic ozone-depleting substances (ODS, the Montreal Protocol was agreed by Governments in 1987, with several Amendments and Adjustments adopted later. In order to assess the benefits of the Montreal Protocol and its Amendments and Adjustments (MPA on ozone and UV radiation, two different runs of the chemistry-climate model (CCM SOCOL have been carried out. The first run was driven by the emission of ozone depleting substances (ODS prescribed according to the restrictions of the MPA. For the second run we allow the ODS to grow by 3% annually. We find that the MPA would have saved up to 80% of the global annual total ozone by the end of the 21st century. Our calculations also show substantial changes of the stratospheric circulation pattern as well as in surface temperature and precipitations that could occur in the world without MPA implementations. To illustrate the changes in UV radiation at the surface and to emphasise certain features, which can only be seen for some particular regions if the influence of the cloud cover changes is accounted for, we calculate geographical distribution of the erythemally weighted irradiance (Eery. For the no Montreal Protocol simulation Eery increases by factor of 4 to 16 between the 1970s and 2100. For the scenario including the Montreal Protocol it is found that UV radiation starts to decrease in 2000, with continuous decline of 5% to 10% at middle latitudes in the both Northern and Southern Hemispheres.

UV Impacts Avoided by the Montreal Protocol

Science.gov (United States)

Newman, Paul; McKenzie, Richard

2010-01-01

Temporal and geographical variabilities in the future "World Expected" UV environment are compared with the "World Avoided", which would have occurred without the Montreal Protocol on protection of the ozone layer and its subsequent amendments and adjustments. Based on calculations of clear-sky UV irradiances, the effects of the Montreal Protocol have been hugely beneficial to avoid the health risks, such as skin cancer, which are associated with high UV, while there is only a small increase in health risks, such as vitamin D deficiency, that are associated with low UV. However, interactions with climate change may lead to changes in cloud and albedo, and possibly behavioural changes which could also be important.

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

Status of advanced technology and design for water cooled reactors: Heavy water reactors

International Nuclear Information System (INIS)

1989-07-01

In 1987 the IAEA established the International Working Group on Advanced Technologies for Water-Cooled Reactors (IWGATWR). Within the framework of the IWGATWR the IAEA Technical Report on Status of Advanced Technology and Design for Water Cooled Reactors, Part I: Light Water Reactors and Part II: Heavy Water Reactors, has been undertaken to document the major current activities and trends of technological improvement and development for future water reactors. Part I of the report dealing with Light Water Reactors (LWRs) was published in 1988 (IAEA-TECDOC-479). Part II of the report covers Heavy Water Reactors (HWRs) and has now been prepared. This report is based largely upon submissions from Member States. It has been supplemented by material from the presentations at the IAEA Technical Committee and Workshop on Progress in Heavy Water Reactor Design and Technology held in Montreal, Canada, December 6-9, 1988. It is hoped that this part of the report, containing the status of advanced heavy water reactor technology up to 1988 and ongoing development programmes will aid in disseminating information to Member States and in stimulating international cooperation. Refs, figs and tabs

The Importance of the Montreal Protocol in Protecting the Earth's Hydroclimate

Science.gov (United States)

Seager, R.; Wu, Y.; Polvani, L. M.

2012-12-01

The 1987 Montreal Protocol regulating emissions of ozone depleting chlorofluorocarbons (CFCs) was motivated primarily by the harm to human health and ecosystems arising from increased exposure to ultraviolet-B (UV-B) radiation associated with depletion from the ozone layer. It is now known that the Montreal Protocol has reduced global warming since CFCs are greenhouse gases (GHGs). In this paper we show that the Montreal Protocol also significantly protects the Earth's hydroclimate, even though this was also not a motivating factor in the decision-making that led to the Protocol. General Circulation Model (GCM) results show that in the coming decade (2020-29), under the 'World Avoided' scenario of no regulations on CFC emissions, the subtropical dry zones would in general get drier, and the middle and high latitude regions wetter. This change is similar, in both pattern and magnitude, to that in the coming decade caused by projected increases in carbon dioxide concentrations. This implies that because of the Montreal Protocol, and the ozone depletion and global warming associated with CFCs thus avoided, the hydrological cycle changes in the coming decade will be significantly less than what they otherwise would have been.

Seismic Vulnerability Assessment for Montreal -An Application of HAZUS-MH4

Science.gov (United States)

Yu, Keyan

2011-12-01

Seismic loss estimation for Montreal, Canada is performed for a 2% in 50 years seismic hazard using the HAZUS-MH4 tool developed by US Federal Emergency Management. The software is manipulated to accept a Canadian setting for the Montreal study region, which includes 522 census tracts. The accuracy of loss estimations using HAZUS is dependent on the quality and quantity of data collection and preparation. The data collected for Montreal study region comprise: (1) the building inventory (2) hazard maps regarding soil amplification, liquefaction, and landslides (3) population distribution at three different times of the day (4) census demographic information and (5) synthetic ground motion contour maps using three different ground motion prediction equations. All these data are prepared and assembled into geodatabases that are compatible with the HAZUS software. The study estimated that roughly 5% of the building stock would be damaged with direct economic losses evaluated at 1.4 billion dollars for a scenario corresponding to the 2% in 50 years scenario. The maximum number of casualties associated with this scenario corresponds to a time of occurrence of 2pm and would result in approximately 500 people being injured. Epistemic uncertainty was considered by obtaining damage estimates for three attenuation functions that were developed for Eastern North America. The results indicate that loss estimates are highly sensitive to the choice of the attenuation function and suggests that epistemic uncertainty should be considered both for the definition of the hazard function and in loss estimation methodologies. The next steps in the study should be to increase the size of the survey area to the Greater Montreal which includes more than 3 million inhabitants and to perform more targeted studies for critical areas such as downtown Montreal, and the south-eastern tip of Montreal. The current study was performed mainly for the built environment; the next phase will need to

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)

The Montreal Protocol treaty and its illuminating history of science-policy decision-making

Science.gov (United States)

Grady, C.

2017-12-01

The Montreal Protocol on Substances that Deplete the Ozone Layer, hailed as one of the most effective environmental treaties of all time, has a thirty year history of science-policy decision-making. The partnership between Parties to the Montreal Protocol and its technical assessment panels serve as a basis for understanding successes and evaluating stumbles of global environmental decision-making. Real-world environmental treaty negotiations can be highly time-sensitive, politically motivated, and resource constrained thus scientists and policymakers alike are often unable to confront the uncertainties associated with the multitude of choices. The science-policy relationship built within the framework of the Montreal Protocol has helped constrain uncertainty and inform policy decisions but has also highlighted the limitations of the use of scientific understanding in political decision-making. This talk will describe the evolution of the scientist-policymaker relationship over the history of the Montreal Protocol. Examples will illustrate how the Montreal Protocol's technical panels inform decisions of the country governments and will characterize different approaches pursued by different countries with a particular focus on the recently adopted Kigali Amendment. In addition, this talk will take a deeper dive with an analysis of the historic technical panel assessments on estimating financial resources necessary to enable compliance to the Montreal Protocol compared to the political financial decisions made through the Protocol's Multilateral Fund replenishment negotiation process. Finally, this talk will describe the useful lessons and challenges from these interactions and how they may be applicable in other environmental management frameworks across multiple scales under changing climatic conditions.

Tuberculosis and homelessness in Montreal: a retrospective cohort study

Science.gov (United States)

2011-01-01

Background Montreal is Canada's second-largest city, where mean annual tuberculosis (TB) incidence from 1996 to 2007 was 8.9/100,000. The objectives of this study were to describe the epidemiology of TB among homeless persons in Montreal and assess patterns of transmission and sharing of key locations. Methods We reviewed demographic, clinical, and microbiologic data for all active TB cases reported in Montreal from 1996 to 2007 and identified persons who were homeless in the year prior to TB diagnosis. We genotyped all available Mycobacterium tuberculosis isolates by IS6110 restriction fragment length polymorphism (IS6110-RFLP) and spoligotyping, and used a geographic information system to identify potential locations for transmission between persons with matching isolates. Results There were 20 cases of TB in homeless persons, out of 1823 total reported from 1996-2007. 17/20 were Canadian-born, including 5 Aboriginals. Homeless persons were more likely than non-homeless persons to have pulmonary TB (20/20), smear-positive disease (17/20, odds ratio (OR) = 5.7, 95% confidence interval (CI): 1.7-20), HIV co-infection (12/20, OR = 14, 95%CI: 4.8-40), and a history of substance use. The median duration from symptom onset to diagnosis was 61 days for homeless persons vs. 28 days for non-homeless persons (P = 0.022). Eleven homeless persons with TB belonged to genotype-defined clusters (OR = 5.4, 95%CI: 2.2-13), and ten potential locations for transmission were identified, including health care facilities, homeless shelters/drop-in centres, and an Aboriginal community centre. Conclusions TB cases among homeless persons in Montreal raise concerns about delayed diagnosis and ongoing local transmission. PMID:22034944

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

Protocolos de Montreal e Kyoto: pontos em comum e diferenças fundamentais Montreal and Kyoto Protocols: common points and essential differences

Directory of Open Access Journals (Sweden)

Darly Henriques da Silva

2009-12-01

Full Text Available Os Protocolos de Montreal e Kyoto, tratados internacionais de defesa do meio ambiente e da vida, controlam gases que provocam o buraco na camada de ozônio e o efeito estufa, respectivamente, resultantes de atividades industriais e uso da terra. O artigo enfatiza pontos comuns e diferenças entre eles, fornecendo atualização dos protocolos.Montreal and Kyoto Protocols, international treaties, aim at safeguarding the environment and life by controlling the use of gases which deplete the ozone layer and cause the greenhouse effect, respectively, due to industrial and land use activities. The article highlights common points and differences and provides an update discussion about the protocols.

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

Greek women and broken nerves in Montreal.

Science.gov (United States)

Dunk, P

1989-05-01

In this paper, I examine the importance of class, ethnicity and gender in the causation and meaning of somatization for Greek women in Montreal. I argue that nevra--a form of psychosocial distress experienced by many of the women--is a phenomenon of the poor working conditions, low wages and gender relations in the Greek community. Data is based on interviews with 100 Greek families in Montreal and 45 patients in two different clinical settings. Comparing results with material on nervios and nerves from Latin America and the United States, I concur with Low (1985) that nerves should be viewed as a 'culturally-interpreted symptom' rather than a 'culture bound syndrome'. It is further suggested that the importance of social and material conditions and gender relations in mediating the cultural interpretation must be stressed. Failure to do so often results in the medicalization of nevra and the creation of a chronic sick role for the patient.

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

Validity of Montreal Cognitive Assessment in non-english speaking patients with Parkinson's disease.

Science.gov (United States)

Krishnan, Syam; Justus, Sunitha; Meluveettil, Radhamani; Menon, Ramshekhar N; Sarma, Sankara P; Kishore, Asha

2015-01-01

The Montreal Cognitive Assessment is a brief and easy screening tool for accurately testing cognitive dysfunction in Parkinson's disease. We tested its validity for use in non-English (Malayalam) speaking patients with Parkinson's disease. We developed a Malayalam (a south-Indian language) version of Montreal Cognitive Assessment and applied to 70 patients with Parkinson's disease and 60 age- and education-matched healthy controls. Metric properties were assessed, and the scores were compared with the performance in validated Malayalam versions of Mini Mental Status Examination and Addenbrooke's Cognitive Examination. The Montreal Cognitive Assessment-Malayalam showed good internal consistency and test-retest reliability and its scores correlated with Mini Mental Status Examination (patients: R = 0.70; P speaking Parkinson's disease patients for early screening and potential future interventions for cognitive dysfunction.

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

The Montreal Protocol for Identification of Amusia.

Science.gov (United States)

Vuvan, D T; Paquette, S; Mignault Goulet, G; Royal, I; Felezeu, M; Peretz, I

2018-04-01

The Montreal Battery for the Evaluation of Amusia (MBEA; Peretz, Champod, & Hyde Annals of the New York Academy of Sciences, 999, 58-75, 2003) is an empirically grounded quantitative tool that is widely used to identify individuals with congenital amusia. The use of such a standardized measure ensures that the individuals tested will conform to a specific neuropsychological profile, allowing for comparisons across studies and research groups. Recently, a number of researchers have published credible critiques of the usefulness of the MBEA as a diagnostic tool for amusia. Here we argue that the MBEA and its online counterpart, the AMUSIA tests (Peretz et al. Music Perception, 25, 331-343, 2008), should be considered steps in a screening process for amusia, rather than standalone diagnostic tools. The goal of this article is to present, in detailed and easily replicable format, the full protocol through which congenital amusics should be identified. In providing information that has often gone unreported in published articles, we aim to clarify the strengths and limitations of the MBEA and to make recommendations for its continued use by the research community as part of the Montreal Protocol for Identification of Amusia.

The importance of the Montreal Protocol in protecting climate

NARCIS (Netherlands)

Velders, G.J.M.; Andersen, S.O.; Daniel, J.S.; Fahey, D.W.; McFarland, M.

2007-01-01

The 1987 Montreal Protocol on Substances that Deplete the Ozone Layer is a landmark agreement that has successfully reduced the global production, consumption, and emissions of ozone-depleting substances (ODSs). ODSs are also greenhouse gases that contribute to the radiative forcing of climate

Estimating the health benefits of planned public transit investments in Montreal.

Science.gov (United States)

Tétreault, Louis-François; Eluru, Naveen; Hatzopoulou, Marianne; Morency, Patrick; Plante, Celine; Morency, Catherine; Reynaud, Frederic; Shekarrizfard, Maryam; Shamsunnahar, Yasmin; Faghih Imani, Ahmadreza; Drouin, Louis; Pelletier, Anne; Goudreau, Sophie; Tessier, Francois; Gauvin, Lise; Smargiassi, Audrey

2018-01-01

Since public transit infrastructure affects road traffic volumes and influences transportation mode choice, which in turn impacts health, it is important to estimate the alteration of the health burden linked with transit policies. We quantified the variation in health benefits and burden between a business as usual (BAU) and a public transit (PT) scenarios in 2031 (with 8 and 19 new subway and train stations) for the greater Montreal region. Using mode choice and traffic assignment models, we predicted the transportation mode choice and traffic assignment on the road network. Subsequently, we estimated the distance travelled in each municipality by mode, the minutes spent in active transportation, as well as traffic emissions. Thereafter we estimated the health burden attributed to air pollution and road traumas and the gains associated with active transportation for both the BAU and PT scenarios. We predicted a slight decrease of overall trips and kilometers travelled by car as well as an increase of active transportation for the PT in 2031 vs the BAU. Our analysis shows that new infrastructure will reduce the overall burden of transportation by 2.5 DALYs per 100,000 persons. This decrease is caused by the reduction of road traumas occurring in the inner suburbs and central Montreal region as well as gains in active transportation in the inner suburbs. Based on the results of our study, transportation planned public transit projects for Montreal are unlikely to reduce drastically the burden of disease attributable to road vehicles and infrastructures in the Montreal region. The impact of the planned transportation infrastructures seems to be very low and localized mainly in the areas where new public transit stations are planned. Copyright © 2017 Elsevier Inc. All rights reserved.

Face-offs in reproductive immunology: the Montreal forum meeting report.

Science.gov (United States)

Croy, B Anne; Baines, Malcolm G

2004-10-01

The combined 12th International Congress of Immunology (ICI) and the 4th Annual Conference of the Federation of Clinical Immunological Societies (FOCIS) was held in Montreal, Canada July 18-23, 2004 and attracted over 6000 immunologists and almost 4000 abstracts. The host society, the Canadian Society for Immunology (CSI) spent many years in preparation for this large meeting and encouraged its members to propose topics for symposia and mini-symposia and to sponsor satellite meetings. With sponsorship of CSI; the Canadian Institutes of Health Research; the University of Guelph, Guelph, ON; Queen's University, Kingston, ON; McGill University, Montreal, QU, Canada; and the American Society for Reproductive Immunology, a focused, highly successful, one day satellite meeting on human uterine immunology was held. The highlights of the presentations and discussions are reported.

Selections from the ABC 2011 Annual Convention, Montreal, Canada

Science.gov (United States)

Whalen, D. Joel; Andersen, Ken; Campbell, Gloria; Crenshaw, Cheri; Cross, Geoffrey A.; Grinols, Anne Bradstreet; Hildebrand, John; Newman, Amy; Ortiz, Lorelei A.; Paulson, Edward; Phillabaum, Melinda; Powell, Elizabeth A.; Sloan, Ryan

2012-01-01

The 12 Favorite Assignments featured in this article were presented at the 2011 Annual Convention of the Association for Business Communication (ABC), Montreal, Canada. A variety of learning objectives are featured: delivering bad news, handling difficult people, persuasion, reporting financial analysis, electronic media, face-to-face…

Identifying and Measuring Dimensions of Urban Deprivation in Montreal: An Analysis of the 1996 Census Data.

Science.gov (United States)

Langlois, Andre; Kitchen, Peter

2001-01-01

Used 1996 Canadian census data to examine the spatial structure and intensity of urban deprivation in Montreal. Analysis of 20 indicators of urban deprivation identified 6 main types of deprivation in the city and found that they were most visible on the Island of Montreal. Urban deprivation was not confined to the inner city. (SM)

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)

SUSTAINABILITY ASSESSMENT IN URBAN PLANNING. A CHALLENGE FOR A METHODOLOGICAL CONSTRUCTION: MONTREAL AS CASE STUDY

Directory of Open Access Journals (Sweden)

María de Lourdes Flores Lucero

2014-09-01

Full Text Available In this paper we describe the methodological process for the qualitative evaluation of the concept of sustainability and its application in the island of Montreal. At the same time we present our theoretical approach and the main results issued of the assessment. We take as analytical tools the Montreal Urban Plan of 2004 and the Strategic Plan for Sustainable Development 2005. We conclude with two main points, first, that the theoretical and pragmatic aspects of urban sustainability in Montreal have been treated in an organic, complex, dynamic and flexible way, allowing social participation and the inclusion of the values of all stakeholders, which are both key elements to follow the path towards sustainability; and secondly, that the approach to an object with such features requires the construction of complex, organic and methodological processes.

Mini‑Mental State Exam versus Montreal Cognitive Assessment in ...

African Journals Online (AJOL)

Background: Mini‑mental state exam (MMSE) was used several times but no study has examined cognition on the Montreal Cognitive Assessment (MoCA) in diabetes and diabetic retinopathy (DR). In this study, we compared MMSE with MoCA in patients with DR and searched for an association between the severity of DR ...

Phosphorus cycling in Montreal's food and urban agriculture systems.

Science.gov (United States)

Metson, Geneviève S; Bennett, Elena M

2015-01-01

Cities are a key system in anthropogenic phosphorus (P) cycling because they concentrate both P demand and waste production. Urban agriculture (UA) has been proposed as a means to improve P management by recycling cities' P-rich waste back into local food production. However, we have a limited understanding of the role UA currently plays in the P cycle of cities or its potential to recycle local P waste. Using existing data combined with surveys of local UA practitioners, we quantified the role of UA in the P cycle of Montreal, Canada to explore the potential for UA to recycle local P waste. We also used existing data to complete a substance flow analysis of P flows in the overall food system of Montreal. In 2012, Montreal imported 3.5 Gg of P in food, of which 2.63 Gg ultimately accumulated in landfills, 0.36 Gg were discharged to local waters, and only 0.09 Gg were recycled through composting. We found that UA is only a small sub-system in the overall P cycle of the city, contributing just 0.44% of the P consumed as food in the city. However, within the UA system, the rate of recycling is high: 73% of inputs applied to soil were from recycled sources. While a Quebec mandate to recycle 100% of all organic waste by 2020 might increase the role of UA in P recycling, the area of land in UA is too small to accommodate all P waste produced on the island. UA may, however, be a valuable pathway to improve urban P sustainability by acting as an activity that changes residents' relationship to, and understanding of, the food system and increases their acceptance of composting.

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)

ASSESSING THE IMPACT OF THE HIGHWAY 25 EXPANSION PROJECT ON AIR QUALITY IN MONTREAL USING GIS

Directory of Open Access Journals (Sweden)

Mioara CHIABURU

2010-06-01

Full Text Available Assessing the impact of the highway 25 expansion project on air quality in montreal using gis. The aim of the paper is to assess local air pollution implications of the Highway 25 expansion project from Montreal. The basic concept of the roadway air dispersion model consists in calculating air pollutant levels in the vicinity of a highway by considering it as a line source. To fulfill this assessment, GIS software was used in order to determine pollutant distribution around the study area based on data collected by existing air monitoring stations located in the City of Montreal. GIS interpolation methods, notably Kriging and Inverse Distance Weighted (IDW, was used to generate maps of pollutant concentrations across the study area. From the results, recommendations will be made in regards to the project and appropriate mitigatory alternatives suggested.

Climate change impacts on pollinic productivity and allergic rhinitis in Montreal between 1994 and 2002

Energy Technology Data Exchange (ETDEWEB)

Garneau, M.; Breton, M.; Fortier, I. [Quebec Univ., Montreal, PQ (Canada)

2005-07-01

This presentation defined the correlation between pollinic concentrations of ragweed and medical consultations for allergic rhinitis in Montreal between 1994 and 2002, taking into account meteorological variables and socio-economic factors. The spatio-temporal dynamic of pollinic, meteorological, socio-economic and epidemiological values was reconstituted from descriptive, geographical and statistical analyses. Throughout the ragweed pollinic seasons (August to October) between 1994 and 2002 in the Montreal island area, there were 7,138 consultations for allergic rhinitis. The study concluded that the lengthening of the pollinic seasons, as well as the increase in the average number of medical consultations, combined with the significant correlation linking the temperature to pollinic concentrations suggests that the population affected by pollen allergies will increase over the coming decades in Montreal, and that it will affect certain areas more than others, which is consistent with the anticipated impacts of the rise in temperatures forecasted by different models of climate scenarios.

