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Sample records for ontario phwr pickering-5 reactor

  1. Experience with valves for PHWR reactors

    International Nuclear Information System (INIS)

    Narayan, K.; Mhetre, S.G.

    1977-01-01

    Material specifications and inspection and testing requirements of the valves meant for use in nuclear reactors are mentioned. In the heavy water systems (both primary and moderator) of a PHWR type reactor, the valves used are gate valves, globe valves, diaphragm valves, butterfly valves, check valves and relief valves. Their locations and functions they perform in the Rajasthan Atomic Power Station Unit-1 are described. Experience with them is given. The major problems encountered with them have been : (1) leakage from the stem seals and body bonnet joint, (2) leakage due to failure of diaphragm and/or washout of the packing and (3) malfunctioning. Measures taken to solve these are discussed. Finally a mention has been made of improved versions of valves, namely, metal diaphragm valve and inverted relief valve. (M.G.B.)

  2. Aspects regarding the fuel management for PHWR nuclear reactors

    International Nuclear Information System (INIS)

    Dragusin, O.; Bobolea, A.; Voicu, A.

    2001-01-01

    Fuel management for PHWR nuclear reactors is completely different from the PWR reactors fuel management. PHWR reactor fuel loading procedures are repeated after an interval of time, as defined and specified in the project documentation, using a fuel machine that can be attached to the terminal fittings of horizontal pressure tubes while the reactor is a full power. Another aspect of fuel management policy is related to the possibility of bi-directional loading of the reactor, with the primary advantage of uniform and symmetrical characteristics. (authors)

  3. The status of improved pressurized heavy water reactor development - A new option for PHWR -

    International Nuclear Information System (INIS)

    Park, Tae Keun; Yeo, Ji Won

    1996-03-01

    Currently, the 900 MWe class Improved Pressurized Heavy Water Reactor (PHWR), which is a type of CANDU reactor based on the systems and components of operating CANDU plants, is under development. The improved PHWR has a 480 fuel channel calandria, uses 37 element natural uranium fuel bundles and has a single unit containment. Adaptation of a steel-lined containment structure and improved containment isolation systems permit a reduced exclusion area boundary (EAB) compared to the existing larger capacity CANDU reactors (Darlington, Bruce B). The improved PHWR buildings are arranged to achieve minimum spacing between reactor units. Plant safety and economy are increased through various design changes based on the operating experience of existing CANDU plants. 4 refs. (Author)

  4. NERON-Computing system for PHWR reactor cells and heterogeneous parameter calculations

    International Nuclear Information System (INIS)

    Cristian, I.; Cirstoiu, B.; Slavnicu, S.D.

    1976-04-01

    A system of codes for PHWR type reactors is presented. The system includes the cell code NERO and a code PARETE for monopolar and dipolar heterogeneous calculations. A general theory of dipolar flux is necessary for a more accurate evaluation of void coefficient and diffusion moderator coefficient is given. The determination of monopolar and dipolar heterogeneous parameters is very useful for heterogeneous methods developped especially for HWR reactors during the last years. (author)

  5. Simulation of hot-channel transients for PHWR reactors

    International Nuclear Information System (INIS)

    Masriera, N.A.

    1988-01-01

    For the simulation of transients a whole-plant code is needed. These codes model the core in a very simplified way. When local variables have to be calculated a different kind of code is needed: a subchannel-code. This report studies the use of the cobra code as a subchannel-code, for the simulation of a PHWR fuel channel, considering that this code was developed for PWR cores calculation. A special effort is made to obtain optimized models for different calculations: steady state, soft transients and severe transients. These models differ in number of subchannels, axial nodes, and the choice of the most important variables. (Author) [es

  6. The safety of Ontario's nuclear reactors

    International Nuclear Information System (INIS)

    1980-06-01

    A Select Committee of the Legislature of Ontario was established to examine the affairs of Ontario Hydro, the provincial electrical utility. Extensive public hearings were held on several topics including the safety of nuclear power reactors operating in Ontario. The Committee found that these reactors are acceptably safe. Many of the 24 recommendations in this report deal with the licensing process and public access to information. (O.T.)

  7. Irradiation tests on PHWR type fuel elements in TRIGA research reactor of INR Pitesti

    Energy Technology Data Exchange (ETDEWEB)

    Horhoianu, Grigore [Institute for Nuclear Research, Pitesti (Romania). Nuclear Fuel Engineering Lab.; Sorescu, Ion [Institute for Nuclear Research, Pitesti (Romania). TRIGA Reactor Loop Facility; Parvan, Marcel [Institute for Nuclear Research, Pitesti (Romania). Hot Cells Lab.

    2012-12-15

    Nine PHWR type fuel elements with reduced length were irradiated in loop A of the TRIGA Research Reactor of INR Pitesti. The primary objective of the test was to determine the performance of nuclear fuel fabricated at INR Pitesti at high linear powers in pressurized water conditions. Six fuel elements were irradiated with a ramp power history, achieving a maximum power of 45 kW/m during pre-ramp and of 64 kW/m in the ramp. The maximum discharge burnup was of 216 MWh/kgU. Another three fuel elements with reduced length were irradiated with declining power history. At the beginning of irradiation the fuel elements achieved a maximum linear power of 66 kW/m. The maximum fuel power was about 1.3 times the maximum expected in PHWR. The maximum discharge burnup was 205 MWh/kgU. The elements were destructively examined in the hot cells of INR Pitesti. Temperature-sensitive parameters such as UO{sub 2} grain growth, fission-gas release and sheath deformations were examined. The tests proved the feasibility of irradiating PHWR type fuel elements at linear powers up to 66 kW/m under pressurized water conditions and demonstrated the possibility of more flexible operation of this fuel in power reactors. This paper presents the results of the investigation. (orig.)

  8. Comments on nuclear reactor safety in Ontario

    International Nuclear Information System (INIS)

    1987-08-01

    The Chalk River Technicians and Technologists Union representing 500 technical employees at the Chalk River Nuclear Laboratories of AECL submit comments on nuclear reactor safety to the Ontario Nuclear Safety Review. Issues identified by the Review Commissioner are addressed from the perspective of both a labour organization and experience in the nuclear R and D field. In general, Local 1568 believes Ontario's CANDU nuclear reactors are not only safe but also essential to the continued economic prosperity of the province

  9. Detection of SBLOCA in the reactor of PHT system of Indian PHWR using GLR method

    Energy Technology Data Exchange (ETDEWEB)

    Chakrabarti, Dipankar [Indian Institute of Technology, Kanpur (India). Nuclear Engineering and Technology Programme

    1990-01-01

    Detection of Small Break Loss of Coolant Accident (SBLOCA) in nuclear power plants is important from the point of view of safety. Generalised Likelihood Ratio (GLR) test is one of the ways to detect faults like leak, controller bias etc. It can differentiate and diagnose different types of faults. A simplified state-space variable model of a PHWR reactor is developed and the utility of GLR method is investigated to detect leaks in the coolant channel in the reactor portion of the primary heat transport (PHT) system. A simple digital control system to control the outlet pressure of the reactor by manipulating the flow rate through the reactor is also developed. The results indicate that a leak of magnitude as low as 0.25% of the total flow rate through one coolant channel can be detected efficiently and promptly by this method. For instance a leak was detected within 3 minutes properly for 97 times out of 100 leaks simulated. (M.G.B.). 20 refs., 1 appendix.

  10. Design of reactor components (non replaceable) of 500 MWe PHWR for enhanced life

    International Nuclear Information System (INIS)

    Dwivedi, K.P.; Seth, V.K.

    1994-01-01

    A nuclear power station is characterised by large initial cost and low operating cost. So a plant which is capable of operating for a longer period of time will be economically more attractive. In the past approach had been to design a nuclear power plant for 30 to 40 years of life time. However, with the improvement in technology and incorporation of redundant and diverse safety features it is now possible to design a nuclear power plant for longer life. Now internationally it is being realised that without sacrificing safety features, plant life should be extended till the cost of maintenance or refurbishment is larger than the cost of the replacement capacity. In order to meet the objective of long life, for the components which cannot be easily replaced the life time of about 100 years is being considered as the design objective. For other items replacement, layout space, shielding, access route and lifting capacity and component design are receiving additional emphasis so as to provide a long total station life time. With the above background, design improvements to enhance the life of reactor components for 500 MWe PHWR namely calandria, end shields and calandria vault liners which cannot be replaced and on which any repair is extremely difficult, have been made. This paper deals with design life of these components and the modifications incorporated in the design. (author). 3 refs., 2 tabs., 3 figs

  11. 3D modeling of the primary circuit in the reactor pressure vessel of a PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Ramajo, Damian, E-mail: dramajo@santafe-conicet.gov.ar; Corzo, Santiago; Schiliuk, Nicolas; Nigro, Norberto

    2013-12-15

    A computational fluid dynamics (CFD) simulation of the reactor pressure vessel (RPV) of the pressurized heavy water reactor (PHWR) of 745 electrical MW Atucha II nuclear power plant was carried out. A three dimensional (3D) detailed model was employed to simulate coolant circuit considering the upper and lower plenums, the downcomer and the hot and cold legs. Control rods and coolant channel tubes at the upper plenum were included to quantify the mixing flow with more realism. The whole set of 451 coolant channels were modeled by means of a zero dimensional methodology. That is, the effect of each coolant channel was modeled through the introduction of a source point at the upper plenum and a sink point at the lower plenum. For each coupled sink/source points (SSP) the mass, momentum and energy balance were solved considering the local pressure difference and the temperature between the corresponding points where sinks and sources were placed. Based on this strategy, three models with increasingly level of approximation were implemented. For the first model the 451 coolant channels were reduced to only 57 pairs of SSP to represent all the coolant channels, concentrating the effect of several coolant channels in a unique pair of sink and source while taking into account geometric design details. For the second model, 225 pairs of SSP were introduced. Finally, for the third model each one of the 451 coolant channels were modeled by means of one pair of SSP. Depending on the coolant channel location, the radial power distribution and the pressure loss caused by the corresponding flow restrictor present by design were considered. Simulations carried out give insight in the complexity of the flow. As expected, the greater the details of the model the better the accuracy reached in the representation of the RPV behavior. In addition, the flow distributor located at the lower plenum showed to be very efficient since, the mass flow at each channel was found to be fairly

  12. Secondary cycle water chemistry for 500 MWe pressurised heavy water reactor (PHWR) plant: a case study

    International Nuclear Information System (INIS)

    Bhandakkar, A.; Subbarao, A.; Agarwal, N.K.

    1995-01-01

    In turbine and secondary cycle system of 500 MWe PHWR, chemistry of steam and water is controlled in secondary cycle for prevention of corrosion in steam generators (SGs), feedwater system and steam system, scale and deposit formation on heat transfer surfaces and carry-over of solids by steam and deposition on steam turbine blades. Water chemistry of secondary side of SGs and turbine cycle is discussed. (author). 8 refs., 2 tabs., 1 fig

  13. Current issues in the management of low- and intermediate-level radioactive wastes from Ontario Hydro's CANDU reactors

    International Nuclear Information System (INIS)

    Krasznai, J.P.; Vaughan, B.R.; Williamson, A.S.

    1990-01-01

    Nuclear generating stations (NGSs) in Canada are operated by utilities in Ontario, Quebec, and New Brunswick. Ontario Hydro, with a committed nuclear program of 13,600 MW(electric) is the major producer of CANDU pressurized heavy-water reactor (PHWR) low- and intermediate-level radioactive wastes. All radioactive wastes with the exception of irradiated fuel are processed and retrievably stored at a centralized facility at the Bruce Nuclear Power Development site. Solid-waste classifications and annual production levels are given. Solid-waste management practices at the site as well as the physical, chemical, and radiochemical characteristics of the wastes are well documented. The paper summarizes types, current inventory, and estimated annual production rate of liquid waste. Operation of the tritium recovery facility at Darlington NGS, which removes tritium from heavy water and produces tritium gas in the process, gives rise to secondary streams of tritiated solid and liquid wastes, which will receive special treatment and packaging. In addition to the treatment of radioactive liquid wastes, there are a number of other important issues in low- and intermediate-level radioactive waste management that Ontario Hydro will be addressing over the next few years. The most pressing of these is the reduction of radioactive wastes through in-station material control, employee awareness, and improved waste characterization and segregation programs. Since Ontario Hydro intends to store retrievable wastes for > 50 yr, it is necessary to determine the behavior of wastes under long-term storage conditions

  14. MTR and PWR/PHWR in-pile loop safety in integration with the operation of multipurpose reactor - GAS

    International Nuclear Information System (INIS)

    Suharno; Aji, Bintoro; Sugiyanto; Rohman, Budi; Zarkasi, Amin S.; Giarno

    1998-01-01

    MTR and PWR/PHWR In-Pile Loop safety analysis in integration with the operation of Multipurpose Reactor - Gas has been carried out and completed. The assessment is emphasized on the function of the interface systems from the dependence of the operation and the evaluation to the possibility of leakage or failure of the in-pile part inside the reactor pool and reactor core. The analysis is refers to the logic function of the interface system and the possibility of leakage or failure of the in-pile part inside reactor pool and reactor core to consider the integrity of the core qualitatively. The results show that in normal and in transient conditions , the interface system meet the function requirement in safe integrated operation of in-pile loop and reactor. And the results of the possibility analysis of the leakage shows that the possibility based on mechanically assessment is very low and the impact to core integrity is nothing or can be eliminated. The possible position for leakage is on the flen on which one meter above the top level of the core, therefore no influence of leakage to the core

  15. Non-destructive evaluation of stream generator tubes and pressure tubes from the PHWR reactors, using the rotating magnetic field method

    International Nuclear Information System (INIS)

    Premel, D.; Placko, D.; Grimberg, R.; Savin, A.

    2001-01-01

    This work presents a new type of eddy current transducer with a rotating magnetic field devoted to the inspection of steam generator tubes and pressure tubes from the PHWR reactors. A theoretical model has been developed that permits the calculations of the emf induced in the reception coils in the presence of the copper or magnetite deposits, anti-vibration railing and garter springs. (authors)

  16. Comparison of Ontario Hydro's performance with world power reactors - 1981

    International Nuclear Information System (INIS)

    Dumka, B.R.

    1982-04-01

    The performance of Ontario Hydro's CANDU reactors in 1981 is compared with that of 123 world nuclear power reactors rated at 500 MW(e) or greater. The report is based on data extracted from publications, as well as correspondence with a number of utilities. The basis used is the gross capacity factor, which is defined as gross unit generation divided by the perfect gross output for the period of interest. The lowest of the published turbine and generator design ratings is used to determine the perfect gross output, unless the unit has been proven capable of consistently exceeding this value. The first six reactors in the rankings were CANDU reactors operated by Ontario Hydro

  17. Mathematical modeling of CANDU-PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Gaber, F.A.; Aly, R.A.; El-Shal, A.O. [Atomic Energy Authority, Cairo (Egypt)

    2003-07-01

    The paper deals with the transient studies of CANDU 600 pressurized Heavy Water Reactor (PHWR). This study involved mathematical modeling of CANDU-PHWR to study its thermodynamic performances. Modeling of CANDU-PHWR was based on lumped parameter technique. The reactor model includes the neutronic, reactivity, and fuel channel heat transfer. The nuclear reactor power was modelled using the point kinetics equations with six groups of delayed neutrons and the reactivity feed back due to the changes in the fuel temperature and coolant temperature. The CANDU-PHWR model was coded in FORTRAN language and solved by using a standard numerical technique. The adequacy of the model was tested by assessing the physical plausibility of the obtained results. (author)

  18. Cobalt-60 control in Ontario Hydro reactors

    International Nuclear Information System (INIS)

    Lacy, C.S.

    1988-01-01

    This paper discusses the impact of specifying reduced Cobalt-59 in the primary heat transport circuit materials of construction on the radiation fields developed around the primary circuit. An eight-fold reduction in steam generator radiation fields due to Cobalt-60 has been observed for two identical sets of reactors, one with and one without Cobalt-59 control. The comparison is between eight reactors at the Pickering Nuclear Generating Station (PNGS). Units 5 to 8 (PNGS-B) are identical to Units 1 to 4 (PNGS-A) except that PNGS-B has reduced impurity Cobalt-59 in the alloys of construction and a reduced use of stellite. The effects of chemistry control are also discussed

  19. Power Reactor Fuel Reprocessing Plant-2, Tarapur: a benchmark in Indian PHWR spent fuel reprocessing

    International Nuclear Information System (INIS)

    Pradhan, Sanjay; Dubey, K.; Qureshi, F.T.; Lokeswar, S.P.

    2017-01-01

    Power Reactor Fuel Reprocessing Plant-2 (PREFRE-2) is latest operating spent nuclear fuel reprocessing plant in India. This plant has improved design based on latest technology and feedback provided by the earlier plants. The design of PREFRE-2 plant is in five cycles of solvent extraction using TBP as extractant. The plant is commissioned in year 2011 after regulatory clearances

  20. Estimation of release of tritium from measurements of air concentrations in reactor building of PHWR

    International Nuclear Information System (INIS)

    Purohit, R.G.; Sarkar, P.K.

    2010-01-01

    In this paper an attempt has been made to estimate the releases from measured air concentrations of tritium at various locations in Reactor Building (RB). Design data of Kaiga Generating Station and sample measurements of tritium concentrations at various locations in RB and discharges for a period of fortnight were used. A comparison has also been made with actual measurements. It has been observed that there is good matching in estimated and actual measurements of tritium release on some days while on some days there is high difference

  1. Dynamic Analysis of Coolant Channel and Its Internals of Indian 540 MWe PHWR Reactor

    Directory of Open Access Journals (Sweden)

    A. Rama Rao

    2008-04-01

    Full Text Available The horizontal coolant channel is one of the important parts of primary heat transport system in PHWR type of reactors. There are in all 392 channels in the core of Indian 540 MWe reactor. Each channel houses 13 natural uranium fuel bundles and shielding and sealing plugs one each on either side of the channel. The heavy water coolant flows through the coolant channel and carries the nuclear heat to outside the core for steam generation and power production in the turbo-generator. India has commissioned one 540 MWe PHWR reactor in September 2005 and another similar unit will be going into operation very shortly. For a complete dynamic study of the channel and its internals under the influence of high coolant flow, experimental and modeling studies have been carried out. A good correlation has been achieved between the results of experimental and analytical models. The operating life of a typical coolant channel typically ranges from 10 to 15 full-power years. Towards the end of its operating life, its health monitoring becomes an important activity. Vibration diagnosis plays an important role as a tool for life management of coolant. Through the study of dynamic characteristics of the coolant channel under simulated loading condition, an attempt has been made to develop a diagnostics to monitor the health of the coolant channel over its operating life. A study has been also carried out to characterize the fuel vibration under different flow condition.

  2. Mathematical modeling of CANDU-PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Gaber, F.A.; Aly, R.A.; El-Shal, A.O. [Atomic Energy Authority, Cairo (Egypt)

    2001-07-01

    The paper deals with the transient studies of CANDU 600 pressurized Heavy Water Reactor (PHWR) system. This study involved mathematical modeling of CANDU PHWR major system components and the developments of software to study the thermodynamic performances. Modeling of CANDU-PHWR was based on lumped parameter technique.The integrated CANDU-PHWR model includes the neutronic, reactivity, fuel channel heat transfer, piping and the preheater type U-tube steam generator (PUTSG). The nuclear reactor power was modelled using the point kinetics equations with six groups of delayed neutrons and reactivity feed back due to the changes in fuel temperature and coolant temperature. The complex operation of the preheater type U-tube steam generator (PUTSG) is represented by a non-linear dynamic model using a state variable, moving boundary and lumped parameter techniques. The secondary side of the PUTSG model has six separate lumps including a preheater region, a lower boiling section, a mixing region, a riser, a chimmeny section, and a down-corner. The tube side of PUTSG has three main thermal zones. The PUTSG model is based on conservation of mass, energy and momentum relation-ships. The CANDU-PHWR integrated model are coded in FORTRAN language and solved by using a standard numerical technique. The adequacy of the model was tested by assessing the physical plausibility of the obtained results. (author)

  3. Dynamic behaviour of a typical PHWR under earthquake load conditions

    International Nuclear Information System (INIS)

    Fischer, U.; Brandt, K.; Krutzik, N.J.

    1984-01-01

    The paper deals with dynamic calculations for a PHWR reactor building founded on rock and on a base isolation system. The zero period accelerations, displacements, mode shapes and the floor response spectra of both calculations are compared. (Author) [pt

  4. Tritium accounting for PHWR plants

    International Nuclear Information System (INIS)

    Nair, P.S.; Duraisamy, S.

    2012-01-01

    Tritium, the radioactive isotope of hydrogen, is produced as a byproduct of the nuclear reactions in the nuclear power plants. In a Pressurized Heavy Water Reactor (PHWR) tritium activity is produced in the Heat Transport and Moderator systems due to neutron activation of deuterium in heavy water used in these systems. Tritium activity build up occurs in some of the water systems in the PHWR plants through pick up from the plant atmosphere, inadvertent D 2 O ingress from other systems or transfer during processes. The tritium, produced by the neutron induced reactions in different systems in the reactor undergoes multiple processes such as escape through leaks, storage, transfer to external locations, decay, evaporation and diffusion and discharge though waste streams. Change of location of tritium inventory takes place during intentional transfer of heavy water, both reactor grade and downgraded, from one system to another. Tritium accounting is the application of accounting techniques to maintain knowledge of the tritium inventory present in different systems of a facility and to construct activity balances to detect any discrepancy in the physical inventories. It involves identification of all the tritium hold ups, transfers and storages as well as measurement of tritium inventories in various compartments, decay corrections, environmental release estimations and evaluation of activity generation during the accounting period. This paper describes a methodology for creating tritium inventory balance based on periodic physical inventory taking, tritium build up, decay and release estimations. Tritium accounting in the PHWR plants can prove to be an effective regulatory tool to monitor its loss as well as unaccounted release to the environment. (author)

  5. Development and applications of reactor noise analysis at Ontario Hydro's CANDU reactors

    International Nuclear Information System (INIS)

    Gloeckler, O.; Tulett, M.V.

    1995-01-01

    In 1992 a program was initiated to establish reactor noise analysis as a practical tool for plant performance monitoring and system diagnostics in Ontario Hydro's CANDU reactors. Since then, various CANDU-specific noise analysis applications have been developed and validated. The noise-based statistical techniques are being successfully applied as powerful troubleshooting and diagnostic tools to a wide variety of actual operational I and C problems. The dynamic characteristics of critical plant components, instrumentation and processes are monitored on a regular basis. Recent applications of noise analysis include (1) validating the dynamics of in-core flux detectors (ICFDS) and ion chambers, (2) estimating the prompt fraction ICFDs in noise measurements at full power and in power rundown tests, (3) identifying the cause of excessive signal fluctuations in certain flux detectors, (4) validating the dynamic coupling between liquid zone control signals, (5) detecting and monitoring mechanical vibrations of detector tubes induced by moderator flow, (6) estimating the dynamics and response time of RTD (Resistance Temperature Detector) temperature signals, (7) isolating the cause of RTD signal anomalies, (8) investigating the source of abnormal flow signal behaviour, (9) estimating the overall response time of flow and pressure signals, (10) detecting coolant boiling in fully instrumented fuel channels, (11) monitoring moderator circulation via temperature noise, and (12) predicting the performance of shut-off rods. Some of these applications are performed on an as-needed basis. The noise analysis program, in the Pickering-B station alone, has saved Ontario Hydro millions of dollars during its first three years. The results of the noise analysis program have been also reviewed by the regulator (Atomic Energy Control Board of Canada) with favorable results. The AECB have expressed interest in Ontario Hydro further exploiting the use of noise analysis technology. (author

  6. Development and applications of reactor noise analysis at Ontario Hydro`s CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gloeckler, O [Ontario Hydro, Toronto, ON (Canada); Tulett, M V [Ontario Hydro, Pickering, ON (Canada). Pickering Generating Station

    1996-12-31

    In 1992 a program was initiated to establish reactor noise analysis as a practical tool for plant performance monitoring and system diagnostics in Ontario Hydro`s CANDU reactors. Since then, various CANDU-specific noise analysis applications have been developed and validated. The noise-based statistical techniques are being successfully applied as powerful troubleshooting and diagnostic tools to a wide variety of actual operational I and C problems. The dynamic characteristics of critical plant components, instrumentation and processes are monitored on a regular basis. Recent applications of noise analysis include (1) validating the dynamics of in-core flux detectors (ICFDS) and ion chambers, (2) estimating the prompt fraction ICFDs in noise measurements at full power and in power rundown tests, (3) identifying the cause of excessive signal fluctuations in certain flux detectors, (4) validating the dynamic coupling between liquid zone control signals, (5) detecting and monitoring mechanical vibrations of detector tubes induced by moderator flow, (6) estimating the dynamics and response time of RTD (Resistance Temperature Detector) temperature signals, (7) isolating the cause of RTD signal anomalies, (8) investigating the source of abnormal flow signal behaviour, (9) estimating the overall response time of flow and pressure signals, (10) detecting coolant boiling in fully instrumented fuel channels, (11) monitoring moderator circulation via temperature noise, and (12) predicting the performance of shut-off rods. Some of these applications are performed on an as-needed basis. The noise analysis program, in the Pickering-B station alone, has saved Ontario Hydro millions of dollars during its first three years. The results of the noise analysis program have been also reviewed by the regulator (Atomic Energy Control Board of Canada) with favorable results. The AECB have expressed interest in Ontario Hydro further exploiting the use of noise analysis technology. (author

  7. The safety of Ontario's nuclear power reactor. A scientific and technical review. Report to the Minister

    International Nuclear Information System (INIS)

    Hare, F.K.

    1988-01-01

    In December 1986 a study of the safety of the design, operating procedures and emergency plans associated with Ontario Hydro's nuclear generating plants was commissioned by the government of the province of Ontario. After receiving briefs from many interested groups and individuals, visiting the power plants, and consulting with nuclear industry and regulatory representatives in Canada and other countries, the commissioner presented this report to the Minister of Energy for Ontario. His major conclusion is that Ontario Hydro reactors are being operated safely and at high standards of technical performance. No significant adverse impact has been detected in either the work force or the public. The risk of accidents serious enough to affect the public adversely can never be zero, but is very remote. Major recommendations are that: Ontario Hydro re-examine its operational organization closely and commission a study of factors affecting human performance; and, that priority be given to finding a solution to pressure tube performance problems and to improving in-reactor monitoring. Sixteen other recommendations are presented relating to research and development, information exchange with other organizations, reactor performance, training, severe accident analysis, the provincial nuclear emergency plan, epidemiological studies, the Atomic Energy Control Board, public hearings, and women in the nuclear industry

  8. PHWR Fuel - an integrated approach in Indian context

    Energy Technology Data Exchange (ETDEWEB)

    Jayaraj, R.N. [Nuclear Fuel Complex, Dept. of Atomic Energy, Hyderabad (India)

    2008-07-01

    The nuclear power programme in India is based on a three-stage approach in which the Pressurized Heavy Water Reactors (PHWR) forms the backbone of the first stage. Over the years, apart from gaining expertise in design, construction and operation of PHWRs, innovative fuel designs and manufacturing technologies have also been evolved. Presently, thirteen PHWR 220 units and two PHWR 540 units are in operation. Three more PHWR 220 units are in the advanced stage of construction. In addition, the PHWR power generation programme envisages construction of eight more PHWR 700 units. Nuclear Fuel Complex (NFC) at Hyderabad, established in early 70s, is the only manufacturer of fuel and reactor core structurals for all the PHWRs in India. Since inception, the thrust has been on indigenous development of technology in the areas of production processes, equipment manufacture and quality assurance programmes. Commensurate with the PHWR programme, NFC has expanded its production capacities and has fabricated more than 380,000 fuel bundles since inception. Towards optimization of uranium resources and implementation of 'closed fuel cycle' concept, large quantities of reprocessed uranium fuel bundles have been manufactured and introduced in the initial cores of PHWRs. In recent times, NFC introduced several modifications in the production processes like vapour ammonia precipitation for UO{sub 2} powder production, advanced resistance welding controls and improved versions of welding machines, which all have facilitated in improving the quality and productivity of the fuel. Superior quality control systems like spectrophotometric determination of SSA of UO{sub 2} powders, machine vision systems for pellet inspection, thermography for evaluating weld integrity, etc. has channelised NDT techniques into fuel production lines. The paper summarizes various improvements carried out in the design and manufacture of PHWR fuel. New concepts evolved in high burn-up fuels and

  9. PHWR Fuel - an integrated approach in Indian context

    International Nuclear Information System (INIS)

    Jayaraj, R.N.

    2008-01-01

    The nuclear power programme in India is based on a three-stage approach in which the Pressurized Heavy Water Reactors (PHWR) forms the backbone of the first stage. Over the years, apart from gaining expertise in design, construction and operation of PHWRs, innovative fuel designs and manufacturing technologies have also been evolved. Presently, thirteen PHWR 220 units and two PHWR 540 units are in operation. Three more PHWR 220 units are in the advanced stage of construction. In addition, the PHWR power generation programme envisages construction of eight more PHWR 700 units. Nuclear Fuel Complex (NFC) at Hyderabad, established in early 70s, is the only manufacturer of fuel and reactor core structurals for all the PHWRs in India. Since inception, the thrust has been on indigenous development of technology in the areas of production processes, equipment manufacture and quality assurance programmes. Commensurate with the PHWR programme, NFC has expanded its production capacities and has fabricated more than 380,000 fuel bundles since inception. Towards optimization of uranium resources and implementation of 'closed fuel cycle' concept, large quantities of reprocessed uranium fuel bundles have been manufactured and introduced in the initial cores of PHWRs. In recent times, NFC introduced several modifications in the production processes like vapour ammonia precipitation for UO 2 powder production, advanced resistance welding controls and improved versions of welding machines, which all have facilitated in improving the quality and productivity of the fuel. Superior quality control systems like spectrophotometric determination of SSA of UO 2 powders, machine vision systems for pellet inspection, thermography for evaluating weld integrity, etc. has channelised NDT techniques into fuel production lines. The paper summarizes various improvements carried out in the design and manufacture of PHWR fuel. New concepts evolved in high burn-up fuels and development of state

  10. The safety of Ontario's nuclear power reactors. A scientific and technical review. Ontario Hydro Submission to the Ontario Nuclear Safety Review

    International Nuclear Information System (INIS)

    1987-01-01

    Ontario Hydro is responsible for the safety of its nuclear stations: safety analysis, design and construction, training of operators, operating practices, and maintenance procedures. The utility must demonstrate to the regulatory body and the public that it is capable of operating nuclear stations safely. the dedicated attention of management and workers alike has been given to the achievement of an excellent safety record. Safety begins with well understood corporate goals, objectives and policies, and the clear assignment of responsibilities to well-trained, competent people who have the relevant experience and the right information and equipment. A prime cause of both the Chernobyl and the Three Mile Island accidents was a breakdown in operational procedures and human factors. On the contrary, the pressure tube failure at Pickering unit 2 in 1983 was understood almost immediately by the operators, who took the correct steps to shut down the reactor. This success is related to well-designed control room information systems and good understanding of fundamentals by the operators. Increasingly, in the design of nuclear plant control and instrumentation systems and in training in Ontario Hydro, the well-being, capabilities and limitations of humans are being taken into account. This report describes the series of barriers between the radioactive material in the fuel and the series of barriers between the radioactive material in the fuel and the environment, and the stringent quality control and technical measures taken to make the likelihood of malfunctions very small. Defence in depth protection for the public is a feature of all Ontario Hydro nuclear stations. As safety-related systems are updated in new stations, improvements are in some cases being backfitted to older stations

  11. Proceedings of 2nd PHWR operating safety experience meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-04-01

    Papers presented during the eight sessions of the meeting were devoted to the impact of PHWR operating experience on design of civil structures (reactor building integrity); operating experiences related to pressure tubes, nuclear steam supply system, plant stability; reactor maintenance and control systems, reactor operational safety. Some events concerned with reactor shutdown due to power failures are described, as well as action undertaken to prevent major damage.

  12. Proceedings of 2nd PHWR operating safety experience meeting

    International Nuclear Information System (INIS)

    1991-04-01

    Papers presented during the eight sessions of the meeting were devoted to the impact of PHWR operating experience on design of civil structures (reactor building integrity); operating experiences related to pressure tubes, nuclear steam supply system, plant stability; reactor maintenance and control systems, reactor operational safety. Some events concerned with reactor shutdown due to power failures are described, as well as action undertaken to prevent major damage

  13. Design aspects of PHWR for improved performance

    International Nuclear Information System (INIS)

    Das, M.

    1989-01-01

    The PHWR fuel bundle is elegantly simple in design consisting of only six components. The unique features of the design include high density natural UO 2 pellets, collapsible zircaloy cladding, no gas plenums and short (50 cm), simple bundle configuration. Over the last 20 years, considerable efforts have been expended and still being continued on development of analytical tools and computer codes generation of technical specifications tests and experimental studies type tests on prototype bundles irradiation of special documented fuel bundles in power reactors and monitoring and analysis of fuel performance. The knowledge thus gained has helped us to modify design requirements, relax technical specifications and to evolve new, improved designs. The PHWR fuel technology in India can now be considered as well proven but there is considerable scope for further improvements both in design and manufacturing. For example, in design, use of thinner wall cladding (to improve burn up) bundle design with graded elements, double dished pellet, improved coatings, use of MOX fuel etc. are being explored. On the manufacturing side emphasis need to be given on maintaining the quality, improvement on production and process control. The use of automation and advances in machine control techniques, for example, using micro processors can effectively contribute to improvements in quality, productivity and lowering of fuel fabrication costs. In this paper, the PHWR fuel design features, different fuel designs evolved, fuel specifications, influence of fabrication variables and future direction in improved fuel performance are discussed. (author) 9 refs., 7 figs

  14. Power distribution monitoring and control in 500 MWe PHWR

    International Nuclear Information System (INIS)

    Kumar, A.

    1996-01-01

    The 500 MWe Indian Pressurized Heavy Water Reactor (PHWR) is expected to be commissioned in a few years. It has a relatively large sized core with complex material distribution in comparison to the currently operating 220 MWe PHWRs. The resulting neutronically loosely coupled system demands continuous control of the core power distribution. This paper gives a brief description and analysis of the reactor monitoring and control system proposed for this reactor. (author). 11 refs, 8 figs, 3 tabs

  15. Analysis of log rate noise in Ontario's CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hinds, H.W. [Dynamic Simulation and Analysis Corp., Deep River, Ontario (Canada); Banica, C.; Arguner, D. [Ontario Power Generation, Ajax, Ontario (Canada); Scharfenberg, R. [Bruce Power, Tiverton, Ontario (Canada)

    2007-07-01

    In the fall of 2003, the operators noticed that in the recently-refurbished Bruce A Shutdown System no. 1 (SDS1) the noise level in Log Rate signals were much larger than before. At the request of the Canadian Nuclear Safety Commission (CNSC), all Canadian CANDU reactors took action to characterize their Log Rate noise. Staff of the Inspection and Maintenance Services division of Ontario Power Generation (OPG) has collected high-speed high-accuracy noise data from nearly all 16 Ontario reactors, either as part of routine measurements before planned outages or as a dedicated noise recording. This paper gives the results of examining a suitable subset of this data, with respect to the characteristics and possible causes of Log Rate noise. The reactor and instrumentation design is different at each station: the locations of the moderator injection nozzles, the location of the ion chambers for each system, and the design of the Log Rate amplifiers. It was found that the Log noise (source of Log Rate noise) was much larger for those ion chambers in the path of the moderator injection nozzles, compared to those which were not in the path. This 'extra' Log noise would then be either attenuated or amplified depending on the transfer function (time constants) of the Log Rate amplifier. It was also observed that most of the Log and Log Rate noise is independent of any other signal measured. Although all CANDU reactors in Ontario have Log and Log Rate noise, the Bruce A SDS1 system has the largest amount of Log Rate noise, because (a) its SDS1 (and RRS) ion chambers are at the top of the reactor in the path of the moderator injection nozzles, and (b) its SDS1 Log Rate amplifiers have the smallest time constants. (author)

  16. Neutron radiography for quality assurance of PHWR fuel pins

    International Nuclear Information System (INIS)

    Chandrasekharan, K.N.; Patil, B.P.; Ghosh, J.K.; Ganguly, C.