Temporal Evolution of Poststroke Cognitive Impairment Using the Montreal Cognitive Assessment

NARCIS (Netherlands)

Nijsse, Britta; Visser-Meily, Johanna M A; van Mierlo, Maria L; Post, Marcel W M; de Kort, Paul L M; van Heugten, Caroline M

BACKGROUND AND PURPOSE: The Montreal Cognitive Assessment (MoCA) is nowadays recommended for the screening of poststroke cognitive impairment. However, little is known about the temporal evolution of MoCA-assessed cognition after stroke. The objective of this study was to examine the temporal

Temporal Evolution of Poststroke Cognitive Impairment Using the Montreal Cognitive Assessment

NARCIS (Netherlands)

Nijsse, Britta; Visser-Meily, Johanna M.A.; van Mierlo, Maria L.; Post, Marcel W. M.; de Kort, Paul. L. M.; van Heugten, Caroline M.

Background and Purpose-The Montreal Cognitive Assessment (MoCA) is nowadays recommended for the screening of poststroke cognitive impairment. However, little is known about the temporal evolution of MoCA-assessed cognition after stroke. The objective of this study was to examine the temporal pattern

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

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.)

The precautionary principle as a provisional instrument in environmental policy: The Montreal Protocol case study

International Nuclear Information System (INIS)

Jacobs, J. Roger

2014-01-01

Highlights: • I examine whether a policy invoked under the Precautionary Principle can move beyond provisional status. • I review the certainty of conclusions based upon the Global Ozone Research and Monitoring Project. • There is high certainty that anthropogenic ozone depletion has health consequences in polar regions. • Current research focuses on long term projections of risk that perpetuates high uncertainty. • Establishment of a community to generate Assessments acts to perpetuate the period of uncertainty. - Abstract: Environmental studies identify possible threats to the health of the public or the environment when the scientific certainty of risk is low, but the potential cost is high. Governments may respond by invoking the Precautionary Principle, holding that scientific certainty is not required to take actions that reduce possible risk. EU guidelines suggest that precautionary measures remain provisional until sufficient scientific certainty is generated. Here I study the Scientific Assessments produced for the Montreal Protocol, and the scientific community that generates them, and ask whether a long-standing program of scientific investigation and monitoring can generate sufficient scientific certainty to move beyond dependence on the Precautionary Principle. When the Montreal Protocol was ratified, many scientists strongly suspected that anthropogenic substances like chlorofluorocarbons were depleting stratospheric ozone. Although the risk was uncertain, the perceived cost to public health of ozone depletion was high. A quarter century after formulating the Montreal Protocol, science can define the conditions for ozone depletion with great certainty, but uncertainty remains in determining the scale and distribution of the attributable increase in damaging ultra-violet (UV) radiation. Organisations, such as NASA, and scientists that contribute to the Scientific Assessments comprise the community in which the scientific consensus of risk is

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.

The intracarotid amobarbital procedure (Wada test with two protocols combined, Montreal and Seattle Procedimentos do amobarbital intracarotideo (teste de Wada com dois protocolos combinados, Montreal e Seattle

Directory of Open Access Journals (Sweden)

Paulo J. M. Leite

1997-06-01

Full Text Available The intracarotid amobarbital procedure was carried out in 8 male and 7 female candidates to temporal lobectomy, and a female candidate to frontal lesionectomy, aged 18-50 (mean 32.5 years. Language and memory were tested after injection in each hemisphere. Both were measured by the Montreal procedure. In 9 patients language and memory were evaluated with the Seattle procedure too. In 12 patients the left hemisphere was dominant for language; three had bilateral dominance. In I patient the Seattle procedure demonstrated the dominant hemisphere by relatively slowness of speech during the drug effect in the left hemisphere. Memory was defined to be in the left hemisphere in 12 patients, in the right in 2, bilateral in 1 and in another lateralization was not possible. In 1 patient memory dominance was determined by the Montreal protocol alone because of lack of cooperation. These early results indicate that the methods may be complementary for determination of language and memory dominance in epilepsy surgery candidates.O testo do amobarbital intracarotídeo foi realizado em 8 homens e 7 mulheres candidatos a lobectomia temporal e em uma mulher candidata a lesionectomia frontal, com idades de 18-50 (média 32,5 anos. Linguagem e memória foram testadas após a injeção do amobarbial em cada hemisfério cerebral. Todos os pacientes foram avaliados pelo método de Montreal e 9 também pelo método de Seattle. Em 12 pacientes o hemisfério cerebral esquerdo foi dominante para linguagem e em 3 pacientes houve dominância bilateral. Em uma paciente a linguagem foi determinada apenas através do método de Seattle, com lentificação relativa da fal a, sob ação da droga no hemisfério cerebral esquerdo. Dominância da memória à esquerda foi observada em 12 pacientes, à direita em 2, bilateral em 1 e em outro não foi lateralizada. Dominância da memória foi definida apenas através do método de Montreal em um paciente, devido à pouca coopera

New Regional and Global HFC Projections and Effects of National Regulations and Montreal Protocol Amendment Proposals

Science.gov (United States)

Velders, G. J. M.

2015-12-01

Hydrofluorocarbons (HFCs) are used as substitutes for ozone-depleting substances that are being phased out globally under Montreal Protocol regulations. New global scenarios of HFC emissions reach 4.0-5.3 GtCO2-eq yr-1 in 2050, which corresponds to a projected growth from 2015 to 2050 which is 9% to 29% of that for CO2 over the same time period. New baseline scenarios are formulated for 10 HFC compounds, 11 geographic regions, and 13 use categories. These projections are the first to comprehensively assess production and consumption of individual HFCs in multiple use sectors and geographic regions with emission estimates constrained by atmospheric observations. In 2050, in percent of global HFC emissions, China (~30%), India and the rest of Asia (~25%), Middle East and northern Africa (~10%), and USA (~10%) are the principal source regions; and refrigeration and stationary air conditioning are the major use sectors. National regulations to limit HFC use have been adopted recently in the European Union, Japan and USA, and four proposals have been submitted in 2015 to amend the Montreal Protocol to substantially reduce growth in HFC use. Calculated baseline emissions are reduced by 90% in 2050 by implementing the North America Montreal Protocol amendment proposal. Global adoption of technologies required to meet national regulations would be sufficient to reduce 2050 baseline HFC consumption by more than 50% of that achieved with the North America proposal for most developed and developing countries. The new HFC scenarios and effects of national regulations and Montreal Protocol amendment proposals will be presented.

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)

Choix linguistiques, changements et alternances de langue: Les comportements multilingues des italophones de Montreal (Linguistic Choices, Changes, and Code Switching: The Linguistics Behaviors of Italophones of Montreal).

Science.gov (United States)

Labrie, Normand

A study of 15 fathers and their 16 sons in an italophone community in Montreal (Canada) focused on the usage of Italian, French, and English in communication between generations and in a variety of activities. Data were drawn from 45 hours of taped conversation in home and work settings, which included 4,848 instances of language contact. Of the…

Historic cohort study in Montreal's fur industry.

Science.gov (United States)

Guay, D; Siemiatycki, J

1987-01-01

A historic cohort mortality study was carried out among two groups of male workers in the Montreal fur industry: 263 dressers and dyers and 599 fur garment manufacturers. The first group is exposed to a very wide variety of chemicals used in tanning, cleaning, and dyeing fur, including substances considered to be carcinogenic and/or mutagenic. The second group is exposed to residue from the dressing and dyeing stage and to respirable fur dust. The cohorts consisted of all active members of two unions as of January 1, 1966. The mean age of the workers was 43.2 and the mean number of years since first employment 14.1. The follow-up period was from January 1, 1966, to December 31, 1981; 95% of the workers were successfully traced. Observed deaths were compared with those expected based on mortality rates of the population of metropolitan Montreal. Standardized mortality ratios (SMRs) for the manufacturers were significantly low, probably because of the ethnic composition of the cohort and a healthy worker effect. SMRs for the dressers and dyers were also low, but not as low as for the manufacturers. When attention was restricted to the French Canadians in the cohort, the observed deaths were close to the expected; there was a noteworthy excess of colorectal cancer (four observed, 0.8 expected) for dressers and dyers. Apart from this weak suggestive evidence, the results did not indicate any excess mortality risks in the fur industry. However, because of the relatively small number of expected and observed deaths in the cohort and especially among the heavily exposed dressers and dyers, the confidence intervals around SMR estimates were wide and excess risks cannot be ruled out.

The Montreal Protocol's multilateral fund and sustainable development

International Nuclear Information System (INIS)

Luken, Ralph; Grof, Tamas

2006-01-01

The 1987 Montreal Protocol is widely seen as a global environmental accord that has produced tangible results in terms of reductions in ozone-depleting substances. In addition, there have been other benefits, largely unrecognized and undocumented, that can best be characterized in a sustainable development framework based on a review of 50 out of 931 projects implemented over a 13 year period by one of the four implementing agencies of the Multilateral Fund for the Implementation of the Montreal Protocol. All investment projects have reduced ozone depleting potential and global warming potential. Some projects have reduced atmospheric emissions and contamination of groundwater. Other projects have increased the competitiveness of enterprises in domestic and international markets and have sustained and in a few cases created employment opportunities. Others, fewer in number, have potentially contributed to environmental problems, have initially created difficulties in maintaining productivity and quality standards and have decreased the number of employment opportunities because of the need to rationalize manufacturing processes. The potential contributions from Multilateral Fund investment projects to sustainable development could probably have been amplified with project design guidance for the technical staffs of all three implementing agencies executing investment projects. In thinking about other multilateral environmental agreements, one can see the need for similar guidance for Global Environment Facility funded projects supporting the focal areas of climate change, international waters, ozone depletion and persistent organic pollutants. Some of them have the potential to generate multiple beneficial impacts in addition to their stated environmental objective if designed and implemented within a sustainable development framework. (author)

The NAA method at Polytechnique Montreal. An efficient alternative way to use the k0 NAA models

International Nuclear Information System (INIS)

Chilian, C.; Kennedy, G.

2014-01-01

At Ecole Polytechnique Montreal, the philosophy in performing neutron activation analysis (NAA) is long-term and application oriented. Thinking long-term implies a good understanding of the fundamentals of the method, of the samples, of the tools, reactor and detectors, and there must be constant innovation that is experimentally validated with extensive measurements. Application oriented means a NAA method developed to provide users with fast, sensitive, accurate and reliable analyses for various types of materials. This philosophy dictates the manner in which the developments in the areas of NAA software, peak-area calculation, dead-time correction, detection efficiency model, k 0 and Q 0 values, neutron moderation and neutron self-shielding are carried out. This paper presents a survey of the Laboratory’s methodology, reviewing a few of its unique features such as detector efficiency calibration and sample related perturbations of the neutron activation. These features are used as examples to provide the reader with an understanding of the philosophy and the evolution of the NAA method at Ecole Polytechnique. (author)

Economics of "essential use exemptions" for metered-dose inhalers under the Montreal Protocol.

Science.gov (United States)

DeCanio, Stephen J; Norman, Catherine S

2007-10-01

The Montreal Protocol on Substances that Deplete the Ozone Layer has led to rapid reductions in the use of ozone-depleting substances worldwide. However, the Protocol provides for "essential use exemptions" (EUEs) if there are no "technically and economically feasible" alternatives. An application that might qualify as an "essential use" is CFC-powered medical metered-dose inhalers (MDIs) for the treatment of asthma and chronic obstructive pulmonary disease (COPD), and the US and other nations have applied for exemptions in this case. One concern is that exemptions are necessary to ensure access to medications for low-income uninsureds. We examine the consequences of granting or withholding such exemptions, and conclude that government policies and private-sector programs are available that make it economically feasible to phase out chlorofluorocarbons (CFCs) in this application, thereby furthering the global public health objectives of the Montreal Protocol without compromising the treatment of patients who currently receive medication by means of MDIs.

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.

Applicability of Montreal Process Criterion 1 - conservation of biological diversity - to rangeland sustainability

Science.gov (United States)

Curtis H. Flather; Carolyn Hull Sieg

2000-01-01

Nine indicators of biodiversity conservation have been defined by the nations participating in the Montreal Process for assessing sustainability of temperate and boreal forests. Five of these indicators address compositional and spatial diversity of ecosystems; two address species diversity; and two are indirect measures of genetic diversity. Our objective was to...

The Montreal Lectures: 2 August - 2 October, 1944

Energy Technology Data Exchange (ETDEWEB)

Arsenault, J.E

2007-06-15

The Second World War began in the summer of 1939 and spurred atomic science in the direction of weapons development. The United Kingdom (U.K.) was far ahead until about the summer of 1941 at which time the United States (U.S.) began to have serious interest in atomic weapons. Seen from Europe, the U.S. was a greater distance from the theatre of war and was deemed to be a safer place to conduct atomic research. In addition to good research centres it also had greater financial, manpower, and material resources. Early attempts at full collaboration between the U.K. and the U.S. met with little success and this led to the formation of a joint British-Canadian atomic weapons effort in 1942, with research laboratories located in Montreal, which were well up and running by spring 1943. The Montreal laboratory (ML) initially was administered by the National Research Council (NRC) and scientific direction was provided by the U.K. The ML was the foundation from which the Canadian nuclear industry evolved to the present time. Interest in atomic weapons development by the U.S. had been greatly accelerated by the Japanese attack on Pearl Harbour on 7 December 1941. By the beginning of 1943 it was spending 10 times as much as the U.K. on atomic weapons research. From then on, the U.S. set the Allied agenda for the development of atomic weapons, in varying degrees of collaboration with the U.K. and Canada. This spending which grew to about $2B by the middle of 1945, was directed by the U.S. Army Corps of Engineers under the Manhattan Project, officially established on 13 August 1942, and led by Gen. Leslie R. Groves From 17 September 1942. (author)

The Montreal Lectures: 2 August - 2 October, 1944

International Nuclear Information System (INIS)

Arsenault, J.E.

2007-01-01

The Second World War began in the summer of 1939 and spurred atomic science in the direction of weapons development. The United Kingdom (U.K.) was far ahead until about the summer of 1941 at which time the United States (U.S.) began to have serious interest in atomic weapons. Seen from Europe, the U.S. was a greater distance from the theatre of war and was deemed to be a safer place to conduct atomic research. In addition to good research centres it also had greater financial, manpower, and material resources. Early attempts at full collaboration between the U.K. and the U.S. met with little success and this led to the formation of a joint British-Canadian atomic weapons effort in 1942, with research laboratories located in Montreal, which were well up and running by spring 1943. The Montreal laboratory (ML) initially was administered by the National Research Council (NRC) and scientific direction was provided by the U.K. The ML was the foundation from which the Canadian nuclear industry evolved to the present time. Interest in atomic weapons development by the U.S. had been greatly accelerated by the Japanese attack on Pearl Harbour on 7 December 1941. By the beginning of 1943 it was spending 10 times as much as the U.K. on atomic weapons research. From then on, the U.S. set the Allied agenda for the development of atomic weapons, in varying degrees of collaboration with the U.K. and Canada. This spending which grew to about $2B by the middle of 1945, was directed by the U.S. Army Corps of Engineers under the Manhattan Project, officially established on 13 August 1942, and led by Gen. Leslie R. Groves From 17 September 1942. (author)

Beyond Vienna and Montreal: A global framework convention on greenhouse gases

International Nuclear Information System (INIS)

Wirth, D.A.; Lashof, D.A.

1993-01-01

This chapter discusses the need for a framework treaty analogous to the Vienna Convention and to the Montreal Protocol for greenhouse gases. Discussed are the following topics: (1) the immediate need for multilateral greenhouse gas controls, including policy implications of scientific uncertainties; (2) recent steps toward a greenhouse gas convention; (3) an environmentally meaningful plan for a greenhouse gase conventions, including the ozone precident, CO 2 targets, resource transfers, trading emissions allocations, institutional issues

Literacy promotion at the Montreal Children’s Hospital

Science.gov (United States)

Erdos, Caroline; Ferdinand, Jae-Marie

2017-01-01

Abstract The foundations for language and literacy are set in utero when babies hear the tone of their mother’s voice (1). There is strong evidence of a positive relationship between early literacy experiences and language and academic outcomes (2). Unfortunately, many parents do not know about the benefits of reading to and with young children, and many children enter school without the basic skills needed to learn to read and succeed. Physicians who have contact with young families are in a distinctive position to promote reading, though despite its evidence base, it has not yet become a universal intervention. A short description of the projects at the Montreal Children’s Hospital is provided. PMID:29479189

The impact of the petrochemical industry in the economic development framework of the Montreal region

International Nuclear Information System (INIS)

Danis, M.

1992-01-01

A brief overview of the petrochemical industry in Canada was presented. The industry, which employs approximately 100,000 Canadians, has an annual production estimated to be in excess of 20 billion dollars. Similarly, in the province of Quebec, the petrochemical industry makes a very significant contribution to the economy of the province, especially to that of the Montreal region. Recent initiatives and investments by the Canadian Government in the petrochemical sector were summarized. Among these, subsidies to Petromont to improve and modernize its plant facilities in Varennes, to Himont Canada, also of Varennes, to develop a new manufacturing process, to Gaz Metropolitain to establish a centre of gas technology, were highlighted. These and other government measures and initiatives provide a solid foundation for the petrochemical industry to continue to play a pre-eminent role in the economy of the Montreal region

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

The Tanenbaum Open Science Institute: Leading a Paradigm Shift at the Montreal Neurological Institute.

Science.gov (United States)

Poupon, Viviane; Seyller, Annabel; Rouleau, Guy A

2017-08-30

The Montreal Neurological Institute is adopting an Open Science Policy that will be enacted by the Tanenbaum Open Science Institute. The aim is to accelerate the generation of knowledge and novel effective treatments for brain disorders by freeing science. Copyright © 2017 Elsevier Inc. All rights reserved.

Computer mapping as an aid in air-pollution studies: Montreal region study

Energy Technology Data Exchange (ETDEWEB)

Granger, J M

1972-01-01

Through the use of computer-mapping programs, an operational technique has been designed which allows an almost-instant appraisal of the intensity of atmospheric pollution in an urban region on the basis of epiphytic sensitivity. The epiphytes considered are essentially lichens and mosses growing on trees. This study was applied to the Montreal region, with 349 samplings statiions distributed nearly uniformly. Computer graphics of the findings are included in the appendix.

Acquisition and Processing of High Resolution Hyperspectral Imageries for the 3d Mapping of Urban Heat Islands and Microparticles of Montreal

Science.gov (United States)

Mongeau, R.; Baudouin, Y.; Cavayas, F.

2017-10-01

Ville de Montreal wanted to develop a system to identify heat islands and microparticles at the urban scale and to study their formation. UQAM and UdeM universities have joined their expertise under the framework "Observatoire Spatial Urbain" to create a representative geospatial database of thermal and atmospheric parameters collected during the summer months. They innovated in the development of a methodology for processing high resolution hyperspectral images (1-2 m). In partnership with Ville de Montreal, they integrated 3D geospatial data (topography, transportation and meteorology) in the process. The 3D mapping of intraurban heat islands as well as air micro-particles makes it possible, initially, to identify the problematic situations for future civil protection interventions during extreme heat. Moreover, it will be used as a reference for the Ville de Montreal to establish a strategy for public domain tree planting and in the analysis of urban development projects.

Argel, Buenos Aires, Montreal: el Comité de Cine del Tercer Mundo (1973 / 1974 / Algiers, Buenos Aires, Montreal: the Third World Cinema Committee (1973 / 1974

Directory of Open Access Journals (Sweden)

Mariano Mestman

2017-02-01

Full Text Available El encuentro de cineastas de Argel (Argelia en diciembre de 1973 es bien conocido en los estudios sobre el cine del Tercer Mundo. En cuanto oportunidad de intercambio y discusión, este encuentro permitió la organización del trabajo de los cineastas y focalizó el debate en tres ejes principales: la contribución del cine a los procesos de liberación nacional, la descolonización de las pantallas del Tercer Mundo y la lucha contra la «alienación cultural». El resultado más importante fue la creación del Comité de Cine del Tercer Mundo. Solo seis meses más tarde, un nuevo encuentro tuvo lugar en Buenos Aires (Argentina. Por un lado, el presente ensayo muestra cómo un proyecto político-cinematográfico (el «tercermundismo» fue tomando forma gradualmente durante esos años y destaca el rol de ambas reuniones en la promoción de esta nueva identidad político-cultural. Por otro, este trabajo también propone la necesidad de incorporar a esta historia otro evento decisivo: los Rencontres Internationales pour un Nouveau Cinema, realizados en Montreal en 1974. Poco considerado incluso por la bibliografía especializada, este encuentro puede considerarse el más importante del cine polí- tico mundial de los años sesenta y setenta. Dada la cantidad y diversidad de los participantes de Europa, Estados Unidos, África y América Latina, la conferencia de Montreal fue crucial en la constitución del diálogo entre los cineastas políticos del Primer Mundo y la tendencia tercermundista construida entre Argel y Buenos Aires.Palabras clave: Tercer Mundo, tercermundismo, Tercer Cine, Nuevo Cine Latinoamericano, Federación Panafricana de CineastasAbstract:The filmmakers meeting held in Algiers (Algeria in December 1973 is a wellknown event among Third World Cinema´s studies. As an opportunity to exchange and discussion, this gathering organised the work of Third World filmmakers and focused the debate on three main issues: the contribution of

Relocating Precarity and Resiliency within Montreal: The Artists' Bloc of the Immigrant Workers' Centre

Science.gov (United States)

Hall, Koby Rogers; Salamanca, Manuel

2017-01-01

In this document we describe our experience relocating precarity and resiliency by way of arts activism, to denounce and make visible social injustices experienced by im/migrant communities in Montreal. Under the umbrella of the Immigrant Workers' Centre, and other allies from the im/migrant workers' movement, we combine knowledge building, action…

Nerves and Nostalgia: Expression of Loss Among Greek Immigrants in Montreal

Science.gov (United States)

Lock, Margaret; Wakewich-Dunk, Pamela

1990-01-01

The authors interviewed first-generation Greek immigrant women in Montreal about nonspecific somatic symptoms. The concept of nevra (nerves), which was central to these discussions, was used to link environmental and psychosocial variables with distress and painful physical states. The authors discuss the cultural construction of female identity in Greece and analyze the negative effect of immigration on self-esteem, often manifested as attacks of nevra. Metaphorical concepts, such as nevra, can be used to improve physician understanding and to facilitate communication with, and enhance care of, immigrant patients. PMID:21234036

[Factors associated with dental consultation in children in Talca (Chile) and in Chilean immigrants in Montreal (Canada)].