    1993-01-01

    Neutron radiography was employed for quality assurance (QA) for advanced PHWR experimental fuel pins containing mixed uranium-plutonium dioxide and thorium-plutonium dioxide pellets. Direct, transfer and track-etch techniques were utilised. The thermal neutron beam facility of APSARA research reactor at Bhabha Atomic Research Centre was used. (author). 5 refs., 16 figs., 2 tabs

  17. Development of advanced CANDU PHWR -Development of the advanced CANDU technology-

    International Nuclear Information System (INIS)

    Seok, Ho Cheon; Na, Yeong Hwan; Seok, Soo Dong; Lee, Bo Uk; Kwak, Ho Sang; Kim, Bong Ki; Kim, Seok Nam; Min, Byeong Joo; Park, Jong Ryunl; Shin, Jeong Cheol; Lee, Kyeong Ho; Lee, Dae Hee; Lee, Deuk Soo; Lee, Yeong Uk; Lee, Jeong Yang; Jwon, Jong Seon; Jwon, Chang Joon; Ji, Yong Kwan; Han, Ki Nam; Kim, Kang Soo; Kim, Dae Jin; Kim, Seon Cheol; Kim, Seong Hak; Kim, Yeon Seung; Kim, Yun Jae; Kim, Jeong Kyu; Kim, Jeong Taek; Kim, Hang Bae; Na, Bok Kyun; Namgung, In; Moon, Ki Hwan; Park, Keun Ok; Shon, Ki Chang; Song, In Ho; Shin, Ji Tae; Yeo, Ji Won; Oh, In Seok; Jang, Ik Ho; Jeong, Dae Won; Jeong, Yong Hwan; Ha, Jae Hong; Ha, Jeong Koo; Hong, Hyeong Pyo; Hwang, Jeong Ki

    1994-07-01

    The target of this project is to assess the feasibility of improving PHWR and to establish the parameter of the improved concept and requirements for developing it. To set up the requirements for the Improved Pressurized Heavy Water Reactor: (1) Design requirements of PHWR main systems and Safety Design Regulatory Requirements for Safety Related System i.e. Reactor Shutdown System, Emergency Core Cooling System and Containment System were prepared. (2) Licensing Basis Documents were summarized and Safety Analysis Regulatory. Requirements were reviewed and analyzed. To estimate the feasibility of improving PHWR and to establish the main parameters of the concept of new PHWR in future: (1) technical level/developing trend of PHWR in Korea through Wolsong 2, 3 and 4 design experience and Technical Transfer Program was investigated to analyze the state of basic technology and PHWR improvement potential. (2) CANDU 6 design improvement tendency, CANDU 3 design concept and CANDU 9 development state in other country was analyzed. (3) design improvement items to apply to the reactors after Wolsong 2, 3 and 4 were selected and Plant Design Requirements and Conceptual Design Description were prepared and the viability of improved HWR was estimated by analyzing economics, performance and safety. (4) PHWR technology improving research and development plan was established and international joint study initiated for main design improvement items

  18. Process systems of PHWR - Indian experience

    Energy Technology Data Exchange (ETDEWEB)

    Ramandan, T S.V. [Madras Atomic Power Station (MAPS), Madras (India)

    1991-04-01

    Three operational problems are discussed in this paper. The reactors in Madras Atomic Power Station (MAPS), India are Pressurised Heavy Water Reactors PHWR), similar to Douglas Point PGS. The moderator heavy water is pumped into the bottom half of the calandria (horizontal reactor vessel) through one inlet manifold plenum chamber and horizontal louvers which help to distribute the moderator evenly at a very low velocity. The outlet from the calandria is through a smaller manifold structure at a higher elevation. The moderator is held on the shell side of the calandria by means of helium gas pressure differential between top of calandria and dump tank located below. The primary coolant system consists of 306 coolant channels containing the fuel and steam generators (SGs) and pumps on either side of the reactor. Each SC consists of 11 Nos. inverted U tube vertical heat exchangers where heat is transferred from primary coolant heavy water to secondary light water to produce steam. (author)

  19. Process systems of PHWR - Indian experience

    International Nuclear Information System (INIS)

    Ramandan, T.S.V.

    1991-01-01

    Three operational problems are discussed in this paper. The reactors in Madras Atomic Power Station (MAPS), India are Pressurised Heavy Water Reactors PHWR), similar to Douglas Point PGS. The moderator heavy water is pumped into the bottom half of the calandria (horizontal reactor vessel) through one inlet manifold plenum chamber and horizontal louvers which help to distribute the moderator evenly at a very low velocity. The outlet from the calandria is through a smaller manifold structure at a higher elevation. The moderator is held on the shell side of the calandria by means of helium gas pressure differential between top of calandria and dump tank located below. The primary coolant system consists of 306 coolant channels containing the fuel and steam generators (SGs) and pumps on either side of the reactor. Each SC consists of 11 Nos. inverted U tube vertical heat exchangers where heat is transferred from primary coolant heavy water to secondary light water to produce steam. (author)

  20. Acoustic emission experiments for PHWR technology development

    International Nuclear Information System (INIS)

    Pellionisz, P.; Jha, S.K.; Goswami, G.L.

    1992-06-01

    An Indian-Hungarian joint research project has been started with the aim of applying acoustic emission testing to solve specific problems of nuclear power plants. Acoustic emission measurement and analyzing instrumentation and software have been provided by the Hungarian side, while the measurements have been performed at the Bhabha Atomic Research Centre (BARC), India. The first task of the project was to check the capability of the method for leakage detection and shuttle movement monitoring of Pressurized Heavy Water Reactors (PHWR), and for monitoring manufacturing processes as laser welding. The preliminary measurements and results are presented. (R.P.) 15 refs.; 11 figs.; 3 tabs

  1. Slightly enriched uranium fuel for a PHWR

    International Nuclear Information System (INIS)

    Notari, C.; Marajofsky, A.

    1997-01-01

    An improved fuel element design for a PHWR using slightly enriched uranium fuel is presented. It maintains the general geometric disposition of the currently used in the argentine NPP's reactors, replacing the outer ring of rods by rods containing annular pellets. Power density reduction is achieved with modest burnup losses and the void volume in the pellets can be used to balance these two opposite effects. The results show that with this new design, the fuel can be operated at higher powers without violating thermohydraulic limits and this means an improvement in fuel management flexibility, particularly in the transition from natural uranium to slightly enriched uranium cycle. (author)

  2. The safety of Ontario's nuclear power reactors. A scientific and technical review. Selected consultants' reports

    International Nuclear Information System (INIS)

    Hare, F.K.

    1988-01-01

    The Review commissioned 31 consultants to prepare detailed analyses of specific safety-related questions raised by the design and operation of Ontario Hydro's CANDU reactors. This volume presents 10 of these reports, which I judge to be of sufficient general importance to justify the cost of wide circulation. They have been reproduced precisely as they were submitted. They do not express the Review's own judgements, but do contain a major part of the evidence that influenced those judgements. In several cases the consultants have presented formal recommendations. Some of these have been incorporated, often in modified form, as Review recommendations, in the Minister's Report. Others remain simply as recommendations from the individual consultants. I agree with most of them, but have not seen them as central to the Review's conclusions. I suggest that appropriate institutions--most notably Ontario Hydro and Atomic Energy Control Board--study them, and act as they see fit

  3. Consolidating indigenous capability for PHWR fuel manufacturing in India

    Energy Technology Data Exchange (ETDEWEB)

    Jayaraj, R.N., E-mail: cenfc@nfc.gov.in [Nuclear Fuel Complex, Dept. of Atomic Energy, Government of India, Hyderabad (India)

    2010-07-01

    Since inception of Nuclear Power Programme in India greater emphasis was laid on total self- reliance in Fuel manufacturing. For Pressurized Heavy Water Reactors (PHWRs), which forms a base for the first stage of the programme, an integrated approach was adopted encompassing different areas of expertise -Design, Construction and Operation of PHWRs; Heavy Water production and Fuel Design and Manufacturing technologies. For the first PHWR constructed about 35 years back with the Canadian collaboration, known as Rajasthan Atomic Power Station (RAPS), half the core requirement of fuel was met from the fuel manufactured for the first time in India. Since then the fuel production capabilities were enhanced by setting up an industrial scale fuel manufacturing facility - Nuclear Fuel Complex (NFC) at Hyderabad, India during early '70s. NFC has been continuously expanding its capacities to meet the fuel demand of all the PHWRs constructed and operated by Nuclear Power Corporation of India Limited (NPCIL). Presently, fifteen PHWR 220 MWe units and two PHWR 540 MWe units are in operation and one more PHWR 220 MWe unit is in advanced stage of commissioning in India. While continuously engaged in the manufacture of fuel for these reactors, NFC has been upgrading the production lines with new processes and quality assurance systems. In order to multiply the production capacities, NFC has embarked on developing indigenous capability for design and building of special purpose process equipment for Uranium dioxide powder production, pelletisation and final assembly operations. Some of the equipment having state-of-the-art features includes dryers/furnaces for UO{sub 2} powder, presses/ sintering furnaces for pelletisation and resistance welding equipment/ machining stations for assembly operations. In addition, several campaigns were taken over the years for manufacturing PHWR fuel bundles containing reprocessed Uranium, Thoria and slightly enriched Uranium. The paper

  4. Consolidating indigenous capability for PHWR fuel manufacturing in India

    International Nuclear Information System (INIS)

    Jayaraj, R.N.

    2010-01-01

    Since inception of Nuclear Power Programme in India greater emphasis was laid on total self- reliance in Fuel manufacturing. For Pressurized Heavy Water Reactors (PHWRs), which forms a base for the first stage of the programme, an integrated approach was adopted encompassing different areas of expertise -Design, Construction and Operation of PHWRs; Heavy Water production and Fuel Design and Manufacturing technologies. For the first PHWR constructed about 35 years back with the Canadian collaboration, known as Rajasthan Atomic Power Station (RAPS), half the core requirement of fuel was met from the fuel manufactured for the first time in India. Since then the fuel production capabilities were enhanced by setting up an industrial scale fuel manufacturing facility - Nuclear Fuel Complex (NFC) at Hyderabad, India during early '70s. NFC has been continuously expanding its capacities to meet the fuel demand of all the PHWRs constructed and operated by Nuclear Power Corporation of India Limited (NPCIL). Presently, fifteen PHWR 220 MWe units and two PHWR 540 MWe units are in operation and one more PHWR 220 MWe unit is in advanced stage of commissioning in India. While continuously engaged in the manufacture of fuel for these reactors, NFC has been upgrading the production lines with new processes and quality assurance systems. In order to multiply the production capacities, NFC has embarked on developing indigenous capability for design and building of special purpose process equipment for Uranium dioxide powder production, pelletisation and final assembly operations. Some of the equipment having state-of-the-art features includes dryers/furnaces for UO 2 powder, presses/ sintering furnaces for pelletisation and resistance welding equipment/ machining stations for assembly operations. In addition, several campaigns were taken over the years for manufacturing PHWR fuel bundles containing reprocessed Uranium, Thoria and slightly enriched Uranium. The paper summarises

  5. Development of PHWR fuel fabrication in Korea

    International Nuclear Information System (INIS)

    Suh, K.S.; Yang, M.S.; Kim, D.H.; Rim, C.S.

    1988-01-01

    Korea Advanced Energy Research Institute (KAERI) started a research project to develop the PHWR (CANDU) nuclear fuel fabrication technology in 1981. Based on the results of the intensive developmental work, several prototype fuel bundles were fabricated and tested in the Hot Test Loop at KAERI continuously in 1983 and 1984. After that, irradiation test and post-irradiation examination were carried out for two KAERI-made fuel bundles at Chalk River Nuclear Laboratories in Canada in 1984. Since the results of in-pile and out-of-pile tests with prototype fuel bundles proved to be satisfactory, 48 additional fuel bundles were loaded in Wolsung reactor (CANDU) in 1984 and 1985, and all of them were discharged without a defect after excellent performance in the power reactor. In 1985, the Korean government decided that KAERI supplies all the fuel necessary for the Wolsung reactor. For the mass production of nuclear fuel bundle, several process equipment, facilities and automation methods have been improved making use of experience accumulated during research. A quality assurance program was also established, and quality inspection technology was reviewed and improved to fit the mass production. This paper deals with the development experience so far obtained with the design and fabrication of the Korean PHWR fuel

  6. AUTOSORO: A fuel management study program for Ontario Hydro CANDU reactors

    International Nuclear Information System (INIS)

    Wilk, L.

    1988-01-01

    A computer program, AUTOSORO, has been developed to automatically simulate an Ontario Hydro CANDU reactor core for any time duration according to user-defined on-power refuelling criteria. It is a three-dimensional two-group diffusion code coupled to refuelling decision logic at three screening levels: burnup, coupled neighbor, full-core. A central feature is a projected local-iteration scheme for predicting fuelling-induced local neutron flux changes. Comparisons of AUTOSORO results with actual histories demonstrate that it will be an excellent productivity tool for future in-core fuel management studies, reducing several man-months of effort to several man-hours

  7. Quality evaluation of PHWR fuel element end cap weld joints by ultrasonic testing technique

    Energy Technology Data Exchange (ETDEWEB)

    Singh, J L; Nair, V R; Ramadasan, E; Majumdar, S; Sahoo, K C [Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Div.; Kumar, Arun [Atomic Fuel Fabrication Facility, Tarapur (India)

    1994-12-31

    An ultrasonic testing technique has been developed for effective quality evaluation of Pressurised Heavy Water Reactor (PHWR) fuel end plug welds. A focused high frequency shear wave is directed to the weld zone from half skip distance to detect lack of fusion, porosities and wall cracks in the weld zone. A tentative select/reject level has been evolved to sort out the defective weld by examining more than 700 PHWR fuel pin welds. (author). 5 refs., 5 figs.

  8. Performance of containment of Indian PHWR

    International Nuclear Information System (INIS)

    Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

    2006-01-01

    This paper summarizes the various requirements and activities relevant to the testing of containment system of Indian Pressurized Heavy Water Reactor (PHWR). All Indian PHWR containments are constructed from concrete either reinforced or prestressed or a combination of both and lined with polymeric coating based on Epoxy or Vinyl in order to achieve the leak tightness necessary from the radiological considerations following an accident. The current concept includes a complete double containment (except the base raft) extended to all penetrations and some of the pipings (those open to the containment atmosphere). The primary containment fitted with a passive pressure suppression system is enveloped in the secondary containment (confinement) where slight vacuum is maintained during normal operation as well as post accident condition. The Integrated leakage Rate Test (ILRT) conducted so far on the containment indicate that the overall leakages from the containment are lower than those necessary to meet the radiological limits following a postulated accident and interception of leakages by secondary containment as per design. The details of the, tests, repairs carried out and observations are given in this paper. The experience of ILRT also indicate improvement in leak tightness in many areas. (author)

  9. Report of the COG/IAEA international workshop on managing nuclear safety at CANDU (PHWR) plants. Working material

    International Nuclear Information System (INIS)

    1997-01-01

    The workshop, hosted by COG and co-sponsored by the International Atomic Energy Agency (IAEA, Vienna) was held in Toronto, April 28 - May 1st, 1997. The 40 participants included senior managers from IAEA member countries operating or constructing CANDU (PHWR) stations. All the offshore utilities with PHWR stations in Korea, Romania, India, Argentina, Pakistan, and China were present with their domestic counterparts from Ontario Hydro Nuclear, Hydro Quebec, New Brunswick Power, and AECL. The objectives of the workshop were to: provide a forum for exchange of ideas among nuclear safety managers operating CANDU (PHWR) stations and to learn from each other's experiences; to foster sharing of information on different operating approaches to managing safety and, in particular, to highlight the strategies for controlling the overall plant risk to a low level; to identify and discuss issues of mutual interest pertinent to PHWR stations and to define future follow-up activities. Refs, figs

  10. Report of the COG/IAEA international workshop on managing nuclear safety at CANDU (PHWR) plants. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The workshop, hosted by COG and co-sponsored by the International Atomic Energy Agency (IAEA, Vienna) was held in Toronto, April 28 - May 1st, 1997. The 40 participants included senior managers from IAEA member countries operating or constructing CANDU (PHWR) stations. All the offshore utilities with PHWR stations in Korea, Romania, India, Argentina, Pakistan, and China were present with their domestic counterparts from Ontario Hydro Nuclear, Hydro Quebec, New Brunswick Power, and AECL. The objectives of the workshop were to: provide a forum for exchange of ideas among nuclear safety managers operating CANDU (PHWR) stations and to learn from each other`s experiences; to foster sharing of information on different operating approaches to managing safety and, in particular, to highlight the strategies for controlling the overall plant risk to a low level; to identify and discuss issues of mutual interest pertinent to PHWR stations and to define future follow-up activities. Refs, figs.

  11. ARGOS PHWR 380

    International Nuclear Information System (INIS)

    Gonzalez, A.J.; Vanzulli, R.C.

    1987-01-01

    This paper introduces the design of a nuclear power plant of 380 MWe, equipped with a preassure-vessel heavy-water reactor. An explanation is given of the technical, economical and financial factors that led to the design of this medium sized nuclear power plant, which is compatible with the latest advances in the field of nuclear safety. (Author) [es

  12. Status of generic actions items and safety analysis system of PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Park, Joo Hwan; Min, Byung Joo

    2001-05-01

    This report described the review results of a GAIs(Generic Action Item) currently issued on safety analysis of PHWR(Pressurized Heavy Water Reactor) and the research activities and positions to solve the GAIs in each country which possess PHWRs. eviewing the Final Safety Analysis Report for Wolsong-2/3/4 Units, the safety analysis methodology, classification for accident scenarios, safety analysis codes, their interface, etc.. were described. From the present review report, it is intended to establish the CANDU safety analysis system by providing the better understandings and development plans for the safety analysis of PHWR. esults.

  13. Advanced methods for fabrication of PHWR and LMFBR fuels

    International Nuclear Information System (INIS)

    Ganguly, C.

    1988-01-01

    For self-reliance in nuclear power, the Department of Atomic Energy (DAE), India is pursuing two specific reactor systems, namely the pressurised heavy water reactors (PHWR) and the liquid metal cooled fast breeder reactors (LMFBR). The reference fuel for PHWR is zircaloy-4 clad high density (≤ 96 per cent T.D.) natural UO 2 pellet-pins. The advanced PHWR fuels are UO 2 -PuO 2 (≤ 2 per cent), ThO 2 -PuO 2 (≤ 4 per cent) and ThO 2 -U 233 O 2 (≤ 2 per cent). Similarly, low density (≤ 85 per cent T.D.) (UPu)O 2 pellets clad in SS 316 or D9 is the reference fuel for the first generation of prototype and commercial LMFBRs all over the world. However, (UPu)C and (UPu)N are considered as advanced fuels for LMFBRs mainly because of their shorter doubling time. The conventional method of fabrication of both high and low density oxide, carbide and nitride fuel pellets starting from UO 2 , PuO 2 and ThO 2 powders is 'powder metallurgy (P/M)'. The P/M route has, however, the disadvantage of generation and handling of fine powder particles of the fuel and the associated problem of 'radiotoxic dust hazard'. The present paper summarises the state-of-the-art of advanced methods of fabrication of oxide, carbide and nitride fuels and highlights the author's experience on sol-gel-microsphere-pelletisation (SGMP) route for preparation of these materials. The SGMP process uses sol gel derived, dust-free and free-flowing microspheres of oxides, carbide or nitride for direct pelletisation and sintering. Fuel pellets of both low and high density, excellent microhomogeneity and controlled 'open' or 'closed' porosity could be fabricated via the SGMP route. (author). 5 tables, 14 figs., 15 refs

  14. The safety of Ontario's nuclear power reactors. A scientific and tecnical review. Vol. 1: Report to the Minister, technical report and annexes

    International Nuclear Information System (INIS)

    Hare, F.K.

    1988-01-01

    In December 1986 a study of the safety of the design, operating procedures and emergency plans associated with Ontario Hydro's nuclear generating plants was commissioned by the government of the province of Ontario. After receiving briefs from many interested groups and individuals, visiting the power plants, and consulting with nuclear industry and regulatory representatives in Canada and other countries, the commissioner presented this report to the Minister of Energy for Ontario. His major conclusion is that Ontario Hydro reactors are being operated safely and at high standards of technical performance. No significant adverse impact has been detected in either the work force or the public. The risk of accidents serious enough to affect the public adversely can never be zero, but is very remote. Major recommendations are that: Ontario Hydro re-examine its operational organization closely and commission a study of factors affecting human performance; and, that priority be given to finding a solution to pressure tube performance problems and to improving in-reactor monitoring. Sixteen other recommendations are presented relating to research and development, information exchange with other organizations, reactor performance, training, severe accident analysis, the provincial nuclear emergency plan, epidemiological studies, the Atomic Energy Control Board, public hearings, and women in the nuclear industry. This volume contains a detailed technical analysis of the CANDU system, its associated safety procedures, emergency measures required in the case of a nuclear accident, and regulation of the Canadian nuclear industry. Annexes provide further details on the operation of the Ontario Nuclear Safety Review

  15. Performance Shaping Factors Assessments and Application to PHWR Outages

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Woo

    2007-02-15

    Human reliability analysis is definitely related to the quality of PSA because human errors have been identified as major contributors to PSA. According to NRC's 'Office of analysis and evaluation of operational data (AEOD)',82% of the reactor trips and accident during outage is caused by the events related to human errors. There is, however, no one HRA method universally accepted. Furthermore, HRA during PHWR outages has not been performed around the world yet. HRA during PHWR outages is especially important since manual management of operator is more required during PHWR. In this study, accident scenarios which HYU developed are used to perform a quantification of human error probability. In this study, overall procedures of standard HRA methodology are introduced and follows the quantification of 10 possible selected human actions during PHWR outages based on standard HRA methodology. To see the verification, quantified values were compared with the values from 'Generic CANDU Probabilistic Safety Assessment' and the values estimated by ASEP.Core Damage Frequency was estimated 3.35 x 10{sup -4} more higher than CDF estimated by AECL data. It was considered that the differences between the HEPs for OPAFW and OPECC3 make CDF higher. Therefore, complementary study of reestimating HEP for OPAFW and OPECC3 in detail is required for increasing the qualities of HRA and PSA. Moreover, one of the difficulties in performing human reliability analysis is to evaluate performance shaping factors which represent the characteristics and circumstances. For assessing a specific human action more exactly, it is necessary to consider all of the PSFs at the same time which makes an effect on the human action. Also, it requires the effect comparison among PSFs to minimize the uncertainties which are usually caused by the subjective judgements of HRA analysts. To see the sensitivity, performance shaping factors of each decision rule are changed which resulted

  16. Performance Shaping Factors Assessments and Application to PHWR Outages

    International Nuclear Information System (INIS)

    Lee, Seung Woo

    2007-02-01

    Human reliability analysis is definitely related to the quality of PSA because human errors have been identified as major contributors to PSA. According to NRC's 'Office of analysis and evaluation of operational data (AEOD)',82% of the reactor trips and accident during outage is caused by the events related to human errors. There is, however, no one HRA method universally accepted. Furthermore, HRA during PHWR outages has not been performed around the world yet. HRA during PHWR outages is especially important since manual management of operator is more required during PHWR. In this study, accident scenarios which HYU developed are used to perform a quantification of human error probability. In this study, overall procedures of standard HRA methodology are introduced and follows the quantification of 10 possible selected human actions during PHWR outages based on standard HRA methodology. To see the verification, quantified values were compared with the values from 'Generic CANDU Probabilistic Safety Assessment' and the values estimated by ASEP.Core Damage Frequency was estimated 3.35 x 10 -4 more higher than CDF estimated by AECL data. It was considered that the differences between the HEPs for OPAFW and OPECC3 make CDF higher. Therefore, complementary study of reestimating HEP for OPAFW and OPECC3 in detail is required for increasing the qualities of HRA and PSA. Moreover, one of the difficulties in performing human reliability analysis is to evaluate performance shaping factors which represent the characteristics and circumstances. For assessing a specific human action more exactly, it is necessary to consider all of the PSFs at the same time which makes an effect on the human action. Also, it requires the effect comparison among PSFs to minimize the uncertainties which are usually caused by the subjective judgements of HRA analysts. To see the sensitivity, performance shaping factors of each decision rule are changed which resulted in changes of core damage

  17. Korean experience in CANDU-PHWR operation

    International Nuclear Information System (INIS)

    Sang-kee Park

    1987-01-01

    Among KEPCO's 9 nuclear power units, Korea Nuclear Unit No. 3, the Wolsung Nuclear Power Plant is the only CANDU-PHWR Unit, while the rest of 8 others are PWR units. The unit was designed by Atomic Energy of Canada, Ltd(AECL) of Canada, who also perfomed overall project management for the plant construction under the provisions and arrangement of the relevant contracts. The gross electrical output of the plant is 678.7 MWe and thermal output of the reactor is 2061 MWth. While these figures lead to lower plant eficiency than LWR counterparts, unit energy cost for fuel is more favorable than LWRs because natural uranium is utilized for the fuel bundles, some of which are already being fabricated domestically. Annual capacity factors for 1983 and 1984 could have been improved, if two major planned outages for the modification works on steam generator internals and one major forced outage form the heavy water spill incident could be eliminated. The heavy water spill incident in November, 1984 brought plant staffs many lessons to learn and many things to contemplate. Unique design concepts and features such as on-power refuelling, poison prevent mode, versatile plant control system built around digital computers and power step back/set back logics may be credited for these relatively good plant performances. Human related factors such as staff's technical capabilities and strong will toward good performance were other elements which could not be overlooked

  18. Analysis of a PHWR slightly enriched fuel

    International Nuclear Information System (INIS)

    Notari, C.; Marajofsky, A.

    1994-01-01

    It is widely known that the use of slightly enriched uranium in PHWR reactors presents economic advantages derived from the fact that less uranium is required for producing the same amount of energy. Several studies related with the use of this alternative in Atucha I NPP have been performed. The fuel assembly geometry considered up to now has been almost identical to the natural uranium one. In this work a modification consisting in the use of annular pellets in the outer ring of the cluster is analyzed. This design produces several performance benefits. The redistribution of the power in the fuel improves the maximum to average bundle power ratio. The improvement achieved depends on the void volume in the pellets which at the same time represents a certain burnup decrease. These parameters (power ratios and burnup loss) are quantified for the Atucha I and Embalse NPPs. This design improves the fuel behaviour with respect to the burnup extension derived from the slight enrichment. It is also interesting in case an overall power increase is considered. (author). 16 refs, 8 figs, 1 tab

  19. Korean experience in CANDU-PHWR operation

    International Nuclear Information System (INIS)

    Park, S.K.

    1988-01-01

    Among KEPCO's 9 nuclear power units, Korea Nuclear Unit No. 3, the Wolsung Nuclear Power Plant is the only CANDU-PHWR Unit, while the rest of 8 others are PWR units. The unit was designed by Atomic Energy of Canada, Ltd. of Canada, who also performed overall project management for the plant construction under the provisions and arrangement of the relevant contracts. The gross electrical output of the plant is 678.7 MWe and thermal output of the reactor is 2061 MWth. While these figures lead to lower plant efficiency than LWR counterparts, unit energy cost for fuel is more favorable than LWRs because natural uranium is utilized for the fuel bundles, some of which are already being fabricated domestically. Annual capacity factors for 1983 and 1984 could have been improved, if two major planned outages for the modification works on steam generator internals and one major forced outage from the heavy water spill incident could be eliminated. The heavy water spill incident in November, 1984 brought plant staffs many lessons to learn and many things to contemplate. Unique design concepts and features such as on-power refuelling, poison prevent mode, versatile plant control system built around digital computers and power step back/set back logics may be credited for these relatively good plant performances. Human related factors such as staff's technical capabilities and strong will toward good performance were other elements which could not be overlooked

  20. Material and fabrication considerations for the CANDU-PHWR heat transport system

    International Nuclear Information System (INIS)

    Filipovic, A.; Price, E.G.; Barber, D.; Nickerson, J.

    1987-03-01

    CANDU PHWR nuclear systems have used carbon steel material for over 25 years. The accumulated operating experience of over 200 reactor years has proven this unique AECL approach to be both technically and economically attractive. This paper discusses design, material and fabrication considerations for out-reactor heat transport system major components. The contribution of this unique choice of materials and equipment to the outstanding CANDU performance is briefly covered

  1. Feasibility study on production of Co-60 in PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Park, Kyung Bae; Han, Hyon Soo; Joo, Po Kook

    2000-05-01

    The purpose of this study is to analyze the safeties and the economics for Co-60 production from Wolsung PHWR and to verify the feasibility on the manufacturing of the final Co-60 source for industrial irradiation. The feasibility of reactor conversion was carried out with KEPCO collaboration. Through the site survey on the experience of Gentililly-2 in Canada, a feasibility of plant conversion, changes in design, equipment and tools for Co-60 production was verified. It was estimated that the reactor conversion would not impose adverse impact on plant safety. For the encapsulation of radiation source and storage of the final products, a modification of concrete hot cell at KAERI was primary concerns. The installation and improvement of facilities are needed to avoid cross contamination and extra radiation exposure. Main items for these are pressure gauge, separated HEPA filter the ceiling separation, extra-shielding and ceiling hoist system. At present, storage pool has got admission based on 400 kCi. But it is necessary to seismic analysis and design improvement of shielding to store 10 MCi (Co-60) which is the estimated Co-60 capacity produced by 3 PHWRs. According to present investigation, a production of Co-60 by PHWR and RIPE was seemed to be an economically feasible business and it was also expected that a joint venture will be able to realize by cooperation with MDS Nordion Co.

  2. Feasibility study on production of Co-60 in PHWR

    International Nuclear Information System (INIS)

    Park, Kyung Bae; Han, Hyon Soo; Joo, Po Kook

    2000-05-01

    The purpose of this study is to analyze the safeties and the economics for Co-60 production from Wolsung PHWR and to verify the feasibility on the manufacturing of the final Co-60 source for industrial irradiation. The feasibility of reactor conversion was carried out with KEPCO collaboration. Through the site survey on the experience of Gentililly-2 in Canada, a feasibility of plant conversion, changes in design, equipment and tools for Co-60 production was verified. It was estimated that the reactor conversion would not impose adverse impact on plant safety. For the encapsulation of radiation source and storage of the final products, a modification of concrete hot cell at KAERI was primary concerns. The installation and improvement of facilities are needed to avoid cross contamination and extra radiation exposure. Main items for these are pressure gauge, separated HEPA filter the ceiling separation, extra-shielding and ceiling hoist system. At present, storage pool has got admission based on 400 kCi. But it is necessary to seismic analysis and design improvement of shielding to store 10 MCi (Co-60) which is the estimated Co-60 capacity produced by 3 PHWRs. According to present investigation, a production of Co-60 by PHWR and RIPE was seemed to be an economically feasible business and it was also expected that a joint venture will be able to realize by cooperation with MDS Nordion Co

  3. Self reliance in equipment building for PHWR fuel fabrication

    International Nuclear Information System (INIS)

    Sastry, V.S.; Hemantha Rao, G.V.S.; Jayaraj, R.N.

    2009-01-01

    Full text: Keeping in tune with the policy of self-reliance and indigenisation adopted from the very inception of nuclear power programme in India during the mid 1960, Nuclear Fuel Complex, established in the year 1971, developed its own processes, equipment and technologies based on both in-house experience and the expertise available in the indigenous industry. Starting from the basic raw materials, Nuclear Fuel Complex (NFC) manufactures and supplies finished fuel assemblies, apart from zircaloy core components, to all the nuclear power stations in India. Out of several products manufactured by NFC, 19 and 37 element fuel bundles for Pressurised Heavy Water Reactors (PHWRs) is vital for operation of several PHWRs being operated by Nuclear Power Corporation of India Limited (NPCIL). Starting from the manufacturing of half-charge for RAPS-1, more than 3.8 lakh fuel bundles were made till now. Several process improvements were taken up over the years for improving the quality of the fuel. PHWR fuel bundles manufactured by NFC has adopted an unique feature of joining appendages on zirconium alloy tubes by resistance welding before loading natural uranium dioxide pellets. Graphite coating on the inner surface of the zirconium alloy tube and vacuum baking, use of profiled end caps, use of bio-degradable cleaning agents are some of the processes adopted in the manufacturing of PHWR fuel bundles. With the recent opening up of international nuclear trade for India and the enhanced growth of nuclear power, exciting opportunities and challenges confront NFC. This paper presents salient features of some important special purpose equipment developed in-house at NFC for production of PHWR fuel bundles. It looks ahead to develop many more such special purpose equipment towards meeting the diverse demands now showing up to meet the indigenous as well as international requirements

  4. Use of artificial neural network in estimating channel power distribution of a 220 MWe PHWR

    International Nuclear Information System (INIS)

    Dubey, B.P.; Chandra, A.K.; Govindarajan, G.; Jagannathan, V.; Kataria, S.K.

    1998-01-01

    Knowledge of the distribution of power in all the 306 channels of a Pressurised Heavy Water Reactor (PHWR) as a result of the movement of one or more of the four regulating rods is important from the operation and maintenance point view of the reactor. Conventional computer codes available for this purpose take several minutes to calculate the channel power distribution on PC-AT/486. An Artificial Neural network (ANN), based on the RPROP algorithm has been developed and employed in predicting channel power distribution of a 220 MWe Indian PHWR as a result of a perturbation caused by the movement of one or more of the four regulating rods of the reactor. The ANN based system produces the result of an analysis much faster than that produced by a conventional computer code usually employed for this application. The ANN based system is rugged, accurate and fast, and therefore, has potential to be used in real-time applications. (author)

  5. Integrated probabilistic assessment for DHC initiation, growth and leak-before-break of PHWR pressure tubes

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Young-Jin [Power Engineering Research Institute, KEPCO Engineering and Construction, 188 Gumi-dong, Bundang-gu, Seongnam-si, Gyeonggi-do 463-870 (Korea, Republic of); Chang, Yoon-Suk, E-mail: yschang@khu.ac.kr [Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 446-701 (Korea, Republic of)

    2014-08-15

    Highlights: • We develop an integrated approach for probabilistic assessment of PHWR pressure tube. • We examine probabilities of DHC initiation, growth, penetration and LBB failure. • The proposed approach is helpful to calculate rupture probabilities in reactor flaws even in the case of very low rupture probability. - Abstract: A few hundred zirconium alloy pressure tubes in a pressurized heavy water reactor (PHWR) serve as the nuclear fuel channel, as well as the reactor coolant pressure boundary. The pressure tubes are inspected periodically and a fitness-for-service assessment (FFSA) must be conducted if any flaw is detected in the inspection. A Canadian standard provides FFSA procedures of PHWR pressure tubes, which include probabilistic assessment for flaws considering delayed hydride cracking (DHC) and leak-before-break (LBB). In the present study, an integrated approach with detailed stepwise calculation procedures and integration methodology for probabilistic assessment of pressure tube was developed. In the first step of this approach, a probability of the DHC initiation, growth and penetration for single initial flaw is calculated. In the next step, a probability of LBB failure, which means tube rupture, for single through-wall crack (TWC) is calculated. Finally, a rupture probability for all initial flaws in a reactor can be calculated using the penetration probability for single flaw and the LBB failure probability for single TWC, as well as the predicted total number of initial flaw in the reactor.

  6. Integrated probabilistic assessment for DHC initiation, growth and leak-before-break of PHWR pressure tubes

    International Nuclear Information System (INIS)

    Oh, Young-Jin; Chang, Yoon-Suk

    2014-01-01

    Highlights: • We develop an integrated approach for probabilistic assessment of PHWR pressure tube. • We examine probabilities of DHC initiation, growth, penetration and LBB failure. • The proposed approach is helpful to calculate rupture probabilities in reactor flaws even in the case of very low rupture probability. - Abstract: A few hundred zirconium alloy pressure tubes in a pressurized heavy water reactor (PHWR) serve as the nuclear fuel channel, as well as the reactor coolant pressure boundary. The pressure tubes are inspected periodically and a fitness-for-service assessment (FFSA) must be conducted if any flaw is detected in the inspection. A Canadian standard provides FFSA procedures of PHWR pressure tubes, which include probabilistic assessment for flaws considering delayed hydride cracking (DHC) and leak-before-break (LBB). In the present study, an integrated approach with detailed stepwise calculation procedures and integration methodology for probabilistic assessment of pressure tube was developed. In the first step of this approach, a probability of the DHC initiation, growth and penetration for single initial flaw is calculated. In the next step, a probability of LBB failure, which means tube rupture, for single through-wall crack (TWC) is calculated. Finally, a rupture probability for all initial flaws in a reactor can be calculated using the penetration probability for single flaw and the LBB failure probability for single TWC, as well as the predicted total number of initial flaw in the reactor

  7. Production of gadolinium nitrate for TAPS 3 and 4 PHWR

    International Nuclear Information System (INIS)

    Mishra, S.L.; Ramakrishnan, P.; Iyer, N.S.; Singh, Harvinderpal

    2004-01-01

    In India, gadolinium nitrate is being used for the first time in PHWR at Tarapur. Gadolinium is preferred over boron due to high neutron cross section and the water soluble nitrate form works efficiently for reactivity control through moderator liquid poison addition system (MLPS) as well as for reactor shut down system (SDS2). Low concentration of gadolinium (0.1-0.2 g/l) in heavy water is sufficient to shut down the reactor in a very short time. After use, the small amount of gadolinium can be separated quickly from heavy water by ion exchange process. In this paper separation of Gd using of 2-ethyl hexyl phosphoric acid mono 2-ethyl hexyl ester EHEHPA as an extractant has been described

  8. Computation and measurement of calandria tube sag in PHWR

    International Nuclear Information System (INIS)

    Kim, Tae Ryong; Sohn, Seok Man

    2003-01-01

    Calandria tubes and liquid injection shutdown system (LISS) tubes in a pressurized heavy water reactor (PHWR) is known to sag due to irradiation creep and growth during plant operation. When the sag of calandria tube becomes bigger, the calandria tube possibly comes in contact with LISS tube crossing beneath and calandria tube. The contact subsequently may cause the damage on the calandria tube resulting in unpredicted outage of the plant. It is therefore necessary to check the gap between the two tubes in order to periodically confirm no contact by using a proper measure during the plant life. An ultrasonic gap measuring probe assembly which can be inserted into two viewing ports of the calandria was developed in Korea and utilized to measure the sags of both tubes in the PHWR. It was found that the centerlines of calandria tubes and liquid injection shutdown system tubes can be precisely detected by ultrasonic wave. The gaps between two tubes were easily obtained from the relative distance of the measured centerline elevations of the tubes. Based on the irradiation creep equation and the measurement data, a computer program to calculate the sags was also developed. With the computer program, the sag at the end of plant life was predicted. (author)

  9. The Ontario Hydro approach to assuring quality in nuclear heat exchanger tubing

    International Nuclear Information System (INIS)

    Maka, E.P.