Science.gov (United States)

Núñez, Loreto; Icaza, Gloria; Contreras, Violeta; Correa, Gloria; Canales, Tatiana; Mejía, Gloria; Oxman-Martínez, Jacqueline; Moreau, Jacques

2013-01-01

To identify the factors that influence the use of dental services in 4-7-year-olds and in 10-13-year-olds resident in the cities of Talca (Chile) and Montreal (Canada). A nonprobabilistic cross-sectional study was carried out in 147 boys and girls in Talca and in 94 boys and girls in Montreal between 2009 and 2011. Sociodemographic variables were recorded in parents and children, including age and sex. Data were also gathered on parental education, family composition, and proximity to health centers within neighborhoods. The data were analyzed with Fisher's exact test and the robust Cox regression model (with constant time) with a significance level of 0,05. In Talca, parental education was significantly associated with dental care visits at least twice a year. The children of parents with university education were 2.20 times more likely to consult a dentist (95% CI: 1.30-3.73). Children whose parents perceived their children's health positively were 53% (OR = 0,47; 95% CI: 0,28-0,77) less likely to consult a dentist. In Montreal, the children of parents with university education were 2.10 times more likely to consult a dentist (95%CI: 1.17-3.76), while older children (10-13 years) were 2.11 (95% CI: 1.15-3.88) times more likely to consult a dentist. In both cities, parental education level was associated with the use of dental services. Copyright © 2012 SESPAS. Published by Elsevier Espana. All rights reserved.

Strengthening the Montreal Protocol: Does it cool down the greenhouse?

International Nuclear Information System (INIS)

Den Elzen, M.G.J.; Swart, R.J.; Rotmans, J.

1992-01-01

Strengthening of the Montreal Protocol is recently being negotiated in London in 1990 in order to achieve further reductions of the regulated CFCs and to include possibly more substances. The implications of different policies with respect to control of ozone depleting substances for climate change are analysed, including the proposed substitution by HCFCs and HFCs, carbon tetrachloride and methylchloroform. A special halocarbon module was developed within the framework of RIVM's Integrated Model to Assess the Greenhouse Effect (IMAGE). IMAGE is a parametrized science based policy model and has been developed to give policy agencies a concise overview of the quantitative aspects of the greenhouse problem, to evaluate various policy options concerning climate change and to serve as a means of communication. It is concluded, from simulations with the halocarbon module, that it is of primary importance to achieve a further reduction of the regulated CFCs compared to the Montreal Protocol with compliance by as many countries as possible. From the perspective of the greenhouse effect the inclusion of longer lived halocarbons, such as carbon tetrachloride and HCFC-22 in the protocol come second. The application of methylchloroform, halons and HCFCs and HFCs with lower global warming potentials (GWPs) than HCFC-22 contributes only marginally to the greenhouse effect in comparison with the much more important greenhouse gases carbon dioxide, methane, ozone and nitrous oxide. Especially if further growth of the total production of HCFCs after complete replacement of the present CFCs can be avoided by using these alternatives with a lower GWP, these substances could therefore be tolerated in a transition period, from the perspective of global warming. 13 figs., 3 tabs., 29 refs

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

7th International k0-Users' Workshop

International Nuclear Information System (INIS)

Borut Smodis

2018-01-01

Complete text of publication follows. The k 0 method of neutron activation analysis (k 0 -NAA) has become a well-established analytical tool for elemental analysis of various samples since its introduction in mid-1970s. To strengthen its development, applications and use, a series of regular workshops dedicated to this particular analytical method has been introduced twenty-five years ago, held in Astene, Belgium (1992); Ljubljana, Slovenia (1996); Bruges, Belgium (2001); Funchal, Portugal (2005); Belo Horizonte, Brazil (2009) and Budapest, Hungary (2013). The 7th k 0 -Users' Workshop was held at Hotel Novotel Montreal Centre, Canada, 3-8 September 2017. The meeting was organized by Polytechnique Montreal in cooperation with the International Atomic Energy Agency. Twenty-seven participants from 16 different countries (Australia, Austria, Belgium, Brazil, Canada, Czech Republic, Egypt, Germany, Hungary, Italy, Jamaica, Peru, Slovenia, the Netherlands, Turkey, Vietnam) from all five continents discussed the latest developments and applications of k 0 -NAA. Thirty-three papers were presented in the following sessions: Fundamentals of k 0 -NAA, Nuclear Data, Neutron Flux Parameters, k 0 -NAA Methodology, Validation of k 0 -NAA, Facilities, Automatization, and k 0 -NAA Methodology and PGAA. The talks included presentations by two Keynote Speakers and one Honorary Speaker. During the workshop, scientific visits were paid to the SLOWPOKE NAA Laboratory and Thermal Hydraulics Laboratory of the Polytechnique Montreal. The upcoming 12 papers in this issue of the Journal of Radioanalytical and Nuclear Chemistry were selected to be published from the workshop. The next, 8th k 0 -Users' Workshop is expected to be held in Ljubljana, Slovenia in 2021.

Large-Eddy Simulation of pollutant dispersion in downtown Montreal: Evaluation of the convective and turbulent mass fluxes

NARCIS (Netherlands)

Gousseau, P.; Blocken, B.J.E.; Stathopoulos, T.; Heijst, van G.J.F.; Seppelt, R.; Voinov, A.A.; Lange, S.; Bankamp, D.

2012-01-01

Abstract: Large-Eddy Simulation of pollutant dispersion from a stack on the roof of a low-rise building in downtown Montreal is performed. Two wind directions are considered, with different wind flow patterns and plume behaviours. The resulting mean concentration field is observed and analysed with

14 CFR 203.4 - Montreal Agreement as part of airline-passenger contract and conditions of carriage.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Montreal Agreement as part of airline-passenger contract and conditions of carriage. 203.4 Section 203.4 Aeronautics and Space OFFICE OF THE SECRETARY, DEPARTMENT OF TRANSPORTATION (AVIATION PROCEEDINGS) ECONOMIC REGULATIONS WAIVER OF WARSAW CONVENTION LIABILITY LIMITS AND DEFENSES § 203.4...

Growing Physics and Astronomy Public Outreach in Montreal

Science.gov (United States)

Simard, Gabrielle; Lepo, Kelly

2017-01-01

AstroMcGill was founded in 2011 by an enthusiastic group of undergraduate students, graduate students and post-doctoral fellows. It serves as the education and public outreach (EPO) branch of the astronomy group within the Physics Department at McGill University in Montreal, Quebec. Over the last five years, AstroMcGill has grown from organizing sporadic visits in a couple primary schools to running a successful inquiry-based outreach programme for grade 4-6 students, the McGill Space Explorers. During the same time span, the attendance at public AstroNight lectures ramped up from attracting a few dozen people to over 500 people each month. We will highlight the recent successes of the programme and our best guesses for the reasons behind this success. We will also discuss the challenges of working in a bilingual city as we juggle our majority anglophone volunteers, a mandatory french science curriculum for primary school children and the (somewhat) overlapping English- and French-speaking communities in the city.

Clinical applications of positron emission tomography at Montreal Neurological Institute

International Nuclear Information System (INIS)

Morgan, P.P.

1983-01-01

The Montreal Neurological Institute occupies a leading position in positron emission tomography (PET) of the brain with the help of the following three techological gains: they have acquired a 'Therascan' positron emission tomograph manufactured by Atomic Energy of Canada Ltd.; also, a 'Baby Cyclotron' manufactured by Japan Steel Works Ltd.; and they have written a computer program to display the results in colour. Four short-lived isotopes are used; 11 C, 15 O, 18 F, 13 N. Studies of the oxygen uptake of tumours, their glucose metabolism (as monitored by 18 F labelled 2-fluoro-2-deoxyglucose), and their uptake of therapeutic agents, provide valuable research and diagnostic information. PET is also being used to study epilepsy and cerebrovascular disease

Cyberinfrastructure for Open Science at the Montreal Neurological Institute.

Science.gov (United States)

Das, Samir; Glatard, Tristan; Rogers, Christine; Saigle, John; Paiva, Santiago; MacIntyre, Leigh; Safi-Harab, Mouna; Rousseau, Marc-Etienne; Stirling, Jordan; Khalili-Mahani, Najmeh; MacFarlane, David; Kostopoulos, Penelope; Rioux, Pierre; Madjar, Cecile; Lecours-Boucher, Xavier; Vanamala, Sandeep; Adalat, Reza; Mohaddes, Zia; Fonov, Vladimir S; Milot, Sylvain; Leppert, Ilana; Degroot, Clotilde; Durcan, Thomas M; Campbell, Tara; Moreau, Jeremy; Dagher, Alain; Collins, D Louis; Karamchandani, Jason; Bar-Or, Amit; Fon, Edward A; Hoge, Rick; Baillet, Sylvain; Rouleau, Guy; Evans, Alan C

2016-01-01

Data sharing is becoming more of a requirement as technologies mature and as global research and communications diversify. As a result, researchers are looking for practical solutions, not only to enhance scientific collaborations, but also to acquire larger amounts of data, and to access specialized datasets. In many cases, the realities of data acquisition present a significant burden, therefore gaining access to public datasets allows for more robust analyses and broadly enriched data exploration. To answer this demand, the Montreal Neurological Institute has announced its commitment to Open Science, harnessing the power of making both clinical and research data available to the world (Owens, 2016a,b). As such, the LORIS and CBRAIN (Das et al., 2016) platforms have been tasked with the technical challenges specific to the institutional-level implementation of open data sharing, including: Comprehensive linking of multimodal data (phenotypic, clinical, neuroimaging, biobanking, and genomics, etc.)Secure database encryption, specifically designed for institutional and multi-project data sharing, ensuring subject confidentiality (using multi-tiered identifiers).Querying capabilities with multiple levels of single study and institutional permissions, allowing public data sharing for all consented and de-identified subject data.Configurable pipelines and flags to facilitate acquisition and analysis, as well as access to High Performance Computing clusters for rapid data processing and sharing of software tools.Robust Workflows and Quality Control mechanisms ensuring transparency and consistency in best practices.Long term storage (and web access) of data, reducing loss of institutional data assets.Enhanced web-based visualization of imaging, genomic, and phenotypic data, allowing for real-time viewing and manipulation of data from anywhere in the world.Numerous modules for data filtering, summary statistics, and personalized and configurable dashboards. Implementing

Trade restrictions as a means of enforcing compliance with international environmental law. Montreal Protocol on Substances that Deplete the Ozone Layer

International Nuclear Information System (INIS)

Lang, W.

1996-01-01

The contribution reviews primarily Art. 4 of the Montreal Protocol and its efficiency for enforcing compliance with obligations under international environmental law and discusses aspects of possible conflicts with GATT law. (CB)

Revising the diagnosis of congenital amusia with the Montreal Battery of Evaluation of Amusia

OpenAIRE

Pfeifer, Jasmin; Hamann, Silke

2015-01-01

This article presents a critical survey of the prevalent usage of the Montreal Battery of Evaluation of Amusia (MBEA; Peretz et al., 2003) to assess congenital amusia, a neuro-developmental disorder that has been claimed to be present in 4% of the population (Kalmus and Fry, 1980). It reviews and discusses the current usage of the MBEA in relation to cut-off scores, number of used subtests, manner of testing, and employed statistics, as these vary in the literature. Furthermore, data are pres...

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

The Montreal Cognitive Assessment (MoCA) is superior to the Mini Mental State Examination (MMSE) in detection of korsakoffs syndrome

NARCIS (Netherlands)

Oudman, Erik; Postma, Albert; Van Der Stigchel, Stefan; Appelhof, Britt; Wijnia, Jan W.; Nijboer, Tanja C W

2014-01-01

The Montreal Cognitive Assessment (MoCA) and Mini Mental State Examination (MMSE) are brief screening instruments for cognitive disorders. Although these instruments have frequently been used in the detection of dementia, there is currently little knowledge on the validity to detect Korsakoffs

Whispers of the Unspeakable: New York and Montreal Newspaper Coverage of the Oscar Wilde Trials in 1895

Directory of Open Access Journals (Sweden)

Greg Robinson

2015-03-01

Full Text Available Greg Robinson’s article “Whispers of the Unspeakable: New York and Montreal Newspaper Coverage of the Oscar Wilde Trials in 1895,” originally published in 2010 in the French-language journal Rue des Beaux Arts, no. 24 (2010, is here republished and—with much gratitude—translated (for the original text, please see http://www.oscholars.com/RBA/twenty-four/24.7/Articles.htm. Robinson’s transnational study focuses on how reading the specific language of newspaper reports of the Oscar Wilde case, literally from a distance, from places less emotionally attached to and nationally distinct from the scandal’s epicenter in London, England, provides insight into “the state of everyday public knowledge and discussion of (homosexuality, at least west of the Atlantic”; thus Robinson’s fascinating research, which involves numerous newspapers—from the elite New York Times to the New York Herald, from the Montreal Daily Star to the French-language papers of Quebec—concludes that the popular press, read transnationally, offers key insights into the developing attitudes toward and levels of interest in the newly forming identity of the “homosexual” across societies.

A comparison of the mini mental state exam to the Montreal cognitive assessment in identifying cognitive deficits in Parkinson's disease

NARCIS (Netherlands)

Zadikoff, Cindy; Fox, Susan H.; Tang-Wai, David F.; Thomsen, Teri; de Bie, Rob M. A.; Wadia, Pettarusup; Miyasaki, Janis; Duff-Canning, Sarah; Lang, Anthony E.; Marras, Connie

2008-01-01

Dementia is an important and increasingly recognized problem in Parkinson's disease (PD). The mini-mental state examination (MMSE) often fails to detect early cognitive decline. The Montreal cognitive assessment (MoCA) is a brief tool developed to detect mild cognitive impairment that assesses a

Risk of lung cancer associated with six types of chlorinated solvents: results from two case-control studies in Montreal, Canada

Science.gov (United States)

Methods: Two case-control studies of occupation and lung cancer were conducted in Montreal, including 2,016 cases and 2,001 population controls. Occupational exposure to a host of agents was evaluated using a combination of subject-reported job history and expert assessment. We e...

Organizational Strategies for Critical Transportation Infrastructure: Characteristics of Urban Resilience. The Case of Montreal.

Science.gov (United States)

Beauregard, Stéphane; Therrien, Marie-Christine; Normandin, Julie-Maude

2010-05-01

Organizational Strategies for Critical Transportation Infrastructure: Characteristics of Urban Resilience. The Case of Montreal. Stéphane Beauregard M.Sc. Candidate École nationale d'administration publique Julie-Maude Normandin Ph.D. Candidate École nationale d'administration publique Marie-Christine Therrien Professor École nationale d'administration publique The proposed paper presents preliminary results on the resilience of organizations managing critical infrastructure in the Metropolitan Montreal area (Canada). A resilient city is characterized by a network of infrastructures and individuals capable of maintaining their activities in spite of a disturbance (Godschalk, 2002). Critical infrastructures provide essential services for the functioning of society. In a crisis situation, the interruption or a decrease in performance of critical infrastructures could have important impacts on the population. They are also vulnerable to accidents and cascading effects because on their complexity and tight interdependence (Perrow, 1984). For these reasons, protection and security of the essential assets and networks are one of the objectives of organizations and governments. But prevention and recovery are two endpoints of a continuum which include also intermediate concerns: ensuring organizational robustness or failing with elegance rather than catastrophically. This continuum also includes organizational resilience (or system), or the ability to recover quickly after an interruption has occurred. Wildavsky (1988) proposes that anticipation strategies work better against known problems while resilience strategies focus on unknown problems. Anticipation policies can unnecessarily immobilize investments against risks, while resilience strategies include the potential for a certain sacrifice in the interests of a more long-term survival and adaptation to changing threats. In addition, a too large confidence in anticipation strategies can bring loss of capacity of an

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

Montreal Communication Evaluation Battery--Portuguese version: age and education effects.

Science.gov (United States)

Kerr, Mônica de Souza; Pagliarin, Karina Carlesso; Mineiro, Ana; Ferré, Perrine; Joanette, Yves; Fonseca, Rochele Paz

2015-01-01

To verify age and education effects on communication performance of healthy adults in the Montreal Communication Evaluation Battery, Portuguese version (MAC-PT). The sample comprised 90 healthy adults from Portugal, European Portuguese speakers, divided into nine groups according to educational level (4-9, 10-13, and > 13 years of formal schooling) and age (19-40, 41-64, and 65-80 years). The influence of age and education was assessed by comparing mean scores between groups, using a two-way analysis of variance followed by Bonferroni post hoc tests (p ≤ 0.05). The results showed that participants' performance was influenced by age in pragmatic-inferential, discursive, and prosodic tasks. Education had the greatest influence on the performance in all processes evaluated by the MAC-PT. Age and education seem to influence the communicative performance and should be considered in the assessment of neurological patients.

Commissioning of the first Manicouagan--Montreal 735 line

Energy Technology Data Exchange (ETDEWEB)

Baril, G A; Cahill, K; Dupont, A; Roberge, G

1966-01-01

In order to meet increasing demand, Hydro-Quebec will develop seven hydro power sites on the Manicouagan and Outardes Rivers to generate a total of 5,700 MW and an additional 30 billion kWh by 1973. On August 22, 1962, it was decided that the power would be transmitted over a 650-km network, using three 735-kV lines and six stations. The wet switching surge withstand level was set at 1,350 kV, based on the results obtained with a transient network analyser. The main 735-kV equipment was purchased from several manufacturers to insure prompt delivery and continuity of service. On September 21st, 1965, the Manicouagan-Levis section of the first line was energized at 735 kV, transmitting 300 MW. A month later, the second section of the line was energized and the power generated at the Manicouagan 2 plant was thus transmitted to Montreal. So far, only two pieces of equipment have shown signs of failure without causing, however, any serious shutdown. Results of tests carried out show that operation of a 735-kV network is safe and economical.

Solar water heating at Ikea's Montreal store; Chauffage solaire de l'eau courante au magasin Ikea de Montreal

Energy Technology Data Exchange (ETDEWEB)

Lagana, A.; Sonmor, K. [Ecovision experts-conseils inc., Montreal, PQ (Canada)

2010-01-01

The Ikea store in Montreal has integrated an energy efficient solar water heater into its building infrastructure. In June 2010, 30 fixed solar panels were installed on the roof to recuperate energy from the sun for hot water use in the restaurant and store facilities. Prior to this installation, the store was using natural gas for water heating purposes. During a sunny summer day, the solar water heater can provide 100 percent of the hot water needs of the store, even though it was designed to provide only one-third of the heating requirements. The panels are made of copper and painted with black titanium paint. A solution of water and antifreeze circulates in the panels. Digital controls are used at the pumps to control the temperature. The Ikea store uses approximately 3,100 gallons of water per day. The panels provide more than 60 MWh of energy, and represent a savings of 8440 cubic metres of natural gas, and a savings of 19.7 tons of carbon dioxide. The panels cost $1,300 and the return on investment is estimated to be 15.6 years. 3 figs.

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

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

Office-Based Screening for Dementia in Parkinson Disease: The Montreal Parkinson Risk of Dementia Scale in 4 Longitudinal Cohorts.

Science.gov (United States)

Dawson, Benjamin K; Fereshtehnejad, Seyed-Mohammad; Anang, Julius B M; Nomura, Takashi; Rios-Romenets, Silvia; Nakashima, Kenji; Gagnon, Jean-François; Postuma, Ronald B

2018-06-01

Parkinson disease dementia dramatically increases mortality rates, patient expenditures, hospitalization risk, and caregiver burden. Currently, predicting Parkinson disease dementia risk is difficult, particularly in an office-based setting, without extensive biomarker testing. To appraise the predictive validity of the Montreal Parkinson Risk of Dementia Scale, an office-based screening tool consisting of 8 items that are simply assessed. This multicenter study (Montreal, Canada; Tottori, Japan; and Parkinson Progression Markers Initiative sites) used 4 diverse Parkinson disease cohorts with a prospective 4.4-year follow-up. A total of 717 patients with Parkinson disease were recruited between May 2005 and June 2016. Of these, 607 were dementia-free at baseline and followed-up for 1 year or more and so were included. The association of individual baseline scale variables with eventual dementia risk was calculated. Participants were then randomly split into cohorts to investigate weighting and determine the scale's optimal cutoff point. Receiver operating characteristic curves were calculated and correlations with selected biomarkers were investigated. Dementia, as defined by Movement Disorder Society level I criteria. Of the 607 patients (mean [SD] age, 63.4 [10.1]; 376 men [62%]), 70 (11.5%) converted to dementia. All 8 items of the Montreal Parkinson Risk of Dementia Scale independently predicted dementia development at the 5% significance level. The annual conversion rate to dementia in the high-risk group (score, >5) was 14.9% compared with 5.8% in the intermediate group (score, 4-5) and 0.6% in the low-risk group (score, 0-3). The weighting procedure conferred no significant advantage. Overall predictive validity by the area under the receiver operating characteristic curve was 0.877 (95% CI, 0.829-0.924) across all cohorts. A cutoff of 4 or greater yielded a sensitivity of 77.1% (95% CI, 65.6-86.3) and a specificity of 87.2% (95% CI, 84.1-89.9), with a

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)

Indoor air quality, ventilation and energy conservation. Trip report 5th J Cartier Conference, Montreal 1992, FAGO report 92.37.K

NARCIS (Netherlands)

Hensen, J.L.M.

1992-01-01

This trip report serves as a brief description of my visit to the 5th International Jacques Carrier Conference, in Montreal 1992. First some general infonnation about the conference is presented. Then there is a list of contributions. This is followed by a brief indication of my own contribution,

Evaluation of air quality in arenas on the Island of Montreal : winter 2006-2007; Evaluation de la qualite de l'air dans les arenas de l'Ile de Montreal

Energy Technology Data Exchange (ETDEWEB)

Price, K.; Beausoleil, M.; Lefebvre, L.