    1982-01-01

    Ontario Hydro utilizes the CANDU PHWR reactor system. The heat transport system circulates pressurized heavy water through the reactor fuel channels to remove heat produced by the fission of uranium fuel. Heavy water is used for the heat transport medium because it is the most efficient liquid from the standpoint of neutron economy. The heat is carried by the reactor coolant to the steam generators where it is transferred to the light water side to form steam which drives the turbine generators. Many heat exchangers are incorporated in the heat transfer cycle. Their integrity is of prime importance both for the reliability of the power plant and for economic reasons since the loss of heavy water at $300/kg is a substantial penalty. This integrity depends largely on the quality of the heat exchanger tubing and where major heat exchangers are involved, it has been the Ontario Hydro policy to supply tubing to heat exchanger manufacturers on a ''free issue'' basis. This allows better control over the level of inspection perform

  10. Fission-product releases from a PHWR terminal debris bed

    Energy Technology Data Exchange (ETDEWEB)

    Brown, M.J.; Bailey, D.G., E-mail: morgan.brown@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

    2016-06-15

    During an unmitigated severe accident in a pressurized heavy water reactor (PHWR) with horizontal fuel channels, the core may disassemble and relocate to the bottom of the calandria vessel. The resulting heterogeneous in-vessel terminal debris bed (TDB) would likely be quenched by any remaining moderator, and some of the decay heat would be conducted through the calandria vessel shell to the surrounding reactor vault or shield tank water. As the moderator boiled off, the solid debris bed would transform into a more homogeneous molten corium pool located between top and bottom crusts. Until recently, the severe accident code MAAP-CANDU assumed that unreleased volatile and semi-volatile fission products remained in the TDB until after calandria vessel failure, due to low diffusivity through the top crust and the lack of gases or steam to flush released fission products from the debris. However, national and international experimental results indicate this assumption is unlikely; instead, high- and medium-volatility fission products would be released from a molten debris pool, and their volatility and transport should be taken into account in TDB modelling. The resulting change in the distribution of fission products within the reactor and containment, and the associated decay heat, can have significant effects upon the progression of the accident and fission-product releases to the environment. This article describes a postulated PHWR severe accident progression to generate a TDB and the effects of fission-product releases from the terminal debris, using the simple release model in the MAAP-CANDU severe accident code. It also provides insights from various experimental programs related to fission-product releases from core debris, and their applicability to the MAAP-CANDU TDB model. (author)

  11. Use of gadolinium as neutron poison in 540 MWe PHWR

    International Nuclear Information System (INIS)

    Nag, P.K.; Fernando, M.P.S.; Kumar, A.N.

    2006-01-01

    In Pressurised heavy water reactors (PHWRs), neutron poison in the moderator is used to compensate the excess reactivity present in the core on different occasions such as xenon decay during synchronization just after poison out period or start ups from xenon free conditions. It is also used in secondary shutdown system (SDS-2), where required amount of neutron poison is injected directly into the moderator within 2.5 seconds. Further, it is also used for over poisoning the moderator to achieve the guaranteed shutdown state when the regular shutdown systems are taken for maintenance. Generally, two types of moderator poisons are used in power reactors to balance the reactivity of the core and they are boron and gadolinium. Gadolinium is used in the form of gadolinium nitrate (Gd(NO 3 ) 3 .6H 2 O). The paper gives the details of estimation of reactivity coefficients of gadolinium for 540 MWe PHWR for different operating conditions. These neutron poisons are converted into non-absorbing elements and therefore their effective worth will decrease as reactor operation proceeds. The rate of burning of neutron absorbing isotopes depends on its magnitude of absorption cross-section and thermal flux seen by them. The present study discusses the burning characteristics of gadolinium during power operation in 540 MWe PHWR. It is established by detailed analysis that the rate of positive reactivity realized due to burning of neutron absorbing Gd isotopes almost match with the build up rate of xenon. The burning half lives of boron and gadolinium is worked out for different power levels. (author)

  12. The safety of Ontario's nuclear power reactors. A scientific and technical review. Vol. 2: Appendices

    International Nuclear Information System (INIS)

    Hare, F.K.

    1988-01-01

    These appendices contain seven detailed elaborations of matters covered more superficially in the Technical Report. They have been written by well-known authorities, or by the professional staff of the Review. They are essential supplements to the condensed material of the Technical Report. Several of the appendices contain detailed recommendations. Some of these have been incorporated into the Review's overall conclusions and recommendations. Others stand alone, as the opinions of the appendices' authors. I am in broad agreement with most of them, but have preferred to leave them within the authors' material. I hope that they will be given detailed study by appropriate bodies, especially Ontario Hydro and the Atomic Energy Control Board

  13. Flux mapping algorithm (FMA) for 700 MWe PHWR

    International Nuclear Information System (INIS)

    Sonavani, Manoj; Ingle, V.J.; Singhvi, P.K.; Raj, Manish; Fernando, M.P.S.; Kumar, A.N.

    2012-01-01

    For large reactor like 700 MWe PHWR effective spatial control is essential and is provided by RRS. For spatial control purpose reactor core is divided into 14 power zones. Corresponding to each zone is a light water zonal compartment. The 14 ZCCs are located in two radial planes, each containing 7 ZCCs. For each zone, power measurement is carried out using inconel (3 pitch long) self powered neutron detector (SPND) at appropriate location close to the respective ZCC. Since the zone power as obtained by the healthy zone control detector (ZCD) reading belonging to a particular zone may not correspond to its actual power because the detector per zone, measure only average fluxes but the zone extends over a large core region. Therefore accurate estimation of zone power calibration factors is required to estimate the zone powers and also to provide effective spatial power control to avoid the xenon induced spatial power oscillations in large PHWRs like 700 and 540 MWe Reactors. This accurate calculation of zone power is carried out by FMS which uses λ modes in its algorithm. Flux at any point inside the reactor can be represented in terms of the linear combination of these modes. Coefficients used in the expansion are called combining coefficient. If the readings of the detectors are known, then combining coefficients can be estimated by simple matrix operations. Once these combining coefficients are known, flux at any point inside the reactor can be found. (author)

  14. Emerging trends in PHWR safety - post Fukushima measures

    International Nuclear Information System (INIS)

    Nitheanandan, T.

    2015-01-01

    Nuclear power continues to be the choice for many countries that are seeking to enhance their energy security and reduce their carbon emissions. Nuclear power plants are complex systems which require multiple layers of protection. The fundamental principle of nuclear power safety technology is ‘Defence-in-Depth’ that underlies all safety activities - organizational, behavioural and technical. This provides layers of overlapping barrier protections so that, in the unlikely event that failure occurs, it would be compensated or corrected without causing harm to individuals or the public at large. Defence-in-depth encompasses prevention, control, protection, severe accident management and consequence mitigation, and offsite emergency response measures. Reactor Safety Science and Technology (S and T) has evolved over more than four decades in a number of PHWR countries. The PHWR operators, regulators and national research laboratories have dedicated S and T programs to continuously improve plant safety, operations and margins. The S and T is focused on finding simpler, less costly and more reliable safety system designs. These improvements are continuously incorporated in current units, refurbished units and proposed new builds. The Fukushima accident forced most nuclear nations to reassess and implement reactor design upgrades. The lessons learned from Fukushima have generated some nuclear safety enhancements such as: Design considerations for natural hazards, Diversity of heat sinks, Consideration of extended duration station blackout, Improvements to Severe Accident Management and SAM Operational aids, Accident instrumentation, Offsite management such as the use of predictive exposure tools, and Design considerations for Spent Fuel Pools. The plenary presentation will provide some of the emerging trends following the Fukushima accident. Examples of these emerging trends in Canada and on the international scene, will be presented. (author)

  15. Fatigue cycles evaluation of 500 MWe PHWR coolant channel sealdisc

    International Nuclear Information System (INIS)

    Chawla, D.S.; Vaze, K.K.; Kushwaha, H.S.; Gupta, K.S.; Bhambra, H.S.

    1998-07-01

    At each end of coolant channel there is one sealing plug assembly. The sealdisc is a part of sealing plug assembly. The sealdisc is used to avoid leakage of heavy water. The importance of sealdisc can be understood by the fact that there are 784 sealdiscs in one 500 MWe PHWR unit. During the life time of reactor the sealdisc will be subjected to cyclic loads due to reactor startup, shutdown, power setback and also due to refuelling operations. Excessive reversal of stresses may lead to fatigue failure. The sealdisc failure may cause loss of coolant accidents. Since sealdisc is safety class 1 component, it has to be qualified according to ASME Section III Division 1 NB. For cyclic loads, the fatigue analysis is essential to assess the allowable number of cycles and also to check the total usage factor due to different cyclic loads. To evaluate the allowable fatigue cycles, the analysis is carried out using finite element method. The present report deals with the fatigue cycles evaluation of 500 MWe PHWR sealdisc. The finite element model having eight noded axisymmetric elements is used for the analysis. The various loads considered in the analysis are mechanical loads arising due to refuelling operations and number of temperature-pressure transients. During refuelling, the sealdisc is removed and reinstalled back by use of fuelling machine ram which applies load at centre as well as at rocker point of sealdisc. The stress analysis is carried out for each stage of loading during refuelling and fatigue cycles are evaluated. For temperature transient, decoupled thermal analysis is carried out. At various instants of time, the stresses are computed using temperatures calculated in thermal analysis. The pressure variation is also considered along with temperature variation. The fatigue cycles are evaluated for each transient using maximum alternating stress intensities. The usage factors are calculated for various temperature/pressure transients and refuelling loads

  16. Process improvements for enhanced productivity of PHWR garter springs

    International Nuclear Information System (INIS)

    Srinivasula Reddy, S.; Tonpe, Sunil; Saibaba, N.; Jayaraj, R.N.

    2009-01-01

    Full text: In Pressurised Heavy Water Reactors (PHWR), Garter springs are used as spacers between the coolant tube and calandria tube. Garter springs are made from Zirconium alloy containing 2.5 % Niobium and 0.5% copper. The springs are basically manufactured by coiling a wire of cross section 1.7 mm x 1.0 mm, which is produced by series of drawing and swaging operations using hot extruded rods of 19 mm diameter. The manufacturing process also involves heat treatment and chemical cleaning operations at appropriate stages. It is required to ensure that the life of springs against parameters like hydrogen pickup, residual stresses and low stiffness is improved at the manufacturing stage itself by improving manufacturing process. The impact of above problems on spring life and process improvements is briefly discussed. The critical factor affecting the garter spring performance in PHWR Reactor is mainly hydrogen. The life limiting factors for garter springs are the problems arising out of high total hydrogen content, which depends on the hydrogen pickup during reactor operation. This phenomenon can happen during the reactor operation, as springs are prone to pick-up hydrogen in the reactor environment. Hence acceptable hydrogen content for the springs is specified as 25 ppm (max.). Garter spring is susceptible to hydrogen pick-up during various production processes, which make material brittle and difficult for fabrication process such as wire drawing and coiling. By studying and optimizing the process parameters of spring manufacturing, the hydrogen pick-up of springs is brought down from 70 ppm to a level of 20 ppm. Garter springs are provided with a hook at each end to enable its assembly to coolant tube in the reactor. The hook portion is very critical in maintaining the integrity of the spring. It is desirable to have the hook portion relieved of all residual stresses. For this purpose manufacturing process has been modified and solutionising was introduced as

  17. Conceptual design of a large heavy water reactor for US siting

    International Nuclear Information System (INIS)

    Shapiro, N.L.; Jesick, J.F.; Molin, A.T.; Daniel, J.A.

    1979-09-01

    Information on the PHWR type reactor is presented concerning design characteristics; fuel management and resource utilization; economic evaluations; safety, licensing, and environmental impact; and commercial introduction

  18. Modelling of activity transport in PHWR

    International Nuclear Information System (INIS)

    Veena, S.N.; Rangarajan, S.; Narasimhan, S.V.; Horvath, G.L.

    2000-01-01

    The modelling of mass and activity transport in PHWR is of importance in predicting the build up of radiation field in and around the Primary Heat Transport system which will consequently help in planning the Dilute Chemical Decontamination and man rem budgeting. Modeling also helps in understanding the different parameters controlling the transport behaviour. Some of the important parameters include coolant chemistry like pH, physical parameters like temperature, the nature of the corrosion film and hence the effect of passivation techniques. VVER code for activity transport uses six nodes for the primary system and is essentially devised for stainless steel system. In the present work though based on this model, major modifications have been incorporated to suit the PHWR conditions. In the code, the PHT system of PHWR is suitably divided into 14 nodes, 5 in-core and 9 out of core nodes based on material and heat transfer properties. This paper describes the mechanisms involved in the various processes like generation of corrosion products, their release as well as their transport into the primary coolant, the activation of inactive corrosion product nuclides and the build up of radiation field due to 60 Co around the PHT system. (author)

  19. An integrated approach for safer, productive and reliable PHWR fuel manufacturing at NFC

    International Nuclear Information System (INIS)

    Saibaba, N.

    2013-01-01

    India has been pursuing three-stage nuclear power programme and has developed comprehensive capabilities in all aspects of nuclear power and fuel cycle and is now recognized as a country with advanced nuclear technologies in the comity of nations. The first stage of Pressurized Heavy Water Reactors (PHWRs) based on natural uranium has reached a state of maturity. In view of civilian nuclear safeguards agreement with NSG and IAEA, Nuclear Power Reactors in India and associated fuel manufacturing facilities at Nuclear Fuel Complex (NFC) are grouped into IAEA safeguarded and out-of-safeguarded facilities. The civilian nuclear energy generation has to be accelerated for achieving energy security for the country. NFC has pioneered manufacturing technologies of UO 2 fuel, fuel clad and structural components for the PHWRs 220, 540 and PHWR700. Nearly 20 GWe of nuclear energy generation is being planned through PHWR route. Several technological improvements that were carried out recently in the production lines are the key to achieve higher productivity and safety. NFC has also been pursuing capacity augmentation by adding newer equipment in the existing facility and setting up new plants both for uranium production as well as zirconium production. Flexible manufacturing systems consisting of automatic workstations and robots were introduced in the 19 and 37 element PHWR fuel assembly lines. Various safety measures were introduced right from design stage for improving radiological safety for workmen. State-of-art equipment were designed, developed and commissioned for reduction/elimination of fatigue-oriented operations. In addition to natural uranium oxide fuel, NFC has also successfully manufactured virgin slightly enriched uranium (SEU) fuel and reprocessed depleted uranium fuels which were irradiated in the operating PHWRs. The paper brings out NFC's role in Indian nuclear power program and its manufacturing capabilities for types of PHWR fuel, zircaloy structural

  20. Safety analysis procedures for PHWR

    International Nuclear Information System (INIS)

    Min, Byung Joo; Kim, Hyoung Tae; Yoo, Kun Joong

    2004-03-01

    The methodology of safety analyses for CANDU reactors in Canada, a vendor country, uses a combination of best-estimate physical models and conservative input parameters so as to minimize the uncertainty of the plant behavior predictions. As using the conservative input parameters, the results of the safety analyses are assured the regulatory requirements such as the public dose, the integrity of fuel and fuel channel, the integrity of containment and reactor structures, etc. However, there is not the comprehensive and systematic procedures for safety analyses for CANDU reactors in Korea. In this regard, the development of the safety analyses procedures for CANDU reactors is being conducted not only to establish the safety analyses system, but also to enhance the quality assurance of the safety assessment. In the first phase of this study, the general procedures of the deterministic safety analyses are developed. The general safety procedures are covered the specification of the initial event, selection of the methodology and accident sequences, computer codes, safety analysis procedures, verification of errors and uncertainties, etc. Finally, These general procedures of the safety analyses are applied to the Large Break Loss Of Coolant Accident (LBLOCA) in Final Safety Analysis Report (FSAR) for Wolsong units 2, 3, 4

  1. Evolution of Flux Mapping System (FMS) from 540 MWe to 700 MWe Indian PHWR: design perspective

    International Nuclear Information System (INIS)

    Sonavani, Manojkumar; Kelkar, M.G.; Singhvi, P.K.; Roy, S.; Ingle, V.J.

    2013-01-01

    The Flux Mapping System (FMS) of 700 MWe PHWR computes a detailed flux/power distribution of the reactor core using modal synthesis method and is also generate setback on different parameters by monitoring thermal neutron flux at more than 100 points inside the reactor core. These types of setbacks are introduced first time in Indian PHWRs. The paper brings out the Evolution of Flux Mapping System (FMS) from 540 MWe to 700 MWe and the overall design philosophy. The paper emphasizes on comparisons between 540 MWe and 700 MWe design, considerations for architectural design and setbacks for 700 MWe. (author)

  2. Development and Application of MCNP5 and KENO-VI Monte Carlo Models for the Atucha-2 PHWR Analysis

    Directory of Open Access Journals (Sweden)

    M. Pecchia

    2011-01-01

    Full Text Available The geometrical complexity and the peculiarities of Atucha-2 PHWR require the adoption of advanced Monte Carlo codes for performing realistic neutronic simulations. Core models of Atucha-2 PHWR were developed using both MCNP5 and KENO-VI codes. The developed models were applied for calculating reactor criticality states at beginning of life, reactor cell constants, and control rods volumes. The last two applications were relevant for performing successive three dimensional neutron kinetic analyses since it was necessary to correctly evaluate the effect of each oblique control rod in each cell discretizing the reactor. These corrective factors were then applied to the cell cross sections calculated by the two-dimensional deterministic lattice physics code HELIOS. These results were implemented in the RELAP-3D model to perform safety analyses for the licensing process.

  3. Study to use graded cobalt adjuster in 540 MWe PHWR

    International Nuclear Information System (INIS)

    Raj, Manish; Fernando, M.P.S.; Pradhan, A.S.; Kumar, A.N.

    2007-01-01

    Full text: There are 17 adjusters in 540 MWe PHWR, which are essentially provided for xenon override function. They also provide flux flattening being in the central region of the reactor core. The present design of adjusters consists of stainless steel tube. The adjuster rods are grouped into 8 banks for movement. Since adjusters are normally fully inserted during reactor operation, they are best suited for production of cobalt 60. The nickel-plated cobalt in the form of either slugs or pellet are used for the design of cobalt pencils. The number of pencils can be varied to optimize the reactivity load and cobalt 60 production requirement. The worth and activity of cobalt adjusters have been worked out considering different pin configuration for the adjuster assembly. To start with we have assumed all adjusters throughout its length are of the same configuration. The flux depression factors within the cobalt pencils have been considered in the estimations of the specific and total cobalt 60 activities. The option of using graded cobalt adjusters, where different pin configuration along the length is considered for better flux flattening

  4. Investigations on the inadvertent power increase in a PHWR as ASSET experience

    International Nuclear Information System (INIS)

    Kumar, S.H.

    1996-01-01

    Investigations were carried out using the ASSET methodology to find out the root cause of an incident involving inadvertent increase in reactor power in the Unit 1 of Narora Atomic Power Station (NAPS) in India. NAPS is a twin Unit, 220 MWe PHWR based power station. On December 4, 1992, when NPAS Unit 1 was operating at 130 MWe, the reactor power increased steadily on its own and touched 147 MWe, over a period of 14 minutes. The set (demand) power of the triplicated reactor regulating system had increased on its own and in turn has made the reactor to operated at higher power. The power was brought down to 120 MWe by manual intervention. Since adequate system related data during the incident was not available, laboratory studies were carried out using computer simulations for the various process disturbances which could affect the reactor regulating system, for establishing the causes of the event. 4 figs

  5. Investigations on the inadvertent power increase in a PHWR as ASSET experience

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, S H [Operating Plants Safety Div., Atomic Energy Regulatory Board, Mumbai (India)

    1997-12-31

    Investigations were carried out using the ASSET methodology to find out the root cause of an incident involving inadvertent increase in reactor power in the Unit 1 of Narora Atomic Power Station (NAPS) in India. NAPS is a twin Unit, 220 MWe PHWR based power station. On December 4, 1992, when NPAS Unit 1 was operating at 130 MWe, the reactor power increased steadily on its own and touched 147 MWe, over a period of 14 minutes. The set (demand) power of the triplicated reactor regulating system had increased on its own and in turn has made the reactor to operated at higher power. The power was brought down to 120 MWe by manual intervention. Since adequate system related data during the incident was not available, laboratory studies were carried out using computer simulations for the various process disturbances which could affect the reactor regulating system, for establishing the causes of the event. 4 figs.

  6. Absorber materials in CANDU PHWR's

    International Nuclear Information System (INIS)

    Price, E.G.; Boss, C.R.; Novak, W.Z.; Fong, R.W.L.

    1995-03-01

    In a CANDU reactor the fuel channels are arranged on a square lattice in a calandria filled with heavy water moderator. This arrangement allows five types of tubular neutron absorber devices to be located in a relatively benign environment of low pressure, low temperature heavy water between neighbouring rows of columns of fuel channels. This paper will describe the roles of the devices and outline the design requirements of the absorber component from a reactor physics viewpoint. Nuclear heating and activation problems associated with the different absorbers will be briefly discussed. The design and manufacture of the devices will be also discussed. The control rod absorbers and shut off materials are cadmium and stainless steel. In the tubular arrangement, the cadmium is sandwiched between stainless steel tubes. This type of device has functioned well, but there is now concern over the availability and expense of cadmium which is used in two types of CANDU control devices. There are also concerns about the toxicity of cadmium during the fabrication of the absorbers. These concerns are prompting AECL to study alternatives. To minimize design changes, pure boron-10 alloyed in stainless steel is a favoured option. Work is underway to confirm the suitability of the boron-loaded steel and identify other encapsulated absorber materials for practical application. Because the reactivity devices or their guide tubes span the calandria vessel, the long slender components must be sufficiently rigid to resist operational vibration and also be seismically stable. Some of these components are made of Zircaloy to minimize neutron absorption. Slow irradiation growth and creep can reduce the spring tension, and periodic adjustments to the springs are required. Experience with the control absorber devices has generally been good. In one instance liquid zone controllers had a problem of vibration induced fretting but a designed back-fit resolved the problem. (author). 3 refs., 1

  7. Water treatment for 500 MWe PHWR plants

    International Nuclear Information System (INIS)

    Vasist, Sudheer; Sharma, M.C.; Agarwal, N.K.

    1995-01-01

    Large quantities of treated water is required for power generation. For a typical 500 MWe PHWR inland station with cooling towers, raw water at the rate of 6000 m 3 /hr is required. Impurities in cooling water give rise to the problems of corrosion, scaling, microbiological contamination, fouling, silical deposition etc. These problems lead to increased maintenance cost, reduced heat transfer efficiency, and possible production cut backs or shutdowns. The problems in coastal based power plants are more serious because of the highly corrosive nature of sea water used for cooling. An overview of the cooling water systems and water treatment method is enumerated. (author). 2 refs., 1 fig

  8. The safety of Ontario's nuclear power reactors. A scientific and technical review. A submission to the Ontario Nuclear Safety Review by Atomic Energy Canada Limited

    International Nuclear Information System (INIS)

    1987-01-01

    This submission comments on the evolution of the Canadian nuclear program, the management of safety, and the reactor design, analysis, operation and research programs that contribute to the safety of the CANDU reactor and provide assurance of safety to the regulatory agency and to the public. The CANDU reactor system has been designed and developed with close cooperation between Atomic Energy of Canada Ltd. (AECL), utilities, manufacturers, and the Atomic Energy Control Board (AECB). The AECB has the responsibility, on behalf of the public, for establishing acceptable standards with respect to public risk and for establishing through independent review that these standards are satisfied. The plant designer has responsibility for defining how those standards will be met. The plant operator has responsibility for operating within the framework of those standards. The Canadian approach to safety design is based on the philosophy of defence in depth. Defence in depth is achieved through a high level of equipment quality, system redundancy and fail-safe design; regulating and process systems designed to maintain all process systems within acceptable operating parameters; and, independent safety systems to shut down the reactor, provide long-term cooling, and contain potential release of radioactivity in the event of an accident. The resulting design meets regulatory requirements not only in Canada but also in other countries. Probabilistic safety and risk evaluations show that the CANDU design offers a level of safety and least as good as other commercially available reactor designs

  9. Introduction of developing a list of MSO generic scenarios for PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Wan; Park, Jun Hyun; Bae, Hui Soo [STANDARD Testing and Engineering Ing. Ltd, Daejeon (Korea, Republic of)

    2016-10-15

    Multiple Spurious Operation(MSO) scenarios should contain scenarios threatening Post-fire safe shutdown function by MSO of Safe Shutdown Equipments(SSEs) as well as Non-SSEs. The list of MSO generic scenarios(NEI 00-01, Appendix G) was developed by industrial survey. Although not all scenarios of the list of MSO generic scenarios(NEI 00-01, Appendix G) are considered applicable to every reactor type, this list provides an input about MSO identification and treatment process. If NEI 00-01 is applied to other reactor type, analyst should review applicability of the list of generic scenarios(NEI 00-01, Appendix G) and consider potential MSO scenarios undescribed in the list of MSO generic scenarios(NEI 00-01, Appendix G). Especially, in PHWR case, there is no list of MSO generic scenarios in Canada or internationally. There are substantial physical variations between NPPs. So some generic scenarios(NEI 00-01, Appendix G) would need validation. Nevertheless, industrial stakeholder have not did any MSO work until now. In this paper, results of first stage research that develop the list of MSO generic scenarios for pressurized heavy water reactor(PHWR) is introduced. According to the review results, specific review of the list of MSO generic scenarios(NEI 00-01, Appendix G) is required such as how it applies to PHWR. And criteria was established for review of availability of the list of generic scenarios(NEI 00-01, Appendix G). However there are still many tasks such as potential scenario review, risk model review and expert panel review.

  10. Safety margin improvement by adopting the feature of interleaving in 700 MWe PHWR

    International Nuclear Information System (INIS)

    Kumar, Nrependra; Yadav, S.K.; Khan, T.A.; Dixit, A.; Singhal, Mukesh; Nair, Suma R.

    2015-01-01

    Indian Pressurised Heavy Water Reactors (IPHWRs) of 700 MWe are under construction at Kakrapar Atomic Power Project -3,4 and Rajasthan Atomic Power Project-7,8. These units have enhanced safety features with respect to standard IPHWRs. One of the enhanced features is interleaving of feeders/channels. In interleaved feeder configuration, each header located at either end of reactor gets connected to one quarter of core channels, which are uniformly distributed. The core is divided into two loops with feeder connected in interleaved fashioned. In this paper a comparative study has been performed between the two cases: 1) The core splits in two vertical halves and each vertical half is a loop of PHT (TAPS-3 and 4 Type configuration). 2) The core is divided into two loops with feeders/ channels connected in interleaved fashioned (700 MWe Configuration). LOCA studies have been performed for 700 MWe PHWR considering interleaving of feeders configuration using in-house developed computer code ATMIKA and 3-D neutron kinetics code IQS-3D. The issue of interleaving is closely linked to an inherent reactivity characteristic of PHWR reactors (viz., positive void reactivity coefficient) which leads to a power increase following a Large LOCA. In 700 MWe PHWR with intent to improve the safety margin, adopted the feature of interleaving of feeders which causes in reduction in the magnitude of void coefficient and results in reduction of peak power during LBLOCA. The systematic LBLOCA study demonstrates that interleaved configuration of feeder/channels of two loops has higher safety margins (i.e. with respect to peak power, prompt-criticality margin, adiabatic heat deposition on the fuel pins, sheath temperature excursion and clad oxidation) with regard to the effectiveness of shutdown system. (author)

  11. Quick and reliable estimation of power distribution in a PHWR by ANN

    International Nuclear Information System (INIS)

    Dubey, B.P.; Jagannathan, V.; Kataria, S.K.

    1998-01-01

    Knowledge of the distribution of power in all the channels of a Pressurised Heavy Water Reactor (PHWR) as a result of a perturbation caused by one or more of the regulating devices is very important from the operation and maintenance point of view of the reactor. Theoretical design codes available for this purpose take several minutes to calculate the channel power distribution on modern PCs. Artificial Neural networks (ANNs) have been employed in predicting channel power distribution of Indian PHWRs for any given configuration of regulating devices of the reactor. ANNs produce the result much faster and with good accuracy. This paper describes the methodology of ANN, its reliability, the validation range, and scope for its possible on-line use in the actual reactor

  12. An infrared technique for on-line detection of orientation of PHWR fuel pellets

    Energy Technology Data Exchange (ETDEWEB)

    Behere, P G [Bhabha Atomic Research Centre, Tarapur (India). Advanced Fuel Fabrication Facility

    1994-12-31

    The PHWR (Pressurised Heavy Water Reactor) fuel pellets fabricated in a fuel fabrication plant are cylindrical in shape and after sintering acquire a nominal size of 14.3 mm diameter and 17 mm height. These pellets have dish at one end while the other end is flat. The dish is provided to accommodate fission gases and thermal expansion. The sintered pellets are examined for physical damages such as cracks, chippings etc. and these should have one particular orientation while loading. A technique is suggested to solve the problems arising during the fuel pellet loadings. 3 figs.

  13. An infrared technique for on-line detection of orientation of PHWR fuel pellets

    International Nuclear Information System (INIS)

    Behere, P.G.

    1994-01-01

    The PHWR (Pressurised Heavy Water Reactor) fuel pellets fabricated in a fuel fabrication plant are cylindrical in shape and after sintering acquire a nominal size of 14.3 mm diameter and 17 mm height. These pellets have dish at one end while the other end is flat. The dish is provided to accommodate fission gases and thermal expansion. The sintered pellets are examined for physical damages such as cracks, chippings etc. and these should have one particular orientation while loading. A technique is suggested to solve the problems arising during the fuel pellet loadings. 3 figs

  14. Qualification of PHT piping of Indian 500 MW PHWR for LBB, using R-6 method

    International Nuclear Information System (INIS)

    Rastogi, Rohit; Bhasin, V.; Kushwaha, H.S.

    1997-01-01

    This document discusses the qualification of straight pipe portion of the primary heat transport (PHT) piping of Indian 500 MWe pressurised heavy water reactor (PHWR) for leak before break (LBB). The evaluation is done using R-6 [1] method. The results presented here are: the safety margins which exist on straight pipe components of main PHT piping of 500 MWe, under leakage size crack (LSC) and design basis accident loads; the sensitivity of safety margins with respect to different analysis parameters and the qualification of PHT piping for LBB based on criterion given by NUREG-1061 [2] and TECDOC-774 [3]. (author)

  15. Role of pressuriser in enhancing pressure control system capability in primary system of 500 MWe PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Walia, M P.S.; Misri, Vijay; Bapat, C N; Sharma, V K [Nuclear Power Corporation, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    The primary heat transport system of a pressurized heavy water reactor (PHWR) extracts and transports the heat produced in the fuel (located inside coolant channel assemblies) to the steam generators where steam is generated to run the turbo-generator. The heat transport medium (primary coolant) is heavy water which is kept in a pressurized liquid state with the help of a pressure control system. Feed and bleed circuits with associated equipment of PHT main system have traditionally constituted the pressure control system. However, for large size reactors of 500 MWe capacity, a surge tank known as pressurizer was incorporated due to the presence of relatively large inventory in PHT main circuit. The pressurizer acts as a cushion for pressure variations resulting from various transients. This significantly reduces the onerous demand on feed and bleed system, thereby reducing reactor outages on system pressure excursions. The paper describes in detail the pressure control system of 500 MWe PHWR involving pressuriser and feed and bleed system including their functions and instrumentation. The results of mathematical modelling/analysis undertaken to establish the response adequacy of pressure control system, to postulated plant transients vis-a-vis the role of pressurizer are presented. (author). 10 figs.

  16. Quality surveillance experience of PHWR fuel

    International Nuclear Information System (INIS)

    Kulkarni, P.G.; Bandyopadhyay, A.K.; Shah, B.K.

    1997-01-01

    Quality Surveillance activities are being carried out for PHWR fuel for over 25 years in India. A large number of fuel bundles of 19 element design have been produced and successfully irradiated. The quality surveillance practices follow the guidelines given in various Quality Assurance Codes and Guides. An independent third party surveillance is provided to cover major manufacturing and quality control operations. A system of design basis review periodic quality audit and regulatory safety review is in place. Over the years there have been modifications in the quality assurance procedures to comply with changing requirements. Also many innovative improvements have been introduced in the manufacturing procedures. Similarly quality control activities are also modified. Developments in fuel has remained a continuous activity. The paper summarizes the experience gathered over many years in this exciting process of innovation and improvement. (author)

  17. The heavy water reactors

    International Nuclear Information System (INIS)

    Brudermueller, G.

    1976-01-01

    This is a survey of the development so far of this reactor line which is in operation all over the world in various types (e.g. BHWR, PHWR). MZFR and the CANDU-type reactors are discussed in more detail. (UA) [de

  18. Development of 3-dimensional neutronics kinetics analysis code for CANDU-PHWR

    International Nuclear Information System (INIS)

    Kim, M. W.; Kim, C. H.; Hong, I. S.

    2005-02-01

    The followings are the major contents and scope of the research : development of kinetics power calculation module, formulation of space-dependent neutron transient analysis - implementation of 3-D and 2-G unified nodal method, verification of the kinetics module by benchmark problem - 3-D PHWR kinetics benchmark problem suggested by AECL, reactor trip simulation by shutdown system 1 in Wolsong unit 2. Development of a dynamic linked library code, SCAN D LL, for the coupled calculation with RELAP-CANDU : modeling of shutdown system 1, development of automatic shutdown module - automatic trip module based on rate log power control logic, automatic insertion of shutdown system 1. Development of a link code for coupled calculation - development of SCAN D LL(windows version), verification of coupled code by - 40% reactor inlet header break LOCA power pulse, 100% reactor outlet header break LOCA power pulse, 50% pump suction break LOCA power pulse

  19. Evolution of PHWR fuel transfer system based on operating experience

    International Nuclear Information System (INIS)

    Parvatikar, R.S.; Singh, Jaipal; Chaturvedi, P.C.; Bhambra, H.S.

    2006-01-01

    Fuel Transfer System facilitates loading of new fuel into Fuelling Machine, receipt of spent fuel from Fuelling Machine and its further transportation to Storage Bay. To overcome the limitations of transferring a pair of bundles in the single tube Airlock and Transfer Arm in RAPS-1 and 2/MAPS, a new concept of six tube Transfer Magazine was introduced in NAPS. This resulted in simultaneous loading of new fuel from Transfer Magazine into the Fuelling Machine and unloading of spent fuel from the Fuelling Machine through the exchange mode. It further facilitated the parallel/simultaneous operation of refuelling by Fuelling Machines on the reactor and transferring of spent fuel bundles from the Transfer Magazine to the bay. This new design of Fuel Transfer System was adopted for all standardised 220 MWe PHWRs. Based on the experience gained in 220 MWe PHWRs in the area of operation and maintenance, a number of improvements have been carried out over the years. These aspects have been further strengthened and refined in the Fuel Transfer System of 540 MWe units. The operating experience of the system indicates that the presence of heavy water in the Transfer Magazine poses limitations in its maintenance in the Fuel Transfer room. Further, Surveillance and maintenance of large number of under water equipment and associated valves, rams and underwater sensors is putting extra burden on the O and M efforts. A new concept of mobile light water filled Transfer Machine has been evolved for proposed 700 MWe PHWR units to simplify Fuel Transfer System. This has been made possible by adopting snout level control in the Fuelling Machine, elimination of Shuttle Transport System and locating the Storage Bay adjacent to the Reactor Building. This paper describes the evolution of Fuel Transfer System concepts and various improvements based on the experience gained in the operation and maintenance of the system. (author)

  20. Benchmark of Atucha-2 PHWR RELAP5-3D control rod model by Monte Carlo MCNP5 core calculation

    Energy Technology Data Exchange (ETDEWEB)

    Pecchia, M.; D' Auria, F. [San Piero A Grado Nuclear Research Group GRNSPG, Univ. of Pisa, via Diotisalvi, 2, 56122 - Pisa (Italy); Mazzantini, O. [Nucleo-electrica Argentina Societad Anonima NA-SA, Buenos Aires (Argentina)

    2012-07-01

    Atucha-2 is a Siemens-designed PHWR reactor under construction in the Republic of Argentina. Its geometrical complexity and peculiarities require the adoption of advanced Monte Carlo codes for performing realistic neutronic simulations. Therefore core models of Atucha-2 PHWR were developed using MCNP5. In this work a methodology was set up to collect the flux in the hexagonal mesh by which the Atucha-2 core is represented. The scope of this activity is to evaluate the effect of obliquely inserted control rod on neutron flux in order to validate the RELAP5-3D{sup C}/NESTLE three dimensional neutron kinetic coupled thermal-hydraulic model, applied by GRNSPG/UNIPI for performing selected transients of Chapter 15 FSAR of Atucha-2. (authors)

  1. Stresses imposed by coolant channel end shield interaction in 200 MWe PHWR

    International Nuclear Information System (INIS)

    Mehra, V.K.; Singh, R.K.; Soni, R.S.; Kushwaha, H.S.; Kakodkar, A.

    1983-01-01

    End shield of 200 MWe Pressurised Heavy Water Reactor (PHWR) is a composite tube sheet structure consisting of two circular tube sheets joined together by lattice tubes. Each lattice tube houses a coolant channel assembly which is connected to the end shield through shock absorber device. End shield assembly is suspended in the vault by hanger rods and its horizontal position is controlled by a set of pre-compressed springs. Coolant channel assemblies elongate due to their exposure to fast neutron flux in the reactor. This permanent elongation is monitored periodically. When growth of the channel exceeds a present value, it is prevented from further elongation by the shock absorbing device. Resultant force exerted on the end shield makes it move. This paper describes a numerical method used for evaluating these forces and movement of the end shield. Stresses produced by these forces are calculated by using finite element method. Typical stress values are verified by strain gauge measurements. (orig.)

  2. The AECL reactor development programme

    International Nuclear Information System (INIS)

    Menelely, D.A.

    1997-01-01

    The modem CANDU-PHWR power reactor is the result of more than 50 years of evolutionary design development in Canada. It is one of only three commercially successful designs in the world to this date. The basis for future development is the CANDU 6 and CANDU 9 models. Four of the first type are operating and four more will go an line before the end of this decade. The CANDU 9 is a modernized single-unit version of the twelve large multi-unit plants operated by Ontario Hydro. All of these plants use proven technology which resulted from research, development, design construction, and operating experience over the past 25 years. Looking forward another 25 years, AECL plans to retain all of the essential features that distinguish today's CANDU reactors (heavy water moderation, on-power fuelling simple bundle design, horizontal fuel channels, etc.). The end product of the planned 25-year development program is more than a specific design - it is a concept which embodies advanced features expected from ongoing R and D programs. To carry out the evolutionary work we have selected seven main areas for development: Safety Technology, Fuel and Fuel Cycles, Fuel Channels, Systems and Components, Heavy Water and Tritium Information Technology, and Construction. There are three strategic measures of success for each of these work areas: improved economics, advanced fuel cycle utilization, and enhanced safety/plant robustness. The paper describes these work programs and the overall goals of each of them. (author)

  3. PHWR fuel fabrication with imported uranium - procedures and processes

    International Nuclear Information System (INIS)

    Rao, R.V.R.L.V.; Rameswara Rao, A.; Hemantha Rao, G.V.S.; Jayaraj, R.N.

    2010-01-01

    Following the 123 agreement and subsequent agreements with IAEA & NSG, Government of India has entered into bilateral agreements with different countries for nuclear trade. Department of Atomic Energy (DAE), Government of India, has entered into contract with few countries for supply of uranium material for use in the safeguarded PHWRs. Nuclear Fuel Complex (NFC), an industrial unit of DAE, established in the early seventies, is engaged in the production of Nuclear Fuel and Zircaloy items required for Nuclear Power Reactors operating in the country. NFC has placed one of its fuel fabrication facilities (NFC, Block-A, INE-) under safeguards. DAE has opted to procure uranium material in the form of ore concentrate and fuel pellets. Uranium ore concentrate was procured as per the ASTM specifications. Since no international standards are available for PHWR fuel pellets, Specifications have to be finalized based on the present fabrication and operating experience. The process steps have to be modified and fine tuned for handling the imported uranium material especially for ore concentrate. Different transportation methods are to be employed for transportation of uranium material to the facility. Cost of the uranium material imported and the recoveries at various stages of fuel fabrication have impact on the fuel pricing and in turn the unit energy costs. Similarly the operating procedures have to be modified for safeguards inspections by IAEA. NFC has successfully manufactured and supplied fuel bundles for the three 220 MWe safeguarded PHWRs. The paper describes various issues encountered while manufacturing fuel bundles with different types of nuclear material. (author)

  4. Supplementary shutdown system of 220 MWe standard PHWR in India

    International Nuclear Information System (INIS)

    Muktibodh, U.C.

    1997-01-01

    The design objective of the shutdown system is to make the reactor subcritical and hold it in that state for an extended period of time. This objective must be realised under all anticipated operational occurrences and postulated abnormal conditions even during most reactive state of the core. PHWR design criteria for shutdown stipulates requirement of two independent diverse and fast acting shutdown systems, either of which acting alone should meet the above objectives. This requirement would normally call for a large number of reactivity mechanism penetrations into the calandria. From the point of view of space availability at the reactivity mechanism area on top of calandria, for the relatively small core of 220 MWe PHWRs, and ease of maintenance realisation of the total worth by either of the shutdown systems acting alone was difficult. To overcome this engineering constraint and at the same time to satisfy the design criteria, a unique approach to meet the reactivity demands for shutdown was adopted. The reactivity requirements of the shutdown consists of fast and slow reactivity changes. For the shutdown system of 220 MWe PHWRs, the approach of realizing fast reactivity changes with dual redundant, diverse, fast acting shutdown systems aided by a slow acting shutdown system to counter delayed reactivity changes was conceived. The supplementary slow acting shutdown system is called upon to act after actuation of either of the two redundant fast acting systems and is referred to as Liquid Poison Injection System (LPIS). The system adds bulk amount of neutron poison (boric acid), equivalent to 45 mk, directly into the moderator through two nozzles in calandria using pneumatic pressure. This paper describes the design of LPIS as envisaged for the standardised 220 MWe PHWRs. (author)

  5. Measurement and computation for sag of calandria tube due to irradiation creep in PHWR

    International Nuclear Information System (INIS)

    Son, S. M.; Lee, W. R.; Lee, S. K.; Lee, J. S.; Kim, T. R.; Na, B. K.; Namgung I.

    2003-01-01

    Calandria tubes and Liquid Injection Shutdown System(LISS) tubes in a Pressurized Heavy Water Reactor(PHWR) are to sag due to irradiation creep and growth during plant operation. When the sag of calandria tube becomes bigger, the calandria tube possibly comes in contact with LISS tube crossing beneath the calandria tube. The contact subsequently may cause the damage on the calandria tube resulting in unpredicted outage of the plant. It is therefore necessary to check the gap between the two tubes in order to periodically confirm no contact by using a proper measure during the plant life. An ultrasonic gap measuring probe assembly which can be inserted into two viewing ports of the calandria was developed in Korea and utilized to measure the sags of both tubes in the PHWR. It was found that the centerlines of calandria tubes and liquid injection shutdown system tubes can be precisely detected by ultrasonic wave. The gaps between two tubes were easily obtained from the relative distance of the measured centerline elevations of the tubes. Based on the irradiation creep equation and the measurement data, a computer program to calculate the sags was also developed. With the computer program, the sag at the end of plant life was predicted

  6. Blind prediction exercise on modeling of PHWR fuel at extended burnup

    International Nuclear Information System (INIS)

    Sah, D.N.; Viswanathan, U.K.; Viswanadham, C.S.; Unnikrishnan, K.; Rath, B.N.

    2008-01-01

    A blind prediction exercise was organised on Indian Pressurised Heavy Water Reactor (PHWR) fuel to investigate the predictive capability of existing codes for their application at extended burnup and to identify areas of improvement. The blind problem for this exercise was based on a PHWR fuel bundle irradiated in Kakrapar Atomic Power Station-I (KAPS-I) up to about 15 000 MWd/tU and subjected to detailed post-irradiation examination (PIE) in the hot cells facility at BARC. Eleven computer codes from seven countries participated in this exercise. The participants provided blind predictions of fuel temperature, fission gas release, internal gas pressure and other performance parameters for the fuel pins. The predictions were compared with the experimental PIE data which included fuel temperature derived from fuel restructuring, fission gas release measured by fuel pin puncturing, internal gas pressure in pin, cladding oxidation and fuel microstructural data. The details of the blind problem and an analysis of the results of blind predictions by the codes vis-a-vis measured data are provided in this paper

  7. Improved techniques for appendage attachment to PHWR fuel elements

    International Nuclear Information System (INIS)

    Raj, R.N.J.; Laxminarayana, B.; Narayanan, P.S.A.; Gupta, U.C.; Varma, B.P.; Sinha, K.K.

    1995-01-01

    Nuclear Fuel Complex, India switched-over to split-wart type PHWR fuel bundles in mid-80s. Since then over 60,000 bundles of this type have been fabricated for Indian PHWRs. After considering various technical aspects, resistance welding was chosen for appendage attachment to the fuel elements. The paper describes experiences in scaling up of the technique to industrial production of PHWR fuel bundles, design and development of special-purpose equipment for this purpose, and the QA procedures employed for regular production. It also deals with appendage welding of 37 Element fuel bundles and improvements planned in the appendage welding process. (author)

  8. A review of current knowledge on the effects of hydrogen on the pressure tubes of Ontario Hydro operating reactors

    International Nuclear Information System (INIS)

    Leger, M.

    1982-01-01

    Since the occurrence of cracking in Zr-2.5 wt% Nb pressure tubes in Pickering 'A' units 3 and 4 in 1974/75 a great deal of information on the behaviour of hydrogen in pressure tube materials has been generated through research effort by both AECL and Ontario Hydro. In order to use this information effectively and to provide direction and co-ordination for ongoing research, a review of available information and current concerns on hydrogen in pressure tubes was undertaken. The review was divided into two main areas of interest: hydrogen ingress and hydride effects. The uncertainties in the rates of hydrogen ingress into the pressure tubes have been found to be very large. On the basis of current knowledge, predictions of the future behaviour of pressure tubes due to hydride effects are extremely difficult

  9. In-calandria retention of corium in Indian PHWR - experimental simulations with decay heat

    International Nuclear Information System (INIS)

    Nayak, A.K.

    2015-01-01

    The severe accident at Fukushima has compelled the nuclear community to relook at the safety of existing nuclear power plants (NPP) against natural origin events of beyond design basis and prolonged station black out (SBO). A major lesson learned is to assess the capability of the safety systems to cool the reactor core and spent fuel storage facilities in the event of a prolonged station black out (SBO). Similar safety review is planned for the Indian Pressurized Heavy Water Reactors (PHWRs) considering a prolonged SBO. The Indian PHWR is a heavy water-moderated and cooled, natural uranium-fuelled reactor in which the horizontal fuel channels are submerged in a pool of heavy water moderator located inside the calandria vessel. The calandria vessel is surrounded by a calandria vault having large volume of light water. Concerns are raised that in the event of an unmitigated SBO, it may result into a low probable severe accident leading to core melt down. The core melt may further fail the calandria vessel in case the melt is not quenched. If the calandria vessel fails, the corium shall interact with the cold calandria vault water and concrete resulting in generation of large amount of non-condensable gases and steam which will lead to over pressurization of containment and may cause its failure. Therefore, in-calandria corium retention via external cooling using vault water can be considered as an important accident management program in PHWR. In this strategy, the core melt retains inside the calandria vessel by continually removing the stored heat and decay heat through outer surface of the vessel by cooling water and maintaining the integrity of the vessel. The present study focuses on experimental investigation in a scaled facility of an Indian PHWR to investigate the coolability of molten corium with simulated decay heat by using the calandria vault water. Molten borosilicate glass was used as the simulant due to its comparable heat transfer characteristics

  10. On the feasibility of a CANDU PHWR actinide burner

    International Nuclear Information System (INIS)

    Anton, V.

    1995-01-01

    In this work a review of the current solutions to burn the actinide i.e. the spallation method, LWR, FBR, Siemens proposal and inert matrix is presented. Finally, a proposal is made to use the CANDU PHWR for this purpose, taking into account the techniques envisaged for LWR and the prospect of the advanced fuel cycle in CANDU system. (Author) 5 Refs

  11. Modeling of PHWR fuel elements using FUDA code

    International Nuclear Information System (INIS)

    Tripathi, Rahul Mani; Soni, Rakesh; Prasad, P.N.; Pandarinathan, P.R.

    2008-01-01

    The computer code FUDA (Fuel Design Analysis) is used for modeling PHWR fuel bundle operation history and carry out fuel element thermo-mechanical analysis. The radial temperature profile across fuel and sheath, fission gas release, internal gas pressure, sheath stress and strains during the life of fuel bundle are estimated

  12. UO2 - Zr chemical interaction of PHWR fuel pins under high temperature

    International Nuclear Information System (INIS)

    Majumdar, P.; Mukhopadhyay, D.; Gupta, S.K.

    2001-01-01

    At high temperature Zircaloy clad interacts with the UO 2 fuel as well as with the steam to produce oxide layer of a-Zr(O) and ZrO 2 . This layer formation significantly reduces the structural strength of the clad. A computer code SFDCPA/MOD1 has been developed to simulate the interaction and predict the oxide layer thickness for any accidental transient condition. It is well validated with published experimental data on the isothermal and transient temperature condition. The program is applied to Indian Pressurized Heavy Water Reactor (PHWR) fuel pin under certain severe transient condition where it experiences temperature above 1000 C. The study gives an idea of the un-oxidized thickness of Zircaloy, which is an important criterion for fuel integrity. (author)

  13. Characteristics of pressure control system on PWR/PHWR in pile loop facility

    International Nuclear Information System (INIS)

    Sarwani; Hendro, P.; Suwoto; Sutrisno

    1998-01-01

    PWR/PHWR in-pile loop facility is used for testing of fuel element bundle which is correspond to the condition of power reactor operation. So, this facility is designed at 150 bar of pressure and 350 o C of temperature. Pressure control system is one of the components of the facility and it is equipped with 6 electrical heaters (30 KW), water spray, pressure and temperature monitors. The characterization test of pressure control system has been carried out with operating of 2 electrical heaters (10 KW). The K eff calculation value is different 5.2% from pressure in the pressure control system can be increased to 160 bar within 27 hours. After the system pressure reached the nominal pressure, the pressure control system was in the steady state condition

  14. Neutron radiography of irradiated zircaloy coupons of pressure tubes from PHWR`s

    Energy Technology Data Exchange (ETDEWEB)

    Gangotra, S; Ouseph, P M; Tamhane, A B; Singh, H N; Sahoo, K C [Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Div.

    1994-12-31

    The Indian Pressurised Heavy Water Reactors (PHWR`s) are of CANDU type, consisting of 304 zircaloy-2 pressure tubes. These pressure tubes contain the fuel bundles, where the heat is generated and is removed by the heavy water flowing through these pressure tubes at high temperature and pressure. These pressure tubes are surrounded by the calandria tubes, and are separated from them by a pair of garter springs. Over a period of time, as a result of the irradiation creep and assisted by the displacement of the garter springs, the hot pressure tube may come in contact with the cold calandria tube. This would result in the hydrogen migrating to the cold contact location and formation of hydride blisters. These blisters could eventually rupture the pressure tube by the DHC (delayed hydrogen cracking) mechanism. 2 refs., 2 figs.

  15. Studies on water quality parameters due to operation of PHWR at KAPS

    International Nuclear Information System (INIS)

    Jha, Mukesh; John, Jaison T.; Joshi, C.P.; Vyas, P.V.; Hegde, A.G.

    2005-01-01

    The paper elucidates the effect of water quality due to operation of Pressurised Heavy Water Reactor located at Kakrapar as water is the essential commodity for all living beings. It is the main concern in recent times for environmental protection, there is a pressure on all type of industries including nuclear power stations to discharge various types of effluents in such a manner that pollution in surrounding environment is kept to the minimum. Owing the wastewater discharge modes of Kakrapar atomic power station behavior of effluents resulting impact on environment and general public will be guided by the water quality of the aquatic system. To ensure the quality of water, the study of water quality parameters are taken up and the investigated parameters showed no degradation in ecosystem due to the operation of PHWR at KAPS. (author)

  16. Assessment of clad integrity of PHWR fuel pin following a postulated severe accident

    International Nuclear Information System (INIS)

    Dutta, B.K.; Kushwaha, H.S.; Venkat Raj, V.

    2000-01-01

    A mechanistic fuel performance analysis code FAIR has been developed. The code can analyse fuel pins with free standing as well as collapsible clad under normal, off-normal and accident conditions of reactors. The code FAIR is capable of analysing the effects of high burnup on fuel behaviour. The code incorporates finite element based thermo-mechanical module for computing transient temperature distribution and thermal-elastic-plastic stresses in the fuel pin. A number of high temperature thermo-physical and thermo-mechanical models also have been incorporated for analysing fuel pins subjected to severe accident scenario. The present paper describes salient features of code FAIR and assessment of clad integrity of PHWR fuel pins with different initial burnup subjected to severe accident scenario. (author)

  17. CLUB - a multigroup integral transport theory code for lattice calculations of PHWR cells

    International Nuclear Information System (INIS)

    Krishnani, P.D.

    1992-01-01

    The computer code CLUB has been developed to calculate lattice parameters as a function of burnup for a pressurised heavy water reactor (PHWR) lattice cell containing fuel in the form of cluster. It solves the multigroup integral transport equation by the method based on combination of small scale collision probability (CP) method and large scale interface current technique. The calculations are performed by using WIMS 69 group cross section library or its condensed versions of 27 or 28 group libraries. It can also compute Keff from the given geometrical buckling in the input using multigroup diffusion theory in fundamental mode. The first order differential burnup equations can be solved by either Trapezoidal rule or Runge-Kutta method. (author). 17 refs., 2 figs

  18. Considerations in providing purification flows for 500 MWe PHWR primary circuits

    International Nuclear Information System (INIS)

    Sharma, A.K.; Goswami, S.; Bapat, C.N.; Sharma, V.K.

    1995-01-01

    The purpose of the purification system is to keep the primary heat transport (PHT) system clean by removing traces of impurities arising due to corrosion of the carbon steel pipes and heat transfer surfaces and erosion/corrosion of valve trims, pipes and mechanical seals or due to presence of soluble or insoluble fission products. These impurities are undesirable because they are usually radioactive, either naturally or through activation by the neutron flux as they are carried by the coolant through the reactor core. The purification system minimizes the probability of generation of radioactive impurities by controlling the chemistry of PHT coolant so that corrosion is minimum. Various considerations for providing the requisite purification flow to fulfill the above functions for a typical 500 MWe PHWR are presented. (author). 4 refs., 2 tabs., 2 figs

  19. Comparative analysis of station blackout accident progression in typical PWR, BWR, and PHWR

    International Nuclear Information System (INIS)

    Park, Soo Young; Ahn, Kwang Il

    2012-01-01

    Since the crisis at the Fukushima plants, severe accident progression during a station blackout accident in nuclear power plants is recognized as a very important area for accident management and emergency planning. The purpose of this study is to investigate the comparative characteristics of anticipated severe accident progression among the three typical types of nuclear reactors. A station blackout scenario, where all off-site power is lost and the diesel generators fail, is simulated as an initiating event of a severe accident sequence. In this study a comparative analysis was performed for typical pressurized water reactor (PWR), boiling water reactor (BWR), and pressurized heavy water reactor (PHWR). The study includes the summarization of design differences that would impact severe accident progressions, thermal hydraulic/severe accident phenomenological analysis during a station blackout initiated-severe accident; and an investigation of the core damage process, both within the reactor vessel before it fails and in the containment afterwards, and the resultant impact on the containment.

  20. Upgradation of design features of primary coolant pumps of Indian 220 MWe PHWR

    International Nuclear Information System (INIS)

    Sharma, S.S.; Mhetre, S.G.; Manna, M.M.

    1994-01-01

    Evolution in the design features of Primary Coolant Pump (PCP) had started in fifties for catering to stringent specification requirements of reactor coolant systems of larger capacity reactors of various kinds. Primary coolant pumps of PWR and PHWR are employed for circulating radioactive, pressurized hot water in a circuit consisting of reactor (heat source) and steam generator (heat sink). As primary coolant pump capacity decides the station capacity, larger capacity primary coolant pumps have been evolved. Since primary coolant pump pressure containing parts are part of Primary Heat Transport system envelope, the parts are designed, manufactured, inspected and tested in accordance with the applicable system guidelines. Flywheel is mounted on the motor shaft for increasing mass moment of inertia of pump motor rotor to meet the coast down requirements of reactor cooling system under Class-IV electrical power supply failure. Due to limited accessibility of the PCP (PCP installed in shut down accessible area), quick maintenance, condition monitoring, reliable shaft seal system/bearing system aspects have been of great concern to reactor owners and pump manufacturers. In this paper upgradation of design features of RAPS, MAPS and NAPS primary coolant pumps have been covered. (author). 4 figs., 1 tab

  1. Xenon oscillation in a large PHWR core (Atucha II type): TRISIC code applicability

    International Nuclear Information System (INIS)

    Solanilla, Roberto

    2000-01-01

    A three dimensional nuclear reactor simulation code (TRISIC) was developed many years ago to design a PHWR (pressurizer heavy water reactors - Atucha type) based in the 'source-sink model' (heterogeneous theory). The limited processor computational performance available at that time was the constraint of the code when a detailed reactor description was necessary. A modern PC (pentium) code version with a full reactor core representation (461 fuel channels) including diagonal control rod banks and flux-reading detectors with theirs tube guide was used in the present paper for simulation of the Xenon transient when a local asymmetric perturbation was produced in a large core (Atucha II type). The results obtained and the computer time required for the 70 hour's simulation with an adequate time step, established the potential of the code to deal with this kind of transients. The paper shows that the method of TRISIC allows to detect and control azimuthal, radial and axial oscillation. This code is a proper way to elaborate a program of control rods movement from the flux reading detectors to damp the oscillation. TRISIC could also be a accurate tool to supervise the full core flux distribution in real time during the operation of the reactor. (author)

  2. Experience in operation of heavy water reactors

    International Nuclear Information System (INIS)

    Rotaru, Ion; Bilegan, Iosif; Ghitescu, Petre

    1999-01-01

    The paper presents the main topics of the CANDU owners group (COG) meeting held in Mangalia, Romania on 7-10 September 1998. These meetings are part of the IAEA program for exchange of information related mainly to CANDU reactor operation safety. The first meeting for PHWR reactors took place in Vienna in 1989, followed by those in Argentina (1991), India (1994) and Korea (1996). The topics discussed at the meeting in Romania were: operation experience and recent major events, performances of CANDU reactors and safe operation, nuclear safety and operation procedures of PHWR, programs and strategies of lifetime management of installations and components of NPPs, developments and updates

  3. Ontario Hydro looks at security

    International Nuclear Information System (INIS)

    Green, B.J.; Kee, B.

    1995-01-01

    Ontario Hydro operates 20 CANDU reactors on three different sites. Since 1984, a review of security arrangements on all the sites has taken place on a five-yearly basis. The review process for 1995 is outlined. The three objectives were as follows: to assess current security threats and risks to the stations; to assess the adequacy of the existing programme to protect against current threats; by comparing the security programme against those of comparable entities to establish benchmarks for good practice as a basis for improvements at Ontario Hydro. Valuable insights gained through the review are listed. These could be useful to other utilities. (UK)

  4. CARA CVN: inherently safe fuel element for PHWR power plants

    International Nuclear Information System (INIS)

    Brasnarof, Daniel O.; Lestani, Hector A.; Agueda, Horacio C.; Marino, Armando C.; Florido, Pablo C.; Daverio, Hernando

    2007-01-01

    This paper presents design alternatives of the CARA fuel element with negative void reactivity coefficient (CVN) enhancing the PHWR safety for L-LOCA sequences. This design enhances the safety and the operation performance in Atucha and Embalse without changes in the operation conditions. This new design balances wide performance margins of CARA SEU 0.9% previous design, with new intrinsic safety requirements without economic penalties. (author) [es

  5. Recent IAEA activities on CANDU-PHWR fuels and fuel cycles

    International Nuclear Information System (INIS)

    Inozemtsev, V.; Ganguly, C.

    2005-01-01

    Pressurized Heavy Water Reactors (PHWR), widely known as CANDU, are in operation in Argentina, Canada, China, India, Pakistan, Republic of Korea and Romania and account for about 6% of the world's nuclear electricity production. The CANDU reactor and its fuel have several unique features, like horizontal calandria and coolant tubes, on-power fuel loading, thin-walled collapsible clad coated with graphite on the inner surface, very high density (>96%TD) natural uranium oxide fuel and amenability to slightly enriched uranium oxide, mixed uranium plutonium oxide (MOX), mixed thorium plutonium oxide, mixed thorium uranium (U-233) oxide and inert matrix fuels. Several Technical Working Groups (TWG) of IAEA periodically discuss and review CANDU reactors, its fuel and fuel cycle options. These include TWGs on water-cooled nuclear power reactor Fuel Performance and Technology (TWGFPT), on Nuclear Fuel Cycle Options and spent fuel management (TWGNFCO) and on Heavy Water Reactors (TWGHWR). In addition, IAEA-INPRO project also covers Advanced CANDU Reactors (ACR) and DUPIC fuel cycles. The present paper summarises the Agency's activities in CANDU fuel and fuel cycle, highlighting the progress during the last two years. In the past we saw HWR and LWR technologies and fuel cycles separate, but nowadays their interaction is obviously growing, and their mutual influence may have a synergetic character if we look at the world nuclear fuel cycle as at an integrated system where the both are important elements in line with fast neutron, gas cooled and other advanced reactors. As an international organization the IAEA considers this challenge and makes concrete steps to tackle it for the benefit of all Member States. (author)

  6. Innovations in PHWR design, integration of nuclear power stations into power systems and role of small size nuclear power plants in a developing country

    International Nuclear Information System (INIS)

    Mehta, S.K.; Kakodkar, A.; Balakrishnan, M.R.; Ray, R.N.; Murthy, L.G.K.; Chamany, B.F.; Kati, S.L.

    1977-01-01

    PHWR concept of thermal reactors has been considered with a view to exploiting the limited resources of natural uranium and keeping in mind the projected nuclear power programme covering fast breeder reactors. Experience in engineering of current PHWR units in India, gradual build up of necessary infrastructure and operational experience with one unit, have helped in building up design and technological capability in the country. The R and D facilities have been so planned that additional data required for the design of bigger reactor units (i.e.500/600 MWe) could be generated with minimal augmentation. Satisfactory operation of a nuclear power station demands certain prerequisites from the connected power system. The grid should have load patterns suitable for base load operation of these stations, should be stiff so far as voltage and frequency fluctuations are concerned and should have high reliability. A typical power grid in this country is characterised by heavy loads during peak hours and very light loads during night. Regional grids are of small size and the few interconnections existing between the regional grids consist of weak tie lines. Amongst all types of the power stations, it is the nuclear system which undergoes maximum strain and economic penalty while operating when connected to such a power system. Consistent with the above, phase installation of small-size power reactor units of about 200 MWe capacity may facilitate setting up of larger unit sizes at a later date. The effect of any possible reduction in the capital cost of a larger unit power station will enable the power station to partially meet the demand of the more productive types of loads. This paper deals with some of the major design changes that are being incorporated in the PHWR type power reactors currently being set up and the research and development back-up required for the purpose. Since the unit sizes of the power reactors presently contemplated are small compared to nuclear

  7. Partitioning of actinide from simulated high level wastes arising from reprocessing of PHWR fuels: counter current extraction studies using CMPO

    International Nuclear Information System (INIS)

    Deshingkar, D.S.; Chitnis, R.R.; Wattal, P.K.; Theyyunni, T.K.; Nair, M.K.T.; Ramanujam, A.; Dhami, P.S.; Gopalakrishnan, V.; Rao, M.K.; Mathur, J.N.; Murali, M.S.; Iyer, R.H.; Badheka, L.P.; Banerji, A.

    1994-01-01

    High level wastes (HLW) arising from reprocessing of pressurised heavy water reactor (PHWR) fuels contain actinides like neptunium, americium and cerium which are not extracted in the Purex process. They also contain small quantities of uranium and plutonium in addition to fission products. Removal of these actinides prior to vitrification of HLW can effectively reduce the active surveillance period of final waste form. Counter current studies using indigenously synthesised octyl (phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (CMPO) were taken up as a follow-up of successful runs with simulated sulphate bearing low acid HLW solutions. The simulated HLW arising from reprocessing of PHWR fuel was prepared based on presumed burnup of 6500 MWd/Te of uranium, 3 years cooling period and 800 litres of waste generation per tonne of fuel reprocessed. The alpha activity of the HLW raffinate after extraction with the CMPO-TBP mixture could be brought down to near background level. (author). 13 refs., 2 tabs., 12 figs

  8. Partitioning of actinide from simulated high level wastes arising from reprocessing of PHWR fuels: counter current extraction studies using CMPO

    Energy Technology Data Exchange (ETDEWEB)

    Deshingkar, D S; Chitnis, R R; Wattal, P K; Theyyunni, T K; Nair, M K.T. [Bhabha Atomic Research Centre, Bombay (India). Process Engineering and Systems Development Div.; Ramanujam, A; Dhami, P S; Gopalakrishnan, V; Rao, M K [Bhabha Atomic Research Centre, Bombay (India). Fuel Reprocessing Group; Mathur, J N; Murali, M S; Iyer, R H [Bhabha Atomic Research Centre, Bombay (India). Radiochemistry Div.; Badheka, L P; Banerji, A [Bhabha Atomic Research Centre, Bombay (India). Bio-organic Div.

    1994-12-31

    High level wastes (HLW) arising from reprocessing of pressurised heavy water reactor (PHWR) fuels contain actinides like neptunium, americium and cerium which are not extracted in the Purex process. They also contain small quantities of uranium and plutonium in addition to fission products. Removal of these actinides prior to vitrification of HLW can effectively reduce the active surveillance period of final waste form. Counter current studies using indigenously synthesised octyl (phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (CMPO) were taken up as a follow-up of successful runs with simulated sulphate bearing low acid HLW solutions. The simulated HLW arising from reprocessing of PHWR fuel was prepared based on presumed burnup of 6500 MWd/Te of uranium, 3 years cooling period and 800 litres of waste generation per tonne of fuel reprocessed. The alpha activity of the HLW raffinate after extraction with the CMPO-TBP mixture could be brought down to near background level. (author). 13 refs., 2 tabs., 12 figs.

  9. Delayed hydride cracking behavior of Zr-2.5Nb alloy pressure tubes for PHWR700

    Energy Technology Data Exchange (ETDEWEB)

    Sunil, S.; Bind, A.K.; Khandelwal, H.K.; Singh, R.N., E-mail: rnsingh@barc.gov.in; Chakravartty, J.K.

    2015-11-15

    In order to attain improved in-reactor performance few prototypes pressure tubes of Zr-2.5Nb alloy were manufactured by employing forging to break the cast structure and to obtain more homogeneous microstructure. Both double forging and single forging were employed. The forged material was further processed by employing hot extrusion, cold pilgering and autoclaving. A detailed characterization in terms of mechanical properties and microstructure of the prototype tubes were carried for qualifying it for intended use as pressure tubes in PHWR700 reactors. In this work, Delayed Hydride Cracking (DHC) behavior of the forged Zr-2.5Nb pressure tube material characterized in terms of DHC velocity and threshold stress intensity factor associated with DHC (K{sub IH}) was compared with that of conventionally manufactured material in the temperature range of 200–283 °C. Activation energy associated with the DHC in this alloy was found to be ∼60 kJ/mol for the forged materials.

  10. The PHWR of Siemens as appropriate type of the SMPR-class

    International Nuclear Information System (INIS)

    Herzog, G.; Doerfler, U.; Loos, F.

    1988-01-01

    Siemens started its NPP-activities with the development and construction of a number of small and medium size power reactor (SMPR) plants, using different reactor types (PHWRs, PWRs and BWRs). Siemens applied its proven technological modules successfully to all types of nuclear power plants as it is demonstrated by the high availability figures published every year. Based on the experience gained from Atucha I and II, the Argentinian engineering company ENACE (of which KWU holds 25% of the shares) has developed the ARGOS 380, a NPP in the SMPR-class, as an advanced continuation of the KWU PHWR series. The technology transfer provided by Siemens in the course of NPP construction includes all activities in the engineering, construction, manufacturing and erection/commissioning field. Additionally Siemens is prepared to assist in the transfer of manufacturing know-how. On the basis of its successful activities in this field for years, Siemens disposes of all instruments for an efficient know-how transfer. (orig.)

  11. Impacting effects of seismic loading in feeder pipes of PHWR power plants

    International Nuclear Information System (INIS)

    Kumar, R.

    1996-01-01

    The core of a pressurized heavy water reactor (PHWR) consists of a large number of fuel channels. These fuel channels are connected to the feeder pipes through which the heavy water flows and transports heat from the reactor core to the steam generators. The feeder pipes are several hundreds in number. They run close to each other with small gaps and have several bends. Thus they represent a complex piping system. Under seismic loading, the adjacent feeder pipes may impact each other. In this paper a simplified procedure has been established to assess such impacting effects. The results of the proposed analysis include bending moment and impact force, which provide the stresses due to impacting effects. These results are plotted in nondimensional form so that they could be utilized for any set of feeder pipes. The procedure used for studying the impacting effects includes seismic analysis of individual feeder pipes without impacting effects, selection of pipes for impact analysis, and estimating their maximum impact velocity. Based on the static and dynamic characteristics of the selected feeder pipes, the maximum bending moment, impact force, and stresses are obtained. The results of this study are useful for quick evaluation of the impacting effects in feeder pipes

  12. Gear failure of a PHWR refuelling machine

    International Nuclear Information System (INIS)

    Iorio, A.F.; Crespi, J.C.

    1986-01-01

    After ten year service in Atucha Nuclear Station a gear belonging to a pressurized heavy water reactor refuelling machine, failed. The gear box was used to transmit motion to the inlet-outlet heavy-water valve of that machine. Visual examination of the gear device revealed an absence of lubricant and several gear teeth were broken off at the root. The gear motion was transmitted from a speed-reducing device with controlled adjustable times in order to produce a right fitness of the valve closure. The main cause of gear failure was due to misalignment produced during assembly or in-service operation. It is suggested to control periodically the level of oil lubricant. (orig./IHOE) [de

  13. A PHWR with slightly enriched uranium about the first core

    International Nuclear Information System (INIS)

    Notari, C.

    1997-01-01

    Many different studies have been performed in Argentina regarding the use of slightly enriched uranium in the PHWR nuclear plants. These referred mainly to operating plants so that a transition had to be considered from the present natural uranium fuel cycle to the slightly enriched one. In this analysis, technical and economical arguments are presented which favor the use of a natural uranium initial core. The levelized fuel costs are shown to be practically insensitive to the first core and a fast transition is more influential than an initially enriched core. (author)

  14. A three-dimensional analyses of fluid flow and heat transfer for moderator integrity assessment in PHWR

    International Nuclear Information System (INIS)

    Bang, K. H.; Lee, J. Y.; Yoo, S. O.; Kim, M. W.; Kim, H. J.

    2002-01-01

    Three-dimensional analyses of fluid flow and heat transfer has been performed in this study. The simulation of SPEL experimental work and comparison with experimental data has been carried out to verify the analyses models. Moreover, to verify the CANDU-6 reactor type, analyses of fluid flow and heat transfer in the calandria under the condition of steady state has been performed using FLUENT code, which is the conventional code for a three-dimensional analyses of fluid flow and heat transfer for moderator integrity assessment in PHWR thermal-hydraulics. It is found that the maximum temperature in the moderator is 347K (74 ), so that the moderator has the enough subcoolability to ensure the integrity of pressure tube during LOCA conditions

  15. Ontario Hydro's nuclear program

    International Nuclear Information System (INIS)

    McCredie, J.

    1984-01-01

    This report briefly describes Ontario Hydro's nuclear program, examining the design and construction status, and the future from Ontario Hydro's perspective. Ontario Hydro relies heavily on nuclear power. Nuclear fuel was responsible for approximately 34% of Ontario Hydro's energy production in 1983. The nuclear proportion was supplied by twelve operating units located: NPD, Douglas Point, Pickering A and B. It is expected that by approximately 1992, 65% of the total energy needs will be generated through nuclear power

  16. A final report on stress analysis of seal disc of 500 MWe PHWR

    International Nuclear Information System (INIS)

    Chawla, D.S.; Dutta, B.K.; Kushwaha, H.S.; Kakodkar, A.; Sanatkumar, A.