2007-03-15

For the past twenty years, cases of nitrogen dioxide (NO{sub 2}) and carbon monoxide (CO) poisoning have been reported in arenas in Quebec. A 1997 evaluation of air quality in 332 arenas in 9 different countries revealed that 40 per cent of arenas worldwide have high concentration of NO{sub 2}. In Quebec, an air quality review at arenas in Montreal drew similar conclusions, that 69 per cent of the arenas have high concentrations of CO and/or NO{sub 2}. In 1997, Quebec's environmental health committee established criteria of 20 ppm for CO, and 0.5 ppm for NO{sub 2} in arenas, in order to ensure that athletes and the public at large do not suffer negative effects related to the presence of combustible gases. This information was distributed to the administrative personnel in arenas in Quebec by means of an awareness and information campaign. Since then, the number of arenas that have met these criteria for air quality in arenas in Montreal has climbed from 31 per cent in 1997 to 83 per cent in 2004. The practices put into action by arena administrators include: 1) regular maintenance of ice surface cleaning machines and other equipment that use fuel, 2) judicious use of ventilation so that gases can be evacuated from the premises, and, 3) periodic measurements of CO and NO{sub 2} during peak usage times such as tournaments. Other means of lowering gas emissions have also shown to be helpful, such as replacement of ice surface cleaning machines with electrical ones, installation of CO and NO{sub 2} detectors close to the rink surface so that ventilation machines could be activated, and the measurement and constant registration of these gases. It was concluded that these measures could help maintain good air quality in arenas. 15 refs., 1 tabs., 1 fig.

El Protocolo de Montreal relativo a las sustancias que agotan la capa de ozono (1999) y la enmienda de Beijing. Un análisis de sus contenidos, alcances y sus percusiones presentes.

OpenAIRE

Zúñiga, Francisco Javier

2015-01-01

El presente ensayo consta de cuatro partes, una desarrolla de manera actualizadalos alcances del Protocolo de Montreal ysus enmiendas, la segunda examina los alcances de la Enmienda de Beijing, seguido de un análisis del impacto que hatenido el Protocolo de Montreal para el país. Finalmente se repasa la ejecución del Protocolo y sus enmiendas en nuestropaís y se agregan consideraciones que su implementación ha supuesto en el desarrollo ...

Being a Creative and an Immigrant in Montreal

Directory of Open Access Journals (Sweden)

Diane-Gabrielle Tremblay

2016-09-01

Full Text Available Work on creative careers has focused on the main national populations, while little research has addressed the situation of artists and creators of immigrant origin or different ethnic groups to determine whether they have the same access to work and employment rights. To respond for a call for research on different ethnic groups in the cultural sector, or the ethnic consequences of the individualization of careers, we therefore undertook research on the creative careers of immigrants in Montreal. We were interested in how they emerged as an artist, how they developed their careers, the access and rights they have in terms of support to their career, as McRobbie seems to indicate that ethnicity adds its “own weight to the life chances of those who are attempting to make a living in these fields. We found that these immigrant artists consider their main difficulties to be the lack of social networks, access to various forms of support to compensate for financial risks and difficulties in finding a job. We conclude with a few suggestions: measures to facilitate networking for immigrants, more training and information on government programs, mentoring support, as well as the support from community organizations, associations, and programs.

The Economic Value of the Greater Montreal Blue Network (Quebec, Canada: A Contingent Choice Study Using Real Projects to Estimate Non-Market Aquatic Ecosystem Services Benefits.

Directory of Open Access Journals (Sweden)

Thomas G Poder

Full Text Available This study used a contingent choice method to determine the economic value of improving various ecosystem services (ESs of the Blue Network of Greater Montreal (Quebec, Canada. Three real projects were used and the evaluation focused on six ESs that are related to freshwater aquatic ecosystems: biodiversity, water quality, carbon sequestration, recreational activities, landscape aesthetics and education services. We also estimated the value associated with the superficies of restored sites. We calculated the monetary value that a household would be willing to pay for each additional qualitative or quantitative unit of different ESs, and these marginal values range from $0.11 to $15.39 per household per unit. Thus, under certain assumptions, we determined the monetary values that all Quebec households would allocate to improve each ES in Greater Montreal by one unit. The most valued ES was water quality ($13.5 million, followed by education services ($10.7 million, recreational activities ($8.9 million, landscape aesthetics ($4.1 million, biodiversity ($1.2 million, and carbon sequestration ($0.1 million. Our results ascribe monetary values to improved (or degraded aquatic ecosystems in the Blue Network of Greater Montreal, but can also enhance economic analyses of various aquatic ecosystem restoration and management projects.

The Economic Value of the Greater Montreal Blue Network (Quebec, Canada): A Contingent Choice Study Using Real Projects to Estimate Non-Market Aquatic Ecosystem Services Benefits.

Science.gov (United States)

Poder, Thomas G; Dupras, Jérôme; Fetue Ndefo, Franck; He, Jie

2016-01-01

This study used a contingent choice method to determine the economic value of improving various ecosystem services (ESs) of the Blue Network of Greater Montreal (Quebec, Canada). Three real projects were used and the evaluation focused on six ESs that are related to freshwater aquatic ecosystems: biodiversity, water quality, carbon sequestration, recreational activities, landscape aesthetics and education services. We also estimated the value associated with the superficies of restored sites. We calculated the monetary value that a household would be willing to pay for each additional qualitative or quantitative unit of different ESs, and these marginal values range from $0.11 to $15.39 per household per unit. Thus, under certain assumptions, we determined the monetary values that all Quebec households would allocate to improve each ES in Greater Montreal by one unit. The most valued ES was water quality ($13.5 million), followed by education services ($10.7 million), recreational activities ($8.9 million), landscape aesthetics ($4.1 million), biodiversity ($1.2 million), and carbon sequestration ($0.1 million). Our results ascribe monetary values to improved (or degraded) aquatic ecosystems in the Blue Network of Greater Montreal, but can also enhance economic analyses of various aquatic ecosystem restoration and management projects.

The role of advocacy coalitions in a project implementation process: the example of the planning phase of the At Home/Chez Soi project dealing with homelessness in Montreal.

Science.gov (United States)

Fleury, Marie-Josée; Grenier, Guy; Vallée, Catherine; Hurtubise, Roch; Lévesque, Paul-André

2014-08-01

This study analyzed the planning process (summer 2008 to fall 2009) of a Montreal project that offers housing and community follow-up to homeless people with mental disorders, with or without substance abuse disorders. With the help of the Advocacy Coalition Framework (ACF), advocacy groups that were able to navigate a complex intervention implementation process were identified. In all, 25 people involved in the Montreal At Home/Chez Soi project were surveyed through interviews (n=18) and a discussion group (n=7). Participant observations and documentation (minutes and correspondence) were also used for the analysis. The start-up phase of the At Home/Chez may be broken down into three separate periods qualified respectively as "honeymoon;" "clash of cultures;" and "acceptance & commitment". In each of the planning phases of the At Home/Chez Soi project in Montreal, at least two advocacy coalitions were in confrontation about their specific belief systems concerning solutions to address the recurring homelessness social problem, while a third, more moderate one contributed in rallying most key actors under specified secondary aspects. The study confirms the importance of policy brokers in achieving compromises acceptable to all advocacy coalitions. Copyright © 2014 Elsevier Ltd. All rights reserved.

Modeling climate effects on hip fracture rate by the multivariate GARCH model in Montreal region, Canada

Science.gov (United States)

Modarres, Reza; Ouarda, Taha B. M. J.; Vanasse, Alain; Orzanco, Maria Gabriela; Gosselin, Pierre

2014-07-01

Changes in extreme meteorological variables and the demographic shift towards an older population have made it important to investigate the association of climate variables and hip fracture by advanced methods in order to determine the climate variables that most affect hip fracture incidence. The nonlinear autoregressive moving average with exogenous variable-generalized autoregressive conditional heteroscedasticity (ARMA X-GARCH) and multivariate GARCH (MGARCH) time series approaches were applied to investigate the nonlinear association between hip fracture rate in female and male patients aged 40-74 and 75+ years and climate variables in the period of 1993-2004, in Montreal, Canada. The models describe 50-56 % of daily variation in hip fracture rate and identify snow depth, air temperature, day length and air pressure as the influencing variables on the time-varying mean and variance of the hip fracture rate. The conditional covariance between climate variables and hip fracture rate is increasing exponentially, showing that the effect of climate variables on hip fracture rate is most acute when rates are high and climate conditions are at their worst. In Montreal, climate variables, particularly snow depth and air temperature, appear to be important predictors of hip fracture incidence. The association of climate variables and hip fracture does not seem to change linearly with time, but increases exponentially under harsh climate conditions. The results of this study can be used to provide an adaptive climate-related public health program and ti guide allocation of services for avoiding hip fracture risk.

Effect of phenotype on health care costs in Crohn's disease: A European study using the Montreal classification.

Science.gov (United States)

Odes, Selwyn; Vardi, Hillel; Friger, Michael; Wolters, Frank; Hoie, Ole; Moum, Bjørn; Bernklev, Tomm; Yona, Hagit; Russel, Maurice; Munkholm, Pia; Langholz, Ebbe; Riis, Lene; Politi, Patrizia; Bondini, Paolo; Tsianos, Epameinondas; Katsanos, Kostas; Clofent, Juan; Vermeire, Severine; Freitas, João; Mouzas, Iannis; Limonard, Charles; O'Morain, Colm; Monteiro, Estela; Fornaciari, Giovanni; Vatn, Morten; Stockbrugger, Reinhold

2007-12-01

Crohn's disease (CD) is a chronic inflammation of the gastrointestinal tract associated with life-long high health care costs. We aimed to determine the effect of disease phenotype on cost. Clinical and economic data of a community-based CD cohort with 10-year follow-up were analyzed retrospectively in relation to Montreal classification phenotypes. In 418 patients, mean total costs of health care for the behavior phenotypes were: nonstricturing-nonpenetrating 1690, stricturing 2081, penetrating 3133 and penetrating-with-perianal-fistula 3356 €/patient-phenotype-year (P<0.001), and mean costs of surgical hospitalization 215, 751, 1293 and 1275 €/patient-phenotype-year respectively (P<0.001). Penetrating-with-perianal-fistula patients incurred significantly greater expenses than penetrating patients for total care, diagnosis and drugs, but not surgical hospitalization. Total costs were similar in the location phenotypes: ileum 1893, colon 1748, ileo-colonic 2010 and upper gastrointestinal tract 1758 €/patient-phenotype-year, but surgical hospitalization costs differed significantly, 558, 209, 492 and 542 €/patient-phenotype-year respectively (P<0.001). By multivariate analysis, the behavior phenotype significantly impacted total, medical and surgical hospitalization costs, whereas the location phenotype affected only surgical costs. Younger age at diagnosis predicted greater surgical expenses. Behavior is the dominant phenotype driving health care cost. Use of the Montreal classification permits detection of cost differences caused by perianal fistula.

Global warming potential estimates for the C1-C3 hydrochlorofluorocarbons (HCFCs) included in the Kigali Amendment to the Montreal Protocol

Science.gov (United States)

Papanastasiou, Dimitrios K.; Beltrone, Allison; Marshall, Paul; Burkholder, James B.

2018-05-01

Hydrochlorofluorocarbons (HCFCs) are ozone depleting substances and potent greenhouse gases that are controlled under the Montreal Protocol. However, the majority of the 274 HCFCs included in Annex C of the protocol do not have reported global warming potentials (GWPs) which are used to guide the phaseout of HCFCs and the future phase down of hydrofluorocarbons (HFCs). In this study, GWPs for all C1-C3 HCFCs included in Annex C are reported based on estimated atmospheric lifetimes and theoretical methods used to calculate infrared absorption spectra. Atmospheric lifetimes were estimated from a structure activity relationship (SAR) for OH radical reactivity and estimated O(1D) reactivity and UV photolysis loss processes. The C1-C3 HCFCs display a wide range of lifetimes (0.3 to 62 years) and GWPs (5 to 5330, 100-year time horizon) dependent on their molecular structure and the H-atom content of the individual HCFC. The results from this study provide estimated policy-relevant GWP metrics for the HCFCs included in the Montreal Protocol in the absence of experimentally derived metrics.

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.)

Evaluation of air quality in arenas on the Island of Montreal : winter 2006-2007

International Nuclear Information System (INIS)

Price, K.; Beausoleil, M.; Lefebvre, L.

2007-03-01

For the past twenty years, cases of nitrogen dioxide (NO 2 ) and carbon monoxide (CO) poisoning have been reported in arenas in Quebec. A 1997 evaluation of air quality in 332 arenas in 9 different countries revealed that 40 per cent of arenas worldwide have high concentration of NO 2 . In Quebec, an air quality review at arenas in Montreal drew similar conclusions, that 69 per cent of the arenas have high concentrations of CO and/or NO 2 . In 1997, Quebec's environmental health committee established criteria of 20 ppm for CO, and 0.5 ppm for NO 2 in arenas, in order to ensure that athletes and the public at large do not suffer negative effects related to the presence of combustible gases. This information was distributed to the administrative personnel in arenas in Quebec by means of an awareness and information campaign. Since then, the number of arenas that have met these criteria for air quality in arenas in Montreal has climbed from 31 per cent in 1997 to 83 per cent in 2004. The practices put into action by arena administrators include: 1) regular maintenance of ice surface cleaning machines and other equipment that use fuel, 2) judicious use of ventilation so that gases can be evacuated from the premises, and, 3) periodic measurements of CO and NO 2 during peak usage times such as tournaments. Other means of lowering gas emissions have also shown to be helpful, such as replacement of ice surface cleaning machines with electrical ones, installation of CO and NO 2 detectors close to the rink surface so that ventilation machines could be activated, and the measurement and constant registration of these gases. It was concluded that these measures could help maintain good air quality in arenas. 15 refs., 1 tabs., 1 fig

The Domestic Foodscapes of Young Low-Income Women in Montreal: Cooking Practices in the Context of an Increasingly Processed Food Supply

Science.gov (United States)

Engler-Stringer, Rachel

2010-01-01

Over the course of the past century, the quantity of prepackaged, pre-prepared foods available in the North American context has increased dramatically. This study examines the shifts in food practices that are taking place through an exploration of the day-to-day cooking practices of a group of young, low-income women in Montreal and considers…

New developments in small reactors

International Nuclear Information System (INIS)

McDonnell, F.N.; Reed, A.

1990-08-01

During the fifty years since nuclear fission was discovered, nuclear energy has emerged to play an increasingly important role in meeting global energy needs. At the recent World Energy Conference in Montreal, 1989 September, experts agreed that nuclear power will continue to be an essential part of the future energy mix. The demand for economic and reliable energy sources is driven by the growth in the world's population and the essential role energy plays in industrial development. Global energy requirements, expected to double over the next 40 years, will seriously challenge suppliers in their ability to meet the demand. Ultimately, efficient energy utilization will become singularly important. Industrialization and economic development manifest themselves in urbanization. Urban dwellers consume significantly more energy per capita compared with their rural neighbours. Consequently, concentrated and environmentally acceptable energy sources, combined with efficient distribution systems, are now recognized as essential to meet urban energy demands. In considering the alternatives that will meet these requirements, nuclear energy qualifies as both a concentrated and environmentally benign source. Nuclear electricity generation is a mature technology that paves the way for other applications. 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 appropriately designed and sized reactors developed as an investment in the future. To meet this potential, new small reactor concepts are being developed to satisfy the expected energy demands, while also displaying characteristics that address current public concerns for providing minimal environmental impact. Concepts ranging in sized from 10 MW(t) to 1000 MW(t) are being pursued in a number of countries, including Canada, USA, UK, China, and

The recommissioning of Montreal's Palais des Congres; Le recommissioning du Palais des congres de Montreal

Energy Technology Data Exchange (ETDEWEB)

Poirier, M. [Palais des Congres, Montreal, PQ (Canada); Deschamps, J.F. [Pageau Morel et Associes, Montreal, PQ (Canada)

2006-12-15

An addition was constructed onto the Palais des Congres building in Montreal in 2002. When the energy performance of the newly recommissioned building failed to meet the expectations of the construction contractor, an Energy Savings Commission was created with a mandate was to reduce energy consumption by 25 per cent over a 3 to 5 year time period, representing a savings of $500,000 per year. The objective was to make advantageous changes that would not compromise occupant comfort or interior air quality. The Committee identified areas of possible improvements in the building's heating, ventilating and air conditioning (HVAC) system. Improvements in lighting systems and humidity control were also investigated. The Committee identified necessary upgrades and evaluated the changes in terms of technical feasibility, financial profit and sustainability. The Committee was also responsible for acquiring the authorization needed to proceed with the investment and implement change. This paper listed the energy saving measures along with the associated savings in electricity and natural gas. It also listed the associated reduction in greenhouse gas emissions. The energy saving measures undertaken by the Committee were based on 3 fundamental principles which included turning off equipment that was not being used in different areas of the building; optimizing the energy use of equipment; and, replacing or modifying inefficient equipment. In November 2005, the Palais des Congres hosted the Energy Efficiency Week, during which time it made use of CANMET's Diagnostic Agent for Building Operators (DABO) software package to achieve energy savings. A program aimed at training employees in energy efficiency was also implemented and feedback on key issues was acquired. Hydro-Quebec also contributed $25,000 towards the energy analysis performed by the Committee. The objective of saving $500,000 in energy costs over a 3 to 5 year period was met. 3 tabs., 1 fig.

The Montreal General Hospital Pain Centre (1974-2000: The Contributions of Ronald Melzack

Directory of Open Access Journals (Sweden)

Mary Ellen Jeans

2000-01-01

Full Text Available This paper chronicles the development of the Montreal General Hospital Pain Centre from its inception in 1974 to the present. Highlighted in particular are the contributions of Ronald Melzack to this history. Data for the article arose, in the main, from an interview with Dr Melzack carried out earlier in the year. Discussions with former and present members of the pain centre team, including former graduate students, provided additional information. The article begins with a recounting of those individuals and events that inspired Ron early in his 'pain career' to pursue his dream of a multidisciplinary pain centre, the first of its kind in Canada. The forces that helped shape the development of this centre and the challenges that had to be overcome are described.

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

Individual- and area-level disparities in access to the road network, subway system and a public bicycle share program on the Island of Montreal, Canada.

Science.gov (United States)

Fuller, Daniel; Gauvin, Lise; Kestens, Yan

2013-02-01

Few studies have examined potential disparities in access to transportation infrastructures, an important determinant of population health. To examine individual- and area-level disparities in access to the road network, public transportation system, and a public bicycle share program in Montreal, Canada. Examining associations between sociodemographic variables and access to the road network, public transportation system, and a public bicycle share program, 6,495 adult respondents (mean age, 48.7 years; 59.0 % female) nested in 33 areas were included in a multilevel analysis. Individuals with lower incomes lived significantly closer to public transportation and the bicycle share program. At the area level, the interaction between low-education and low-income neighborhoods showed that these areas were significantly closer to public transportation and the bicycle share program controlling for individual and urbanicity variables. More deprived areas of the Island of Montreal have better access to transportation infrastructure than less-deprived areas.

‘THE BIGGEST MISTAKE GOD EVER MADE WAS TO CREATE JUNKIES’: UNSAFE INJECTION PRACTICES, HEALTH CARE DISCRIMINATION AND OVERDOSE DEATHS IN MONTREAL, CANADA

Directory of Open Access Journals (Sweden)

Jozaghi, Ehsan

2013-01-01

Full Text Available Despite the existence of prevention programmes in Montreal, Canada, injection drug users (IDUs continue to share their injection drug equipment. This practice has led to an increase in the incidences of HIV and Hepatitis C (HCV among IDUs since 2003. The present study was conducted to explore factors contributing to the increased risks of this morbidity. Semi-structured qualitative interviews were conducted as drug users were actively involved in their routine activities. The participants’ narratives indicate that IDUs in Montreal are involved in risky injection behaviour that increases HIV, HCV and bacterial transmission. Moreover, IDUs in Montreal are at an increased risk of overdose and death when they are forced to inject in public washrooms or alleys. In addition, many IDUs have placed the general public at risk by discarding their used needles in public parks, sidewalks and public washrooms. Furthermore, many IDUs in Montreal have faced discrimination and are refused treatment by the health care system. Micro- environmental factors, such as a paucity of safe injection sites, inaccessibility of injection equipment and discrimination all seem to be contributing factors in recent increases in HIV and HCV in Montreal.Malgré les programmes de prévention qui existent à Montréal, Canada, les utilisateurs de drogues injectables (UDI continuent de partager leurs seringues. Cette pratique a mené à une augmentation de l’incidence du virus de l’immunodéficience humaine (VIH et du virus de l’hépatite C (VHC parmi les UDI depuis 2003. La présente étude a été menée afin d’examiner les facteurs qui contribuent à l’augmentation des risques de cette morbidité. Des entretiens qualitatifs semi-directifs ont été réalisés pendant que les utilisateurs faisaient usage de drogues. Les commentaires recueillis auprès des participants ont confirmé que les UDI de Montréal adoptent des comportements d’injection qui augmentent les

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

El programa de prevención de Montreal: lecciones para Colombia

Directory of Open Access Journals (Sweden)

Enrique Chaux

2005-08-01

Full Text Available The Montreal Prevention Program has demonstrated a mayor world success in prevention of delinquency and violence. The most aggressive students of second and third grade participated in an intervention that had two components. First, several activities were done to develop social abilities and competencies. These activities occurred in small groups with one or two aggressive boys and other prosocial kids. Second, the families of the aggressive boys were visited several times in a two year period in order to help them develop child rearing practices such as constructive management of conflicts and crisis, handling of rewards, and monitoring the child behavior. Assessment demonstrated that the program decreased the delinquent and aggressive behavior, and also some risk behaviors such as drug use, early sexual activities, gang membership and school dropout. Some of these effects are still measurable in adulthood, almost 15 years after participating in the program. The article presents a detailed analysis of this experience, and also eight lessons for Colombia, among them, that the prevention is rewarding, especially when done early in life.

Psychic centrality: reflections on two psychohistoriographic cultural therapy workshops in Montreal.

Science.gov (United States)

Hickling, Frederick W; Guzder, Jaswant; Robertson-Hickling, Hilary; Snow, Stephen; Kirmayer, Laurence J

2010-02-01

The use of psychohistoriographic cultural therapy (PCT) developed in Jamaica is described in the context of two workshops in Montreal. PCT is a form of group intervention that seeks to elicit and clarify the "psychic centrality" of a group. Psychic centrality refers to a sense of psychological containment or organization of diverse individual points of view through creating a historical map of collective experience. In PCT, this collective map is constructed and techniques borrowed from creative arts therapies are used to develop a performance. This performance provides additional containment and fosters a group process that can contain collective conflicts. The performance can also be used to engage an audience, working to contain conflict while representing diverse perspectives within the group. Factors that may contribute to the effectiveness of PCT and those that may derail the process are identified through the systematic comparison of the two workshops. PCT was demonstrated to cross successfully from a Third to a First World culture, and established potential as a method to facilitate group conflict resolution and for the promotion of pluralistic civil societies.

Soundscape studies in Montreal's Biodome: using enclosed ecosystems to explain biodiversity to the public

Science.gov (United States)

Fisher Favret, K. E.

2016-02-01

The Biodome in Montreal is a unique public museum with over 750 species organized into five different ecosystems. We spent several weeks obtaining soundscapes from three of these: Gulf of St. Lawrence, Labrador Coast, and Sub-Antarctic Islands. The idea was to leverage the accessibility and known biodiversity of these mesocosms to calibrate instruments, evaluate methods for assessing biodiversity, and educate people ranging from the penguin keeper to the general public about soundscape ecology and biodiversity assessments. The Gulf of St. Lawrence exhibit has hundreds of fish that belong to 20 species swimming in 2.5 million gallons of seawater, with seabirds and invertebrates nearby. The Sub-Antarctic Islands exhibit, by contrast, has four species of penguins. As part of Montreal's Space for Life program, there is a searchable index of the species available to the public: http://espacepourlavie.ca/en/fauna-and-flora-biodome.The emerging field of soundscape ecology offers a new approach for effectively monitoring changes in sounds generated by communities ranging from urban centers to oceans. The entropy-based approach pioneered by Sueur et al., (2008) characterizes acoustic spectrograms based on the spectral space-filling properties of the sound producers. By calculating the complexity of the acoustic environment, we can detect cycles over various time scales. Disturbed systems can be detected by changes in the timing and frequency of sounds filling various "niches" in the soundscape that might act as early warnings of changes induced on scales from single events to climate shifts. These changes range from presence or absence of vocalizations by individual species, to changes in the higher order statistics of the daily sound structures that include sounds with physical, biological, and human origins. Here we show what we have learned so far about comparing enclosed ecosystems to the real world outside, and some of the challenges and rewards of using soundscape

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.)

L'evaluation du francais des jeunes Anglo-montrealais par leurs pairs francophones (Evaluation of the French of Young Montreal Anglophones by Their Francophone Peers).

Science.gov (United States)

Thibault, Pierrette; Sankoff, Gillian

1999-01-01

Analyzes the reactions of francophone Montrealers (n=116) to the recorded speech of English speakers using French. Particular focus is on finding out which linguistic traits of speech triggered the judgments on the speakers' competence and to what extent they met the judges expectations with regard to their job suitability. (Author/VWL)

[Rape by 2 assaillants and gang rape in Montreal].

Science.gov (United States)

Lamontagne, Y; Boyer, R; Lamontagne, C; Giroux, J

1984-11-01

A survey was conducted in 230 cases of rape and rape attempts heard in the Judicial District of Montreal between January 1975 and May 1978. Data were compiled from the 30 assaults including two or more assaillants. Results show that in cases of rape committed by two men the aggressors are older than gang rapists, meet the victim mainly in her flat or in a bar, and rape her in her own home, in a car or a hotel. In these cases, voyeurism seems to be an important factor since, most of the time, rape is committed by only one of the two aggressors. On the other hand, gang rapists are younger, meet the victim in public places, on the street or when she is hitch-hiking and attack her in one of the aggressors' house, in public places or on the street. Exhibitionism seems more present in this group of rapists. For both groups the victims are mainly single, younger than the aggressors and have diverse occupations. Finally, regarding the legal outcome half of the subjects were liberated or acquitted in both groups. Rape committed by two men had never been studied or compared with gang rape up until now. Results of this survey show dynamic and demographic differences between these two groups of sexual delinquents.

Control and monitoring of landfill gas underground migration at the City of Montreal sanitary landfill site

International Nuclear Information System (INIS)

Heroux, M.; Turcotte, L.

1997-01-01

The proposed paper covers the various aspects of control and monitoring of potential landfill gas (LFG) migration through soil voids or rock fractures at the City of Montreal sanitary landfill site. It depicts the social, geographical and geological context and presents a brief history of the landfill site. It describes the LFG collecting system and LFG migration monitoring equipment and programs. Finally it presents monitoring data taken over last few years. The landfill site is located in a well populated urban area. Since 1968, about 33 million metric tons of domestic and commercial waste have been buried in a former limestone quarry. Because of houses and buildings in the vicinity, 100 m in some locations, LFG underground migration is a major risk. LFG could indeed infiltrate buildings and reach explosive concentrations. So it must be controlled. The City of Montreal acquired the site in 1988 and has progressively built a LFG collecting system, composed of more than 288 vertical wells, to pump out of the landfill 280 million m 3 of gas annually. To verify the efficiency of this system to minimize LFG underground migration, monitoring equipment and programs have also been designed and put into operation. The monitoring network, located all around the landfill area, is composed of 21 well nests automated to monitor presence of gas in the ground in real time. In addition, 55 individual wells, where manual measurements are made, are also available. To complete the monitoring program, some measurements are also taken in buildings, houses and underground utilities in the neighborhood of the site. Monitoring data show that LFG underground migration is well controlled. They also indicate significant decrease of migration over the years corresponding to improvements to the LFG collecting system

Montreal Cognitive Assessment (MoCA): validation study for frontotemporal dementia.

Science.gov (United States)

Freitas, Sandra; Simões, Mário R; Alves, Lara; Duro, Diana; Santana, Isabel

2012-09-01

The Montreal Cognitive Assessment (MoCA) is a brief instrument developed for the screening of milder forms of cognitive impairment, having surpassed the well-known limitations of the Mini-Mental State Examination (MMSE). The aim of the present study was to validate the MoCA as a cognitive screening test for behavioral-variant frontotemporal dementia (bv-FTD) by examining its psychometric properties and diagnostic accuracy. Three matched subgroups of participants were considered: bv-FTD (n = 50), Alzheimer disease (n = 50), and a control group of healthy adults (n = 50). Compared with the MMSE, the MoCA demonstrated consistently superior psychometric properties and discriminant capacity, providing comprehensive information about the patients' cognitive profiles. The diagnostic accuracy of MoCA for bv-FTD was extremely high (area under the curve AUC [MoCA] = 0.934, 95% confidence interval [CI] = 0.866-.974; AUC [MMSE] = 0.772, 95% CI = 0.677-0.850). With a cutoff below 17 points, the MoCA results for sensitivity, specificity, positive predictive value, negative predictive value, and classification accuracy were significantly superior to those of the MMSE. The MoCA is a sensitive and accurate instrument for screening the patients with bv-FTD and represents a better option than the MMSE.

Manganese concentrations in the air of the Montreal (Canada) subway in relation to surface automobile traffic density

Energy Technology Data Exchange (ETDEWEB)

Boudia, Nacera; Gareau, Lise; Zayed, Joseph [GRIS Interdisciplinary Health Research Group, University of Montreal (Canada); Halley, Renee [Transport Montreal Society (Canada); Kennedy, Greg [Department of Engineering Physics, Ecole Polytechnique de Montreal, Montreal (Canada); Lambert, Jean [Department of Social and Preventive Medicine, Faculty of Medicine, University of Montreal (Canada)

2006-07-31

Methylcyclopentadienyl manganese tricarbonyl (MMT) is an organic derivative of manganese (Mn), used since 1976 in Canadian gasoline as an octane enhancer. Its combustion leads to the emission of Mn particles. Several studies carried out by our research group have established a correlation between atmospheric Mn concentrations and automobile traffic density, suggesting that MMT in gasoline could play a significant role. This study aims to measure Mn concentrations in the air of the underground subway in Montreal (Canada) and to examine the relation with nearby surface automobile traffic density and, by extension, with the use of MMT in gasoline. Three subway stations were chosen for their location in different microenvironments with different traffic densities. Respirable (MnR<5 {mu}m) and total Mn (MnT) were sampled over two weeks, 5 days/week, 12 h/day. For the station located in the lower traffic density area, relatively low levels of MnR and MnT were found, with averages of 0.018 and 0.032 {mu}g/m{sup 3}, respectively. These concentrations are within the range of the background levels in Montreal. For the other two stations, the average concentrations of MnR were twice as high and exceeded the US EPA reference concentration of 0.05 {mu}g/m{sup 3}. Although there may be several sources of Mn from different components of the subway structure and vehicles, no correlation was found between subway traffic and atmospheric Mn in the subway. Since the air in the underground subway is pumped directly from outside without filtration, our findings strongly suggest that the combustion of MMT in automobiles is an important factor. (author)

Bank of Montreal v. Dynex Petroleum Ltd.: the priority of overriding royalties and net profit interests

International Nuclear Information System (INIS)

Dearlove, F.R.

1996-01-01

The practice by the petroleum industry of granting overriding royalties (ORRs) and net profit interests (NPIs), was discussed. Some of the reasons for granting ORRs or NPIs included: (1) securing a lease, (2) obtaining geological information, (3) a condition of employment, or (4) acceptance of risk in exploration. In the recent case of Bank of Montreal versus Dynex Petroleum Ltd., it was held that in Alberta, ORRs and NPIs issuing out of a lessee's interest in an oil and gas lease cannot be a grant of interest in land. The effect of this decision is that it will make it difficult to create an ORR or NPI that is not merely a contract. An appeal is expected

Musical cognition in Alzheimer's disease: application of the Montreal Battery of Evaluation of Amusia.

Science.gov (United States)

Campanelli, Alessandra; Rendace, Lidia; Parisi, Francesco; D'Antonio, Fabrizia; Imbriano, Letizia; de Lena, Carlo; Trebbastoni, Alessandro

2016-07-01

The aim of this study was to assess certain musical abilities in 30 patients with Alzheimer's disease (AD) and 30 healthy controls by using the complete version of the Montreal Battery of Evaluation of Amusia (MBEA). This battery evaluates melodic (scale, contour, and interval) and temporal (rhythm and meter) perception of music and musical memory. We found that altered musical processing is a common feature in AD. Despite that, AD subjects show partially spared abilities for temporal organization of music, though not for melodic perception and musical memory. This peculiar dysfunctional pattern could depend on the neurodegenerative involvement of some specific areas for music perception and memory in the brains of AD patients. Further studies are needed to investigate the usefulness of additional musical tests like the MBEA on larger samples to confirm our preliminary data. © 2016 New York Academy of Sciences.

Comparison of Alternate and Original Items on the Montreal Cognitive Assessment.

Science.gov (United States)

Lebedeva, Elena; Huang, Mei; Koski, Lisa

2016-03-01

The Montreal Cognitive Assessment (MoCA) is a screening tool for mild cognitive impairment (MCI) in elderly individuals. We hypothesized that measurement error when using the new alternate MoCA versions to monitor change over time could be related to the use of items that are not of comparable difficulty to their corresponding originals of similar content. The objective of this study was to compare the difficulty of the alternate MoCA items to the original ones. Five selected items from alternate versions of the MoCA were included with items from the original MoCA administered adaptively to geriatric outpatients (N = 78). Rasch analysis was used to estimate the difficulty level of the items. None of the five items from the alternate versions matched the difficulty level of their corresponding original items. This study demonstrates the potential benefits of a Rasch analysis-based approach for selecting items during the process of development of parallel forms. The results suggest that better match of the items from different MoCA forms by their difficulty would result in higher sensitivity to changes in cognitive function over time.

Montreal Protocol meeting looks to speed up phaseout of ozone depleters

International Nuclear Information System (INIS)

Rotman, D.; Chynoweth, E.

1992-01-01

Delegates from around the world are meeting in Copenhagen this week to debate an accelerated phaseout of chlorofluorocarbons (CFCs), a time schedule for the eventual phaseout of hydrochlorofluorocarbons (HCFCs), and phaseouts of methyl chloroform and carbon tetrachloride. The fate of methyl bromide will also be a hot issue. The fourth meeting of the parties to the Montreal Protocol is widely expected to put through a 100% CFC phaseout by Jan. 1, 1996, coming into agreement with current US and European Community rules. But debate continues over the intermediate phaseout schedule, with European members pushing for an 85% reduction - from a 1986 baseline - by Jan. 1, 1994, and others arguing for a 70% cut by 1994. Delegates are expected to agree to the final phaseout of halons on Jan. 1, 1996, with an 85% cut in carbon tet by 1995. The meeting is also expected to broadly agree on a Jan. 1, 1996 phaseout of methyl chloroform, with a 50% reduction from a 1989 baseline by Jan. 1, 1994. A critical debate for chemical producers will be on the fate of methyl bromide. Many observers expect some phaseout for the chemical, but when and how is undetermined

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)

Report, realized on behalf of the foreign Affairs, the Defense and the Armed Forces Commission: - on the law project, carried by the Senate, authorizing the approval of the amendment for the 16 september 1987 Montreal protocol relative to the substances which impoverish the ozone layer, adopted at Montreal the 17 september 1997; - and on the law project, carried by the Senate, authorizing the approval of the amendment for the 16 september 1987 Montreal protocol relative to the substances which impoverish the ozone layer, adopted at Pekin the 3 december 1999

Energy Technology Data Exchange (ETDEWEB)

Guillet, J.J.

2003-07-01

The document presents the text of the law projects concerning the substances which impoverish the ozone layer. Facts of science,protection systems and the two amendments adopted at Montreal in 1997 and Pekin in 1999 are discussed. For each countries data on the substances impoverish the ozone layer, are also given. (A.L.B.)

Use of alumni and employer surveys for internal quality assurance of the DVM program at the University of Montreal.

Science.gov (United States)

Doucet, Michèle Y; Vrins, André

2010-01-01

Annual alumni and employer surveys, initially designed as outcomes assessment tools, were integrated into a new internal quality assurance strategy to improve the doctor of veterinary medicine program at the University of Montreal's Faculté de Médecine Vétérinaire. Data collected annually from the classes of 2004-2007 indicated that alumni and their employers were generally satisfied with their level of preparation after one year of professional activity. Specific weaknesses were found in non-technical skills such as communication and resource management. These data were used in support of other forms of feedback to guide curricular reform.

Review of plants to mitigate particulate matter, ozone as well as nitrogen dioxide air pollutants and applicable recommendations for green roofs in Montreal, Quebec.

Science.gov (United States)

Gourdji, Shannon

2018-05-28

In urbanized regions with expansive impervious surfaces and often low vegetation cover, air pollution due to motor vehicles and other combustion sources, is a problem. The poor air quality days in Montreal, Quebec are mainly due to fine particulate matter and ozone. Businesses using wood ovens are a source of particulates. Careful vegetation selection and increased green roof usage can improve air quality. This paper reviews different green roofs and the capability of plants in particulate matter (PM), ozone (O 3 ) as well as nitrogen dioxide (NO 2 ) level reductions. Both the recommended green roof category and plants to reduce these pollutants in Montreal's zone 5 hardiness region are provided. Green roofs with larger vegetation including shrubs and trees, or intensive green roofs, remove air pollutants to a greater extent and are advisable to implement on existing, retrofitted or new buildings. PM is most effectively captured by pines. The small Pinus strobus 'Nana', Pinus mugho var. pumilio, Pinus mugho 'Slowmound' and Pinus pumila 'Dwarf Blue' are good candidates for intensive green roofs. Drought tolerant, deciduous broadleaved trees with low biogenic volatile organic compound emissions including Japanese Maple or Acer palmatum 'Shaina' and 'Mikawa-Yatsubusa' are options to reduce O 3 levels. Magnolias are tolerant to NO 2 and it is important in their metabolic pathways. The small cold-tolerant Magnolia 'Genie' is a good option to remove NO 2 in urban settings and to indirectly reduce O 3 formation. Given the emissions by Montreal businesses' wood ovens, calculations performed based on their respective complex roof areas obtained via Google Earth Pro indicates 88% Pinus mugho var. pumilio roof coverage can annually remove 92.37 kg of PM 10 of which 35.10 kg is PM 2.5 . The removal rates are 4.00 g/m 2 and 1.52 g/m 2 for PM 10 and PM 2.5 , respectively. This paper provides insight to addressing air pollution through urban rooftop greening. Copyright �

Seasonal Difference in Postthyroidectomy Hypocalcemia: A Montreal-Based Study.

Science.gov (United States)

Mascarella, Marco A; Forest, Véronique-Isabelle; Nhan, Carol; Leboeuf, Rébecca; Tamilia, Michael; Mlynarek, Alex M; Payne, Richard J

2016-02-01

Hypocalcemia following thyroidectomy often prolongs hospital stay and is potentially life-threatening. The objective of this study is to determine whether the season when thyroidectomy is performed is associated with postoperative hypocalcemia. Retrospective case series of patients undergoing thyroid surgery from 2009 to 2015. Tertiary care academic institution in Montreal, Canada. A consecutive sample of 823 patients undergoing thyroidectomy by a single high-volume otolaryngologist for a suspected or confirmed thyroid malignancy. Patient demographics, procedure type, calcium and vitamin D supplementation, and seasonal rate of hypocalcemia postthyroidectomy were calculated and compared. Average seasonal rates of postthyroidectomy hypocalcemia in the winter, spring, summer, and autumn were, respectively, 8.3% (8 of 216), 7.3% (12 of 165), 1.5% (3 of 201), and 3.5% (8 of 228; P operated in the winter were 5.6 times more likely to develop hypocalcemia as compared with those in the summer (P factoring in season when surgery was performed, procedure type, and preoperative vitamin D/calcium supplementation, surgery occurring in the winter predicted a hypocalcemia event (correlation coefficient [SE]: 0.72 [0.024], P = .026; 0.006 [0.025], P = .81; 0.004 [0.019], P = .82, respectively). In this study, patients undergoing thyroidectomy in the winter months were more likely to develop postoperative hypocalcemia when compared with those operated in the summer. Further studies are needed to understand the role of vitamin D in the observed seasonal difference in hypocalcemia rates. © American Academy of Otolaryngology—Head and Neck Surgery Foundation 2015.

Captive breeding of the barndoor skate (Dipturus laevis) at the Montreal Biodome, with comparison notes on two other captive-bred skate species.

Science.gov (United States)

Parent, Serge; Pépin, Serge; Genet, Jean-Pierre; Misserey, Laurent; Rojas, Salvador

2008-03-01

In 1997, the Montreal Biodome obtained five barndoor skates (Dipturus laevis) from the waters off Boston, Massachusetts. Six years later, those specimens began reproducing, and the first egg case was collected in November 2003. Since then, 73 hatchlings have been born and raised. Egg cases were observed year round, and annual fecundity was measured for the first time: one female laid 69 eggs in 2005, 85 in 2006 and 115 in 2007. Egg incubation was longer than believed previously, ranging from 342 to 494 days. Hatching occurred throughout the year. Hatchlings averaged 193 mm total length and 128 mm disk width and weighed 32 g. They were fed krill and diced fish. All but one survived the first month. A photo identification system was useful in recognizing two groups of 10 specimens during their first year, and transponders could be inserted in the wing muscles of 1-year-old skates. Total lengths at birth and at age 2 were similar to the data reported from the wild, suggesting a similar growth pattern in captivity. The reproduction characteristics of the barndoor skate were compared with those of two other skate species currently bred at the Montreal Biodome, the winter skate (Leucoraja ocellata) and the thorny skate (Amblyraja radiata). Zoo Biol 27:145-153, 2008. (c) 2008 Wiley-Liss, Inc.

Required internship in diagnostic radiology in the fifth year of medicine at Montreal University

International Nuclear Information System (INIS)

Saint-Georges, G.; Raymond-Tremblay, D.; Danais, S.; Dussault, R.; Grignon, A.; Lafortune, M.; Saltiel, J.

1984-01-01

Problems of methodology, organization, and evaluation confronting the radiology departments of the university hospitals affiliated with the University of Montreal, the medical students, and the University itself in connection with an elective internship in radiology offered in the fifth year of medicine, resulted in the formation of a committee to reorganize the course of study. In this concise article the authors describe this and other measures taken by the University to solve these problems. The committees' main purpose was to restructure the internship which was made compulsory so that future physicians would be prepared to draw on the resources of diagnostic radiology and nuclear medicine. To this end, the committee formulated the objectives, content, evaluation system, and pedagogical methods to be used in those courses. The 25 self-teaching modules, together with the observation and practical interpretation of radiology sessions, proved highly useful in solving the initial problems, and were of particular interest to the students. (author)

Selecting corporate political tactics: The Montreal Protocol on substances that deplete the ozone layer

International Nuclear Information System (INIS)

Getz, K.A.

1991-01-01

This study examines factors influencing the choice of one set of tactics over others. The case of ozone depletion is used as the research context, and the data are drawn from US companies having a stake in this issue. A model is developed which suggests that a firm's choice of political tactics (dependent variable) is dependent on the targets of political activity and the nature of the issue of concern (independent variables), and a variety of organizational and industry factors (moderating variables). The paradigm of agency is used to systematically assess the relative importance of these factors. To test the relevance of the model, an empirical study was done. The case of the Montreal protocol on Substances That Deplete the Ozone Layer was chosen as a setting; and 551 firms directly affected by policy intended to protect the ozone layer were surveyed. There were 151 usable responses. Generally, the findings were consistent with the model

Velódromo Olímpico de Montreal – Canadá

Directory of Open Access Journals (Sweden)

Taillibert, Roger

1976-12-01

Full Text Available This stadium is one of the most interesting ones that have been constructed lately. It has the following basic conditions: harmonious integration with the other Olympic installations; possibilities for future enlargements; total absence of supports; perfect permeability for the natural daylight; and perfect insulations in view of the hard climate of Montreal. Bearing these features in mind, the building consists of two parts: — The velodrome itself with lawn; 285.70 m long and 7.50 m wide courses with a slope varying between 18° and 48° with regard to the horizontal line; gallery for the public; auxiliary premises; dressing rooms, etc. — And the regular spheric roof the plan form of which represents three segments beginning with one buttress in the northeast end and increasing to three buttresses in the southeast end. This entirely self-supporting dome is 172 m long with a maximum height of 32 m. The total surface is 15,000 m2. The work was calculated by means of computers and was carried out with prefabricated pieces of concrete so as to achieve a better quality control of the concrete, and above all, a greater exactness of the prefabricated members. This was an indispensable factor in this case, where the maximum admissible error in most of the pieces was only 1.5 mm.Es uno de los estadios más interesantes de los últimos tiempos, con las siguientes condiciones básicas: armónica integración con las restantes instalaciones olímpicas; posibilidad de transformación para futuras aplicaciones; total ausencia de soportes; amplia permeabilidad a la luz natural; y perfecta estanquidad ante las duras condiciones climáticas de Montreal. Partiendo de estas premisas, el edificio consta de dos partes: — El velódromo propiamente dicho, con: césped; pista de carreras de 285,70 m de desarrollo, 7,50 m de anchura e inclinación variable entre 18° y 48° respecto a la horizontal; gradas para el público; locales auxiliares

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)

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

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)

Effects of diurnal variations in temperature on non-accidental mortality among the elderly population of Montreal, Québec, 1984-2007.