    1989-01-01

    In Pressurised Heavy Water Reactor (PHWR) on-power refuelling is done by use of fuelling machine. Before refuelling, sealing plug assembly is removed from the end-fitting of the coolant channel and after refuelling the sealing plug is reinstalled back in to the end-fitting. The seal disc is a part of sealing plug assembly. Its function is to create sealing action for the heavy water inside the coolant channel. A systematic developmental work is done to arrive at a final configuration of the seal disc. This is done to minimise the stresses in the body of the seal disc and at the same time to obtain required seating reaction to avoid heavy water leakage. It is observed that stresses computed for the final configuration by linear elastic analysis are more than the allowable value as per ASME Section III, Division 1. This calls for elasto-plastic analysis to find out collapse load to satisfy ASME codal limits as per special provision of NB-3228.1 (1986). The elasto-plastic analysis showed that the seal disc meets ASME codal limits for all stages of loading. (author). 8 refs., 2 tabs., 7 figs

  17. Design of shutdown system no.2 liquid poison injection system for 500 MWe PHWR

    International Nuclear Information System (INIS)

    Bhatnagar, S.; Balasubrahmanian, A.K.; Pillai, A.V.

    1997-01-01

    Defence in depth and two group system concepts form the basic design philosophy for the shutdown systems. There are two independent, diverse and fast acting shutdown systems provided for the 500 MWe PHWR. The design is based on fail-safe principle, sufficient component redundancy and on-line testing. Liquid poison injection system, as shutdown system 2, is newly developed for the 500 MWe PHWRs. The system operates by rapidly injecting gadolinium nitrate solution into bulk moderator using stored helium pressure thereby inserting negative reactivity. A high pressure helium supply tank which provides the energy for system actuation, is connected, through an array of fast acting valves in series-parallel arrangement, to the individual poison tanks storing gadolinium nitrate solution. The valves, belonging to three different channels of reactor Protection System 2, are the only active components in the system. The valves are fail safe and are periodically tested on-line without actually firing the system. The system comprising of in-core assemblies and the external process system has been engineered. Experimental work is being carried out by BARC for design validation and data generation. This paper describes the conceptual development, design basis, design parameters and detailed engineering of the system. (author)

  18. Fuel handling system of Indian 500 MWe PHWR-evolution and innovations

    International Nuclear Information System (INIS)

    Sanatkumar, A.; Jit, I.; Muralidhar, G.

    1996-01-01

    India has gained rich experience in design, manufacture, testing, operation and maintenance of the Fuel Handling System of CANDU type PHWRs. When design and layout of the first 500 MWe PHWR was being evolved, it was possible for us to introduce many special and innovative features in the Fuel Handling System which are friendly for operations and maintenance personnel. Some of these are: Simple, robust and modular mechanisms for ease of maintenance; Shorter turnaround time for refuelling a channel by introduction of transit equipment between the Fuelling Machine (FM) Head and light water equipment; Optimised layout to transport spent fuel in straight and short path and also to facilitate direct wheeling out of the FM Head from the Reactor Building to the Service Building; Provision to operate the FM Head even when the Primary Heat Transport (PHT) System is open for maintenance; Control-console engineered for carrying out refuelling operations in the sitting position; and, Dedicated calibration and maintenance facility to facilitate quick replacement of the FM Head as a single unit. The above special features have been described in this paper. (author). 7 figs

  19. Fuel handling system of Indian 500 MWe PHWR-evolution and innovations

    Energy Technology Data Exchange (ETDEWEB)

    Sanatkumar, A; Jit, I; Muralidhar, G [Nuclear Power Corporation of India Ltd., Mumbai (India)

    1997-12-31

    India has gained rich experience in design, manufacture, testing, operation and maintenance of the Fuel Handling System of CANDU type PHWRs. When design and layout of the first 500 MWe PHWR was being evolved, it was possible for us to introduce many special and innovative features in the Fuel Handling System which are friendly for operations and maintenance personnel. Some of these are: Simple, robust and modular mechanisms for ease of maintenance; Shorter turnaround time for refuelling a channel by introduction of transit equipment between the Fuelling Machine (FM) Head and light water equipment; Optimised layout to transport spent fuel in straight and short path and also to facilitate direct wheeling out of the FM Head from the Reactor Building to the Service Building; Provision to operate the FM Head even when the Primary Heat Transport (PHT) System is open for maintenance; Control-console engineered for carrying out refuelling operations in the sitting position; and, Dedicated calibration and maintenance facility to facilitate quick replacement of the FM Head as a single unit. The above special features have been described in this paper. (author). 7 figs.

  20. Performance of water cooled nuclear power reactor fuels in India – Defects, failures and their mitigation

    International Nuclear Information System (INIS)

    Ganguly, Chaitanyamoy

    2015-01-01

    Water cooled and moderated nuclear power reactors account for more than 95% of the operating reactors in the world today. Light water reactors (LWRs) consisting of pressurized water reactor (PWR), their Russian counterpart namely VVER and boiling water reactor (BWR) will continue to dominate the nuclear power market. Pressurized heavy water reactor (PHWR), also known as CANDU, is the backbone of the nuclear power program in India. Updates on LWR and PHWR fuel performance are being periodically published by IAEA, OECD-NEA and the World Nuclear Association (WNA), highlighting fuel failure rate and the mitigation of fuel defects and failures. These reports clearly indicate that there has been significant improvement in in – pile fuel performance over the years and the present focus is to achieve zero fuel failure in high burn up and high performance fuels. The present paper summarizes the status of PHWR and LWR fuel performance in India, highlighting the manufacturing and the related quality control and inspection steps that are being followed at the PHWR fuel fabrication plant in order to achieve zero manufacturing defect which could contribute to achieving zero in – pile failure rate in operating and upcoming PHWR units in India. (author)

  1. The Feasibility of Multidimensional CFD Applied to Calandria System in the Moderator of CANDU-6 PHWR Using Commercial and Open-Source Codes

    Directory of Open Access Journals (Sweden)

    Hyoung Tae Kim

    2016-01-01

    Full Text Available The moderator system of CANDU, a prototype of PHWR (pressurized heavy-water reactor, has been modeled in multidimension for the computation based on CFD (computational fluid dynamics technique. Three CFD codes are tested in modeled hydrothermal systems of heavy-water reactors. Commercial codes, COMSOL Multiphysics and ANSYS-CFX with OpenFOAM, an open-source code, are introduced for the various simplified and practical problems. All the implemented computational codes are tested for a benchmark problem of STERN laboratory experiment with a precise modeling of tubes, compared with each other as well as the measured data and a porous model based on the experimental correlation of pressure drop. Also the effect of turbulence model is discussed for these low Reynolds number flows. As a result, they are shown to be successful for the analysis of three-dimensional numerical models related to the calandria system of CANDU reactors.

  2. Studies on flow induced vibration of reactivity devices of 700 MWe Indian PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Prabhakaran, K.M., E-mail: kmprabha@yahoo.com [Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai 400 085 (India); Goyal, P.; Dutta, Anu; Bhasin, V.; Vaze, K.K.; Ghosh, A.K. [Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai 400 085 (India); Pillai, Ajith V.; Mathew, Jimmy [Nuclear Power Corporation of India Ltd., Mumbai 400 094 (India)

    2012-03-15

    Highlights: Black-Right-Pointing-Pointer FIV studies on internals of heavy water filled calandria of 700 MWe Indian PHWR is presented. Black-Right-Pointing-Pointer This includes CFD and structural dynamic analysis to predict the dynamic behavior of component lying inside calandria. Black-Right-Pointing-Pointer Results of these calculations as well as conclusions from this investigation are presented. Black-Right-Pointing-Pointer It is established that FIV is not a concern in the present design of calandria internals. - Abstract: Component failures due to excessive flow-induced vibration are still affecting the performance and reliability of nuclear power stations. Tube failures due to fretting-wear in nuclear steam generators, and vibration related damage of reactor internals are of particular concern. In the Indian nuclear industry, flow induced vibrations are assessed early in the design process and the results are incorporated in the design procedures. In this paper the details of flow induced vibration studies on internals like liquid zone control unit and poison injection units of heavy water filled calandria of 700 MWe Indian pressurized heavy water reactor is given. This includes computational fluid dynamics studies from which the velocities are extracted for the components lying inside the calandria. With these velocities as input, further studies are performed to predict the dynamic behavior of these components. Results of these calculations as well as conclusions derived from this investigation are presented. Based on the studies it has been established that flow induced vibration is not a concern in the present design of 700 MWe calandria internals.

  3. Ontario Hydro's DSP update

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Ontario Hydro's Demand/Supply Plan (DSP), the 25 year plan which was submitted in December 1989, is currently being reviewed by the Environmental Assessment Board (EAB). Since 1989 there have been several changes which have led Ontario Hydro to update the original Demand/Supply Plan. This information sheet gives a quick overview of what has changed and how Ontario Hydro is adapting to that change

  4. Advances in appendage joining techniques for PHWR fuel cladding

    International Nuclear Information System (INIS)

    Desai, P.B.; Ray, T.K.; Date, V.G.; Purushotham, D.S.C.

    1995-01-01

    This paper describes work carried out at the BARC on the development of a technique to join tiny appendages (spacers and bearing pads) to thin cladding (before loading of UO 2 pellets) by resistance welding for PHWR fuel assemblies. The work includes qualifying the process for production environment, designing prototype equipment for regular production and quality monitoring. In the first phase of development, welding of appendages on UO 2 loaded elements was successfully developed, and is being used in production. Welding of appendages on to empty clad tubes is a superior technique for several reasons. Many problems associated with development of welding on empty tubes were resolved. work was initiated, in the second phase of the development task, to select a suitable technique to join appendages on empty clad tubes without any collapse of thin clad. Several alternatives were reviewed and assessed such as laser, full face welding, shim welding and shrink fitting ring spacers. Selection of a method using a mandrel and a modified electrode geometry was fully developed. Results were optimized and process development successfully completed. Appropriate weld monitoring techniques were also reviewed for their adaptation. This technique is useful for 19, 22 as well as 37 element assemblies. (author)

  5. Post-irradiation examination of a failed PHWR fuel bundle of KAPS-2

    International Nuclear Information System (INIS)

    Mishra, Prerna; Unnikrishnan, K.; Viswanathan, U.K.; Shriwastaw, R.S.; Singh, J.L.; Ouseph, P.M.; Alur, V.D.; Singh, H.N.; Anantharaman, S.; Sah, D.N.

    2006-08-01

    Detailed post irradiation examination was carried out on a PHWR fuel bundle irradiated at Kakrapar Atomic Power Station unit 2 (KAPS-2). The fuel bundle had failed early in life at a low burnup of 387 MWd/T. Non destructive and destructive examination was carried out to identify the cause of fuel failure. Visual examination and leak testing indicated failure in two fuel pins of the outer ring of the bundle in the form of axial cracks near the end plug location. Ultrasonic testing of the end cap weld indicated presence of lack of fusion type defect in the two fuel pins. No defect was found in other fuel pins of the bundle. Metallographic examination of fuel sections taken from the crack location in the failed fuel pin showed extensive restructuring of fuel. The centre temperature of the fuel had exceeded 1700 degC at this location in the failed fuel pin, whereas fuel centre temperature in the un-failed fuel pin was only about 1300 degC. Severe fuel clad interaction was observed in the failed fuel pin at and near the location of failure but no such interaction was observed in the un-failed fuel pins. Several incipient cracks originating from the inside surface were found in the cladding near failure location in addition to the main through wall crack. The incipient cracks were filled with interaction products and hydride platelets were present at tip of the cracks. It was concluded from the observations that the primary cause of failure was the presence of a part-wall defect in the end cap weld of the fuel pins. These defects opened up during reactor operation leading to steam ingress into the fuel, which caused high fuel centre temperature and severe fuel-cladding interaction resulting in secondary failures. A more stringent inspection and quality control of end plug weld during fabrication using ultrasonic test has been recommended to avoid such failure. (author)

  6. Experiences and lessons learnt on staffing from the first Indian nuclear power plant (PHWR)

    International Nuclear Information System (INIS)

    Bhattacharya, A.S.

    2001-01-01

    Three decades of operating experience in India has led to sustained high performance of NPPs. The staffing modules and policies are standardised. The basic functions of operation, maintenance, technical support and quality assurance are carried out by a team of 727 in-plant persons (for a 2 x 220 MW PHWR station) organised at five levels, for fifty positions in ten job families. Specific qualification levels apply to each position - six at management positions, five licensed positions with the rest qualified through an equivalent training scheme. Practically all O and M activities are carried out on-site by the utility manpower with minimum involvement of contractors. The entire process of human resource development is in-house - with each NPP organisation comprised of 30% experienced staff transferred from older NPPs and 70% totally developed out of fresh recruits. Four to eight years lead time goes to qualify fresh recruits depending on the position. This optimisation of manpower is a result of continuous learning - through operating experience and regulatory feed back and self assessment for (i) optimising quantum of work load and (ii) improving productivity. For the first category, design improvements over older NPP's increased reliability, operability, maintainability and human factors are described separately in the companion paper. In this paper the organisation factors are discussed, starting with the initial lessons that demanded improved management and enhanced quality programmes and caused temporarily, high demand of staffing for bringing out new systems, e.g., (i) attaining maturity of units; (ii) standardising training, retraining and cross training and qualifications; (in) job rotations, (iv) in service inspection of reactor components; (v) quality audits. The experiences on subsequent optimisation of staffing levels are outlined. (author)

  7. Modelling of oxidation and hydriding behaviour of Zircaloy-2 pressure tubes in PHWR

    International Nuclear Information System (INIS)

    Sah, D.N.; Sunil Kumar; Khan, K.B.

    2002-01-01

    A computer model named DOCTOR (Deuteriding of Coolant Tubes during Operation of Reactor) has been developed for predicting the axial profile of oxide thickness and hydrogen (Deuterium) concentration in PHWR pressure tubes. This model is applicable to single channel or full core analysis. The main source of hydrogen is considered to be oxidation of pressure tube on the i.d. surface by high temperature coolant water. Three stages of oxidation is considered namely, pre- transition, post transition and accelerated. Oxidation rate is considered to be dependent on channel power, axial power/flux distribution, coolant temperature and pre-existing oxide thickness at the location. The kinetics parameters for oxidation model are derived from the actual measurement of oxide thickness on a number of pressure tubes examined in PIE Division. The input data required for the model are: channel power, channel power factor, axial flux distribution, coolant inlet temperature, critical oxide thickness, hydrogen pick up fraction, initial hydrogen in the material and time of operation (efpy). The model calculates the oxide layer thickness on the inside surface of the pressure tube along the length. The amount of hydrogen picked up by the pressure tube is calculated from the oxide thickness using hydrogen pick up fraction determined from the PIE data. The pressure tube length is divided into a number of axial segments for calculation. The temperature and fast neutron flux assumed to be constant in a given segment. The axial temperature profile calculated from the axial power profile in the channel is used for calculating the oxidation rate at various locations in the pressure tube. The model has been validated with PIE data of hydrogen equivalent measurement on a number of irradiated Zircaloy-2 pressure tubes of various PHWRs. The performance of the model in predicting the axial profile of hydrogen in the pressure tubes has been found to be good. (author)

  8. Ontario electricity industry restructuring

    International Nuclear Information System (INIS)

    1999-01-01

    The objective of Ontario's electricity industry restructuring was described as an effort to enhance Ontario's competitiveness. It is believed that restructuring can be accomplished without an increase in electricity rates. In a series of charts, the report provides the timeline of restructuring from the time of the Macdonald report in 1995 to the beginning of open competition in Ontario electricity markets. It oulines the principles underlying the financial restructuring and the financial results of restructuring, including the size of the stranded debt ($ 7.8 billion). It lists the changes that have occurred since October 1998, explains some key factors in valuing the successor companies and profiles the Ontario Electricity Financial Corporation. Restructuring of the industry is expected to have a neutral to positive impact on Ontario's fiscal position. The residual stranded debt of $7.8 billion will be retired through revenues generated by the electricity sector, without recourse to the Provincial Treasury. 9 figs

  9. Market surveillance in Ontario

    International Nuclear Information System (INIS)

    Chandler, H.

    2002-01-01

    On May 1, 2002 both wholesale and retail electricity markets in Ontario were opened to competition. Wholesale electricity market sales of 150 TWh were valued at over $11 billion with 27,500 MW in service installed capacity and 4,000 to 6,000 MW import/export capability with strong interconnections to the Quebec, the Midwest and the Northeast. The key players in Ontario's electricity market are the Ontario Energy Board (OEB), the Independent Electricity Market Operator (IMO), Ontario Power Generation, and Hydro One. The OEB regulatory framework includes licensing and front line, daily monitoring of whole sale market. Serious capacity problems in Ontario have manifested themselves in tight supply and demand situations and highly volatile prices. The paper included graphs of available reserves for 1996 to 2002, HOEP trends and frequency, HOEP comparison, and a sensitivity to demand forecast. 1 tab., 6 figs

  10. Ontario energy review

    International Nuclear Information System (INIS)

    1990-03-01

    This publication provides a review of the developments in Ontario in relation to the national and international energy scene. Ontario is the largest energy consumer in Canada and is highly dependent on external energy sources. Several developments have significantly altered the Ontario energy scene. Oil and gas markets have become deregulated and market forces increasingly determine prices. A free trade agreement with the United States makes Ontario even more affected by international markets. Oil and gas prices have fallen from the high levels of the 1980s, but energy efficiency and conservation continue to be extremely important because they affect economic performance and the environment. In the next few years the greatest challenges will be to continue improving energy efficiency, to reduce the impact of energy on the environment, and to ensure the availability of sufficient energy supplies for future needs. This review contains statistics on energy in Ontario and explains them for the non-specialist. (7 tabs., figs.)

  11. New experience on construction and installation work in Qinshan PHWR nuclear power plant

    International Nuclear Information System (INIS)

    Lu Huaxiang

    2004-01-01

    The article provides a summary of the new experience on construction management and construction technology in the field of civil construction and installation work in Qinshan PHWR nuclear power plant, with focus on innovation in project management mode, new technology application and computerized management of construction and installation work. Management innovation, technical innovation and information technology are the key contributors to overall success of Qinshan PHWR nuclear power plant in construction and installation work. The new experience derived in these fields will be of great significance to promote independent construction of the new-round nuclear power projects in China. (author)

  12. Bathymetry of Lake Ontario

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Bathymetry of Lake Ontario has been compiled as a component of a NOAA project to rescue Great Lakes lake floor geological and geophysical data and make it more...

  13. Engineered safety in development of liquid poison injection system (shut down system-2) for 500 MWe PHWR

    International Nuclear Information System (INIS)

    Sapra, M.K.; Kundu, S.N.; Mohan, L.R.

    2002-01-01

    Full text: The provision of shut down systems (SDS) is a mandatory requirement for safety of any nuclear reactor. The SDS shall be capable of making and holding the core adequately subcritical in the event of any anticipated operational occurrence and postulated accident conditions. The shut down function will perform as intended when its design and components are thoroughly evaluated for their reliability and effectiveness. A full scale mock up for one injection unit was designed and developed at Hall No.7, BARC. Experimental studies were carried out to qualify the design and evolve process parameters such as gas tank pressure, poison discharge rate and poison injection time. In liquid poison injection system i.e. shutdown system -2, there is no physical barrier, between the two liquids i.e. the poison and the moderator. A liquid in liquid interface, called poison moderator interface (PMI) separates these fluids. Extensive lab scale studies have been carried out on PMI movement study i.e. the interface movement due to molecular diffusion and due to process disturbances under simulated reactor condition. On the basis of lab scale results, a full-scale PMI setup has been designed and developed to generate plant data. From reactor safety consideration, the floating ball in poison tank is designed in such a way that it prevents the over pressurisation of calandria. For this purpose a non-intrusive ultrasonic ball detection system (U-BDS) has been developed. This paper covers the PMI system for 500 MWe PHWR with relevant safety aspects and describes in detail, the experimental results of PMI study. The engineered safety in design, methodology and qualification of U-BDS and its role intended in performance of SDS-2 have been also discussed in the paper

  14. A series of lectures on operational physics of power reactors

    International Nuclear Information System (INIS)

    Mohanakrishnan, P.; Rastogi, B.P.

    1982-01-01

    This report discusses certain aspects of operational physics of power reactors. These form a lecture series at the Winter College on Nuclear Physics and Reactors, Jan. - March 1980, conducted at the International Centre for Theoretical Physics, Trieste, Italy. The topics covered are (a) the reactor physics aspects of fuel burnup (b) theoretical methods applied for burnup prediction in power reactors (c) interpretation of neutron detector readings in terms of adjacent fuel assembly powers (d) refuelling schemes used in power reactors. The reactor types chosen for the discussion are BWR, PWR and PHWR. (author)

  15. Effect of Flow Configuration on Velocity and Temperature Distribution of Moderator Inside 540 MWe PHWR Calandria using CFD Techniques

    International Nuclear Information System (INIS)

    Bharj, J.S.; Sahaya, R.R.; Datta, D.; Dharne, S.P.

    2006-01-01

    The calandria of a Pressurized Heavy Water Reactor (PHWR) is a horizontal cylindrical vessel housing a matrix of horizontal tubes called calandria tubes, through which pass the pressure tubes that house the fuel bundles. The calandria is filled with heavy water acting as moderator. A large amount of heat (about 95 MW) is generated within the moderator mainly due to neutron slowing down and attenuation of gamma radiations. In the present configuration of 540 MWe calandria, moderator inlet diffusers are directed upwards and the outlet is from the bottom of the calandria. This configuration is not conducive for the buoyancy-dominated flows generated due to large volumetric heat generation in the moderator. In order to decide the effects of changes in flow configuration by changing location/direction of inlet/outlet nozzles, a study was done for moderator flows in the using PHOENICS CFD software. The results of study with various flow configurations show that modification in moderator flow configuration, reduces the peak temperature of moderator in calandria by about 12 deg C as well as gives a much more uniform temperature distribution. (authors)

  16. Full length channel Pressure Tube sagging under completely voided full length pressure tube of an Indian PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Negi, Sujay, E-mail: negi.sujay@gmail.com [Indian Institute of Technology, Roorkee 247667 (India); Kumar, Ravi, E-mail: ravikfme@gmail.com [Indian Institute of Technology, Roorkee 247667 (India); Majumdar, P., E-mail: pmajum@barc.gov.in [Bhabha Atomic Research Centre, Mumbai 400085 (India); Mukopadhyay, D., E-mail: dmukho@barc.gov.in [Bhabha Atomic Research Centre, Mumbai 400085 (India)

    2017-03-15

    Highlights: • At 16 kW/m input, thermal stability was attained at 595 °C, without PT-CT contact. • At 20 kW/m step input, PT-CT contact occurred at 637 °C near bottom-center of the tube. • PT integrity was maintained throughout the experiment. - Abstract: An experimental investigation was conducted to simulate the sagging behavior of a full length Pressure Tube of a channel of 220 MWe Indian PHWR. The investigation aimed to recreate a condition resembling Loss of Coolant Accident (LOCA) with Emergency Core Cooling System (ECCS) failure in a nuclear power plant. A full length channel assembly immersed in moderator was subjected to electrical resistance heating of Pressure Tube (PT) to simulate the residual heat after shutting down of reactor. The temperature of PT started rising and the contact between PT and CT was established at the center of the tube where average bottom temperature was 637 °C. The integrity of PT was maintained throughout the experiment and the PT heat up was arrested on contact with the CT due to transfer of heat to the moderator.

  17. Development of high pressure conductivity probe (HPCP) for secondary shut down system (SDS-2) of 500 MWe PHWR

    International Nuclear Information System (INIS)

    Sapra, M.K.; Kundu, S.; Mohan, L.R.

    2003-09-01

    The poison solution and the moderator in Secondary Shutdown System (SDS-2) of 500 MWe PHWR, are separated by their own liquid in liquid interface. This interface moves towards the calandria because of molecular diffusion, temperature difference and physical disturbances in the moderator level. It is proposed to install two numbers of high pressure conductivity probes (HPCP) to monitor the interface movement as well as to provide the safe annunciation value for interface location. On actuation of the SDS-2 signal, high-pressure helium will inject the poison into the moderator to shutdown the reactor. During poison injection, these probes will experience high pressure of nearly 85 kg/sq.cm. Global market survey indicated that conductivity probes having built in temperature sensor are available for a maximum pressure rating of 35 kg/sq.cm. Hence in order to meet the process requirement of SDS-2, the development of HPCP suitable for a pressure of 85 kg/sq.cm. was taken up. Two numbers of such probes were successfully designed, fabricated and evaluated for their performance. The developed conductivity probes fully meet the laid design and performance criteria. The aforesaid development work was a successful endeavour towards indigenisation of high-pressure conductivity probe for future applications. This report deals with the design aspects, fabrication technique, material and performance evajuation criteria and test results of HPCP. (author)

  18. 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.)

  19. 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.)

  20. Cogeneration markets in Ontario

    International Nuclear Information System (INIS)

    Poredos, S.

    1993-01-01

    Cogeneration offers a key strategy which supports global competitiveness for Ontario businesses, encourages energy efficiency and environmental protection, and offers natural gas utilities and producers stable long-term incremental markets. By supporting cogeneration projects, electric utilities will benefit from increased flexibility. Natural gas is the fuel of choice for cogeneration, which can in most cases be easily integrated into existing operations. In Ontario, electric demand grew along with the gross domestic product until 1990, but has decreased with the recent economic recession. The provincial utility Ontario Hydro is resizing itself to stabilize total rate increases of 30% over the last three years and supporting reduction of its high debt load. Rate increases are supposed to be limited but this may be difficult to achieve without further cost-cutting measures. Cogeneration opportunities exist with many institutional and industrial customers who are trying to remain globally competitive by cutting operating costs. In general, cogeneration can save 20% or more of total annual energy costs. Due to excess capacity, Ontario Hydro is not willing to purchase electric power, thus only electric load displacement projects are valid at this time. This will reduce overall savings due to economies of scale. In southwestern Ontario, Union Gas Ltd. has been successful in developing 40 MW of electric displacement projects, providing a total load of 5 billion ft 3 of natural gas (50% of which is incremental). Over 3,000 MW of technical cogeneration potential is estimated to exist in the Union Gas franchise area

  1. Design, construction and operation of Ontario Hydro's CANDU plants

    International Nuclear Information System (INIS)

    Campbell, P.G.

    1981-06-01

    Ontario Hydro has been producing electricity commercially from nuclear power since 1968, using CANDU reactors which have proved enormously successful. The 206-MW Douglas Point station, nearly 10 times larger than the first Canadian power reactor, NPD-2, resulted from a cooperative effort between Atomic Energy of Canada Ltd., the provincial government of Ontario, and Ontario Hydro. This approach led to a basic working relationship between the parties, with Ontario Hydro acting as project manager and builder, and AECL acting as consultant with respect to the nuclear components. Before Douglas Point was fully commissioned Ontario Hydro was ready to commit itself to more nuclear stations, and work was started on the four-unit Pickering nuclear generating station. Multi-unit stations were adopted to achieve economies of scale, and the concept has been retained for all subsequent nuclear power plants constructed in the province. The organization of Ontario Hydro's project management, construction, and operation of nuclear generating stations is described. Performance of the existing stations and cost of the power they produce have been entirely acceptable

  2. Trend of R and D publications in pressurised heavy water reactors: A study using INIS and other databases

    International Nuclear Information System (INIS)

    Kumar, V.; Kalyane, V.L.; Prakasan, E.R.; Kumar, A.; Sagar, A.; Mohan, L.

    2004-01-01

    Digital databases INIS (1970-2002), INSPEC (1969-2002), Chemical Abstracts (1977-2002), ISMEC (1973-June 2002), Web of Sciences (1974-2002), and Science Citation Index (1982-2002), were used for comprehensive retrieval of bibliographic details of research publications on Pressurized Heavy Water Reactor (PHWR) research. Among the countries contributing to PHWR research, India (having 1737 papers) is the forerunner followed by Canada (1492), Romania (508) and Argentina (334). Collaboration of Canadian researchers with researchers of other countries resulted in 75 publications. Among the most productive researchers in this field, the first 15 are from India. Top three contributors to PHWR publications with their respective authorship credits are: H.S. Kushwaha (106), Anil Kakodkar (100) and V. Venkat Raj (76). Prominent interdomainary interactions in PHWR subfields are: Specific nuclear reactors and associated plants with General studies of nuclear reactors (481), followed by Environmental sciences (185), and Materials science (154). Number of publications dealing with Geosciences aspect of environmental sciences are 141. Romania, Argentina, India and Republic of Korea have used mostly (≥75%) non-conventional media for publications. Out of the 4851 publications, 1228 have been published in 292 distinct journals. Top most journals publishing PHWR papers are: Radiation Protection and Environment (continued from: Bulletin of Radiation Protection since 1997), India (115); Nuclear Engineering International, UK (84); and Transactions of the American Nuclear Society, USA (68). (author)

  3. Thorium utilisation in thermal reactors

    International Nuclear Information System (INIS)

    Balakrishnan, K.

    1997-01-01

    It is now more or less accepted that the best way to use thorium is in thermal reactors. This is due to the fact that U233 is a good material in the thermal spectrum. Studies of different thorium cycles in various reactor concepts had been carried out in the early days of nuclear power. After three decades of neglect, the world is once again looking at thorium with some interest. We in India have been studying thorium cycles in most of the existing thermal reactor concepts, with greater emphasis on heavy water reactors. In this paper, we report some of the work done in India on different thorium cycles in the Indian pressurized heavy water reactor (PHWR), and also give a description of the design of the advanced heavy water reactor (AHWR). (author). 1 ref., 2 tabs., 5 figs

  4. Ontario Hydro decontamination experience

    Energy Technology Data Exchange (ETDEWEB)

    Lacy, C S; Patterson, R W; Upton, M S [Chemistry and Metallurgy Department, Central Production Services, Ontario Hydro, ON (Canada)

    1991-04-01

    Ontario Hydro currently operates 18 nuclear electric generating units of the CANDU design with a net capacity of 12,402 MW(e). An additional 1,762 MW(e) is under construction. The operation of these facilities has underlined the need to have decontamination capability both to reduce radiation fields, as well as to control and reduce contamination during component maintenance. This paper presents Ontario Hydro decontamination experience in two key areas - full heat transport decontamination to reduce system radiation fields, and component decontamination to reduce loose contamination particularly as practised in maintenance and decontamination centres. (author)

  5. Ontario Hydro decontamination experience

    International Nuclear Information System (INIS)

    Lacy, C.S.; Patterson, R.W.; Upton, M.S.

    1991-01-01

    Ontario Hydro currently operates 18 nuclear electric generating units of the CANDU design with a net capacity of 12,402 MW(e). An additional 1,762 MW(e) is under construction. The operation of these facilities has underlined the need to have decontamination capability both to reduce radiation fields, as well as to control and reduce contamination during component maintenance. This paper presents Ontario Hydro decontamination experience in two key areas - full heat transport decontamination to reduce system radiation fields, and component decontamination to reduce loose contamination particularly as practised in maintenance and decontamination centres. (author)

  6. Ontario Hydro statistical yearbook 1990

    International Nuclear Information System (INIS)

    1990-01-01

    Ontario Hydro was created in 1906 by a special statute of the Province of Ontario. It is a financially self-sustaining corporation without share capital. The yearbook is a compilation of financial data detailed by financial statements and sales and revenue figures for the year 1990. It is broken down by municipalities served in Ontario

  7. Ontario Hydro statistical yearbook 1990

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-12-31

    Ontario Hydro was created in 1906 by a special statute of the Province of Ontario. It is a financially self-sustaining corporation without share capital. The yearbook is a compilation of financial data detailed by financial statements and sales and revenue figures for the year 1990. It is broken down by municipalities served in Ontario.

  8. Experimental study of poison moderator interface movement for shut down system #2(SDS#2) of 540 MWe PHWR

    International Nuclear Information System (INIS)

    Sapra, M.K.; Kundu, S.; Chawan, D.B.; Ananthan, P.; Sharma, B.S.V.G.; Mohan, L.R.

    2005-03-01

    The poison solution and the moderator in Secondary Shutdown System (SDS-2) of 500 MWe PHWR, are separated by their own liquid in liquid interface, termed as poison moderator interface (PMI). During normal operation of the reactor, the interface moves towards the calandria, mainly because of molecular diffusion from poison to moderator. Other reasons for movement are mixing of poison and moderator due to physical disturbances in the moderator level and to some extent due to temperature difference between the two liquids. The electrical conductivity of these liquids was found to be the most reliable parameter indicating interface movement. For this purpose, two on-line high-pressure conductivity probes have been installed on moderator side for each one of the six poison tanks. During normal operation of reactor, the interface moves slowly towards the calandria over a period of time and gives rise to increase in conductivity. To study the interface pattern and factors affecting the same, a full-scale experimental setup was developed and series of experiments carried out. The experimental results showed that the interface is quite stable and annunciation can be placed around 100 micro siemens/cm before back flushing is initiated. One dimensional diffusion analysis of the obtained experimental data showed that the derived model for PMI setup with diffusion parameter of 900 cm 2 /hr is able to predict the interface movement quite satisfactorily. This report gives an insight into the experiments carried out for estimation of the effective diffusion parameter for the poison moderator interface, model formulation and its prognostic behavior. (author)

  9. Process Control Logic Modification to Mitigate Transient Following Tripping of a Primary Circulating Pump for a 540 MWe PHWR Power Plant

    International Nuclear Information System (INIS)

    Contractor, Ankur D; Gaikwad, Avinash J.; Kumar, Rajesh; Chakraborty, G.; Vhora, S.F.

    2006-01-01

    The 540 MWe Indian Pressurised Heavy Water Reactor (PHWR) incorporates many new features as compared to the earlier 220 MWe PHWRs. To evaluate the new design features like Primary Heat Transport (PHT) system configuration with two loops, four Primary Circulating Pumps (PCPs) and four passes through core, addition of a Pressurizer (surge Tank) in the PHT system along with Feed/Bleed system and their safety related implications, simulation model have been developed. A reactor step-back is proposed following one PCP trip. The corresponding PCP in the healthy loop is tripped to avoid asymmetrical flow and pressure distribution in the two identical loops. In spite of such elaborate provisions, the margins from high/low PHT pressure are small following tripping of one PCP. Mathematical models for all the major components and sub-systems of the proposed 540 MWe PHWR were developed based on the conservation equations of mass, momentum, energy and equation of state. All the associated control systems are also modeled. The PHT system includes the reactor core with nuclear fuel, PCP, PHT system pressure controller with feed/bleed system and Pressurizer (Surge Tank). The secondary system includes mainly the Steam Generators (SGs), the SG level and pressure controllers, apart from the various steam cycle components. All these models are integrated together to form the Plant Transient Analysis Computer Code Dyna540. The scenario following one PCP trips leads to different states (high/low pressure in Reactor Outlet Header (ROH)) depending upon the banks in which the PCP trips. The pressurizer is connected to two ROHs on one side of the reactor. The system pressure is controlled based on average of four ROHs pressure. In the case of asymmetrical pump operation, this logic leads to a situation where individual ROH pressure goes very near the low/high PHT system pressure trip set point, even though the controlled average pressure is very close to the set pressure. The PHT high

  10. Ontario's energy action plan

    International Nuclear Information System (INIS)

    2003-07-01

    In the fall of 2002, the government of Ontario announced an action plan designed to ensure stable electricity prices while additional electricity generating capacity is built. The action plan included a strategy for encouraging major private sector investments in wind, solar and other renewable energy sources. The strategies for new renewable energy projects include: property tax incentives, business income tax incentives, and sales tax rebates. Initiatives to increase supply include: Toronto's Portland 550 megawatt, natural gas-fired generating station, Niagara Falls' Beck Tunnel Project, and Windsor's 580 megawatt natural gas-fired generating station. The government is promoting energy conservation by reducing its electricity consumption by 10 per cent, and setting a target where 20 per cent of electricity consumed in the province must be from renewable energy sources. The use of interval meters by Ontario residents is being encouraged. A provincial sales tax rebate is being offered to customers buying select energy efficient appliances. In its commitment to environmental protection, the Ontario government is phasing out coal, offering rebates for solar energy systems, implementing measures to reduce acid rain, and investing $3.25 billion over ten years to renew and expand public transit. In Chatham, Ontario, a plant producing ethanol from corn was built, and others are planned for other parts of the province. Tax incentives are also offered for alternative fuel users. 1 ref., 1 tab

  11. Determination of overall decontamination factors for common impurity elements in PHWR spent fuel reprocessing

    International Nuclear Information System (INIS)

    Pant, D.K.; Bhalerao, B.A.; Gupta, K.K.; Kulkarni, P.G.; Gurba, P.B.; Janardan, P.; Changrani, R.D.; Dey, P.K.