Science.gov (United States)

Vutcovici, Maria; Goldberg, Mark S; Valois, Marie-France

2014-07-01

The association between ambient temperature and mortality has been studied extensively. Recent data suggest an independent role of diurnal temperature variations in increasing daily mortality. Elderly adults-a growing subgroup of the population in developed countries-may be more susceptible to the effects of temperature variations. The aim of this study was to determine whether variations in diurnal temperature were associated with daily non-accidental mortality among residents of Montreal, Québec, who were 65 years of age and over during the period between 1984 and 2007. We used distributed lag non-linear Poisson models constrained over a 30-day lag period, adjusted for temporal trends, mean daily temperature, and mean daily concentrations of nitrogen dioxide and ozone to estimate changes in daily mortality with diurnal temperature. We found, over the 30 day lag period, a cumulative increase in daily mortality of 5.12% [95% confidence interval (CI): 0.02-10.49%] for a change from 5.9 °C to 11.1 °C (25th to 75th percentiles) in diurnal temperature, and a 11.27% (95%CI: 2.08-21.29%) increase in mortality associated with an increase of diurnal temperature from 11.1 to 17.5 °C (75th to 99th percentiles). The results were relatively robust to adjustment for daily mean temperature. We found that, in Montreal, diurnal variations in temperature are associated with a small increase in non-accidental mortality among the elderly population. More studies are needed in different geographical locations to confirm this effect.

Average number of compressors in operation per day in 25 skating rinks of the City of Montreal; Nombre moyens de compresseurs par jour en fonction dans 25 arenas de la Ville de Montreal

Energy Technology Data Exchange (ETDEWEB)

Dumas, C. [Ville de Montreal, PQ (Canada). Direction des Immeubles Gestion de l' Energie et du Genie Climatique

2002-09-30

Since the summer of 2001, 25 skating rinks from the territory of the old City of Montreal have been linked through a network to the remote management system. This initiative enables the people responsible for the skating rink to easily obtain statistics on the operation of refrigeration systems and to compile this information in the memory of a personal computer (PC). Each compressor system is equipped with a current transformer which acts as proof of monitored operation by the remote management system. Every minute, the compressors are asked in sequence to report on their status. The process by which the data is entered, filtered and analysed was explained and an example provided to better illustrate the concept. As a rule, management believes that it is possible to lower the power of existing refrigeration systems and to select new refrigeration systems according to the data acquired. Based on the results obtained so far, the power of some of the refrigeration systems has already been reduced by letting go one or two of the six refrigeration circuits of a skating rink. 2 tabs.

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.)

Screening of cognitive impairment in patients with Parkinson's disease: diagnostic validity of the Brazilian versions of the Montreal Cognitive Assessment and the Addenbrooke's Cognitive Examination-Revised

OpenAIRE

Emmanuelle Sobreira; Márcio A. Pena-Pereira; Alan L. Eckeli; Manoel A. Sobreira-Neto; Marcos H. N. Chagas; Maria P. Foss; Brenna Cholerton; Cyrus P. Zabetian; Ignacio F. Mata; Vitor Tumas

2015-01-01

ABSTRACTObjective The aim of the present study is to examine the accuracy of the Brazilian versions of the Montreal Cognitive Assessment (MoCA) and the Addenbrooke's Cognitive Examination-Revised (ACE-R) to screen for mild cognitive impairment (PDMCI) and dementia (PDD) in patients with Parkinson's disease (PD).Method Both scales were administered to a final convenience sample of 79 patients with PD. Patients were evaluated by a neurologist, a psychiatrist and a neuropsychologist using UPDRS,...

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.)

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

Emergy Evaluation of Dwelling Operation in Five Housing Units of Montreal Island, Canada

Directory of Open Access Journals (Sweden)

Ricardo Enrique Vega-Azamar

2017-04-01

Full Text Available Sustainability of cities and the environmental implications of high resource utilization by the domestic sector are growing concerns related to urban regions. Well-informed urban planning decision-making is an essential tool to help in the task and, for that, an important point to consider is the influence of parameters like residential density and housing typology on the intensity of resource utilization. Emergy synthesis, a life-cycle energy analysis methodological approach that considers the interaction of natural and human-made flows, was used to evaluate the environmental support for dwelling operational stage in five typical present-day housing units on the island of Montreal. As expected, resource utilization, measured as total emergy used, was positively correlated to housing unit size both with respect to number of occupants and dwelling size. Results suggest that variables affecting notably the intensity of resource utilization are per household income and per dweller habitable space and, while a higher income increased per capita emergy in all cases, increasing space availability per resident did not result in a decrease of empower density after 50 m2/person. Future work should consider lower and higher densities and analyses at the scale of blocks, neighborhoods and urban planning zones.

Increased Arctic Deposition of Persistent Compounds as a Result of the Montreal Protocol

Science.gov (United States)

Young, C.; Pickard, H. M.; De Silva, A. O.; Spencer, C.; Criscitiello, A. S.; Muir, D.; Sharp, M. J.

2017-12-01

Perfluorocarboxylic acids (PFCAs) are among the diverse groups of compounds characterized as persistent organic pollutants. They are toxic, resistant to environmental degradation, and adversely impact human and environmental health. PFCAs with four or fewer carbons, short-chain PFCAs (scPFCAs), are of particular interest because of their increasing levels in the environment, toxicity to plants, and potential for accumulation in some aquatic ecosystems, making them an emerging environmental concern. A minor source of scPFCAs to the Arctic has been shown to be atmospheric transformation of fluoropolymer precursors, followed by deposition. Additional potential sources of scPFCAs to the Arctic are chlorofluorocarbon (CFC)-replacement compounds. Through analysis of an ice core from the Canadian High Arctic, we show that Montreal Protocol-mandated introduction of CFC-replacement compounds for the heat-transfer industry has led to increasing inputs of these scPFCAs to the remote environment. Flux measurements for scPFCAs as a class of contaminants have only been reported in a couple studies to date. Here, we provide the first multi-decadal temporal record of scPFCA deposition, demonstrating a dramatic increase in deposition resulting from emission of CFC-replacements. These results bring to the forefront a need for a holistic approach to environmental risk assessment that considers impacts of replacement substances and degradation products.

SCREENING FOR POSTSTROKE COGNITIVE IMPAIRMENT VIA MINI MENTAL STATE EXAMINATION AND MONTREAL COGNITIVE ASSESSMENT SCALE

Directory of Open Access Journals (Sweden)

Mirena Valkova

2012-10-01

Full Text Available Objective: The aim of our study is to examine cognitive performance after mild stroke via Mini Mental State Examination (MMSE and Montreal cognitive assessment scale (MoCA and to compare the results.Material and methods: We examined 54 patients with mild stroke (aged 52 to 72 (mean 63.17, SD 5.96; 34 males and 20 females and 54 controls, adjusted by age, sex and education level. All subjects were tested via MMSE (Bulgarian version and MoCa (Bulgarian version. Data was collected in the single step model at the 90th day after stroke incident for patients and at the day of obtaining informed consent for controls. Results: Patients have poorer performance on both MMSE and MoCa than controls. MoCa has comparatively good discriminative validity and sensitivity.Conclusions: Although MMSE is one of the classical screening tools for cognitive impairment widely used in Bulgaria, other screening tools should not be ignored. On the basis of our results, MoCa is also a good screening instrument, especially for poststroke cognitive impairment.

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

The phase-in and phase-out of European emissions of HCFC-141b and HCFC-142b under the Montreal Protocol: Evidence from observations at Mace Head, Ireland and Jungfraujoch, Switzerland from 1994 to 2004

Science.gov (United States)

Derwent, R. G.; Simmonds, P. G.; Greally, B. R.; O'doherty, S.; McCulloch, A.; Manning, A.; Reimann, S.; Folini, D.; Vollmer, M. K.

The mixing ratios of HCFC-141b (1,1-dichlorofluoroethane) and HCFC-142b (1-chloro-1,1-difluoroethane) have been rising steadily in baseline air at Mace Head, Ireland over the 10-year period from 1994 to 2004. These HCFCs are widely used replacements for the chlorofluorocarbons phased out under the Montreal Protocol and its subsequent amendments. Analysis of the HCFC content of regionally-polluted air arriving at Mace Head from the European continent shows that European emissions reached a peak during 2000-2001 and have declined subsequently, following the phase-out in their usage. European emissions of HCFC-141b have been further constrained by observations at the High-Alpine Jungfraujoch site. The reductions are consistent with the phase-out of HCFC production and use from the year 2001 onwards mandated by European regulations designed to exceed the requirements of the Montreal Protocol.

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.)

[The Assistance maternelle de Montreal (1912-1961). An example of marginalization of philanthropic active women in the field of care for pregnants (French)].

Science.gov (United States)

Baillargeon, D

1999-01-01

This article examines the story of the Assistance maternelle de Montreal, an organization founded in 1912 by a group of bourgeois catholic women to provide material assistance and free medical services to poor pregnant mothers of the city. I want to show that even if the timid intervention of the Quebec state allowed the AM to survive during the almost 50 years, the rise of the experts in the health field--a phenomenon to which the AM has largely contributed--and in the philanthropic sector led to the marginalization of the female volunteers within the very institution they had created.

Accessibility to health care facilities in Montreal Island: an application of relative accessibility indicators from the perspective of senior and non-senior residents

Directory of Open Access Journals (Sweden)

Morency Catherine

2010-10-01

Full Text Available Abstract Background Geographical access to health care facilities is known to influence health services usage. As societies age, accessibility to health care becomes an increasingly acute public health concern. It is known that seniors tend to have lower mobility levels, and it is possible that this may negatively affect their ability to reach facilities and services. Therefore, it becomes important to examine the mobility situation of seniors vis-a-vis the spatial distribution of health care facilities, to identify areas where accessibility is low and interventions may be required. Methods Accessibility is implemented using a cumulative opportunities measure. Instead of assuming a fixed bandwidth (i.e. a distance threshold for measuring accessibility, in this paper the bandwidth is defined using model-based estimates of average trip length. Average trip length is an all-purpose indicator of individual mobility and geographical reach. Adoption of a spatial modelling approach allows us to tailor these estimates of travel behaviour to specific locations and person profiles. Replacing a fixed bandwidth with these estimates permits us to calculate customized location- and person-based accessibility measures that allow inter-personal as well as geographical comparisons. Data The case study is Montreal Island. Geo-coded travel behaviour data, specifically average trip length, and relevant traveller's attributes are obtained from the Montreal Household Travel Survey. These data are complemented with information from the Census. Health care facilities, also geo-coded, are extracted from a comprehensive business point database. Health care facilities are selected based on Standard Industrial Classification codes 8011-21 (Medical Doctors and Dentists. Results Model-based estimates of average trip length show that travel behaviour varies widely across space. With the exception of seniors in the downtown area, older residents of Montreal Island tend to be

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

La acción comunitaria en la inserción social en Montreal: un estudio de caso en la colectividad haitiana

Directory of Open Access Journals (Sweden)

Reina Victoria Vega

2016-10-01

Full Text Available This article examines contributions to the strengthening of social cohesion by community organizations for social integration in the city of Montreal, based on the Center N A Rive case. The aim is to identify the strategies used by these organizations in order to increase social cohesion on the basis of immigrant integration. The methodology used is the case study. The research made it possible to identify the social innovations the organization studied had achieved in the field of literacy among adult immigrants, as well as its contributions in terms of access to employment, civic empowerment of immigrants at risk of social exclusion, and development of social entrepreneurship among immigrants.

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.)

Processo de adaptação da bateria Montreal de avaliação da comunicação: bateria MAC - ao português brasileiro Adaptation process to Brazilian Portuguese of the Montreal communication evaluation battery: MAC battery

Directory of Open Access Journals (Sweden)

Rochele Paz Fonseca

2007-01-01

Full Text Available O presente estudo tem por objetivo apresentar a adaptação do "Protocole Montréal d'Évaluation de la Communication - Protocole MEC" (Bateria Montreal de Avaliação da Comunicação - Bateria MAC ao Português Brasileiro. Esta bateria canadense foi construída para avaliar quatro processamentos comunicativos de ativação do hemisfério direito: discursivo, pragmático-inferencial, léxico-semântico e prosódico. Participaram do estudo seis tradutores, três juízes especialistas, 54 juízes não-especialistas e 16 participantes dos estudos piloto. Os procedimentos gerais promovidos foram tradução, análise de critérios psicolingüísticos por juízes e aplicação do instrumento em estudos piloto. As tarefas Interpretação de metáforas, Discurso narrativo e Julgamento semântico exigiram um processo de adaptação mais complexo e rigoroso. Com base em critérios psicolingüísticos, realizaram-se algumas mudanças nos estímulos, com a finalidade principal de manutenção do objetivo de cada tarefa do instrumento original. Este instrumento neuropsicológico pode ser uma ferramenta de avaliação da comunicação de indivíduos com lesão de hemisfério direito, lesão frontal, traumatismo crânio-encefálico e demência.This research aims to present the adaptation of the "Protocole Montréal d'Évaluation de la Communication - Protocole MEC" (Montreal Communication Evaluation Battery - MAC Battery to Brazilian Portuguese, in accordance with psycholinguistics criteria. MAC Battery is a Canadian instrument constructed to evaluate right hemisphere communicative and linguistic abilities, considering four processing domains: discoursive, pragmatic-inferential, lexical-semantic and prosodic. The participants were six translators, three specialist judges, 54 non-specialist judges and 16 subjects from pilot studies. Adaptation procedures included translation, judge analysis of psycholinguistics criteria and two pilot tests. Some tasks required

Cross-Cultural Applicability of the Montreal Cognitive Assessment (MoCA): A Systematic Review.

Science.gov (United States)

O'Driscoll, Ciarán; Shaikh, Madiha

2017-01-01

The Montreal Cognitive Assessment (MoCA) is widely used to screen for mild cognitive impairment (MCI). While there are many available versions, the cross-cultural validity of the assessment has not been explored sufficiently. We aimed to interrogate the validity of the MoCA in a cross-cultural context: in differentiating MCI from normal controls (NC); and identifying cut-offs and adjustments for age and education where possible. This review sourced a wide range of studies including case-control studies. In addition, we report findings for differentiating dementias from NC and MCI from dementias, however, these were not considered to be an appropriate use of the MoCA. The subject of the review assumes heterogeneity and therefore meta-analyses was not conducted. Quality ratings, forest plots of validated studies (sensitivity and specificity) with covariates (suggested cut-offs, age, education and country), and summary receiver operating characteristic curve are presented. The results showed a wide range in suggested cutoffs for MCI cross-culturally, with variability in levels of sensitivity and specificity ranging from low to high. Poor methodological rigor appears to have affected reported accuracy and validity of the MoCA. The review highlights the necessity for cross-cultural considerations when using the MoCA, and recognizing it as a screen and not a diagnostic tool. Appropriate cutoffs and point adjustments for education are suggested.

Evaluating Recall and Recognition Memory Using the Montreal Cognitive Assessment: Applicability for Alzheimer's and Huntington's Diseases.

Science.gov (United States)

Van Liew, Charles; Santoro, Maya S; Goldstein, Jody; Gluhm, Shea; Gilbert, Paul E; Corey-Bloom, Jody

2016-12-01

We sought to investigate whether the Montreal Cognitive Assessment (MoCA) could provide a brief assessment of recall and recognition using Huntington disease (HD) and Alzheimer disease (AD) as disorders characterized by different memory deficits. This study included 80 participants with HD, 64 participants with AD, and 183 community-dwelling control participants. Random-effects hierarchical logistic regressions were performed to assess the relative performance of the normal control (NC), participants with HD, and participants with AD on verbal free recall, cued recall, and multiple-choice recognition on the MoCA. The NC participants performed significantly better than participants with AD at all the 3 levels of assessment. No difference existed between participants with HD and NC for cued recall, but NC participants performed significantly better than participants with HD on free recall and recognition. The participants with HD performed significantly better than participants with AD at all the 3 levels of assessment. The MoCA appears to be a valuable, brief cognitive assessment capable of identifying specific memory deficits consistent with known differences in memory profiles. © The Author(s) 2016.

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

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.)

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

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.)

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.)

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

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)

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

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)

Is gentrification all bad? Positive association between gentrification and individual's perceived neighborhood collective efficacy in Montreal, Canada.

Science.gov (United States)

Steinmetz-Wood, Madeleine; Wasfi, Rania; Parker, George; Bornstein, Lisa; Caron, Jean; Kestens, Yan

2017-07-14

Collective efficacy has been associated with many health benefits at the neighborhood level. Therefore, understanding why some communities have greater collective efficacy than others is important from a public health perspective. This study examined the relationship between gentrification and collective efficacy, in Montreal Canada. A gentrification index was created using tract level median household income, proportion of the population with a bachelor's degree, average rent, proportion of the population with low income, and proportion of the population aged 30-44. Multilevel linear regression analyses were conducted to measure the association between gentrification and individual level collective efficacy. Gentrification was positively associated with collective efficacy. Gentrifiers (individuals moving into gentrifying neighborhoods) had higher collective efficacy than individuals that lived in a neighborhood that did not gentrify. Perceptions of collective efficacy of the original residents of gentrifying neighborhoods were not significantly different from the perceptions of neighborhood collective efficacy of gentrifiers. Our results indicate that gentrification was positively associated with perceived collective efficacy. This implies that gentrification could have beneficial health effects for individuals living in gentrifying neighborhoods.

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

CANDU lectures

International Nuclear Information System (INIS)

Rouben, B.

1984-06-01

This document is a compilation of notes prepared for two lectures given by the author in the winter of 1983 at the Institut de Genie Nucleaire, Ecole Polytechnique, Montreal. The first lecture gives a physical description of the CANDU reactor core: the nuclear lattice, the reactivity mechanisms, their functions and properties. This lecture also covers various aspects of reactor core physics and describes different calculational methods available. The second lecture studies the numerous facets of fuel management in CANDU reactors. The important variables in fuel management, and the rules guiding the refuelling strategy, are presented and illustrated by means of results obtained for the CANDU 600

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.)

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

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.)

Report on the behalf of the Foreign Affairs Commission on the bill project authorizing the approval of the amendment to the Montreal protocol of 16 September 1987 related to substances which impoverish the ozone layer, and its Annexe: text of the foreign affairs Commission. Nr 415

International Nuclear Information System (INIS)

Di Pompeo, Christophe

2017-01-01

The objective of the Montreal protocol, adopted in 1987, was to banish the chlorofluorocarbons (CFC) used as refrigerants since the 1930's, as they are responsible for the impoverishment of the ozone layer. While this objective has been met (the ozone layer is progressively restored), substitutes to CFC have been developed; however some of these substitutes, hydro-fluorocarbons, have been proved to be powerful greenhouse gases. The banishment of HFCs has thus been decided, leading to the Kigali amendment to the Montreal protocol. This report explains the CFC and HFC context and issues in details, and presents its examination by the French Commission of Foreign Affairs. The full text of the report is included (in an annex) at the end of the report

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.)

Perceptions, Preferences, and Behavior Regarding Energy and Environmental Costs: The Case of Montreal Transport Users

Directory of Open Access Journals (Sweden)

Nayer Daher

2018-02-01

Full Text Available Providing travel-related fuel and environmental information to transport users is becoming increasingly relevant. However, the impact of providing such information on users’ travel behavior is yet to be determined. This research examined the perceptions and preferences related to the fuel consumption costs, greenhouse gas (GHG social costs, and health-related air pollution costs, and the influence such information could have on travel behavior. Examining the case of Montreal transport users, the authors conducted a survey in which the respondents were asked general and stated preference questions. The respondents were found to be unaware of the energy and environmental footprints of their travel. Approximately 85% of the respondents were not able to estimate GHG social costs and health-related air pollution costs across different modes. The respondents generally overestimated these costs and they interestingly reported higher environmental costs for public transport (metro compared to cars. They also preferred to receive such information in monetary units, and they were more comfortable in receiving the information through mobile applications over other tools/means. The research also found that fuel and environmental information influence respondents’ travel decisions especially their route choices. Finally, the respondents would be willing to pay an average of 7 Canadian dollars/month in exchange for obtaining the information.

Montreal Cognitive Assessment and Mini-Mental State Examination reliable change indices in healthy older adults.

Science.gov (United States)

Kopecek, Miloslav; Bezdicek, Ondrej; Sulc, Zdenek; Lukavsky, Jiri; Stepankova, Hana

2017-08-01

Cognitive tests are used repeatedly to assess the treatment response or progression of cognitive disorders. The Montreal Cognitive Assessment (MoCA) is a valid screening test for mild cognitive impairment. The aim of our study was to establish 90% reliable change indices (RCI) for the MoCA together with the Mini-Mental State Examination (MMSE) in cognitively healthy older adults. We analyzed 197 cognitively healthy and functional independent volunteers aged 60-94 years, who met strict inclusion criteria for four consecutive years. The RCI methods by Chelune and Hsu were used. For 1, 2, and 3 years, the 90% RCI for MoCA using Chelune's formula were -4 ≤, ≥4; -4 ≤, ≥4 and -5 ≤, ≥4 points, respectively, and -3 ≤, ≥3 for the MMSE each year. Ninety percent RCI for MoCA using Hsu's formula ranged from -6 to 0, respectively, and +3 to +8 dependent on the baseline MoCA. Our study demonstrated RCI for the MoCA and MMSE in a 3-year time period that can be used for the estimation of cognitive decline or improvement in clinical settings. Copyright © 2016 John Wiley & Sons, Ltd. Copyright © 2016 John Wiley & Sons, Ltd.

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

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.

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

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.)

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.

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

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

Setting the census household into its urban context: Visualizations from 19th-century Montreal

Directory of Open Access Journals (Sweden)

Sherry Olson

2017-04-01

Full Text Available Background: Organized by household, North American census data promoted research into household composition, but discouraged research into connections between urban households. Yet these constitute "communications communities" that powerfully influence demographic decisions (Szreter 1996. Objective: How can we uncover relations between urban households? From spatial cues, can we infer social connections that generate constraints on or incentives for the formation of a household, its break-up, reconstitution, or relocation? Methods: For Montreal and its suburbs, 1881‒1901, we employ double geocoding and lot-level precision to explore a dozen types of relationships. Samples for experiment are drawn from a local historical geographic information system (HGIS that integrates tax roll and directory with census data. Results: 'Family' was socially embedded at three levels. Neighbouring of kin was strategic, and kinship was a factor in employment, enterprise, and property development as well as residential choices. In managing property, family networks operated with a horizon of four generations. Conclusions: Introduction of geographic coordinates offers a critical set of neglected cues to relationships between households, such as business partnerships, credit, or use of transit or telephone. In an urban HGIS, advantageous features are lot-level precision and facilities for coding and matching addresses to accommodate alternative levels of spatial aggregation. Contribution: Geocoding is shown to be a breakthrough innovation for exploring urban connectivity. Experiments with maps and networks as tools of visual thinking invite us to rethink the 'census family' at higher levels of relatedness.

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.

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.

Agreement and conversion formula between mini-mental state examination and montreal cognitive assessment in an outpatient sample.

Science.gov (United States)

Helmi, Luqman; Meagher, David; O'Mahony, Edmond; O'Neill, Donagh; Mulligan, Owen; Murthy, Sutha; McCarthy, Geraldine; Adamis, Dimitrios

2016-09-22

To explore the agreement between the mini-mental state examination (MMSE) and montreal cognitive assessment (MoCA) within community dwelling older patients attending an old age psychiatry service and to derive and test a conversion formula between the two scales. Prospective study of consecutive patients attending outpatient services. Both tests were administered by the same researcher on the same day in random order. The total sample (n = 135) was randomly divided into two groups. One to derive a conversion rule (n = 70), and a second (n = 65) in which this rule was tested. The agreement (Pearson's r) of MMSE and MoCA was 0.86 (P < 0.001), and Lin's concordance correlation coefficient (CCC) was 0.57 (95%CI: 0.45-0.66). In the second sample MoCA scores were converted to MMSE scores according to a conversion rule from the first sample which achieved agreement with the original MMSE scores of 0.89 (Pearson's r, P < 0.001) and CCC of 0.88 (95%CI: 0.82-0.92). Although the two scales overlap considerably, the agreement is modest. The conversion rule derived herein demonstrated promising accuracy and warrants further testing in other populations.

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

Petro-Canada's project to add petroleum product storage tanks to the Municipality of Montreal-East

International Nuclear Information System (INIS)

Lefebvre, G.; Joly, R.; Guay, T.

2006-01-01

This paper explored the environmental impacts associated with Petro-Canada's project to add petroleum product storage tanks to its refinery in the east-end of Montreal. The project plan is based on a 6 year horizon from 2006-2012. The additional reservoirs would store new products destined for the petrochemical industry and for consumers, thus improving the flexibility and reliability of the refinery. The products would include low sulfur diesel and ethanol gasoline. The project does not involve any increase in refining capacity, and is estimated to cost $15 million. The main issues associated with this project are ambient air quality, the protection of groundwater and soil, as well as the security of areas inhabited by neighbouring areas in risk of a major accident. Emissions of organic compounds, including benzene, are considered minimal considering the use of sealed floating roofs. Geomembranes will be installed under the storage tanks to ensure the protection of groundwater and soil. Any consequences to the population of neighbouring areas resulting from accidents inside the industrial park will be limited since the reservoirs will be located more than 1 km away from a populated area. Quebec's Ministry of Sustainable Development, Environment and Parks recommended that this project be approved as long as the terms and measures of environmental regulations are respected, and that an emergency plan is submitted before the operation of the first reservoir. 1 tab

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%

Sustainability Assessment of the Residential Land Use in Seven Boroughs of the Island of Montreal, Canada

Directory of Open Access Journals (Sweden)

Ricardo Enrique Vega-Azamar

2015-02-01

Full Text Available High resource utilization in the residential sector, and the associated environmental impacts, are central issues in the growth of urban regions. Land-use urban planning is a primary instrument for the proper development of cities; an important point is the consideration of the urban form’s influence on resource utilization intensity. Emergy synthesis, an energy-based methodological approach that allows the quantification and integration of both natural and human-generated flows interacting in urban environments, was used to assess sustainability of the residential land use of seven boroughs on the Island of Montreal. Natural resources, food, water, acquired goods and services, electricity and fuels were the main flows considered in the analysis. Results suggest that income, household size and distance to downtown are the variables affecting resource utilization intensity more noticeably and that allocation of green area coverage is an important parameter for controlling land use intensity. With the procedure used for calculating resource use intensity in the seven boroughs, it is possible to generate a tool to support urban planning decision-making for assessing sustainable development scenarios. Future research should consider urban green space potential for accommodating local waste treatment systems, acting as a greenhouse gas emissions sink and promoting human health.

Broken English, broken bones? Mechanisms linking language proficiency and occupational health in a Montreal garment factory.

Science.gov (United States)

Premji, Stéphanie; Messing, Karen; Lippel, Katherine

2008-01-01

Language barriers are often cited as a factor contributing to ethnic inequalities in occupational health; however, little information is available about the mechanisms at play. The authors describe the multiple ways in which language influences occupational health in a large garment factory employing many immigrants in Montreal. Between 2004 and 2006, individual, semi-structured interviews were conducted with 15 women and 10 men from 14 countries of birth. Interviews were conducted in French and English, Canada's official languages, as well as in non-official languages with the help of colleague-interpreters. Observation within the workplace was also carried out at various times during the project. The authors describe how proficiency in the official languages influences occupational health by affecting workers' ability to understand and communicate information, and supporting relationships that can affect work-related health. They also describe workers' strategies to address communication barriers and discuss the implications of these strategies from an occupational health standpoint. Along with the longer-term objectives of integrating immigrants into the linguistic majority and addressing structural conditions that can affect health, policies and practices need to be put in place to protect the health and well-being of those who face language barriers in the short term.

Associations between grass and weed pollen and emergency department visits for asthma among children in Montreal.

Science.gov (United States)

Héguy, Léa; Garneau, Michelle; Goldberg, Mark S; Raphoz, Marie; Guay, Frédéric; Valois, Marie-France

2008-02-01

Asthma among children is a major public health problem worldwide. There are increasing number of studies suggesting a possible association between allergenic pollen and exacerbations of asthma. In the context of global climate change, a number of future climate and air pollution scenarios predict increases in concentrations of pollen, an extension of the pollen season, and an increase in the allergenicity of pollen. The goal of the present study is to evaluate the short-term effects of exposure to grass and weed pollen on emergency department visits and readmissions for asthma among children aged 0-9 years living in Montreal between April and October, 1994-2004. Time-series analyses were carried out using parametric log-linear overdispersed Poisson models that were adjusted for temporal variations, daily weather conditions (temperature, atmospheric pressure), and gaseous air pollutants (ozone and nitrogen dioxide). We have found positive associations between emergency department visits and concentrations of grass pollen 3 days after exposure. The effect of grass pollen was higher on emergency department readmissions as compared to initial visits. Weak negative associations were found between weed pollen (including ragweed pollen) and emergency department visits 2 days after exposure. The data indicate that among children, emergency department visits increased with increasing concentrations of grass pollen.

A Decontamination Process to Remove Metals and Stabilise Montreal Sewage Sludge

Directory of Open Access Journals (Sweden)

G. Mercier

2002-01-01

Full Text Available The Montreal Urban Community (MUC treatment plant produces approximately 270 tons of dry sludge daily (tds/day during physicochemical wastewater treatment. The sludges are burned and contribute to the greenhouse effect by producing atmospheric CO2. Moreover, the sludge emanates a nauseating odour during its thermal stabilisation and retains unpleasant odours for the part (25% that is dried and granulated. To solve this particular problem, the treatment plant authorities are currently evaluating an acidic chemical leaching (sulfuric or hydrochloric acid process at a pH between 2 and 3, using an oxidizing agent such as ferric chloride or hydrogen peroxide (METIX-AC technology, patent pending; [20]. They could integrate it to a 70 tds/day granulated sludge production process. Verification of the application of METIX-AC technology was carried out in a pilot plant set up near the sludge production plant of the MUC. The tests showed that METIX-AC technology can be advantageously integrated to the process used at the MUC. The residual copper (274 ± 58 mg/kg and cadmium (5.6 ± 2.9 mg/kg concentrations in the treated sludge meet legislation standards. The results have also shown that odours have been significantly eliminated for the dewatered, decontaminated, and stabilized biosolids (> 97% compared to the non-decontaminated biosolids. A high rate of odour elimination also was obtained for the liquid leached biosolids (> 93%, compared to the untreated liquid biosolids. The fertilising value (N and P is well preserved by the METIX-AC process. Dissolved organic carbon measurements have showed that little organic matter is brought in solution during the treatment. In fact, the average concentration of dissolved organic carbon measured in the treated liquid phase is 966 ± 352 mg/l, whereas it is 1190 ± 325 mg/l in untreated sludge. The treated sludge was first conditioned with an organic polymer and a coagulant aid. It was successfully dewatered with

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.)

Nuclear industry prospects: A Canadian perspective

International Nuclear Information System (INIS)

Morden, Reid

1995-01-01

Canada, with its proven, safe and versatile CANDU reactor is well poised for the second half-century of nuclear fission. Canada's nuclear pedigree goes back to the turn-of-the-century work of Ernest Rutherford in Montreal. This year, Canada's nuclear industry celebrates the 50th anniversary of the start-up of its first research reactor at Chalk River. Last year, the pioneering work of Bert ram Blockhouse in Physics was honoured with a Nobel Prize. Future international success for the nuclear industry, such as has been achieved here in Korea, depends on continued cooperative and collaborative team work between the public and private sectors, continued strong research and development backing by the government, and new strategic partnerships. The biggest challenge is financing for the emerging markets. The brightness or dimness of future prospects are relative to the intensity of the lessons learned from history. In Canada we have a fairly long nuclear pedigree, It goes back almost a century to 1898, when Ernest Rutherford set up a world centre at McGill University in Montreal for research into the structure of the atom and into radioactivity

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.)

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.)

Early years of nuclear energy research in Canada

International Nuclear Information System (INIS)

Laurence, G.C.

1980-01-01

The first experimental attempts in Canada to obtain energy from uranium fission were carried out by the author in the Ottawa laboratories of the National Research Council from 1940 to 42. This program grew into a joint British-Canadian laboratory in Montreal. Work done at this laboratory, which moved to Chalk River in 1946, led to the construction of ZEEP (the first nuclear reactor to operate outside of the United States) NRX, and ultimately to the development of the CANDU power reactors. People involved in the work and events along the way are covered in detail. (LL)

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

Bilinguisme et problematique des langues ethniques. Enquete sur le comportement linguistique des jeunes montrealais d'origine italienne (Bilingualism and the Problem of Ethnic Languages. A Study of the Linguistic Behavior of Young Montrealers of Italian Descent). Publication B-149.

Science.gov (United States)

Villata, Bruno

A study is reported of the language behavior of trilingual 9-to-12-year-old native Italian speakers in Montreal, some of whom were studying Italian on Saturdays and some of whom were not. The study focused on their available vocabulary in the three languages (Italian, French, and English) and on their language productivity during their various…

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

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.)

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)

Revitalización urbana y calidad de vida en el sector central de las ciudades de Montreal y México

Directory of Open Access Journals (Sweden)

Carlos Alberto Tello Campos

2017-07-01

Full Text Available El abandono y consiguiente despoblamiento del sector central asociado a una desenfrenada expansión y poblamiento de los sectores periféricos de muchas de las grandes ciudades norteamericanas como Montreal y México, es un problema de actualidad muy difícil de resolver. Encontrar las causas que provocan dicho proceso se convierte en una necesidad crítica para mejorar el diseño de políticas urbanas que promuevan la re-utilización del espacio central, desalentando la utilización de los periféricos. En función de diversos programas urbanos tanto Canadienses como Mexicanos implementados al momento en el sector central de las dos ciudades mencionadas, ésta tesis se apoya en dos estudios de campo y los correspondientes análisis estadísticos de correlación y de regresión entre otros, para explicar el estado que el continuo revitalización urbana-calidad de vida-calidad del lugar guarda en el sector central de los casos de estudio desde la propia perspectiva de sus residentes. Los resultados informan que en revitalización urbana, los residentes Canadienses favorecen más a los atributos de calidad del lugar mientras que sus homólogos Mexicanos favorecen más a los de calidad de vida. ABSTRACT:  The neglect and further depopulation in many of the large North American cities’ inner-cores such as Montreal and Mexico coupled with sprawl and repopulation in their peripheral areas is very much a today’s problem difficult to solve. Finding out the causes that incite that process becomes a critical need to improve the design of urban policies that promote the re-utilization of the central space, to discourage the equivalent in the peripherals one. Taking into account several urban Canadian and Mexican programs already implemented on those cities’ inner cores, this thesis makes use of two field surveys and the corresponding correlation and regression statistical analyses among others, to explain the current urban revitalization > quality

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

Awareness of cytomegalovirus and risk factors for susceptibility among pregnant women, in Montreal, Canada.

Science.gov (United States)

Wizman, Sarah; Lamarre, Valérie; Coic, Lena; Kakkar, Fatima; Le Meur, Jean-Baptiste; Rousseau, Céline; Boucher, Marc; Tapiero, Bruce

2016-03-15

Advances in diagnostic and therapeutic modalities for congenital cytomegalovirus (CMV) infection have generated a mounting interest in identifying mothers susceptible to CMV. The objectives of this study were to evaluate the prevalence and socio-demographic determinants of CMV susceptibility and CMV awareness, among pregnant women, in Montreal, Quebec. Between April and December 2012, women delivering at Centre Hospitalier Universitaire Sainte Justine were recruited for the study. Stored serum from the first trimester of pregnancy was tested for CMV IgG. Knowledge about CMV and socio-demographic characteristics were collected via standardized questionnaire. Four hundred and ninety one women were enrolled in the study. Overall, 225 mothers (46%) were seronegative for CMV, and 85% (n = 415) were unaware of CMV or the associated risks in pregnancy. Significant risk factors for CMV seronegative status included Canadian vs. foreign born (aOR 6.88, 95% CI 4.33-10.94), and high vs. low family income (aOR 4.68, 95% CI 2.09-10.48). Maternal employment status was the only significant predictor of CMV unawareness, with unemployed mothers at the highest risk (aOR 85.6, 95% CI 17.3-421.3). Nearly half of pregnant women studied were at risk of primary infection, and yet, the majority was unaware of potential risks associated with CMV. Canadian born mothers and those with a high socioeconomic status were more likely to be CMV seronegative. Increased education about CMV infection, through public health interventions and obstetrician/pediatric counseling, is needed for all pregnant women.

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

From Osler's Library to the Osler Library of the History of Medicine, McGill University, Montreal: an overview.

Science.gov (United States)

Lyons, Christopher

2007-01-01

The Osler Library of the History of Medicine was opened in 1929 at McGill University, Montreal, Canada. Sir William Osler (1849-1919), arguably McGill's and Canada's most famous doctor at the time, had bequeathed his magnificent library of almost 8,000 historical works in medicine and, to a lesser extent, science and literature to the university. Under the 30-year reign of its first librarian, Dr. W W. Francis, the Osler Library became famous for its rare books and for its connection with Sir William. Since the 1950s, however, the library has pursued an active collection development policy for both primary and secondary material that has taken it far beyond Osler's original gift. The library has grown in both the size and scope of its holdings and the services it offers to scholars and students of the history of medicine. These have made the Osler Library a major resource centre for studies in the history of the health sciences. This article looks at the Osler Library today in the hopes of making the range of its collections and services better known to the Canadian and international communities.

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

Analyse des attitudes envers les sciences chez des eleves du secondaire d'origine haitienne de milieux defavorises de la region de Montreal

Science.gov (United States)

Fils-Aime, Nestor

Having in perspective the slight representativeness of students, from Haitian background, from the most unprivileged sections of the great region of Montreal in the scientific fields in High School and in the choices of career, this study intends to examine the effect of the individual characteristics as well as the associated factors related to the familial, scholastic, socio-economic, and cultural environment upon the attitudes of those students toward sciences. The analysis of the datum is based on the results of a questionnaire focusing on the socio-demographic profile of a group of students from fourth and fifth year attending two multiethnic High Schools of the North-Crown of Montreal as well as on the interviews with fifteen of those students who are from a haitian background. There were also interviews with some parents, a member of a community organism, some staff members of some schools as well as some Haitian-Quebecer professionals and scientists, in order to have a critical viewpoint upon the different positions expressed by the fifteen students. The Bronfenbrenner's ecosystemic model (1979, 1986) has been used as scope of reference allowing to draw the prominent aspects from the attitudes toward science in the students, from haitian background. The synthesis of ideas expressed by different interviewee reveals the existence of a environment not much enhancing the value of sciences around of students, from Haitian background. The socio-economic conditions, the familial practices, the ethnocultural status as well as some individual representations of sciences contribute to create and maintain some attitudes very little committed to sciences in those students. The study shows how much it is urgent to demystify the sciences by breaking with some stereotypes that prevent some categories of students from acceding to sciences. It also commands to politicians, concerning education, to be more open to ethnocultural differences and to explore some dynamic ways in

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)

Montreal Cognitive Assessment and Mini-Mental State Examination are both valid cognitive tools in stroke.

Science.gov (United States)

Cumming, T B; Churilov, L; Linden, T; Bernhardt, J

2013-08-01

To determine the validity of the Montreal Cognitive Assessment (MoCA) and the Mini-Mental State Examination (MMSE) as screening tools for cognitive impairment after stroke. Cognitive assessments were administered over 2 sessions (1 week apart) at 3 months post-stroke. Scores on the MoCA and MMSE were evaluated against a diagnosis of cognitive impairment derived from a comprehensive neuropsychological battery (the criterion standard). Sixty patients participated in the study [mean age 72.1 years (SD = 13.9), mean education 10.5 years (SD = 3.9), median acute NIHSS score 5 (IQR 3-7)]. The MoCA yielded lower scores (median = 21, IQR = 17-24; mean = 20.0, SD = 5.4) than the MMSE (median = 26, IQR = 22-27; mean = 24.2, SD = 4.5). MMSE data were more skewed towards ceiling than MoCA data (skewness = -1.09 vs -0.73). Area under the receiver operator curve was higher for MoCA than for MMSE (0.87 vs 0.84), although this difference was not significant (χ(2) = 0.48, P = 0.49). At their optimal cut-offs, the MoCA had better sensitivity than the MMSE (0.92 vs 0.82) but poorer specificity (0.67 vs 0.76). The MoCA is a valid screening tool for post-stroke cognitive impairment; it is more sensitive but less specific than the MMSE. Contrary to the prevailing view, the MMSE also exhibited acceptable validity in this setting. © 2013 John Wiley & Sons A/S.

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)

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)

Sociology in Global Environmental Governance? Neoliberalism, Protectionism and the Methyl Bromide Controversy in the Montreal Protocol

Directory of Open Access Journals (Sweden)

Brian J. Gareau

2017-10-01

Full Text Available Sociological studies of global agriculture need to pay close attention to the protectionist aspects of neoliberalism at the global scale of environmental governance. With agri-food studies in the social sciences broadening interrogations of the impact of neoliberalism on agri-food systems and their alternatives, investigating global environmental governance (GEG will help reveal its impacts on the global environment, global science/knowledge, and the potential emergence of ecologically sensible alternatives. It is argued here that as agri-food studies of neoliberalism sharpen the focus on these dimensions the widespread consequences of protectionism of US agri-industry in GEG will become better understood, and the solutions more readily identifiable. This paper illustrates how the delayed phase out of the toxic substance methyl bromide in the Montreal Protocol exemplifies the degree to which the US agri-industry may be protected at the global scale of environmental governance, thus prolonging the transition to ozone-friendly alternatives. Additionally, it is clear that protectionism has had a significant impact on the dissemination and interpretation of science/knowledge of methyl bromide and its alternatives. Revealing the role that protectionism plays more broadly in the agriculture/environmental governance interface, and its oftentimes negative impacts on science and potential alternatives, can shed light on how protectionism can be made to serve ends that are at odds with environmental protection.

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.

735 kV air-blast circuit breakers for Hydro Quebec

Energy Technology Data Exchange (ETDEWEB)

Lindstrom, I

1966-01-01

In 1962 the Quebec Hydro-Electric Commission started the development of aproject for utilizing water power in Manicouagan and Outardes, two rivers some 350 miles northeast of the city of Montreal on the left bank of the St. Lawrence estuary. The project involved the transmission of power at 735 kV ac from Manicouagan and Outardes to the heavy and growing load centers of Quebec and Montreal. The total amount of energy to be transmitted in the final stage is about 6,000 MW. The project involved the need of considerable quantities of apparatus for 735 kV, such as transformers, reactors, lightning arrestors, circuit-breakers, and disconnectors. Since the supply of the major part of the 735 kV circuit-breakers, altogether 14 three-pole units, was awarded to ASEA in Sweden, a short presentation of these airblast circuit-breakers is presented.

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)

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)

Bridging cognitive screening tests in neurologic disorders: A crosswalk between the short Montreal Cognitive Assessment and Mini-Mental State Examination.

Science.gov (United States)

Roalf, David R; Moore, Tyler M; Mechanic-Hamilton, Dawn; Wolk, David A; Arnold, Steven E; Weintraub, Daniel A; Moberg, Paul J

2017-08-01

To provide a crosswalk between the recently proposed short Montreal Cognitive Assessment (s-MoCA) and Mini-Mental State Examination (MMSE) within a clinical cohort. A total of 791 participants, with and without neurologic conditions, received both the MMSE and the MoCA at the same visit. s-MoCA scores were calculated and equipercentile equating was used to create a crosswalk between the s-MoCA and MMSE. As expected, s-MoCA scores were highly correlated (Pearson r = 0.82, P < .001) with MMSE scores. s-MoCA scores correctly classified 85% of healthy older adults and 91% of individuals with neurologic conditions that impair cognition. In addition, we provide an easy to use table that enables the conversion of s-MoCA score to MMSE score. The s-MoCA is quick to administer, provides high sensitivity and specificity for cognitive impairment, and now can be compared directly with the MMSE. Copyright © 2017 the Alzheimer's Association. Published by Elsevier Inc. All rights reserved.