    2009-01-01

    An attempt has been made to determine overall decontamination factors for elemental impurities normally encountered in the U 3 O 8 product obtained by reprocessing of PHWR spent fuel. The solution obtained by dissolution of spent fuel and corresponding U 3 O 8 product were analyzed for 24 elemental impurities by ICP-AES for this purpose. Decontamination factors achieved for major neutron poisons are in the range of 200-400. (author)

  12. Performance of indigenous resistance welding equipment for PHWR fuel fabrication in NFC

    International Nuclear Information System (INIS)

    Hemantha Rao, G.V.S.; Jayaraj, R.N.; Prakash, M.S.; Gupta, U.C.; Ganguly, C.

    1999-01-01

    Indigenisation of critical equipment for manufacturing of PHWR fuel and automation in the production line have been the main thrust in NFC in recent years. As part of this endeavour, resistance welding equipment for end plug welding of Zircaloy-4 clad Uranium Oxide fuel pin and end plates of 19-element fuel bundles have been developed. The paper discusses the equipment design features, critical operating parameters and performance of these indigenous welding machines. (author)

  13. Fine element (F.E.) modelling of hydrogen migration and blister formation in PHWR coolant channels

    International Nuclear Information System (INIS)

    Prasad, P.S.; Dutta, B.K.; Sinha, R.K.; Kushwaha, H.S.; Mahajan, S.C.; Kakodkar, A.

    1995-01-01

    The formation of a cold spot in pressure tube due to its contact with calandria tube of PHWR coolant results in the migration of Hydrogen in pressure tube towards contact zone from its surrounding material. A 3-D finite element code SPARSH is developed to model the hydrogen redistribution and consequent hydride blister formation due to thermal and Hydrogen concentration gradients. In the present paper, the details and performance of this code are presented. (author). 6 refs., 2 figs

  14. Retailers test Ontario market

    International Nuclear Information System (INIS)

    Kishewitsch, S.

    2000-01-01

    In anticipation of the full opening of the Ontario electricity market in November 2000, some of the newly-licensed electricity retailers are reported to be ready to begin testing the market early, hoping that all the uncertainties that still exist about pricing will be worked out in time. Among those jumping in now is Direct Energy Marketing, a retailer which claims 800,000 households in Ontario as electricity supply customers, as well as a wholesale gas marketing business. Direct Energy began retail electrical marketing on April 3, 2000, starting cautiously with small commercial operations as the initial target. Greengrid Electric, another of the new marketers, planned to begin marketing in mid-April, offering 100 per cent renewable-sourced electricity. Provident Energy Management, one of the new marketers whose licence is still pending, hopes to begin direct marketing as soon as its licence is confirmed. Another marketer ready to go as soon its license is issued is the former Sault Ste. Marie Hydro, now reorganized as PUC Energies Inc. PUC has the advantage of having a firm contract with a NUG (non-utility generator), Great Lakes Power, signed while PUC was still a municipal electric utility. As far as the other potential marketers are concerned, caution overrides opportunity for the present. Principal concerns are uncertainty over the retail settlement code, the electronic business data transfer system, transmission and distribution tariffs, whether existing non-utility generator contracts will allow for supply to another party, and over how quickly Ontario Power Generation Inc's (successor to Ontario Hydro) market power will be ratcheted down. Many of the potential marketers feel that despite the Ontario government's desire to see more competition, the power mitigation agreement, as it now reads, leaves little room for the small retailer to compete

  15. Retailers test Ontario market

    Energy Technology Data Exchange (ETDEWEB)

    Kishewitsch, S.

    2000-04-01

    In anticipation of the full opening of the Ontario electricity market in November 2000, some of the newly-licensed electricity retailers are reported to be ready to begin testing the market early, hoping that all the uncertainties that still exist about pricing will be worked out in time. Among those jumping in now is Direct Energy Marketing, a retailer which claims 800,000 households in Ontario as electricity supply customers, as well as a wholesale gas marketing business. Direct Energy began retail electrical marketing on April 3, 2000, starting cautiously with small commercial operations as the initial target. Greengrid Electric, another of the new marketers, planned to begin marketing in mid-April, offering 100 per cent renewable-sourced electricity. Provident Energy Management, one of the new marketers whose licence is still pending, hopes to begin direct marketing as soon as its licence is confirmed. Another marketer ready to go as soon its license is issued is the former Sault Ste. Marie Hydro, now reorganized as PUC Energies Inc. PUC has the advantage of having a firm contract with a NUG (non-utility generator), Great Lakes Power, signed while PUC was still a municipal electric utility. As far as the other potential marketers are concerned, caution overrides opportunity for the present. Principal concerns are uncertainty over the retail settlement code, the electronic business data transfer system, transmission and distribution tariffs, whether existing non-utility generator contracts will allow for supply to another party, and over how quickly Ontario Power Generation Inc's (successor to Ontario Hydro) market power will be ratcheted down. Many of the potential marketers feel that despite the Ontario government's desire to see more competition, the power mitigation agreement, as it now reads, leaves little room for the small retailer to compete.

  16. Development of innovative inspection tools for higher reliability of PHWR fuel

    International Nuclear Information System (INIS)

    Kamalesh Kumar, B.; Viswanathan, B.; Laxminarayana, B.; Ganguly, C.

    2003-01-01

    'Full text:' Advent of Computer aided manufacturing systems has led to very high rate of production with greater reliability. The conventional inspection tools and systems, which are often manual based do not complement with output of highly automated production line. In order to overcome the deficiency, a strategic plan was developed for having automated inspection facility for PHWR fuel assembly line. Laser based systems with their inherently high accuracy and quick response times are a favorite for metrology purpose. Non-contact nature of laser-based measurement ensures minimal contamination, low wear and tear and good repeatability. So far two laser-based systems viz. Pellet density measurement systems and triangulation sensors have been developed. Laser based fuel pellet inspection system and PHWR fuel bundle metric station are under development. Machine vision-based systems have been developed to overcome certain limitations when inspection has to be carried out on such a large scale manually. These deficiencies arise from limitations of resolution, accessibility, fatigue and absence of quantification ability. These problems get further compounded in inspection of fuel components because of their relatively small sizes, close tolerances required and the reflective surfaces. PC based vision system has been developed for inspecting components and fuel assemblies. The paper would touch upon the details of the various laser systems and vision systems that have been indigenously developed for PHWR Fuel Metrology and their impact on the assembly production line. (author)

  17. New avenues in cobalt-60 production at Ontario Hydro

    International Nuclear Information System (INIS)

    Mylvaganam, C.K.; Ronchka, R.A.

    1990-01-01

    Ontario Hydro produces cobalt-60 in the control rods of twelve power reactors. These reactors have a typical flux of 2 x 10 14 neutrons/cm 2 /s, making them efficient producers of cobalt-60. Current annual production is 45 million curies. Since the primary function of these reactors is the production of electricity, their flexibility to meet the needs of commercial cobalt production by the control rod route is limited. Ontario Hydro is therefore developing innovative production techniques, making use of the CANDU reactor's unique ability to be fuelled on-power. These techniques will enable production to better respond to the market's requirements for quantity and specific activity. As it is supplementary to control rod production, annual supply could potentially reach 165 million curies. (author)

  18. Monitoring of PHWR end cap weld quality by ultrasonic testing

    International Nuclear Information System (INIS)

    Laxminarayana, B.

    1996-01-01

    In Pressurized Heavy Water Reactor fuel fabrication, the end cap welding is an important process. Till date about 16,000 welds have been studied ultrasonically. This paper discusses the experimental results and the design of a semi automatic ultrasonic equipment incorporating features for both backward and forward integration. (author)

  19. Detection of gaseous heavy water leakage points in CANDU 6 pressurized heavy water reactors

    International Nuclear Information System (INIS)

    Park, T-K.; Jung, S-H.

    1996-01-01

    During reactor operation, the heavy water filled primary coolant system in a CANDU 6 Pressurized Heavy Water (PHWR) may leak through routine operations of the plant via components, mechanical joints, and during inadvertent operations etc. Early detection of leak points is therefore important to maintain plant safety and economy. There are many independent systems to monitor and recover heavy water leakage in a CANDU 6 PHWR. Methodology for early detection based on operating experience from these systems, is investigated in this paper. In addition, the four symptoms of D 2 O leakage, the associated process for clarifying and verifying the leakage, and the probable points of leakage are discussed. (author)

  20. A multinode digital control system for 500 MWe PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Patil, G N; Suresh Babu, R M; Jangra, L R; Das, Shantanu; Mallik, S B [Bhabha Atomic Research Centre, Bombay (India). Reactor Control Div.

    1994-12-31

    A fault tolerant distributed digital computer system for 500 MWe reactor power regulation is configured around standard microcomputer boards designed indigenously. The system is configured as functionally partitioned distributed control system having 8 nodes linked by high-speed dual redundant high-way. The paper gives the details of the configuration of system and how the features of fault-tolerance and fail-safeness are achieved through design. (author). 1 fig.

  1. Ontario's uranium mining industry

    International Nuclear Information System (INIS)

    Runnalls, O.J.C.

    1981-01-01

    This report traces the Ontario uranium mining industry from the first discovery of uranium north of Sault Ste. Marie through the uranium boom of the 1950's when Elliot Lake and Bancroft were developed, the cutbacks of the 1960s, the renewed enthusiasm in exploration and development of the 1970s to the current position when continued production for the domestic market is assured. Ontario, with developed mines and operational expertise, will be in a position to compete for export markets as they reopen. The low level of expenditures for uranium exploration and the lack of new discoveries are noted. The report also reviews and places in perspective the development of policies and regulations governing the industry and the jurisdictional relationships of the Federal and Provincial governments

  2. Main coolant pump testing at Ontario Hydro

    International Nuclear Information System (INIS)

    Hartlen, R.

    1991-01-01

    This article describes Ontario Hydro Research Division's experience with a computerized data acquisition and analysis system for monitoring mechanical vibration in reactor coolant pumps. The topics covered include bench-marking of the computer system and the coolant pumps, signatures of normal and malfunctioning pumps, analysis of data collected by the monitoring system, simulation of faults, and concerns that have been expressed about data interpretation, sensor types and locations, alarm/shutdown limits and confirmation of nondestructive examination testing. This presentation consists of overheads only

  3. Ontario hydro waste storage concepts and facilities

    International Nuclear Information System (INIS)

    Carter, T.J.; Mentes, G.A.

    1976-01-01

    Ontario Hydro presently operates 2,200 MWe of CANDU heavy water reactors with a further 11,000 MWe under design or construction. The annual quantities of low and medium level solid wastes expected to be produced at these stations are tabulated. In order to manage these wastes, Ontario Hydro established a Radioactive Waste Operations Site within the Bruce Nuclear Power Development located on Lake Huron about 250 km northwest of Toronto. The Waste Operations Site includes a 19-acre Storage Site plus a Radioactive Waste Volume Reduction Facility consisting of an incinerator and waste compactor. Ontario has in use or under construction both in-ground and above-ground storage facilities. In-ground facilities have been used for a number of years while the above-ground facilities are a more recent approach. Water, either in the form of precipitation, surface or subsurface water, presents the greatest concern with respect to confinement integrity and safe waste handling and storage operations

  4. Nuclear cluster strategy Carolinas - Ontario - Saskatchewan

    International Nuclear Information System (INIS)

    Oberth, R.

    2012-01-01

    Organization of Candu Industries (OCI) is an industry association representing the interests of 170 private sector suppliers of products and services to the Canadian and offshore nuclear industries. OCI member companies, mainly in Ontario, employ over 30,000 highly specialized workers with over 12,000 working in nuclear area. OCI's objectives are to sustain the domestic nuclear program by building support among political leaders, the public and local communities, assist OCI member companies in becoming the preferred suppliers for domestic nuclear projects (competitive), assist OCI member companies in international nuclear markets - trade missions and vendor workshops. OCI is at the heart of an 'Ontario nuclear cluster'. The Carolinas have shown what can be achieved when industry, academia, S&T centers and governments collaborate with a shared vision to achieve a common goals. Ontario has the assets to become a stronger center for nuclear excellence. OCI is working to bring the pieces together. Saskatchewan has the assets to become a center of excellence in Small Modular Reactors (SMR) by licensing and constructing the first SMR in Canada.

  5. Design and development of improved ballscrew and control circuit for reactivity mechanisms of 220 MWe PHWR operating stations

    International Nuclear Information System (INIS)

    Jain, A.K.; Rama Mohan, N.; Mathew, Jimmy; Mathur, M.K.; Roy, S.; Ingle, V.J.; Ghoshal, B.; Ashok Kumar, B.; Patil, D.C.; Dwivedi, K.P.; Bhambra, H.S.

    2006-01-01

    There has been persistent failure of Ballscrews used for Reactivity Mechanism in standardised 220 MWe PHWR units. The detailed review of failures indicated that on one hand the number of demands for operation of Absorber Rod and Regulating Rod had increased due to use of digital circuit in the drive control system as compared analog circuits used earlier. On the other hand, the existing design of ballscrew had some inherent weaknesses to withstand the loads generated during starting and stopping of the regulating rods. To solve these problems two-pronged approach was adopted. The control problem was traced to overshooting of the servomotor of Absorber Rod and Regulating Rod to the full speed at the time of starting and thereafter, settling to the required speed. This sudden overshooting produces a jerk in the drive mechanism. A modified circuit has been evolved to solve this problem. Also, Changing the dead band and gain of control circuits have reduced the number of rod movements. A 'new design' of Ballscrew assembly was finalised by NPCIL with a view to withstand the severe loads generated during starting and stopping of the regulating rods and to achieve enhanced service life under water-lubrication condition. Based on this design, prototype assemblies were successfully manufactured by two Indian manufacturers. The design was cleared for manufacturing of the bulk production of Ballscrew assemblies after evaluation of its performance during rigorous 'Acceptance Testing'. Two ballscrews of new design were installed in the KGS-1 reactor and are operating since July 2005. This paper covers operational feedback including ballscrew failures in various units, Design/Development of Modified Reactivity Mechanism Ballscrews and Control Circuit based on analysis of underlying causes of failures and feedback on performance of new design. (author)

  6. Reactors

    DEFF Research Database (Denmark)

    Shah, Vivek; Vaz Salles, Marcos António

    2018-01-01

    The requirements for OLTP database systems are becoming ever more demanding. Domains such as finance and computer games increasingly mandate that developers be able to encode complex application logic and control transaction latencies in in-memory databases. At the same time, infrastructure...... engineers in these domains need to experiment with and deploy OLTP database architectures that ensure application scalability and maximize resource utilization in modern machines. In this paper, we propose a relational actor programming model for in-memory databases as a novel, holistic approach towards......-level function calls. In contrast to classic transactional models, however, reactors allow developers to take advantage of intra-transaction parallelism and state encapsulation in their applications to reduce latency and improve locality. Moreover, reactors enable a new degree of flexibility in database...

  7. Ontario Hydro annual report 1985

    International Nuclear Information System (INIS)

    1986-04-01

    Ontario Hydro is a corporation without share capital created by a special statute of the Province of Ontario in 1906. It now operates under the authority of the Power Corporation Act, R.S.O. 1980, Chapter 384, as amended, with broad powers to generate, supply and deliver electric power throughout the province. It is also authorized to produce and sell steam and hot water as primary products. The Corporation's prime objective is to supply the people of Ontario with electricity at the lowest feasible cost consistent with high safety and quality of service standards. Ontario Hydro's main activity is wholesaling electric power to municipal utilities in urban areas who, in turn, retail it to customers in their service areas. In 1985, approximately 3,166,000 customers were served by Ontario Hydro and the municipal utilities in the province. Ontario Hydro operates 81 hydraulic, fossil and nuclear generating stations and an extensive power grid across Ontario to meet the province's demands for electric energy. Interconnections with other systems place the Corporation in an extensive electrical grid that covers a large segment of the North American continent. Ontario Hydro is a financially self-sustaining corporation. The Province of Ontario guarantees bonds and notes issued to the public by the Corporation

  8. Evolution of MMI for 500 MWe PHWR plant

    International Nuclear Information System (INIS)

    Surendar, Ch.; Sharma, M.P.; Jayanthi, S.

    1994-01-01

    The Indian nuclear power programme for building Pressurized Heavy Water Reactors began with the construction of two units at Kota, Rajasthan. Although the concept of a centralized control room has been used since the beginning, the man-machine interface design has evolved with technological developments. The man-machine interaction in the earliest plants imposed a considerable burden on the operators and led to a need for more sophisticated instrumentation. Several microprocessor and computer based systems were identified and developed and many were retrofitted into existing plants providing immediate advantages. This paper traces the evolution of many of these systems and also describes the basis and the architecture for the man-machine interaction scheme in the 500 MWe nuclear power plants currently being designed. (author). 7 refs., 2 figs., 1 tab

  9. Evaluation of microstructure of irradiated fuel channel components of PHWR

    International Nuclear Information System (INIS)

    Ramadasan, E.

    2005-01-01

    Performance evaluation and failure analysis of irradiated reactor structural components such as those in-core and PHT circuit components necessitate metallographic evaluation using special metallographic specimen preparation techniques due to the radiation dose and contamination levels involved in handling the specimens. The metallographic specimen preparation techniques that are resorted to involve use of fully automatic and semi automatic machines, shielded metallographic microscope and specialised equipment developed for lead-cell metallography. The techniques used and the results obtained in the metallographic studies on irradiated fuel channel components such as pressure tubes and garter springs of various Indian PHWRs at RAPS, NAPS and MAPS are presented as case studies in the paper. The evaluation of oxidation and hydriding behaviour of zircaloy-2 pressure tubes and garter springs are presented. The paper also gives in detail the microstructural evaluation of hydride blistering seen at the PT-CT contact location of the pressure tubes of RAPS-2. The evaluation revealed that the hydride blisters was small compared to their length, unlike the hydride blisters seen in the CANDU pressure tube G-16 of Pickering-2. This could be attributed to be due to the difference in the annulus conditions between the two types of reactors. The hydride blisters in J-07 pressure tube of RAPS-2 had ductile material adjacent to them. The paper also gives the hydride blistering observation on irradiated Zr-2.5% Nb-0.5% Cu garter springs of RAPS-2. It was seen that there was only negligible hydriding of the garter springs during service through they showed presence of benign hydride blisters in them. The general hydriding observations made on the pressure tubes of Indian PHWRs under different conditions are also presented. (author)

  10. Ontario demand response scenarios

    International Nuclear Information System (INIS)

    Rowlands, I.H.

    2005-09-01

    Strategies for demand management in Ontario were examined via 2 scenarios for a commercial/institutional building with a normal summertime peak load of 300 kW between 14:00 and 18:00 during a period of high electricity demand and high electricity prices. The first scenario involved the deployment of a 150 kW on-site generator fuelled by either diesel or natural gas. The second scenario involved curtailing load by 60 kW during the same periods. Costs and benefits of both scenarios were evaluated for 3 groups: consumers, system operators and society. Benefits included electricity cost savings, deferred transmission capacity development, lower system prices for electricity, as well as environmental changes, economic development, and a greater sense of corporate social responsibility. It was noted that while significant benefits were observed for all 3 groups, they were not substantial enough to encourage action, as the savings arising from deferred generation capacity development do not accrue to individual players. The largest potential benefit was identified as lower prices, spread across all users of electricity in Ontario. It was recommended that representative bodies cooperate so that the system-wide benefits can be reaped. It was noted that if 10 municipal utilities were able to have 250 commercial or institutional customers engaged in distributed response, then a total peak demand reduction of 375 MW could be achieved, representing more than 25 per cent of Ontario's target for energy conservation. It was concluded that demand response often involves the investment of capital and new on-site procedures, which may affect reactions to various incentives. 78 refs., 10 tabs., 5 figs

  11. Sizing of ion exchange column for PHT purification system of 500 MWe Indian PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Goswami, S; Sharma, A K; Bapat, C N; Sharma, V K [Nuclear Power Corporation, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    Strict chemistry control is required on the heavy water coolant in the primary loop of the PHWR to ensure stability of oxide corrosion film and to prevent corrosion build up on the surfaces. This is achieved by maintaining PD value of PHT coolant at about 10.45 and sp. conductivity between 20 to 40 mhos/cm by ion exchange column and filtration of coolant. This paper deals with the sizing and selection of bed height of ninth column from different methods. (author). 7 refs., 6 figs.

  12. On the optimization of thorium bundle distribution in the initial core loading for a PHWR

    International Nuclear Information System (INIS)

    Mishra, S.; Ray, S.; Kumar, A.N.; Modak, R.S.; Ganesan, S.

    2009-01-01

    If the initial core of Indian 220 MWe PHWR is loaded with all fresh Natural Uranium fuel, only about 70% Full Power can be drawn in the initial operation due to large power peaking. It is possible to load few tens of Th bundles at selected locations to get nearly full power without violating any safety limits. Finding the best possible locations is, however, a fairly complex and massive combinatorial optimization problem. Here, optimum solutions are obtained by a latest evolutionary algorithm called EDA implemented on the EKA built at Computational Research Laboratories (CRL) in Pune. The effect of varying the number of Th bundles on results is discussed. (author)

  13. Ontario Hydro CANDU operating experience

    International Nuclear Information System (INIS)

    Jackson, H.A.; Woodhead, L.W.; Fanjoy, G.R.

    1984-03-01

    The CANDU Pressurized Heavy Water (CANDU-PHW) type of nuclear-electric generating station has been developed jointly by Atomic Energy of Canada Limited and Ontario Hydro. This report highlights Ontario Hydro's operating experience using the CANDU-PHW system, with a focus on the operating performance and costs, reliability of system components and nuclear safety considerations for the workers and the public

  14. Ontario Hydro CANDU operating experience

    International Nuclear Information System (INIS)

    Bartholomew, R.W.; Woodhead, L.W.; Horton, E.P.; Nichols, M.J.; Daly, I.N.

    1987-01-01

    The CANDU Pressurized Heavy Water (CANDU-PHW) type of nuclear-electric generating station has been developed jointly by Atomic Energy of Canada Limited and Ontario Hydro. This report highlights Ontario Hydro's operating experience using the CANDU-PHW system, with a focus on worker and public safety, operating performance and costs, and reliability of system components

  15. Ontario Hydro annual report 1975

    International Nuclear Information System (INIS)

    A financial report and statistics on Ontario energy demand are presented. Efforts to secure a reliable supply of coal and uranium are described. Ontario Hydro's expansion is now controlled by capital availability and not power demand, and this has affected 11 construction projects, including heavy water plants and nuclear generating stations. (E.C.B.)

  16. Power Reactor Fuel Reprocessing Plant-1: a stepping stone in Indian PHWR spent fuel reprocessing

    International Nuclear Information System (INIS)

    Pradhan, Sanjay; Dubey, K.; Qureshi, F.T.; Lokeswar, S.P.

    2017-01-01

    India has low reserves of uranium and high reserves of thorium. In order to optimize resource utilization India has adopted a closed fuel cycle to ensure long-term energy security. The optimum resource utilization is feasible only by adopting reprocessing, conditioning and recycle options. It is very much imperative to view spent fuel as a vital resource material and not a waste to be disposed off. Thus, spent nuclear fuel reprocessing forms an integral part of the Indian Nuclear Energy Programme. Aqueous reprocessing based on PUREX technology is in use for more than 50 years and has reached a matured status

  17. Operating experiences with programmable logic controller (PLC) system of Indian Pressurised Heavy Water Reactors (PHWR)

    International Nuclear Information System (INIS)

    Ughade, A.V.; Singh, Ranjeet; Bhattacharya, P.K.; Kulkarni, R.K.; Chandra, Umesh

    2005-01-01

    PLC system was introduced for the first time in Kaiga-1,2 and RAPS-3,4 Nuclear Power Plants (NPPs) for Station Logic Control of Non Safety Related (NSR) and Safety related (SR) systems. However, the safety system logics are still relay based. The experience on the deployment of PLC system, which is computer-based, has brought out various implementation issues. This paper give details of such experiences, the solutions emerged and applied for plants under operation/construction. (author)

  18. Ontario regulatory update

    International Nuclear Information System (INIS)

    Thompson, P.

    1998-01-01

    This paper provides a summary of recent events which when combined add up to a gradual but unmistakable movement of the energy sector in Ontario towards a fully competitive market. Some of the events precipitating this movement towards competition include the passing of the Energy Competition Act of 1998 (Bill 35), electricity deregulation, regulatory reform of the natural gas sector, and changes to the consumer protection legislation. The role of the Ontario Energy Board was also updated to bring it in line with the demands of the competitive marketplace. Among the new roles that the Board will assume are to facilitate competition, to maintain fair and reasonable rates, and to facilitate rational expansion. Another objective is to provide opportunities for including energy efficiency in government policies. Implications of the changes in the OEB's mandate for market participants were also discussed, including (1) regulated gas sales and delivery mechanisms, (2) transactional services, (3) contract restructuring, (4) consumer protection, (5) supervision of competitive market participants, and (6) market surveillance

  19. Ontario electricity bill review

    International Nuclear Information System (INIS)

    O'Neill, G.

    2003-01-01

    Findings of an independent review of charges to electricity bills and recommendations to assist in the development of a standard, province-wide residential electricity bill for Ontario are discussed. The review was requested by the province's Minister of Energy in an effort to dispel growing confusion about the variations in customer billing practices used by the province's 90+ local distribution companies. Key recommendations and findings were as follows: (1)Consumer bill formats issued by local distribution companies should be more consumer-friendly, adhere to minimum design standards, adapt uniform terminology and common line charges; (2) charges on customer bills should be grouped into four standard line items, with full details available to customers: the four line items should be a basic service charge, a charge for delivering electricity to the customer, a charge for the electricity itself, and a separate charge for retiring the outstanding debt of the former Ontario Hydro; (3) bills should take advantage of opportunities for promoting province-wide energy conservation, such as encouraging the long-term use of interval meters, presenting historical consumption data on residential bills on a period-to-period basis, and education and communications initiatives. Details of the recommendations, including the calculation of the fixed and variable components of usage charges, an explanation of the concept of electricity system loss adjustments, a method for phasing in the recommendations, and the anticipated benefits to consumers are provided

  20. Enthalpy and void distributions in subchannels of PHWR fuel bundles

    Energy Technology Data Exchange (ETDEWEB)

    Park, J W; Choi, H; Rhee, B W [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1999-12-31

    Two different types of the CANDU fuel bundles have been modeled for the ASSERT-IV code subchannel analysis. From calculated values of mixture enthalpy and void fraction distribution in the fuel bundles, it is found that net buoyancy effect is pronounced in the central region of the DUPIC fuel bundle when compared with the standard CANDU fuel bundle. It is also found that the central region of the DUPIC fuel bundle can be cooled more efficiently than that of the standard fuel bundle. From the calculated mixture enthalpy distribution at the exit of the fuel channel, it is found that the mixture enthalpy and void fraction can be highest in the peripheral region of the DUPIC fuel bundle. On the other hand, the enthalpy and the void fraction were found to be highest in the central region of the standard CANDU fuel bundle at the exit of the fuel channel. This study shows that the subchannel analysis is very useful in assessing thermal behavior of the fuel bundle that could be used in CANDU reactors. 10 refs., 4 figs., 2 tabs. (Author)

  1. Enthalpy and void distributions in subchannels of PHWR fuel bundles

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. W.; Choi, H.; Rhee, B. W. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    Two different types of the CANDU fuel bundles have been modeled for the ASSERT-IV code subchannel analysis. From calculated values of mixture enthalpy and void fraction distribution in the fuel bundles, it is found that net buoyancy effect is pronounced in the central region of the DUPIC fuel bundle when compared with the standard CANDU fuel bundle. It is also found that the central region of the DUPIC fuel bundle can be cooled more efficiently than that of the standard fuel bundle. From the calculated mixture enthalpy distribution at the exit of the fuel channel, it is found that the mixture enthalpy and void fraction can be highest in the peripheral region of the DUPIC fuel bundle. On the other hand, the enthalpy and the void fraction were found to be highest in the central region of the standard CANDU fuel bundle at the exit of the fuel channel. This study shows that the subchannel analysis is very useful in assessing thermal behavior of the fuel bundle that could be used in CANDU reactors. 10 refs., 4 figs., 2 tabs. (Author)

  2. Mechanical testing of PHWR components at different fabrication stages

    International Nuclear Information System (INIS)

    Saibaba, N.

    2007-01-01

    Zirconium alloys are extensively used for reactor structural and cladding components for PHWRs and BWRs due to their low neutron absorption cross-section, corrosion resistance to high temperature aqueous environments, adequate mechanical properties and resistance to radiation damage. The coolant tube fabrication route consists of a series of intermediate process steps. The working parameters of each process have a definite bearing on the final properties of these tubes. In order to ascertain the effect of these parameters, mechanical testing is carried out at intermediate stage of coolant tube fabrication. The mechanical properties of the products can be correlated with process parameters and reflect the quality of the product to a great extent. These properties at intermediate stages can serve as process controlling parameters. This paper discusses the correlation of mechanical properties of pressure tubes between the intermediate stage and final stage. The effect of process parameters like annealing temperature, honing, sand blasting pressure and eccentricity on the final mechanical properties was highlighted. (author)

  3. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

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

  4. Clinical Telemedicine Utilization in Ontario over the Ontario Telemedicine Network.

    Science.gov (United States)

    O'Gorman, Laurel D; Hogenbirk, John C; Warry, Wayne

    2016-06-01

    Northern Ontario is a region in Canada with approximately 775,000 people in communities scattered across 803,000 km(2). The Ontario Telemedicine Network (OTN) facilitates access to medical care in areas that are often underserved. We assessed how OTN utilization differed throughout the province. We used OTN medical service utilization data collected through the Ontario Health Insurance Plan and provided by the Ministry of Health and Long Term Care. Using census subdivisions grouped by Northern and Southern Ontario as well as urban and rural areas, we calculated utilization rates per fiscal year and total from 2008/2009 to 2013/2014. We also used billing codes to calculate utilization by therapeutic area of care. There were 652,337 OTN patient visits in Ontario from 2008/2009 to 2013/2014. Median annual utilization rates per 1,000 people were higher in northern areas (rural, 52.0; urban, 32.1) than in southern areas (rural, 6.1; urban, 3.1). The majority of usage in Ontario was in mental health and addictions (61.8%). Utilization in other areas of care such as surgery, oncology, and internal medicine was highest in the rural north, whereas primary care use was highest in the urban south. Utilization was higher and therapeutic areas of care were more diverse in rural Northern Ontario than in other parts of the province. Utilization was also higher in urban Northern Ontario than in Southern Ontario. This suggests that telemedicine is being used to improve access to medical care services, especially in sparsely populated regions of the province.

  5. The Sensitivity Analysis of Axial Pressure Tube Creep Profile for Dryout Power in PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Euiseung; Kim, Youngae [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The Stern Laboratory performed the CHF tests with only one axial pressure tube creep profile per 3.3%, 5.1% peak crept channel and made CHF correlation including creep factor from the CHF test results. Wolsong nuclear power plants also have utilized the same CHF correlation derived by CNL. Pressure tube diameter creep rate is function of fast neutron, coolant temperature, and coolant pressure in a channel. It means that various axial pressure tube creep profiles exist in PHWR due to the history of operating conditions. Usually, CHF correlation is used during ROP(Regional Overpower Protection) Trip Setpoint Analysis or Safety Analysis in PHWR. The sensitivity analysis for CHF effects using various creep profiles is needed. This paper summarizes the comparison results of dryout power between CHF test creep profile and estimated creep profiles of Wolsong units. The effect of axial pressure tube creep profile for dryout power in fuel channel is evaluated by using Stern Lab. CHF test creep profile and 380 channel creep profiles of Wolsong. The dryout powers at 3.3% and 5.1% test conditions are slightly smaller when using 380 Wolsong channels creep profiles. These also show that the simulated dryout powers maintain consistency regardless of flow conditions.

  6. The control of emissions from nuclear power reactors in Canada

    International Nuclear Information System (INIS)

    Gorman, D.J.; Neil, B.C.J.; Chatterjee, R.M.

    1988-01-01

    Nuclear power reactors in Canada are of the CANDU pressurised heavy water design. These are located in the provinces of Ontario, Quebec, and New Brunswick. Most of the nuclear generating capacity is in the province of Ontario which has 16 commissioned reactors with a total capacity of 11,500 MWe. There are four reactors under construction with an additional capacity of 3400 MWe. Nuclear power currently accounts for approximately 50% of the electrical power generation of Ontario. Regulation of the reactors is a Federal Government responsibility administered by the Atomic Energy Control Board (AECB) which licenses the reactors and sets occupational and public dose limits

  7. Ontario Hydro's nuclear program

    International Nuclear Information System (INIS)

    Jackson, H.A.

    1982-06-01

    In 1981 Ontario Hydro generated over 100 billion KWh of electrical energy. Approximately one third of this was from nuclear units. There are ten CANDU units (5 250 MW) currently in operation, and another twelve (8 600 MW) are under construction. The presently committed nuclear expansion program is estimated to involve expenditures of 16 billion dollars over the next 10 years. About 10 000 people are employed in the nuclear design and construction program. All projects are generally on schedule, with the stations coming into service during the following time periods: Pickering B, 1983-85; Bruce B, 1984-87; Darlington, 1988-90. The status of each project is reviewed. Planning is underway for some retubing projects, as early as 1985 for Pickering A

  8. Ontario perspective on interregional markets

    International Nuclear Information System (INIS)

    Shalaby, A.

    2003-01-01

    On May 1, 2002, wholesale and retail electricity markets in Ontario were opened to competition. The industry structure has been completely unbundled into separate entities for power generation, distribution and transmission. There are currently 20 generators, 90 distributors and 4 transmitters in Ontario. Trade with neighbouring jurisdictions has increased and now accounts for 10 to 15 per cent of demand on summer peak days. Import/export capability with the United States (northeast and midwest) and other Canadian provinces (Quebec and Manitoba) is 4,000 to 6,000 MW. Ontario has not had new generation or transmission capacity in several years and the heat waves of summer 2002 resulted in a heavier power demand than forecasted. The province had to rely heavily on power imports resulting in high and volatile electricity prices. In response to customer complaints, the Ontario government froze retail rates and in a recent policy directive announced a public ownership policy for transmission with further consultation on improving supply competition in Ontario. FERC order 888 and the increased role of independent power producers has improved trading opportunities between Canada and the United States. The presentation highlighted recent trade trends and outlined the specific impact of the Standard Market Design on Canadian markets. It was noted that Ontario should work on ensuring power reliability, transmission planning, inter-regional coordination, and joint investments with neighbouring jurisdictions. 9 figs

  9. Current status of 700 MWe class PHWR NSSS design and engineering technology

    International Nuclear Information System (INIS)

    Park, Tae Keun; Suh, Sung Ki

    1996-06-01

    The capability of NSSS design and engineering technology of KAERI for 700 MWe class PHWR (CANDU 6) as of 1996 March 30 is comprehensively summarized in this report. The design and engineering capability of KAERI which have been gained during the implementation of Wolsung 2, 3 and 4 project are assessed, and showed with tangible scale. The status of Technology Transfer Materials received from Atomic Energy of Canada Limited under the Technology Transfer Agreement (TTA) which is effective simultaneously to Wolsung 3 and 4 contract, is also given in this report. The division of responsibility (DOR) of KAERI for Wolsung 2 and Wolsung 3 and 4 contract is also given, and expansion of DOR from Wolsung 2 contract to Wolsung 3 and 4 is presented. 3 refs. (Author)

  10. Computerised weld strength testing machine for PHWR fuel elements with a versatile control system

    International Nuclear Information System (INIS)

    Gupta, U.C.; Sastry, V.S.; Rasheed, Jawad; Bibawe, S.R.

    1994-01-01

    Spacer pads and bearing pads are resistance spot welded on PHWR fuel elements to ensure inter-element gap for coolant flow. These welds are subjected to destructive tests as per SQC specifications while qualifying a machine and during production. The testing machine used earlier over the years was tedious involving manual operations of clamping, tool actuation, increasing and decreasing the pressure, referring to charts and statistical calculations. To carry out the destructive testing of the welds conveniently and reliably, an automatic machine is developed in-house in which are incorporated a quartz force transducer and a computerized data-acquisition and processing system together with a very versatile electronic control system based on a single-chip microcomputer. This paper describes the salient features of the machine and the control system. (author). 4 figs

  11. Garter spring location of pressure tube for PHWR using eddy current testing methods

    International Nuclear Information System (INIS)

    Lee, Y. S.; Yang, D. J.; Jeong, H. K.

    2001-01-01

    There are garter springs between pressure tube and calandria tube for PHWR. If the space of these garter springs become to be changed, the sagging of tube is caused and the contact between the pressure tube and calandria tube will cause the tube to be failed. AECL has applied the eddy current testing methods using send-receive type probe for this purpose, but this study apply eddy current testing methods using bobbin differential type probe to detection of garter spring location. And we did the computer simulation using VIC-3D code and compared it with experiments results for inspection 1 ∼ 11kHz. The results was that the garter spring signal was successfully detected for every frequency, and 5 kHz was best

  12. Ergonomic design of mosaic control panel and standardised control tile configurations for 500 MWe PHWR

    International Nuclear Information System (INIS)

    Ughade, A.V.; Das, R.N.; Ramakrishnan, S.