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

Mundialización, acción colectiva e iniciativa local en la reconversión de Montreal

Directory of Open Access Journals (Sweden)

Juan-Luis Klein

2003-05-01

Full Text Available Este texto presenta un análisis del rol que juegan las iniciativas locales de base comunitaria en los procesos de desarrollo local, en el marco de la reconversión de las economías metropolitanas impulsada por la mundialización. La reconversión lleva a las metrópolis a especializarse en sectores económicos de alto tenor científico-técnico. Esto pone en peligro la viabilidad de los sectores más tradicionales, y sobre todo, fragiliza a la dotación de los espacios intrametropolitanos (municipios, distritos, barrios en los cuales estos sectores se habían especializado, en tanto que medios de vida y de trabajo. A partir del caso de Montreal, se verá que en estos espacios tienen lugar experiencias alternativas cuyo objetivo es el de conectar a las colectividades excluidas de la reconversión que se experimenta en los sectores de alta tecnología, la cual es impulsada por las fuerzas del mercado. Esto auspicia una vía de reconversión más incluyente desde el punto de vista social, en la cual la innovación tecnológica se combina con la innovación social. Pero también muestra que esta asociatividad es el resultado de un proceso en el cual las iniciativas locales, a través de acciones colectivas, estructuran el territorio, delimitan espacios de identidad y construyen las bases de un modelo de desarrollo en el cual lo económico se inserta en lo social, y en el cual el medio territorial se construye progresivamente.This text presents an analysis of the role played by communitarian based local initiatives in the process of local development, within the frame of the metropolitan economic reconversion driven by globalization. Reconversion makes metropolis specialize in high economic sectors, both technically and scientifically developed. This fact puts in danger the viability of the more traditional sectors and overall, fragilizes the endowment of intrametropolitan spaces (municipalities, districts, neighbourhoods in wich those sectores had

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

Socio-economic status and time trends associated with early ART initiation following primary HIV infection in Montreal, Canada: 1996 to 2015.

Science.gov (United States)

Mehraj, Vikram; Cox, Joseph; Lebouché, Bertrand; Costiniuk, Cecilia; Cao, Wei; Li, Taisheng; Ponte, Rosalie; Thomas, Réjean; Szabo, Jason; Baril, Jean-Guy; Trottier, Benoit; Côté, Pierre; LeBlanc, Roger; Bruneau, Julie; Tremblay, Cécile; Routy, Jean-Pierre

2018-02-01

Guidelines regarding antiretroviral therapy (ART) initiation in HIV infection have varied over time, with the 2015 World Health Organization recommendation suggesting ART initiation at the time of diagnosis regardless of CD4 T-cell counts. Herein, we investigated the influence of socio-demographic and clinical factors in addition to time trends on early ART initiation among participants of the Montreal Primary HIV Infection Study. The Montreal Primary HIV Infection Study is a prospective cohort established in three community medical centres (CMCs) and two university medical centres (UMCs). Recently diagnosed HIV-infected adults were categorized as receiving early (vs. delayed) ART if ART was initiated within 180 days of the baseline visit. Associations between early ART initiation and socio-demographic, socio-economic and behavioural information were examined. Independent associations of factors linked with early ART initiation were determined using multivariable binary logistic regression analysis. A total of 348 participants had a documented date of HIV acquisition of age of participants was 35 (28; 42) years and the majority were male (96%), having paid employment (63%), men who have sex with men (MSM) (78%) and one to four sexual partners in the last three months (70%). Participants presented with a median IQR HIV plasma viral load of 4.6 (3.7; 5.3) log 10 copies/ml, CD4 count of 510 (387; 660) cells/μl and were recruited in CMCs (52%) or UMCs (48%). Early ART initiation was observed in 47% of the participants and the trend followed a V-shaped curve with peaks in 1996 to 1997 (89%) and 2013 to 2015 (88%) with a dip in 2007 to 2009 (22%). Multivariable analyses showed that having a paid employment adjusted odds ratio (aOR: 2.43; 95% CI: 1.19, 4.95), lower CD4 count (aOR per 50 cell increase: 0.93; 95% CI: 0.87, 0.99) and care at UMCs (aOR: 2.03; 95% CI: 1.06 to 3.90) were independently associated with early ART initiation. Early ART initiation during primary

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)

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)

Revising the diagnosis of congenital amusia with the Montreal Battery of Evaluation of Amusia.

Science.gov (United States)

Pfeifer, Jasmin; Hamann, Silke

2015-01-01

This article presents a critical survey of the prevalent usage of the Montreal Battery of Evaluation of Amusia (MBEA; Peretz et al., 2003) to assess congenital amusia, a neuro-developmental disorder that has been claimed to be present in 4% of the population (Kalmus and Fry, 1980). It reviews and discusses the current usage of the MBEA in relation to cut-off scores, number of used subtests, manner of testing, and employed statistics, as these vary in the literature. Furthermore, data are presented from a large-scale experiment with 228 German undergraduate students who were assessed with the MBEA and a comprehensive questionnaire. This experiment tested the difference between scores that were obtained in a web-based study (at participants' homes) and those obtained under laboratory conditions with a computerized version of the MBEA. In addition to traditional statistical procedures, the data were evaluated using Signal Detection Theory (SDT; Green and Swets, 1966), taking into consideration the individual's ability to discriminate and their response bias. Results show that using SDT for scoring instead of proportion correct offers a bias-free and normally distributed measure of discrimination ability. It is also demonstrated that a diagnosis based on an average score leads to cases of misdiagnosis. The prevalence of congenital amusia is shown to depend highly on the statistical criterion that is applied as cut-off score and on the number of subtests that is considered for the diagnosis. In addition, three different subtypes of amusics were found in our sample. Lastly, significant differences between the web-based and the laboratory group were found, giving rise to questions about the validity of web-based experimentation.

Revising the diagnosis of congenital amusia with the Montreal Battery of Evaluation of Amusia

Directory of Open Access Journals (Sweden)

Jasmin ePfeifer

2015-04-01

Full Text Available This article presents a critical survey of the prevalent usage of the Montreal Battery of Evaluation of Amusia (MBEA; Peretz et al., 2003 to assess congenital amusia, a neuro-developmental disorder that has been claimed to be present in 4% of the population (Kalmus and Fry, 1980. It reviews and discusses the current usage of the MBEA in relation to cut-off scores, number of used subtests, manner of testing, and employed statistics, as these vary in the literature. Furthermore, data are presented from a large-scale experiment with 228 German undergraduate students who were assessed with the MBEA and a comprehensive questionnaire. This experiment tested the difference between scores that were obtained in a web-based study (at participants’ homes and those obtained under laboratory conditions with a computerized version of the MBEA. In addition to traditional statistical procedures, the data were evaluated using Signal Detection Theory (SDT; Green and Swets, 1966, taking into consideration the individual’s ability to discriminate and their response bias. Results show that using SDT for scoring instead of proportion correct offers a bias-free and normally distributed measure of discrimination ability. In addition it is also demonstrated that a diagnosis based on an average score leads to cases of misdiagnosis. The prevalence of congenital amusia is shown to depend highly on the statistical criterion that is applied as cut-off score and on the number of subtests that is considered for the diagnosis. In addition, three different subtypes of amusics were found in our sample. Lastly, significant differences between the web-based and the laboratory group were found, giving rise to questions about the validity of web-based experimentation.

Revising the diagnosis of congenital amusia with the Montreal Battery of Evaluation of Amusia

Science.gov (United States)

Pfeifer, Jasmin; Hamann, Silke

2015-01-01

This article presents a critical survey of the prevalent usage of the Montreal Battery of Evaluation of Amusia (MBEA; Peretz et al., 2003) to assess congenital amusia, a neuro-developmental disorder that has been claimed to be present in 4% of the population (Kalmus and Fry, 1980). It reviews and discusses the current usage of the MBEA in relation to cut-off scores, number of used subtests, manner of testing, and employed statistics, as these vary in the literature. Furthermore, data are presented from a large-scale experiment with 228 German undergraduate students who were assessed with the MBEA and a comprehensive questionnaire. This experiment tested the difference between scores that were obtained in a web-based study (at participants’ homes) and those obtained under laboratory conditions with a computerized version of the MBEA. In addition to traditional statistical procedures, the data were evaluated using Signal Detection Theory (SDT; Green and Swets, 1966), taking into consideration the individual’s ability to discriminate and their response bias. Results show that using SDT for scoring instead of proportion correct offers a bias-free and normally distributed measure of discrimination ability. It is also demonstrated that a diagnosis based on an average score leads to cases of misdiagnosis. The prevalence of congenital amusia is shown to depend highly on the statistical criterion that is applied as cut-off score and on the number of subtests that is considered for the diagnosis. In addition, three different subtypes of amusics were found in our sample. Lastly, significant differences between the web-based and the laboratory group were found, giving rise to questions about the validity of web-based experimentation. PMID:25883562

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)

Brad Patterson, Tom Brooking, and Jim McAloon, Unpacking the Kist: The Scots in New Zealand. McGill-Queen's Studies in Ethnic History Series, No. 2.33. Montreal: McGill-Queen’s University Press, 2013. Pp. 412. ISBN 978-0-7735-4190-0. CAD $100.00.

Directory of Open Access Journals (Sweden)

Seán Gerard Brosnahan

2014-11-01

Full Text Available Brad Patterson, Tom Brooking, and Jim McAloon, Unpacking the Kist: The Scots in New Zealand. McGill-Queen's Studies in Ethnic History Series, No. 2.33. Montreal: McGill-Queen’s University Press, 2013. Pp. 412. ISBN 978-0-7735-4190-0. CAD $100.00.

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

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

Advances in reactor physics education: Visualization of reactor parameters

International Nuclear Information System (INIS)

Snoj, L.; Kromar, M.; Zerovnik, G.

2012-01-01

Modern computer codes allow detailed neutron transport calculations. In combination with advanced 3D visualization software capable of treating large amounts of data in real time they form a powerful tool that can be used as a convenient modern educational tool for reactor operators, nuclear engineers, students and specialists involved in reactor operation and design. Visualization is applicable not only in education and training, but also as a tool for fuel management, core analysis and irradiation planning. The paper treats the visualization of neutron transport in different moderators, neutron flux and power distributions in two nuclear reactors (TRIGA type research reactor and a typical PWR). The distributions are calculated with MCNP and CORD-2 computer codes and presented using Amira software. (authors)

Reactor feedwater system

International Nuclear Information System (INIS)

Hikabe, Katsumi.

1978-01-01

Purpose: In order to prevent thermal stresses of a core of PWR type reactor, described has been a method for feeding heated recirculating water to the core in the case of the reactor start-up or shut-down. Constitution: A recirculating water is degassed, cleaned up and heated in the steam condensers, and then feeds the water to the reactor, characterized in that heaters are provided in the bypasses of the turbine, so that heated water is constantly supplied to the reactor. (Nakamura, S.)

New reactor concepts

International Nuclear Information System (INIS)

Meskens, G.; Govaerts, P.; Baugnet, J.-M.; Delbrassine, A.

1998-11-01

The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

Nuclear reactor design

CERN Document Server

2014-01-01

This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

Fission reactors and materials

International Nuclear Information System (INIS)

Frost, B.R.T.

1981-12-01

The American-designed boiling water reactor and pressurized water reactor dominate the designs currently in use and under construction worldwide. As in all energy systems, materials problems have appeared during service; these include stress-corrosion of stainless steel pipes and heat exchangers and questions regarding crack behavior in pressure vessels. To obtain the maximum potential energy from our limited uranium supplies is is essential to develop the fast breeder reactor. The materials in these reactors are subjected to higher temperatures and neutron fluxes but lower pressures than in the water reactors. The performance required of the fuel elements is more arduous in the breeder than in water reactors. Extensive materials programs are in progress in test reactors and in large test rigs to ensure that materials will be available to meet these conditions

Spectral shift reactor control method

International Nuclear Information System (INIS)

Impink, A.J. Jr.

1981-01-01

A method of operating a nuclear reactor having a core and coolant displacer elements arranged in the core wherein is established a reator coolant temperature set point at which it is desired to operate said reactor and first reactor coolant temperature band limits are provided within which said set point is located and it is desired to operate said reactor charactrized in that said reactor coolant displacer elements are moved relative to the reactor core for adjusting the volume of reactor coolant in said core as said reactor coolant temperature approaches said first band limits thereby to maintain said reactor coolant temperature near said set point and within said first band limits

Method of operating a reactor

International Nuclear Information System (INIS)

Oosumi, Katsumi; Yamamoto, Michiyoshi.

1980-01-01

Purpose: To prevent stress corrosion cracking in the structural material of a reactor pressure vessel. Method: Prior to the starting of a reactor, the reactor pressure vessel is evacuated to carry out degassing of reactor water, and, at the same time, reactor water is heated. After reactor water is heated to a predetermined temperature, control rods are extracted to start nuclear heating. While the temperature of the reactor water is in a temperature range where elution of a metal which is a structural material of the reactor pressure vessel becomes vigorous and the sensitivity to the stress corrosion cracks increases, the reactor is operated at the maximum permissible temperature raising speed or maximum permissible cooling speed. (Aizawa, K.)

Reactor container

International Nuclear Information System (INIS)

Abe, Yoshihito; Sano, Tamotsu; Ueda, Sabuo; Tanaka, Kazuhisa.

1987-01-01

Purpose: To improve the liquid surface disturbance in LMFBR type reactors. Constitution: A horizontal flow suppressing mechanism mainly comprising vertical members is suspended near the free liquid surface of coolants in the upper plenum. The horizontal flow of coolants near the free liquid surface is reduced by the suppressing mechanism to effectively reduce the surface disturbance. The reduction in the liquid surface disturbance further prevails to the entire surface region with no particular vertical variations to the free liquid surface to remarkably improve the preventive performance for the liquid surface disturbance. Accordingly, it is also possible to attain the advantageous effects such as prevention for the thermal fatigue in reactor vessel walls, reactor upper mechanisms, etc. and prevention of burning damage to the reactor core due to the reduction of envolved Ar gas. (Kamimura, M.)

Reactor Engineering Department annual report

International Nuclear Information System (INIS)

1993-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Reactor engineering department annual report

International Nuclear Information System (INIS)

1990-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1989 (April 1, 1989 - March 31, 1990). One of major Department's programs is the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Development of a high energy proton linear accelerator for the nuclear engineering including is also TRU incineration promoted. Other major tasks of the Department are various basic researches on nuclear data and group constants, theoretical methods and code development, on reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Montreal Archive of Sleep Studies: an open-access resource for instrument benchmarking and exploratory research.

Science.gov (United States)

O'Reilly, Christian; Gosselin, Nadia; Carrier, Julie; Nielsen, Tore

2014-12-01

Manual processing of sleep recordings is extremely time-consuming. Efforts to automate this process have shown promising results, but automatic systems are generally evaluated on private databases, not allowing accurate cross-validation with other systems. In lacking a common benchmark, the relative performances of different systems are not compared easily and advances are compromised. To address this fundamental methodological impediment to sleep study, we propose an open-access database of polysomnographic biosignals. To build this database, whole-night recordings from 200 participants [97 males (aged 42.9 ± 19.8 years) and 103 females (aged 38.3 ± 18.9 years); age range: 18-76 years] were pooled from eight different research protocols performed in three different hospital-based sleep laboratories. All recordings feature a sampling frequency of 256 Hz and an electroencephalography (EEG) montage of 4-20 channels plus standard electro-oculography (EOG), electromyography (EMG), electrocardiography (ECG) and respiratory signals. Access to the database can be obtained through the Montreal Archive of Sleep Studies (MASS) website (http://www.ceams-carsm.ca/en/MASS), and requires only affiliation with a research institution and prior approval by the applicant's local ethical review board. Providing the research community with access to this free and open sleep database is expected to facilitate the development and cross-validation of sleep analysis automation systems. It is also expected that such a shared resource will be a catalyst for cross-centre collaborations on difficult topics such as improving inter-rater agreement on sleep stage scoring. © 2014 European Sleep Research Society.

Criterion and convergent validity of the Montreal cognitive assessment with screening and standardized neuropsychological testing.

Science.gov (United States)

Lam, Benjamin; Middleton, Laura E; Masellis, Mario; Stuss, Donald T; Harry, Robin D; Kiss, Alex; Black, Sandra E

2013-12-01

To compare the validity of the Montreal Cognitive Assessment (MoCA) with the criterion standard of standardized neuropsychological testing and to compare the convergent validity of the MoCA with that of existing screening tools and global measures of cognition. Cross-sectional observational study. Tertiary care hospital-based cognitive neurology subspecialty clinic. A convenience sample of 107 individuals with mild Alzheimer's disease (AD, n=75) or mild cognitive impairment (MCI, n=32) from the Sunnybrook Dementia Study. In addition to the MoCA, all participants completed the Mini-Mental State Examination (MMSE), the Mattis Dementia Rating Scale (DRS), and detailed neuropsychological testing. Convergent validity was supported, with MoCA scores correlating well with the MMSE (correlation coefficient (r)=0.66, Pvalidity was supported, with MoCA subscores according to cognitive domain correlating well with analogous neuropsychological tests and, in the case of memory (area under the receiver operating characteristic curve (AUC)=0.86), executive (AUC=0.79), and visuospatial function (AUC=0.79), being reasonably sensitive to impairment in those domains. The MoCA is a valid assessment of cognition that shows good agreement with existing screening tools and global measures (convergent validity) and was superior to the MMSE in this regard. The MoCA domain-specific subscores align with performance on more-detailed neuropsychological tests, suggesting not only good criterion validity for the MoCA, but also that it may be useful in guiding further neuropsychological testing. © 2013, Copyright the Authors Journal compilation © 2013, The American Geriatrics Society.

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

Hirota, Jitsuya; Asaoka, Takumi; Suzuki, Tomoo; Mitani, Hiroshi; Akino, Fujiyoshi

1977-09-01

Research activities in the Division of Reactor Engineering in fiscal 1976 are described. Works of the division concern mainly the development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and the development of Liquid Metal Fast Breeder Reactor in 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 activities of the Committee on Reactor Physics. (auth.)

Reactor Engineering Department annual report

International Nuclear Information System (INIS)

1984-08-01

Research and development activities in the Department of Reactor Engineering in fiscal 1983 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, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

1976-09-01

Research activities conducted in Reactor Engineering Division in fiscal 1975 are summarized in this report. Works in the division are closely related to the development of multi-purpose High-temperature Gas Cooled Reactor, the development of Liquid Metal Fast Breeder Reactor by Power Reactor and Nuclear Fuel Development Corporation, and engineering research of thermonuclear fusion reactor. Many achievements are described concerning 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 activities of the Committee on Reactor Physics. (auth.)

Department of reactor technology

International Nuclear Information System (INIS)

1980-01-01

The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

Material test reactor fuel research at the BR2 reactor

Energy Technology Data Exchange (ETDEWEB)

Dyck, Steven Van; Koonen, Edgar; Berghe, Sven van den [Institute for Nuclear Materials Science, SCK-CEN, Boeretang, Mol (Belgium)

2012-03-15

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

Reactor Safety Commission Code of Practice for Pressurized Water Reactors

International Nuclear Information System (INIS)

1990-01-01

The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

Remote Reactor Monitoring

Energy Technology Data Exchange (ETDEWEB)

Bernstein, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dazeley, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dobie, Doug [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Marleau, Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brennan, Jim [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gerling, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sumner, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sweany, Melinda [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-10-21

The overall goal of the WATCHMAN project is to experimentally demonstrate the potential of water Cerenkov antineutrino detectors as a tool for remote monitoring of nuclear reactors. In particular, the project seeks to field a large prototype gadolinium-doped, water-based antineutrino detector to demonstrate sensitivity to a power reactor at ~10 kilometer standoff using a kiloton scale detector. The technology under development, when fully realized at large scale, could provide remote near-real-time information about reactor existence and operational status for small operating nuclear reactors out to distances of many hundreds of kilometers.

The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

2001-07-01

Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

Canada-India Reactor (CIR)

Energy Technology Data Exchange (ETDEWEB)

None

1960-12-15

Design information on the Canada-India Reactor is presented. Data are given on reactor physics, the core, fuel elements, core heat transfer, control, reactor vessel, fluid flow, reflector and shielding, containment, cost estimates, and research facilities. Drawings of vertical and horizontal sections of the reactor and fluid flow are included. (M.C.G.)

REACTOR: an expert system for diagnosis and treatment of nuclear reactor accidents

International Nuclear Information System (INIS)

Nelson, W.R.

1982-01-01

REACTOR is an expert system under development at EG and G Idaho, Inc., that will assist operators in the diagnosis and treatment of nuclear reactor accidents. This paper covers the background of the nuclear industry and why expert system technology may prove valuable in the reactor control room. Some of the basic features of the REACTOR system are discussed, and future plans for validation and evaluation of REACTOR are presented. The concept of using both event-oriented and function-oriented strategies for accident diagnosis is discussed. The response tree concept for representing expert knowledge is also introduced

One piece reactor removal

International Nuclear Information System (INIS)

Chia, Wei-Min; Wang, Song-Feng

1993-01-01

The strategy of Taiwan Research Reactor Renewal plan is to remove the old reactor block with One Piece Reactor Removal (OPRR) method for installing a new research reactor in original building. In this paper, the engineering design of each transportation works including the work method, the major equipments, the design policy and design criteria is described and discussed. In addition, to ensure the reactor block is safety transported for storage and to guarantee the integrity of reactor base mat is maintained for new reactor, operation safety is drawn special attention, particularly under seismic condition, to warrant safe operation of OPRR. ALARA principle and Below Regulatory Concern (BRC) practice were also incorporated in the planning to minimize the collective dose and the total amount of radioactive wastes. All these activities are introduced in this paper. (J.P.N.)

Nuclear reactors

International Nuclear Information System (INIS)

Middleton, J.E.

1977-01-01

Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)