    1994-01-01

    A review of control rooms of operating nuclear power plants identified many design problems having potential for degrading the performance of operators. Many indications and controls on existing control panels are placed outside the recommended visual and reach envelopes for acceptable operator usage. As a result, the application of human factor principles was found to be needed. This paper describes the design approach for working out the dimensions of main control room panels and console using human engineering principles and recommends the ergonomic dimensions of the main control room panels and console. Further it gives the basis and works out the control tile configurations for 500 MWe PHWR project. It also suggests the use of a full scale mock up for design evaluation and verification. (author). 7 refs., 4 figs

  13. Ontario freight movement study

    International Nuclear Information System (INIS)

    Anon.

    1995-11-01

    The freight (cargo) transportation sector accounts for a major use of fossil fuels and contributes significantly to greenhouse gas emissions. A study was conducted to estimate and forecast emissions from transportation in Ontario, by mode, over the next 15 years, and to examine ways in which those emissions could be reduced. Published data of freight transportation industries was used to examine the fuel consumption characteristics of each mode, followed by a review of emission rates. It was determined that truck transportation accounts for most CO 2 emissions (about 70%). Rail follows with 21% and the marine and air modes contribute relatively small shares (6% and 2%). New intermodal technologies being introduced by the railways were discussed. They have been designed to make intermodal transport more accessible to a wider segment of the freight market. A recommendation was made which would require all truck shipments over 500 km, accounting for fully one half of truck tonne-km, to have their line-haul component diverted to this new more fuel-efficient mode (i.e., from truck to rail). refs., tabs., figs

  14. Reactor simulator development. Workshop material

    International Nuclear Information System (INIS)

    2001-01-01

    The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in reactor operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. This publication consists of course material for workshops on development of such reactor simulators. Participants in the workshops are provided with instruction and practice in the development of reactor simulation computer codes using a model development system that assembles integrated codes from a selection of pre-programmed and tested sub-components. This provides insight and understanding into the construction and assumptions of the codes that model the design and operational characteristics of various power reactor systems. The main objective is to demonstrate simple nuclear reactor dynamics with hands-on simulation experience. Using one of the modular development systems, CASSIM tm , a simple point kinetic reactor model is developed, followed by a model that simulates the Xenon/Iodine concentration on changes in reactor power. Lastly, an absorber and adjuster control rod, and a liquid zone model are developed to control reactivity. The built model is used to demonstrate reactor behavior in sub-critical, critical and supercritical states, and to observe the impact of malfunctions of various reactivity control mechanisms on reactor dynamics. Using a PHWR simulator, participants practice typical procedures for a reactor startup and approach to criticality. This workshop material consists of an introduction to systems used for developing reactor simulators, an overview of the dynamic simulation

  15. Theoretical and experimental investigations into natural circulation behaviour in a simulated facility of the Indian PHWR under reduced inventory conditions

    International Nuclear Information System (INIS)

    Satish Kumar, N.V.; Nayak, A.K.; Vijayan, P.K.; Pal, A.K.; Saha, D.; Sinha, R.K.

    2004-01-01

    A theoretical and experimental investigation has been carried out to study natural circulation characteristics of an Indian PHWR under reduced inventory conditions. The theoretical model incorporates a quasi-steady state analysis of natural circulation at different system inventories. It predicts the system flow rate under single-phase and two-phase conditions and the inventory at which reflux condensation occurs. The model predictions were compared with test data obtained from FISBE (facility for integral system behaviour experiments), which simulates the thermal hydraulic behaviour of the Indian 220 MWe PHWR. The experimental results were found to be in close agreement with the predictions. It was also found that the natural circulation could be oscillatory under reduced inventory conditions. (orig.)

  16. Direct harvesting of Helium-3 (3He) from heavy water nuclear reactors

    International Nuclear Information System (INIS)

    Bentoumi, G.; Didsbury, R.; Jonkmans, G.; Rodrigo, L.; Sur, B.

    2013-01-01

    The thermal neutron activation of deuterium inside a heavy-water-moderated or -cooled nuclear reactor produces a build-up of tritium in the heavy water. The in situ decay of tritium can, for certain reactor types and operating conditions, produce potentially useable amounts of 3 He, which can be directly extracted via the heavy-water cover gas without first separating, collecting and storing tritium outside the reactor. It is estimated that the amount of 3 He available for recovery from the moderator cover gas of a 700 MWe class Pressurized Heavy Water Reactor (PHWR) ranges from 0.1 to 0.7 m 3 (STP) per annum, varying with the tritium activity buildup in the moderator. The harvesting of 3 He would generate approximately 12.7 m 3 (STP) of 3 He, worth more than $30M at current market rates, over a typical 25-year operating cycle of the PHWR. This paper discusses the production of 3 He in the moderator of a PHWR and its extraction from the 4 He moderator cover gas system using conventional methods. (author)

  17. Development of inspection equipment for fuel bundles of CANDU-PHWR using R981 underwater radiation tolerant camera

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Dae-Seo; Cho, Moon-Sung; Jo, Chang-Keun; Jun, Ji-Su; Jung, Jong Yeob; Park, Kwang-June; Suk, Ho-Chun

    2005-03-15

    The inspection equipment of fuel bundles was developed, which could perform visual inspection and dimensional measurement on fuel bundles of CANDU-PHWR, to evaluate, analyze the defective behavior of fuel bundles and inner surface of pressure tubes of inherent two-phase flow over 24kg/s in CANDU-6. The R981 radiation tolerant camera system with pan and tilt function was ordered and manufactured, which was waterproof, shielding radiation in underwater 10m in depth. The performance test, of the system ,due to camera-object distance was carried out in air/underwater atmosphere. The results of performance test of R981 radiation tolerant camera system are good. The inspection equipment of fuel bundles using R981 radiation tolerant camera system and underwater-radiation tolerant LVDT sensor(D5/200AW) was fabricated, which could perform visual inspection and dimensional measurement on fuel bundles of CANDU-PHWR with measurement accuracy 10{mu}m. This equipment will be utilizable integrity evaluation of fuel bundles which are irradiated in pressure tube of CANDU-PHWR.

  18. Reactivity control of nuclear power reactors: new options

    International Nuclear Information System (INIS)

    Alcala, F.

    1984-01-01

    Some actual aspects (referring to economy, non-proliferation and environmental impact) of nuclear power reactors has been analyzed from the point of view of the reactivity control physics. Specially studied have been the physical mechanisms related with the spectral shift control method and their general positive effects on those aspects. The analysis carried out suggested the application of the above method of control to reactors with non-hydrogenous fuel cells, which are mainly characterized by their high moderator/fuel ratio. Finally three different types of such fuel cells are presented and some results about one of them (belonging to a PHWR controlled by graphite rods) are given. (author)

  19. Transmission system planning in Ontario

    Energy Technology Data Exchange (ETDEWEB)

    Barrie, D; Macedo, F X; Mcconnach, J S [Ontario Hydro, Toronto, ON (Canada)

    1994-12-31

    In recent years, new and modified approaches to planning the large transmission system that serves the province of Ontario, Canada, have been necessary to accommodate the rapidly changing planning environment including slower uncertain growth, ageing of facilities, integration of demand side management and non utility generation options, increased competitiveness, increased financial stresses and affordable constraints. This paper describes some of the new and modified approaches and tools that have been adopted or are being developed by Ontario Hydro to cope with this changing environment. (author) 9 refs., 4 figs.

  20. Development of a diagnostic system for identifying accident conditions in a reactor

    International Nuclear Information System (INIS)

    Santhosh; Gera, B.; Kumar, Mithilesh; Thangamani, I.; Prasad, Hari; Srivastava, A.; Dutta, Anu; Sharma, Pavan K.; Majumdar, P.; Verma, V.; Mukhopadhyay, D.; Ganju, Sunil; Chatterjee, B.; Sanyasi Rao, V.V.S.; Lele, H.G.; Ghosh, A.K.

    2009-07-01

    This report describes a methodology for identification of accident conditions in a nuclear reactor from the signals available to the operator. A large database of such signals is generated through analyses - for core, containment, environmental dispersion and radiological dose to train a computer code based on an Artificial Neural Networks (ANNs). At present, in the prediction mode, information on LOCA (location and size of break), status of availability of ECCS, and expected doses can be predicted well for a 220 MWe PHWR. (author)

  1. Ontario Hydro annual report 1986

    Energy Technology Data Exchange (ETDEWEB)

    1987-04-01

    Ontario Hydro`s annual report of the financial position and activities for the year 1986 consists of their financial highlights; corporate profile; customer service and satisfaction; message from Chairman; message from President; 1986 in review; financial section; management report; five-year summary of financial statistics; and comparative statistics.

  2. Ontario Hydro annual report 1986

    International Nuclear Information System (INIS)

    1987-04-01

    Ontario Hydro's annual report of the financial position and activities for the year 1986 consists of their financial highlights; corporate profile; customer service and satisfaction; message from Chairman; message from President; 1986 in review; financial section; management report; five-year summary of financial statistics; and comparative statistics

  3. [Ontario Hydro]. Corporate performance report, 1994

    International Nuclear Information System (INIS)

    1995-01-01

    Summarizes Ontario Hydro's corporate performance for the year, with actual results being compared against planned values. Also includes additional indicators that illustrate noteworthy trends in corporate performance. Corporate results are reported under the new organizational structure implemented in 1993, beginning with overall results in such areas as customer service, environmental stewardship, human resources, and finance. This is followed by reports from the Generation Business Group, Customer Services Group, Corporate Business Group, General Counsel and Secretary, Ontario Hydro Audit, Strategic Planning, Environment and Communication Group, and Ontario Hydro enterprises (Ontario Hydro Technologies, Ontario Hydro International). The appendix includes summary financial statements

  4. Ontario Energy Corporation annual report 1981. [Monograph

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    The Ontario Energy Corporation's mission of providing leadership and investment capital for selected energy ventures brought its total participation in projects from $16.4 million to $669 million, and its total assets increased from $44.4 million to $693 million during the year. The annual report review major operations with Ontario Energy Resources Ltd., Onexco Ltd., Ontario Alternate Energy Ltd., Ontario Power Share Ltd., and Ontario Energy in Transportation Ltd. The financial report includes a balance sheet, income and retained earnings statement, and a summary of financial changes during the reporting period. 1 figure, 4 tables. (DCK)

  5. Accident sequences evaluation using SFATs for low power and shutdown operation of pressurized heavy water reactors

    International Nuclear Information System (INIS)

    Kim, Chansoo; Chung, Chang-Hyun; Yang, Huichang

    2004-01-01

    To maintain the level of defense-in-depth safety of Pressurized Heavy Water Reactor (PHWR) during LP/SD operation, the qualitative risk evaluation methods such as Safety Function Assessment Trees (SFATs) are required. Therefore SFATs are suggested to assess and manage the PHWR safety in LP/SD. Before this study, safety functions of PHWR were classified into 7 groups; Reactivity Control, Core Cooling, Secondary Heat Removal, Primary Heat Transport Inventory, Essential Electrical Power, Cooling Water, and Containment Integrity. The SFATs for PHWR LP/SD operations were developed along with the Plant Outage Status (POS) variation, and totally 38 SFATs were developed for Wolsung Unit 2. For the verification of SFATs logics developed, top 5 accident sequences those contribute the CDF of PHWR were selected, and plant safety status were evaluated for those accident sequences. Accident sequences such as DCC-4 (Dual Control Computer Failure), CL4-16 (Total Loss of Class IV Power), and FWPV-11 (Loss of Feedwater Supply to SG due to Failure of Pumps/Values) were included. In this research the evaluation of plant safety status by accident sequences using SFATs and the verification of the SFATs were performed. Through the verification of SFAT logics, the enhancements to the internal logics of the SFATs were made, and the dependencies between safety systems and support systems were considered. It is expected the defense-in-depth evaluation model of PHW just as SFATs can be utilized in the configuration risk management program (CRMP) development and improve technical specifications development for Korean PHWRs. (author)

  6. Ontario electricity rates and industrial competitiveness

    International Nuclear Information System (INIS)

    2006-01-01

    Industrial electricity prices in Ontario rose significantly after the opening of the competitive Ontario electricity market in 2002, thereby widening the gap between industrial electricity prices in Ontario and those in other Canadian provinces. Navigant Consulting Ltd. conducted this study at the request of the Association of Major Power Consumers in Ontario (AMPCO) to research and compare current and historical electricity prices in Ontario and other jurisdictions in North America. The study provided an independent analysis of how industrial electricity prices in Ontario compare to those in other jurisdiction in which AMPCO members operate. It also formed the basis for comparing the impacts of electricity policy on the economic competitiveness of major power consumers in Ontario. The relative electricity intensity in the United States, Ontario and other Canadian provinces was reviewed for specific industries, including forest products, steel manufacturing, petroleum refining, chemical manufacturing and cement manufacturing. Publicly available aggregate data from Statistics Canada and the United States Bureau of the Census was then used to compare average electricity prices for industrial customers in Ontario. The data confirmed that Ontario has experienced a decline in its competitive price advantage in industrial electricity. Delivered industrial electricity prices in Ontario have increased by more than 60 per cent since 2001. Industrial electricity prices in Ontario rose above those in Quebec, Manitoba, British Columbia and New Brunswick. In addition, industrial electricity prices in Ontario rose above those in competing states such as Ohio and Illinois, in part due to the increase in the value of the Canadian dollar. It was concluded that the price increase may lead to a greater decline in economic output in Ontario compared to competing jurisdictions. 2 tabs., 14 figs., 1 appendix

  7. Pressure suppression pool hydrodynamic studies for horizontal vent exit of Indian PHWR containment

    International Nuclear Information System (INIS)

    Mohan, N.; Bajaj, S.S.; Saha, P.

    1994-01-01

    The standard Indian PHWR incorporates a pressure suppression type of containment system with a suppression pool.The design of KAPS (Kakrapar Atomic Power Station) suppression pool system adopts a modified system of downcomers having horizontal vents as compared to vertical vents of NAPS (Narora Atomic Power Station). Hydrodynamic studies for vertical vents have been reported earlier. This paper presents hydrodynamic studies for horizontal type vent system during LOCA. These studies include the phenomenon of vent clearing (where the water slug standing in downcomer initially is injected to wetwell due to rapid pressurization of drywell) followed by pool swell (elevation of pool water due to formation of bubbles due to air mass entering pool at the exit of horizontal vents from drywell). The analysis performed for vent clearing and pool swell is based on rigorous thermal hydraulic calculation consisting of conservation of air-steam mixture mass, momentum and thermal energy and mass of air. Horizontal vent of downcomer is modelled in such a way that during steam-air flow, variation of flow area due to oscillating water surface in downcomer could be considered. Calculation predicts that the vent gets cleared in about 1.0 second and the corresponding downward slug velocity in the downcomer is 4.61 m/sec. The maximum pool swell for a conservative lateral expansion is calculated to be 0.56 m. (author). 3 refs., 12 figs

  8. Final report on the evolution of supporting conditions for the feeders of 500 MWe PHWR

    International Nuclear Information System (INIS)

    Mishra, Rajesh; Soni, R.S.; Kushawaha, H.S.; Mahajan, S.C.; Kakodkar, A.; Hariprasad, K.

    1994-01-01

    This report deals with the evolution of generic supporting conditions for the feeders of 500 MWe PHWR based on the analysis and qualification of a few representative feeders. There are 196 different feeder pipe configurations for a total of 748 feeders. The present analysis was aimed at evolving a generalised supporting criteria based on the analysis of some representative feeders. The analysis was carried out for various loadings viz. pressure, temperature, dead weight, operating basis earthquake (OBE), safe shutdown earthquake (SSE) and creep loadings. The analysis for OBE and SSE loadings were carried out using response spectrum method. The effect of spacers between various feeders was modelled using higher damping values than those prescribed in ASME code. Based on the above analyses, generic supporting arrangements for the feeders of various groups have been finalized. This report gives details about the mathematical modelling, the analysis approach, the optimised supporting criteria, finalization of grouping and fixing of boundaries between various groups of feeders. (author). 34 refs., 51 figs., 69 tabs

  9. Mathematical modelling of heat absorption capacity of containment spray system in a 700 MWe PHWR

    International Nuclear Information System (INIS)

    Kota, Sampath Bharadwaj; Ali, Seik Mansoor; Balasubramaniyan, V.

    2015-01-01

    This paper presents a mathematical model for estimating the heat removal by containment spray system in the post Loss of Coolant Accident (LOCA) environment. The procedure involves firstly, the calculation of heat removal rates by droplets of spray dispersed in the air-steam mixture by an appropriate direct contact condensation model accounting for the presence of non-condensable gas (air). Parametric influence of droplet size, ambient pressure and temperature on heat flux is brought out. It was found that the heat flux is inversely proportional to the ambient pressure and diameter. A spray module was subsequently developed and incorporated into an in-house containment thermal hydraulics code. The pressure and temperature transients in a 700 MWe PHWR containment building following a Large Break LOCA was obtained using this code. The efficacy of the spray in condensing the steam is shown by comparing the transients with and without the operation of spray system. Parametric studies are also conducted with respect to droplet size and flow rate of water droplet spray. The details of the investigation are presented and discussed in this paper. (author)

  10. Studies on the separation and purification of uranium from thoria irradiated in PHWR

    International Nuclear Information System (INIS)

    Kedari, C.S.; Sinalkar, N.; Dhami, P.S.; Achuthan, P.V.; Vijayan, K.; Moorthy, A.D.; Jambunathan, U.; Munshi, S.K.; Dey, P.K.

    2005-10-01

    About 5 g of thoria pellet extracted from the thoria bundle irradiated to 508 full power days in PHWR at KAPS and cooled for about 4.5 years was dissolved in 25 mL of 13 M HNO 3 containing 0.03 M HF and 0.1 M Al(NO 3 ) 3 under reflux condition in a shielded glove box. Thorium concentration and acidity of the dissolved solution was adjusted to ∼97 g/L and 4M HNO 3 , suitable for solvent extraction studies. The feed solution had a uranium concentration of 1.36 g/L and gross gamma activity of ∼6 Ci/L. Liquid-liquid extraction experiments were carried out in batch with this feed using 3% TBP in n-dodecane as extractant. The uranium product solution obtained from the solvent extraction was further purified by ion-exchange method using cation exchange resin Dowex 50 x 4. Fission product activity and the isotopic composition of the final recovered product were measured. The uranium product had an overall decontamination factor of 10 4 and 2 x 10 4 with respect to thorium and fission product activity respectively. A part of the solution was monitored for dose build-up due to the growth of the decay products of 232 U which is a vital input for designing the shielding of a 233 U separation facility. (author)

  11. Licensing assessment of the Candu Pressurized Heavy Water Reactor. Preliminary safety information document. Volume II

    International Nuclear Information System (INIS)

    1977-06-01

    ERDA has requested United Engineers and Constructors (UE and C) to evaluate the design of the Canadian natural uranium fueled, heavy water moderated (CANDU) nuclear reactor power plant to assess its conformance with the licensing criteria and guidelines of the U.S. Nuclear Regulatory Commission (USNRC) for light water reactors. This assessment was used to identify cost significant items of nonconformance and to provide a basis for developing a detailed cost estimate for a 1140 MWe, 3-loop Pressurized Heavy Water Reactor (PHWR) located at the Middletown, USA Site

  12. Measurement of fission gas release, internal pressure and cladding creep rate in the fuel pins of PHWR bundle of normal discharge burnup

    Energy Technology Data Exchange (ETDEWEB)

    Viswanathan, U.K. [Post Irradiation Examination Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India); Sah, D.N., E-mail: dnsah@barc.gov.i [Post Irradiation Examination Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India); Rath, B.N.; Anantharaman, S. [Post Irradiation Examination Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India)

    2009-08-01

    Fuel pins of a Pressurised Heavy Water Reactor (PHWR) fuel bundle discharged from Narora Atomic Power Station unit no. 1 after attaining a fuel burnup of 7528 MWd/tU have been subjected to two types of studies, namely (i) puncture test to estimate extent of fission gas release and internal pressure in the fuel pin and (ii) localized heating of the irradiated fuel pin to measure the creep rate of the cladding in temperature range 800 deg. C - 900 deg. C. The fission gas release in the fuel pins from the outer ring of the bundle was found to be about 8%. However, only marginal release was found in fuel pins from the middle ring and the central fuel pin. The internal gas pressure in the outer fuel pin was measured to be 0.55 +- 0.05 MPa at room temperature. In-cell isothermal heating of a small portion of the outer fuel pins was carried out at 800 deg. C, 850 deg. C and 900 deg. C for 10 min and the increase in diameter of the fuel pin was measured after heat treatment. Creep rates of the cladding obtained from the measurement of the diameter change of the cladding due to heating at 800 deg. C, 850 deg. C and 900 deg. C were found respectively to be 2.4 x 10{sup -5} s{sup -1}, 24.6 x 10{sup -5} s{sup -1} and 45.6 x 10{sup -5} s{sup -1}.

  13. MATLAB/SIMULINK model of CANDU reactor for control studies

    International Nuclear Information System (INIS)

    Javidnia, H.; Jiang, J.

    2006-01-01

    In this paper a MATLAB/SIMULINK model is developed for a CANDU type reactor. The data for the reactor are taken from an Indian PHWR, which is very similar to CANDU in its design. Among the different feedback mechanisms in the core of the reactor, only xenon has been considered which plays an important role in spatial oscillations. The model is verified under closed loop scenarios with simple PI controller. The results of the simulation show that this model can be used for controller design and simulation of the reactor systems. Adding models of the other components of a CANDU reactor would ultimately result in a complete model of CANDU plant in MATLAB/SIMULINK. (author)

  14. Ontario Hydro Research Division, 1980

    International Nuclear Information System (INIS)

    The work of the Research Division of Ontario Hydro provides technical and scientific support for the engineering and operation of a power system that includes hydraulic, fossil-fired, and nuclear generation. It also relates to the transmission and distribution of electricity and to the need to help customers use electricity with safety and economy. Among the examples of projects given are qualification of CANDU heat transport system components, pressure tube replacement, steam generator integrity, testing for earthquake resistance, and radioactive waste disposal

  15. Transforming Ontario's Power Generation Company

    International Nuclear Information System (INIS)

    Manley, J.; Epp, J.; Godsoe, P.C.

    2004-01-01

    The OPG Review Committee was formed by the Ontario Ministry of Energy to provide recommendations and advice on the future role of Ontario Power Generation Inc. (OPG) in the electricity sector. This report describes the future structure of OPG with reference to the appropriate corporate governance and senior management structure. It also discusses the potential refurbishing of the Pickering A nuclear generating Units 1, 2 and 3. The electricity system in Ontario is becoming increasingly fragile. The province relies heavily on electricity imports and the transmission system is being pushed to near capacity. Three nuclear generating units are out of service. The problems can be attributed to the fact that the electricity sector has been subjected to unpredictable policy changes for more than a decade, and that the largest electricity generator (OPG) has not been well governed. OPG has had frequent senior management change, accountability has been weak, and cost overruns have delayed the return to service of the Pickering nuclear power Unit 4. It was noted that the generating assets owned and operated by OPG are capable of providing more than 70 per cent of Ontario's electricity supply. Decisive action is needed now to avoid a potential supply shortage of about 5,000 to 7,000 megawatts by 2007. In its current state, OPG risks becoming a burden on ratepayers. Forty recommendations were presented, some of which suggest that OPG should become a rate-regulated commercial utility focused on running and maintaining its core generating assets. This would require that the government act as a shareholder, and the company operate like a commercial business. It was also emphasized that the market must be allowed to bring in new players. refs., tabs., figs

  16. Safety characteristics analysis of nuclear power plants with PHWR PT; Analiza sigurnosnh karakteristika nuklearnih elektrana sa reaktorima PHWR-PT tipa

    Energy Technology Data Exchange (ETDEWEB)

    Stosic, Z [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1983-07-01

    The paper deals with analysis of basic safety characteristics of heavy water Candu reactor. Inherent safety characteristics, r/a material inventory, systematization of normal abnormal and transient conditions, safety systems and availability analysis are considered. (author)

  17. [Ontario Hydro International Inc.]. Annual report 1993

    International Nuclear Information System (INIS)

    1994-01-01

    Ontario Hydro International Inc. is the international representative of Ontario Hydro. OHII operates as a global utility that markets Ontario Hydro's services and products. Its mission is to be the leader in energy efficiency and sustainable development in the international marketplace. This report describes the year's activities in the following areas: Energy management and environment, hydroelectric generation, nuclear products and services, fossil generation, grid (transmission) business, utility management, Asia Power Group Inc. The document also includes financial highlights and international and customer contracts

  18. Ultrasonic evaluation of end cap weld joints of fuel elements of pressurized heavy water reactors using signal analysis methods

    International Nuclear Information System (INIS)

    Raj, B.; Thavasimuthu, M.; Subramanian, C.V.; Kalyanasundaram, P.; Rajagopalan, C.

    1992-01-01

    This paper describes the application of ultrasonic digital signal analysis for the detection of fine defects of the order of 10% or lower of wall thickness (WT) of 370 microns in the resistance welded end cap-cladding tube joints of fuel elements used in Pressurised Heavy Water Reactors (PHWR s). The results obtained for the detection of such defects, have confirmed the sensitivity and reliability of this approach, and were further validated by destructive metallography. (author)

  19. Alternative models for restructuring Ontario's electric sector

    International Nuclear Information System (INIS)

    Bright, D.; Salaff, S.

    1996-01-01

    The future of Ontario Hydro and the provincial electrical sector was discussed. Various models proposed for restructuring Ontario's electric sector were described and views of some of the stake holders were presented, among them the views of AMPCO, MEA, the Ontario Chamber of Commerce, IPPSO, Ontario Hydro Management, Energy Probe and the Power Workers' Union. In general, most stake holders were in favour of privatization to some degree except for the Power Workers' Union which was unalterably opposed to privatization, claiming that it would lead to quantum increases in electricity rates. 2 figs

  20. [Ontario Hydro]. Corporate performance report, 1993

    International Nuclear Information System (INIS)

    1994-01-01

    Summarizes Ontario Hydro's corporate performance for the year, with actual results being compared against planned values established in the approved corporate financial plan and work program budget. Also includes additional indicators that illustrate noteworthy trends in corporate performance. Corporate results are reported under the new organizational structure implemented in mid-1993, beginning with overall results in such areas as customer satisfaction, electricity sales, human resources, and environmental protection. This is followed by reports from the Electricity Group (supply, generation, transmission), the Energy Services and Environment Group (load saved and shifted, non-utility generation, retail distribution), and Ontario Hydro enterprises (Ontario Hydro Technologies, Ontario Hydro International). The appendix contains summary financial statements

  1. The restructuring of the Ontario electricity market

    International Nuclear Information System (INIS)

    Doucet, J.A.

    1999-01-01

    A summary of the current status of the deregulation of the electricity market in Ontario was presented. To follow global deregulation trends, the Ontario Government has embarked on a considerable restructuring of the Ontario electricity market. The monopoly position of Ontario Hydro has been removed by restructuring the provincial utility into two separate companies, GENCO and SERVCO, which will be responsible for the generation and transmission and distribution of electricity, respectively. Other mechanisms put in place to favour a free and competitive market for electricity in the province, such as the arrival on the market of other electricity producers, and the establishment of the independent market operator, are also discussed. 2 tabs

  2. The Education Act (Ontario) 1980: A Review.

    Science.gov (United States)

    Hodder, C. J.

    1984-01-01

    Ontario has provided special education legislation through the Education Amendment Act, 1980. Issues related to teacher preparation for special education and program planning and implementation are reviewed. (DF)

  3. Post Chernobyl safety review at Ontario Hydro

    International Nuclear Information System (INIS)

    Frescura, G.M.; Luxat, J.C.; Jobe, C.

    1991-01-01

    It is generally recognized that the Chernobyl Unit 4 accident did not reveal any new phenomena which had not been previously identified in safety analyses. However, the accident provided a tragic reminder of the potential consequences of reactivity initiated accidents (RIAs) and stimulated nuclear plant operators to review their safety analyses, operating procedures and various operational and management aspects of nuclear safety. Concerning Ontario Hydro, the review of the accident performed by the corporate body responsible for nuclear safety policy and by the Atomic Energy Control Board (the Regulatory Body) led to a number of specific recommendations for further action by various design, analysis and operation groups. These recommendations are very comprehensive in terms of reactor safety issues considered. The general conclusion of the various studies carried out in response to the recommendations, is that the CANDU safety design and the procedures in place to identify and mitigate the consequences of accidents are adequate. Improvements to the reliability of the Pickering NGSA shutdown system and to some aspects of safety management and staff training, although not essential, are possible and would be pursued. In support of this conclusion, the paper describes some of the studies that were carried out and discusses the findings. The first part of the paper deals with safety design aspects. While the second is concerned with operational aspects

  4. Licensing assessment of the CANDU pressurized heavy water reactor. Volume I. Preliminary safety information document

    International Nuclear Information System (INIS)

    1977-06-01

    The PHWR design contains certain features that will require significant modifications to comply with USNRC siting and safety requirements. The most significant of these features are the reactor vessel; control systems; quality assurance program requirements; seismic design of structures, systems and components; and providing an inservice inspection program capability. None of these areas appear insolvable with current state-of-the-art engineering or with upgrading of the quality assurance program for components constructed outside of the USA. In order to be licensed in the U. S., the entire reactor assembly would have to be redesigned to comply with ASME Boiler and Pressure Vessel Code, Section III, Division 1 and Division 2. A summary matrix at the end of this volume identifies compliance of the systems and structures of the PHWR plant with the USNRC General Design Criteria. The matrix further identifies the estimated incremental cost to a 600 MWe PHWR that would be required to license the plant in the U. S. Further, the matrix identifies whether or not the incremental licensing cost is size dependent and the relative percentage of the base direct cost of a Canadian sited plant

  5. Acoustic emission technique for leak detection in an end shield of a pressurized heavy water reactor

    International Nuclear Information System (INIS)

    Kalyanasundaram, P.; Jayakumar, T.; Raj, B.

    1989-01-01

    This paper discusses the successful application of the Acoustic Emission Technique (AET) for detection and location of leak paths present on the inaccessible side of an end shield of a Pressurized Heavy Water Reactor (PHWR). The methodology was based on the fact that air and water leak AE signals have different characteristic features. Baseline data was generated from a sound end-shield of a PHWR for characterizing the background noise. A mock up end-shield system with saw cut leak paths was used to verify the validity of the methodology. It was found that air leak signals under pressurisation (as low as 3 psi) could be detected by frequency domain analysis. Signals due to air leaks from various locations of a defective end-shield were acquired and analysed. It was possible to detect and locate leak paths. Presence of detected leak paths were further confirmed by alternate test. (orig.)

  6. Evaluation of a dilute chemical decontaminant for pressurized heavy water reactors

    International Nuclear Information System (INIS)

    Velmurugan, S.; Narasimhan, S.V.; Mathur, P.K.; Venkateswarlu, K.S.

    1991-01-01

    In this paper a dilute chemical decontamination formulation based on ethylene diamine tetraacetic acid, oxalic acid, and citric acid is evaluated for its efficacy in removing oxide layers in a pressurized heavy water reactor (PHWR). An ion exchange system that is specifically suited for fission product-dominated contamination in a PHWR is suggested for the reagent regeneration stage of the decontamination process. An attempt has been made to understand the redeposition behavior of various isotopes during the decontamination process. The polarographic method of identifying the species formed in the dissolution process is explained. Electrochemical measurements are employed to follow the course of oxide removal during the dissolution process. Scanning electron micrographs of metal coupons before and after the dissolution process exemplify the involvement of base metal in the formation of a ferrous oxalate layer. Material compatibility tests between the decontaminant and carbon steel, Monel-400, and Zircaloy-2 are reported

  7. MCCI study for Pressurized Heavy Water Reactor under hypothetical accident condition

    International Nuclear Information System (INIS)

    Verma, Vishnu; Mukhopadhyay, Deb; Chatterjee, B.; Singh, R.K.; Vaze, K.K.

    2011-01-01

    In case of severe core damage accident in Pressurized Heavy Water Reactor (PHWR), large amount of molten corium is expected to come out into the calandria vault due to failure of calandria vessel. Molten corium at high temperature is sufficient to decompose and ablate concrete. Such attack could fail CV by basement penetration. Since containment is ultimate barrier for activity release. The Molten Core Concrete Interaction (MCCI) of the resulting pool of debris with the concrete has been identified as an important part of the accident sequence. MCCI Analysis has been carried out for PHWR for a hypothetical accident condition where total core material is considered to be relocated in calandria vault. Concrete ablation rate in vertical and radial direction is evaluated for rectangular geometry using MEDICIS module of ASTEC Code. Amount of gases released during MCCI is also evaluated. (author)

  8. Health physics in fusion reactor design

    International Nuclear Information System (INIS)

    Wong, K.Y.; Dinner, P.J.

    1984-06-01

    Experience in the control of tritium exposures to workers and the public gained through the design and operation of Ontario Hydro's nuclear stations has been applied to fusion projects and to design studies on emerging fusion reactor concepts. Ontario Hydro performance in occupational tritium exposure control and environmental impact is reviewed. Application of tritium control technologies and dose management methodology during facility design is highlighted

  9. Thermal hydraulic simulation of the CANDU nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Athos M.S.S. de; Ramos, Mario C.; Costa, Antonella L.; Fernandes, Gustavo H.N., E-mail: athos1495@yahoo.com.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Instituto Nacional de Ciência e Tecnologia de Reatores Nucleares Inovadores (INCT/CNPq), Rio de janeiro, RJ (Brazil)

    2017-07-01

    The CANDU (Canada Deuterium Uranium) is a Canadian-designed power reactor of PHWR type (Pressurized Heavy Water Reactor) that uses heavy water (deuterium oxide) for moderator and coolant, and natural uranium for fuel. There are about 47 reactors of this type in operation around the world generating more than 23 GWe, highlighting the importance of this kind of device. In this way, the main purpose of this study is to develop a thermal hydraulic model for a CANDU reactor to aggregate knowledge in this line of research. In this way, a core modeling was performed using RELAP5-3D code. Results were compared with reference data to verify the model behavior in steady state operation. Thermal hydraulic parameters as temperature, pressure and mass flow rate were verified and the results are in good agreement with reference data, as it is being presented in this work. (author)

  10. Nuclear power at Ontario Hydro

    International Nuclear Information System (INIS)

    Tapon, F.; Osborne, T.J.

    1980-01-01

    This case study shows that the diffusion of nuclear power in the electric public utility industry in Canada approximates the logistic growth curve, in agreement with previous results on technological innovation diffusion in the U.S. private sector. Many of the economic variables that affect this diffusion in the private sectors in the U.S. and Canada are also significant in the public sector in Canada. Too few utilities have adopted nuclear technology to permit using regression analysis to study the effect of environmental and regulatory factors on the growth of Ontario Hydro. Thus, cost-benefit analysis for each province might be more effective

  11. The Ontario Energy Marketers Association

    International Nuclear Information System (INIS)

    Baker, W.F.C.

    1998-01-01

    An overview of the role of the Ontario Energy Marketers Association (OEMA) and its future orientation was presented. Participants in the OEMA include agents, brokers, marketers, local distribution companies, public interest representatives, associations and government representatives. The role of the OEMA is to encourage open competition for the benefit and protection of all energy consumer and market participants. As well, the OEMA serves as a forum for key industry stakeholders to resolve market issues outside the regulatory arena, set standards and codes of practice, establish customer education programs, and develop industry input into public policy making

  12. Thermal-hydraulic interfacing code modules for CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Liu, W.S.; Gold, M.; Sills, H. [Ontario Hydro Nuclear, Toronto (Canada)] [and others

    1997-07-01

    The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis.

  13. Thermal-hydraulic interfacing code modules for CANDU reactors

    International Nuclear Information System (INIS)

    Liu, W.S.; Gold, M.; Sills, H.

    1997-01-01

    The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis

  14. Reactor safety

    International Nuclear Information System (INIS)

    Meneley, D.A.

    The people of Ontario have begun to receive the benefits of a low cost, assured supply of electrical energy from CANDU nuclear stations. This indigenous energy source also has excellent safety characteristics. Safety has been one of the central themes of the CANDU development program from its very beginning. A great deal of work has been done to establish that public risks are small. However, safety design criteria are now undergoing extensive review, with a real prospect of more stringent requirements being applied in the future. Considering the newness of the technology it is not surprising that a consensus does not yet exist; this makes it imperative to discuss the issues. It is time to examine the policies and practice of reactor safety management in Canada to decide whether or not further restrictions are justified in the light of current knowledge

  15. Annual progress report for 1982 of Theoretical Reactor Physics Section

    International Nuclear Information System (INIS)

    Rastogi, B.P.; Kumar, Vinod

    1983-01-01

    The progress of work done in the Theoretical Reactor Physics Section of the Bhabha Atomic Research Centre, Bombay, during the calendar year 1982 is reported in the form of write-ups and summaries. The main thrust of the work has been to master the neutronic design technology of four different types of nuclear reactor types, namely, pressurized heavy water reactors, boiling light water reactors, pressurized light water reactors and fast breeder reactors. The development work for the neutronic analysis, fuel design, and fuel management of the BWR type reactors of the Tarapur Atomic Power Station has been completed. A new reactor simulator system for PHWR design analysis and core follow-up was completed. Three dimensional static analysis codes based on nodal and finite element methods for the design work of larger size (500-750 MWe) reactors have been developed. Space link kinetics codes in one, two and three dimensions for above-mentioned reactor systems have been written and validated. Fast reactor core disruptive analysis codes have been developed. In the course of R and D work concerning various types of reactor projects, investigations were also carried in the allied areas of Monte Carlo techniques, integral transform methods, path integral methods, high spin states in heavy nuclei and a hydrodynamics model for a laser driven fusion system. (M.G.B.)

  16. Indian experience with radionuclide transport, deposition and decontamination in water-cooled nuclear power reactors

    International Nuclear Information System (INIS)

    Narasimhan, S.V.; Das, P.C.; Lawrence, D.A.; Mathur, P.K.; Venkateswarlu, K.S.

    1983-01-01

    The present generation of water-cooled nuclear reactors uses construction materials chosen with utmost care so that minimum corrosion occurs during the life of the reactor. As interaction between the primary coolant and the construction materials is unavoidable, the coolant is chemically treated to achieve maximum compatibility. First measurements of the chemical and radiochemical composition of the crud present on the in-core and out-of-core primary heat transport system surfaces of a pressurized heavy-water-moderated and cooled reactor (PHWR) are given; then experience in India in the development of a low temperature, one-stage decontaminating formulation for chemical decontamination of the radioactive deposits formed on stainless steel surfaces under BWR conditions is discussed. The effect of the magnitude of the transients in parameters such as reactor power, system temperature, dissolved oxygen content in the coolant, etc. on the nature and migration behaviour of primary heat transport system crud in a PHWR is described. Contributions to radioactive sources and insoluble crud from different primary heat transport system materials are identified and correlated with reactor operations in a PHWR. Man-rem problems faced by nuclear reactors, especially during off-line maintenance, stress the need for reducing the deposited radioactive sources from system surfaces which would otherwise be accessible. Laboratory and on-site experimentation was carried out to effect chemical decontamination on the radioactive deposits formed on the stainless steel surfaces under BWR conditions. Both the reducing and oxidizing formulations were subsequently used in a small-scale, in-plant trial in the clean-up system of a BWR. More than 85% of the deposited 60 Co activity was found to have been removed by the oxidizing formulation. Efforts to develop a decontaminating mixture containing a reducing agent with the help of a circulating loop are in progress in the laboratory. (author)

  17. Growth scenarios with thorium fuel cycles in pressurised heavy water reactors

    International Nuclear Information System (INIS)

    Balakrishnan, M.R.

    1991-01-01

    Since India has generous deposits of thorium, the availability of thorium will not be a limiting factor in any growth scenario. It is fairly well accepted that the best system for utilisation of thorium is the heavy water reactor. The growth scenarios possible using thorium in HWRs are considered. The base has been taken as 50,000 tons of natural uranium and practically unlimited thorium. The reference reactor has been assumed to be the PHWR, and all other growth scenarios are compared with the growth scenario provided by the once-through natural cycle in the PHWR. Two reactor types have been considered: the heavy water moderated, heavy water cooled, pressure tube reactor, known as the PHWR; and the heavy water moderated and cooled pressure vessel kind, similar to the ATUCHA reactor in Argentina. For each reactor, a number of different fuel cycles have been studied. All these cycles have been based on thorium. These are: the self-sustaining equilibrium thorium cycle (SSET); the high conversion ratio high burnup cycle; and the once through thorium cycle (OTT). The cycle have been initiated in two ways: one is by starting the cycle with natural uranium, reprocessing the spent fuel to obtain plutonium, and use that plutonium to initiate the thorium cycle; the other is to enrich the uranium to about 2-3% U-235 (the so-called Low Enriched Uranium or LEU), and use the LEU to initiate the thorium cycle. Both cases have been studied, and growth scenarios have been projected for every one of the possible combinations. (author). 1 tab

  18. Examining Competition in Ontario's Higher Education Market

    Science.gov (United States)

    Farhan, Bayan Yousef

    2017-01-01

    Financial challenges have forced many publicly funded academic institutions in Ontario to adopt a corporate model and to use market tools to compete in the higher education market and maintain their enrolment and revenue levels. This study has analyzed how competition affects publicly funded universities in Ontario. Competition was examined by…

  19. Ontario Hydro Research Division annual report 1988

    International Nuclear Information System (INIS)

    1988-01-01

    The Research Division of Ontario Hydro conducts research in the fields of chemistry, civil engineering, electrical engineering, mechanical engineering, metallurgy, and operations. Much of the research has a bearing on the safe, environmentally benign operation of Ontario Hydro's nuclear power plants. Particular emphasis has been placed on nuclear plant component aging and plant life assurance

  20. [Overview of acupuncture development in Ontario Canada].

    Science.gov (United States)

    Wang, Fang; Wu, Bin-jiang

    2012-04-01

    The history of acupuncture in Ontario, Canada was traced, and the current status as welI as the prospection were introduced in this paper. Statistics showed that the history of acupuncture in Ontario started in the 1880s, and it was only popular in China Town and Chinese community. In the 1970s, it gradually merged into the mainstream of the society, and entered into a growing period. With the tide of Chinese immigration in the 1980s and 1990s, acupuncture matured rapidly. In 2006, the "Traditional Chinese Medicine Act" was passed in Ontario, it was considered as a milestone in the history of acupuncture. At present, just like the other 23 health care professions, acupuncture has already be included into the legislation system, and become a component of Ontario's health care system. At the same time, the law and regulation may also promote the establishment of "pure Chinese Medicine" in Ontario.

  1. Ontario hydro radioactive material transportation field guide

    International Nuclear Information System (INIS)

    Howe, W.

    1987-01-01

    The recent introduction of both the AECB Transport Packaging of Radioactive Material Regulations and Transport Canada's Transportation of Dangerous Goods Regulations have significantly altered the requirements for transporting radioactive material in Canada. Extensive additional training as well as certification of several hundred Ontario Hydro employees has been necessary to ensure compliance with the additional and revised regulatory requirements. To assist in the training of personnel, an 'active' corporate Ontario Hydro Field Guide for Radioactive Material Transport document has been developed and published. The contents of this Field Guide identify current Ontario Hydro equipment and procedures as well as the updated relevant regulatory requirements within Canada. In addition, to satisfying Ontario Hydro requirements for this type of information over two thousand of these Field Guides have been provided to key emergency response personnel throughout the province of Ontario to assist in their transportation accident response training

  2. Green power opportunities for Ontario

    International Nuclear Information System (INIS)

    Elwell, C.; Rotenberg, E.; Torrie, R.; Poch, D.; Allen, G.

    2002-02-01

    Green energy is defined as the energy generated from renewable and environmentally benign sources. In this document, the authors demonstrated that Ontario possesses the potential to reduce energy waste on an economic basis while generating sufficient green energy to enable the province to decommission its coal burning power plants. In turn, this would lead to a more sustainable energy economy and a lesser reliance on nuclear generation. It was determined that a three-fold policy would enable the province to achieve this goal. First, there is a need to remove hidden subsidies to polluting forms of generation. The second aspect of this policy is the implementation of a robust Demand Side Management Program, and the third aspect calls for the reform of the price of electricity that includes all costs. In this manner, all forms of generation would compete on an equal footing. The authors identified an alternative to immediate price reform in the form of a legislated Renewable Portfolio Standard. A growing percentage of new renewable electricity in the supply portfolio offered by electricity providers would be required by the Renewable Portfolio Standard. It was suggested that the Ontario government adopt this measure before the opening of the electricity market in May 2002, as strong support for the measure is present. 13 refs

  3. The uranium deposits of Ontario

    International Nuclear Information System (INIS)

    Robertson, J.A.

    1981-01-01

    The principal types of uranium deposits in Ontario are carbonatites and fenites, alkalic volcanic rocks, pegiatites, calc-silicate rocks, pyritic quartz-pebble conglomerates, polymictic conglomerates and some pelitic rocks, and various 'pitchblende' deposits including late Precambrian unconformities, possibly late Precambrian diabase dikes, and other unconformities: carbonates, sandstones, lignites, and semi-pelitic rocks of middle and upper Precambrian age. Only red unzoned pegmatite and the pyritic quartz-pebble conglomerate have supported production. Ontario reasonably assured and estimated resources in the economic and subeconomic categories in 1977 amounted to 553 000 tonnes U, and 1977 production was 4000 tonnes U. Measured, indicated, and inferred resources in the Elliot Lake - Agnew Lake area are at least 400 000 tonnes U. The latter deposits are also a significant thorium resource. Geological features reflecting major changes in physics and chemistry are prime controls on distribution of uranium deposits. Geological province and subprovince boundaries, major faults, higher metamorphic grades, domain boundaries related to quartz monzonite batholiths, alkalic complexes, and the distribution of carbonate rocks are examples of such geological features

  4. Ontario is not ready to face a large-scale nuclear accident

    International Nuclear Information System (INIS)

    2017-07-01

    On paper, in Japan as elsewhere, nuclear emergency plans are based on international standards and all look similar. The counter measures are sheltering, potassium iodate prophylaxis, evacuation and control of foodstuffs. With 18 nuclear reactors to produce electricity and a research reactor, Ontario should be especially well prepared. Moreover, in USA, there are six power plants located at less than 100 km from the Canadian border. Would Ontario do better than Japan in case of a severe nuclear disaster? Ontario is not ready to face a severe nuclear accident and the population surrounding nuclear power stations are at risk. The large number of inhabitants will hamper protective response actions. Consequently, Canadian authorities keep lax protective action levels. Using more stringent levels would mean to extend the protection zone that would include a too large number of persons. Canadian authorities should openly acknowledge that a severe nuclear accident could happen in Ontario like in any other country and trigger a complete reorganisation of emergency preparedness and response (EP and R) to cope with such a possibility. New response plans should be defined with the involvement of stakeholders

  5. Operating performance and reliability of CANDU PHWR fuel channels in Canada

    International Nuclear Information System (INIS)

    Strachan, B.; Brown, D.R.

    1983-03-01

    CANDU nuclear plants use many small-diameter high-pressure fuel channels. Good operating performance from the CANDU fuel channels has made a major contribution to the world-leading operating record of the CANDU nuclear power plants. As of 1982 December 31, there were 7,480 fuel channels installed in 18 CANDU reactors over 500 MW(e) in size. Eight of these reactors have been declared in-service and have accumulated 24,000 fuel channel-years of operation. The only significant operating problems with fuel channels have been the occurrence of leaking cracks in 70 fuel channels and a larger amount of axial creep on the early reactors than was originally provided for in the design. Both of these problems have been corrected on all CANDU reactors built since the Bruce GS 'A' station and the newer reactors should exhibit even better performance

  6. Experimental and inspection facilities in post-irradiation of spent fuel pools for the analysis of the behaviour of nuclear fuels in power reactors

    International Nuclear Information System (INIS)

    Ruggirello, G.; Zawerucha, A.

    1992-01-01

    Since the beginning of the Atomic Nuclear Reactors (PHWR) Atucha I and Embalse in Argentine are employed different techniques for the knowing of the fuel bundles performances. It is detailed the facilities on post-irradiation examination. The techniques described are: online measurements, visual inspections, identifications of defective fuels and rods assemblies in spent fuel pools. This controls have made possible the feed-back to the manufactory process and the changes in the manufactory quality controls. (author)

  7. Recent experience related to neutronic transients in Ontario Hydro CANDU nuclear generating stations

    International Nuclear Information System (INIS)

    Frescura, G.M.; Smith, A.J.; Lau, J.H.

    1991-01-01

    Ontario Hydro presently operates 18 CANDU reactors in the province of Ontario, Canada. All of these reactors are of the CANDU Pressurized Heavy Water design, although their design features differ somewhat reflecting the evolution that has taken place from 1971 when the first Pickering unit started operation to the present as the Darlington units are being placed in service. Over the last three years, two significant neutronic transients took place at the Pickering Nuclear Generating Station 'A' (NGS A) one of which resulted in a number of fuel failures. Both events provided valuable lessons in the areas of operational safety, fuel performance And accident analysis. The events and the lessons learned are discussed in this paper

  8. Meeting Ontario's electricity needs : a critical review of the Ontario Power Authority's supply mix advice report

    International Nuclear Information System (INIS)

    Gibbons, J.; Fracassi, J.

    2006-01-01

    In December, 2005 the Ontario Power Authority (OPA) outlined its proposed blueprint for meeting Ontario's electricity needs to 2025 in the document entitled Supply Mix Advice Report. As a result of the actions taken by the current government, the OPA believes that Ontario will have adequate electricity supplies to meet the province's needs until 2013. However, it stated that Ontario will require an additional 15,000 megawatts of new generation capacity between 2013 and 2025. The OPA also recommends that a significant proportion of this new generation capacity be nuclear. The Ontario Clean Air Alliance undertook a review of the OPA report and identified several discrepancies including an over-estimation of Ontario's rate of electricity load growth from 2005 to 2025; an under-estimation of the potential for electricity productivity improvements to reduce electricity demand and raise living standards; an under-estimation of renewable energy supply potential; an under-estimation of the potential for biomass and natural gas fired combined heat and power plants to meet electricity needs and increase the competitiveness of Ontario's industries; an under-estimation of the economic costs and risks of nuclear power; and a biased recommendation for a 70 million dollar resource acquisition budget against energy efficiency investments that would reduce demand and raise living standards. This report provides the Ontario Clean Air Alliances' analysis of the OPA report and presents it own recommendations for how Ontario can increase its electricity productivity and meet its electricity supply needs until 2025. The report concluded that the Government of Ontario should direct the OPA to develop a long-term strategy to raise the price of electricity up to its full cost without raising the electricity bills of low income consumers or impairing the competitiveness of Ontario's industries. It was suggested that Ontario's electricity productivity should be increased to the same level as

  9. Evaluation of ultimate load bearing capacity of the primary containment of a typical 540 MWe Indian PHWR

    International Nuclear Information System (INIS)

    Ray, Indrajit; Roy, Raghupati; Verma, U.S.P.; Warudkar, A.S.

    2003-01-01

    This paper presents the analysis of the Inner Containment Structure (ICS) of a typical 540 MWe Indian PHWR for the purpose of evaluating its ultimate load bearing capacity (ULBC) under beyond postulated design basis accident (DBA) scenario. The methodology adopted for the non-linear analysis of the prestressed concrete ICS including the various issues, viz. behaviour of concrete under compression and tension, tension stiffening, cracked shear modulus etc. have also been discussed in this paper. The effect of accident temperature on ULBC has been studied and discussed in this paper. This paper also discusses about the study carried out for mesh sensitivity of the finite element (FE) discretization on ULBC of ICS in the non-linear range. Based on the detailed analysis, the factor of safety of the ICS under beyond postulated DBA scenario has been evaluated. (author)

  10. An evolutionary approach to advanced water cooled reactors

    International Nuclear Information System (INIS)

    Antariksawan, A.R.; Subki, I.

    1997-01-01

    Based on the result of the Feasibility Study undertaken since 1991, Indonesia may enter in the new nuclear era by introduction of several Nuclear Power Plants in our energy supply system. Requirements for the future NPP's are developed in two step approach. First step is for the immediate future that is the next 50 years where the system will be dominated by A-LWR's/A-PHWR's and the second step is for the time period beyond 50 years in which new reactor systems may start to dominate. The integral reactor concept provides a revolutionary improvements in terms of conceptual and safety. However, it creates a new set of complex machinery and operational problems of its own. The paper concerns with a brief description of nuclear technology status in Indonesia and a qualitative assessment of integral reactor concept. (author)

  11. In-core fuel management programs for nuclear power reactors

    International Nuclear Information System (INIS)

    1984-10-01

    In response to the interest shown by Member States, the IAEA organized a co-ordinated research programme to develop and make available in the open domain a set of programs to perform in-core fuel management calculations. This report summarizes the work performed in the context of the CRP. As a result of this programme, complete in-core fuel management packages for three types of reactors, namely PWR's, BWR's and PHWR are now available from the NEA Data Bank. For some reactor types, these program packages are available with three levels of sophistication ranging from simple methods for educational purposes to more comprehensive methods that can be used for reactor design and operation. In addition some operating data have been compiled to allow code validation. (author)

  12. Selection of the number of moderator circuits for Argos PHWR 380 by means of multicriteria decision aiding technique

    International Nuclear Information System (INIS)

    Espejo, J.A.

    1989-01-01

    One of the problems in the design of Argos PHWR 380 was the selection of the number of moderator circuits. Two options were proposed, one with three circuits and the other with two circuits. The multicriteria outranking technique was applied to choose the best option. This method has the ability to handle both commensurable and qualitative criteria. It was considered The following prior criteria were cosidered to estimate the weighting factors in decreasing order of importance: public safety, licensing risk, availability (from the point of view of service quality), investment, normal operating dose. The qualification of these factors is discussed in the report as well as the utility functions. For the criteria operating cost and normal operating dose the differences between the utility values of the two options are masked by other factors. For this reason these two criteria were excluded and the analysis was made taking into account the remainding four criteria. The utility matrix was made with the utility values. From the utility matrix and the weighting factors, the concordance and the discordance matrixes were obtained. Adopting appropriate thresholds, both options were compared with the aid of the code Mulcri - I. The result of the comparison, described in the report, shows that the option of three moderator circuits is preferable to the option of two circuits. With the help of code Mulcri - I, a sensitivity analysis by modifying the utility values one by one was made. The analysis shows those variations lower than 50 % which do not revert the result. Variations from 50 % to 80 % revert the result in only a few cases. This means that it is not necessary to go deeper in the analysis of the estimations of the utility values. It is concluded that the option of three circuits finally adopted in Argos PHWR 380 design is preferable to the option of two circuits. (Author)

  13. Ontario energy market review and outlook

    International Nuclear Information System (INIS)

    Brett, J.T.

    1997-01-01

    The current status of the natural gas industry and the electric power industry in Ontario, in terms of deregulation, was described. Natural gas utilities will exit the regulated gas market over the next few years and transfer their existing residential and small commercial gas contracts to their unregulated affiliates. Nevertheless, a regulated gas supply option will remain until the regulator is assured that consumer protection issues have been properly addressed, and there is a truly competitive market. Ontario Hydro is a vertically integrated virtual monopoly. It lags behind B.C., Alberta, Quebec and Nova Scotia in terms of deregulation and restructuring, although the MacDonald Commission's recent report recommended sweeping changes to Ontario Hydro's monopoly over the electric power industry. A final response from the Ontario government is still pending. The convergence of the electric power and natural gas industries was also discussed

  14. Revitalizing the nuclear business at Ontario Hydro

    International Nuclear Information System (INIS)

    Talbot, K.

    1994-01-01

    Ontario Hydro, North America's largest electric power utility, with an installed capacity of 34,000 MW, has under gone a major restructuring over the past year to better align itself with a changing electricity market and evolving customer needs. The single largest new business unit within the new Ontario Hydro is Ontario Hydro Nuclear (OHN), responsible for engineering, operation and maintenance of the Corporation's 20 large nuclear units at three generating sites, OHN faces a significant challenge in returning Ontario's nuclear units to the world-leading performance levels they enjoyed in the past, particularly the older Pickering A and Bruce A plants. However, steady progress is being made as evidenced by improving peer reviews and overall capacity and financial performance

  15. Water chemistry features of advanced heavy water reactor

    International Nuclear Information System (INIS)

    Sriram, Jayasree; Vijayan, K.; Kain, Vivekanad; Velmurugan, S.

    2015-01-01

    Advanced Heavy Water Reactor (AHWR) being designed in India proposes to use Plutonium and Thorium as fuel. The objective is to extract energy from the uranium-233 formed from Thorium. It is a heavy water moderated and light water cooled tube type boiling water reactor. It is a heavy water moderated and light water cooled tube type boiling water reactor. It is a natural circulation reactor. Thus, it has got several advanced passive safety features built into the system. The various water coolant systems are listed below. i) Main Heat transport System ii) Feed water system iii) Condenser cooling system iv) Process water system and safety systems. As it is a tube type reactor, the radiolysis control differs from the normal boiling water reactor. The coolant enters the bottom of the coolant channel, boiling takes place and then the entire steam water mixture exits the core through the long tail pipes and reaches the moisture separator. Thus, there is a need to devise methods to protect the tail pipes from oxidizing water chemistry condition. Similarly, the moderator heavy water coolant chemistry differs from that of moderator system chemistry of PHWR. The reactivity worth per ppm of gadolinium and boron are low in comparison to PHWR. As a result, much higher concentration of neutron poison has to be added for planned shutdown, start up and for actuating SDS-2. The addition of higher concentration of neutron poison result in higher radiolytic production of deuterium and oxygen. Their recombination back to heavy water has to take into account the higher production of these gases. This paper also discusses the chemistry features of safety systems of AHWR. In addition, the presentation will cover the chemistry monitoring methodology to be implemented in AHWR. (author)

  16. X-ray safety in Ontario

    International Nuclear Information System (INIS)

    1980-03-01

    In July 1979 the Ontario Advisory Committee on Radiology was formed to develop a comprehensive strategy for x-ray safety in the province. At its hearings the committee recieved submissions from groups representing physicians, dentists, chiropractors, radiological technicians, physiotherapists, podiatrists, and consumers, among others; these briefs are included as appendices to the report. The report surveys the historical background and the current situation in Ontario, and makes recommendations for an organized safety program. (L.L.)

  17. Market prices for solar electricity in Ontario

    International Nuclear Information System (INIS)

    Rowlands, I.H.

    2006-01-01

    The Ontario electricity supply is facing considerable challenges while demand is increasing due to a growing population and increased economic growth needs. In response to these challenges, the government of Ontario established the Ontario Power Authority (OPA) in 2004 to ensure adequate, reliable and secure electricity supply and resources in Ontario. The OPA has also engaged in activities to facilitate the diversification of sources of electricity supply by promoting the use of cleaner energy sources and technologies, including alternative energy sources and renewable energy. The purpose of this paper was to advance discussions regarding the contribution that solar PV can make to Ontario's supply mix. In particular, it determined the value of the electricity that would have been produced by a PV system located in Waterloo, Ontario under the following 4 pricing regimes: (1) the conventional small user tariff system currently in place in Ontario, (2) the time-of-use pricing system that is voluntarily available to those who have smart meters installed in their facilities, (3) the spot market, hourly prices, to which some of Ontario's largest electricity users are exposed, and (4) the recently-proposed rate for standard offer contracts for PV systems. The study showed that a solar PV system that produces 3,000 kWh of electricity over the course of a year would generate different revenue amounts, ranging from the smallest amount of approximately $174.00 to $1,260.00, depending on the pricing regime. The pricing regime that reflects real, time-of-day electricity prices appears to be most advantageous to solar PV systems. It was recommended that additional work is needed regarding the other benefits of solar PV, such as avoided capacity/generation needs, avoided transmission and distribution cost and losses, environmental benefits, and job creation. 3 refs., 4 tabs., 8 figs

  18. Annual report 1993 (Ontario Hydro, Toronto)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    Ontario Hydro`s prime objective is to supply the people of Ontario with electricity at cost while maintaining high standards of safety and service. The annual report presents energy efficiency and competitiveness, operations in review, the environmental performance of the Corporation, the future, and choices for a sustainable future. A financial review and analysis is also provided, along with an auditor`s report and financial statements.

  19. Application of Genetic Algorithm methodologies in fuel bundle burnup optimization of Pressurized Heavy Water Reactor

    International Nuclear Information System (INIS)

    Jayalal, M.L.; Ramachandran, Suja; Rathakrishnan, S.; Satya Murty, S.A.V.; Sai Baba, M.

    2015-01-01

    Highlights: • We study and compare Genetic Algorithms (GA) in the fuel bundle burnup optimization of an Indian Pressurized Heavy Water Reactor (PHWR) of 220 MWe. • Two Genetic Algorithm methodologies namely, Penalty Functions based GA and Multi Objective GA are considered. • For the selected problem, Multi Objective GA performs better than Penalty Functions based GA. • In the present study, Multi Objective GA outperforms Penalty Functions based GA in convergence speed and better diversity in solutions. - Abstract: The work carried out as a part of application and comparison of GA techniques in nuclear reactor environment is presented in the study. The nuclear fuel management optimization problem selected for the study aims at arriving appropriate reference discharge burnup values for the two burnup zones of 220 MWe Pressurized Heavy Water Reactor (PHWR) core. Two Genetic Algorithm methodologies namely, Penalty Functions based GA and Multi Objective GA are applied in this study. The study reveals, for the selected problem of PHWR fuel bundle burnup optimization, Multi Objective GA is more suitable than Penalty Functions based GA in the two aspects considered: by way of producing diverse feasible solutions and the convergence speed being better, i.e. it is capable of generating more number of feasible solutions, from earlier generations. It is observed that for the selected problem, the Multi Objective GA is 25.0% faster than Penalty Functions based GA with respect to CPU time, for generating 80% of the population with feasible solutions. When average computational time of fixed generations are considered, Penalty Functions based GA is 44.5% faster than Multi Objective GA. In the overall performance, the convergence speed of Multi Objective GA surpasses the computational time advantage of Penalty Functions based GA. The ability of Multi Objective GA in producing more diverse feasible solutions is a desired feature of the problem selected, that helps the

  20. Large catchment area recharges Titan's Ontario Lacus

    Science.gov (United States)

    Dhingra, Rajani D.; Barnes, Jason W.; Yanites, Brian J.; Kirk, Randolph L.

    2018-01-01

    We seek to address the question of what processes are at work to fill Ontario Lacus while other, deeper south polar basins remain empty. Our hydrological analysis indicates that Ontario Lacus has a catchment area spanning 5.5% of Titan's surface and a large catchment area to lake surface area ratio. This large catchment area translates into large volumes of liquid making their way to Ontario Lacus after rainfall. The areal extent of the catchment extends to at least southern mid-latitudes (40°S). Mass conservation calculations indicate that runoff alone might completely fill Ontario Lacus within less than half a Titan year (1 Titan year = 29.5 Earth years) assuming no infiltration. Cassini Visual and Infrared Mapping Spectrometer (VIMS) observations of clouds over the southern mid and high-latitudes are consistent with precipitation feeding Ontario's large catchment area. This far-flung rain may be keeping Ontario Lacus filled, making it a liquid hydrocarbon oasis in the relatively dry south polar region.

  1. Ontario's power market post November 11

    International Nuclear Information System (INIS)

    Murphy, P.

    2003-01-01

    This paper provides a review of Ontario's first year with an open electricity market. The year 2002 to 2003 had record energy demands with challenges on the supply side. In particular, generation availability was below expectations during the summer months. This demonstrated that price predictability and volatility needs to be addressed and investment in new power generation is needed in Ontario. Ontario demand forecasts outpace supply for the long term outlook. In addition, most of Ontario's generating plants are aging and will soon exceed their nominal service life, requiring major refurbishment or replacement. Decisions are needed now on the future of coal in Ontario's generation mix. It was also noted that transmission reinforcements are needed in the Greater Toronto Area (GTA). In the short term, consumers can expect delays in return to service of nuclear units, forced extensions to planned outages, and reduced outlook for energy from hydroelectric resources. It was noted that Ontario will continue to rely on imports, although emergency generation is being installed. 5 figs

  2. Development of pre-startup equipment for light water reactors

    International Nuclear Information System (INIS)

    Ram, Rajit; Borkar, S.P.; Dixit, M.Y.; Das, Debashis; Patil, R.K.

    2010-01-01

    Light water reactor (LWR) core typically has high excess reactivity as compared to Pressurized Heavy Water Reactor (PHWR). Unlike PHWR, where online refueling is done, LWR is operated for a long period to achieve maximum fuel burn-up before refueling. Since the reactivity is always reducing with burn-up of the core, the positions of control rods at criticality are always changing in a single direction, i.e. away from the core. Therefore it is possible to start the LWR even if the nuclear instrumentation is not online, provided the criticality position of control rods is known for previous operation. However, for the very first startup, the criticality position of control rods is required to be determined. A special nuclear instrumentation system, called Pre-startup equipment (PSE) is developed using two numbers of in-core detectors along with the processing electronics. The PSE enables operators to determine the criticality position of control rods for the first startup at zero power. The same equipment can also be used during loading of fuel assemblies. This paper discusses the features and architecture of PSE, its individual circuit blocks and specifications. (author)

  3. Aspects on thorium utilization in heavy water reactors

    International Nuclear Information System (INIS)

    1978-11-01

    Some of the main problems of the Th - PHWR cycles are analyzed. With respect to the burnup limitations introduced by SSET cycle conditions and the burnup sensitivities of this reference cycle, estimates are presented using an integrated neutron-heavy element balance method. A PHWR of 1 GW(e) very similar to the CANDU current design was selected. In the case of 0.5% uranium losses, 11000 MWD/tHE and 13000 MWD/tHE were considered for U-235, respectively, for the Pu initialization of the cycle, the corresponding inventory being 4 t U-235/GW(e) and 5 t Pu (with 72% fissile content) per GW(e) for one year delay time between reactor out to reactor in, 66% capacity factor, 27 MW (fission)/tHE medium specific power. The following aspects are also analyzed: Safety problems associated with low delayed neutron fraction values; High and intermediate burnup fuel elements conceptual problems; Specific problems of thorium reprocessing; Specific problems for radioactive wastes and thorium storage; U-232 content evaluations and related fuel fabrication problems

  4. Reactivity requirements and safety systems for heavy water reactors

    International Nuclear Information System (INIS)

    Kati, S.L.; Rustagi, R.S.

    1977-01-01

    The natural uranium fuelled pressurised heavy water reactors are currently being installed in India. In the design of nuclear reactors, adequate attention has to be given to the safety systems. In recent years, several design modifications having bearing on safety, in the reactor processes, protective and containment systems have been made. These have resulted either from new trends in safety and reliability standards or as a result of feed-back from operating reactors of this type. The significant areas of modifications that have been introduced in the design of Indian PHWR's are: sophisticated theoretical modelling of reactor accidents, reactivity control, two independent fast acting systems, full double containment and improved post-accident depressurisation and building clean-up. This paper brings out the evolution of design of safety systems for heavy water reactors. A short review of safety systems which have been used in different heavy water reactors, of varying sizes, has been made. In particular, the safety systems selected for the latest 235 MWe twin reactor unit station in Narora, in Northern India, have been discussed in detail. Research and Development efforts made in this connection are discussed. The experience of design and operation of the systems in Rajasthan and Kalpakkam reactors has also been outlined

  5. Proceedings of the Canadian Institute's 3. annual conference on generation adequacy in Ontario : strategies to increase capacity to ensure a reliable electricity supply in Ontario

    International Nuclear Information System (INIS)

    2006-01-01

    This conference provided a forum for the discussion of issues related to generation adequacy in Ontario. Members of the electricity industry as well as members from governmental and non-governmental agencies discussed a variety of recommendations for cost-effective reliable energy in Ontario. Issues related to the overhaul or replacement of nuclear power reactors and coal-fired generators in the province were reviewed. The status of various wind power projects in the province was examined along with issues related to interconnected power systems. Best practices for the planning and execution of electricity infrastructure projects were also reviewed, and issues related to stakeholder involvement in electricity generation projects were discussed. The discussions also described recent developments in electricity generation in various jurisdictions in Canada and the United States. The conference featured 19 presentations, of which 7 have been catalogued separately for inclusion in this database. tabs., figs

  6. The low enriched uranium fuel cycle in Ontario

    International Nuclear Information System (INIS)

    Archinoff, G.H.

    1979-02-01

    Six fuel-cycle strategies for use in CANDU reactors are examined in terms of their uranium-conserving properties and their ease of commercialization for three assumed growth rates of installed nuclear capacity in Ontario. The fuel cycle strategies considered assume the continued use of the natural uranium cycle up to the mid-1990's. At that time, the low-enriched uranium (LEU) cycle is gradually introduced into the existing power generation grid. In the mid-2020's one of four advanced cycles is introduced. The advanced cycles considered are: mixed oxide, intermediate burn-up thorium (Pu topping), intermediate burn-up thorium (U topping), and LMFBR. For comparison purposes an all natural uranium strategy and a natural uranium-LEU strategy (with no advanced cycle) are also included. None of the strategies emerges as a clear, overall best choice. (LL)

  7. Introducing Physician Assistants to Ontario

    Directory of Open Access Journals (Sweden)

    Meredith Vanstone

    2014-02-01

    Full Text Available In 2006, the Ontario Ministry of Health and Long-Term Care (MOHLTC introduced Physician Assistants (PAs through the announcement of demonstration projects, education and training programs, and subsequent funding. PAs are directly supervised by physicians and act as physician extenders by performing acts as delegated to them by their supervising physicians. PAs were proposed as a potential solution to help improve access to health care and reduce wait times throughout the province. Prior to the 2006 Ministry announcement, there was little public discussion regarding the acceptance of the PA role or its sustainability. Opposition from nursing and other groups emerged in response to the 2006 announcement and flared again when stakeholder comments were solicited in 2012 as part of the PA application for status as regulated health professionals. As a health reform, the introduction of PAs has neither succeeded nor failed. In 2013, the majority of PA funding continues to be provided by the MOHLTC, and it is unknown whether the PA role will be sustainable when the MOHTLC withdraws salary funding and health system employers must decide whether or not to continue employing PAs at their own expense.

  8. Ontario Hydro annual report, 1988

    International Nuclear Information System (INIS)

    1989-04-01

    Ontario continues a strong growth in electricity consumption; over the past five years consumption has risen an average of 5 percent a year. In 1988 consumption rose by 6.5 percent to 133.1 billion kilowatt-hours. Peak demand was 23 million kilowatts. The top priority for the 1990s will be improving the energy efficiency of customers and the operating efficiency of the Corporation, with a target saving of 4500 megawatts through demand management and energy efficiency by the year 2000. A new environmental division has been formed, as well as a division for non-utility generation. Safety is of particular importance to the Nuclear Generating Division; in all nuclear operations, after 143 million hours worked from 1955 to 1988, there has never been a work-related fatality or a detectable injury due to radiation. The average radiation dose per worker continues to decline and is now under 10 percent of the legal dose limit. Retubing of Pickering Nuclear Generating Station unit 2 has been completed. Retubing of unit 1 is under way, and work on units 3 and 4 has been approved. Construction continues on the Darlington Nuclear Generating Station, where the first unit is expected to go into service in 1989. The Darlington Tritium Removal Facility was completed

  9. Reactor protection systems of 500 MWe PHWRs

    Energy Technology Data Exchange (ETDEWEB)

    Mallik, G; Kelkar, M G; Apte, Ravindra [C and I Group, Nuclear Power Corporation, Mumbai (India)

    1997-03-01

    The 500 MWe PHWR has two totally independent, diverse, fast acting shutdown system called Shutdown System 1 (SDS 1) and Shutdown System 2 (SDS 2). The trip generation circuitry of SDS 1 and SDS 2 are known as Reactor Protection System 1 (RPS 1) and Reactor Protection System 2 (RPS 2) respectively. Some of the features specific to 500 MWe reactors are Core Over Power Protection System (COPPS) based upon in core Self Powered Neutron Detector (SPND) signals, use of local two out of three coincidence logic and adoption of overlap testing for RPS 2, use of Fine Impulse Testing (FIT) in RPS 2, testing of the final control elements namely electro-magnetic clutch of individual Shutoff Rods (SRs) of SDS 1 and all the fast acting valves of SDS 2, etc. The two shutdown systems have totally separate sets of sensors and associated signal processing circuitry as well as physical arrangements. A separate computerised test and monitoring unit is used for each of the two shutdown systems. Use of Programmable Digital Comparator (PDC) unit exclusively for reactor protection systems, has been adopted. The capability of PDC unit is enhanced and communication links are provided for its integration in over all system. The paper describes the design features of reactor protection systems. (author). 3 refs., 7 figs., 3 tabs.

  10. Ontario Hydro diversifies into tritium

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    A report is given on a plant which is to be built at the Darlington Candu reactor site in Canada for the extraction of tritium from heavy water. As tritium is used as a fuel in fusion research the market for it is expected to grow. The design of the system is outlined with the help of a flow diagram. (U.K.)

  11. Development of the advanced PHWR technology -Verification tests for CANDU advanced fuel-

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Jang Hwan; Suk, Hoh Chun; Jung, Moon Kee; Oh, Duk Joo; Park, Joo Hwan; Shim, Kee Sub; Jang, Suk Kyoo; Jung, Heung Joon; Park, Jin Suk; Jung, Seung Hoh; Jun, Ji Soo; Lee, Yung Wook; Jung, Chang Joon; Byun, Taek Sang; Park, Kwang Suk; Kim, Bok Deuk; Min, Kyung Hoh [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    This is the `94 annual report of the CANDU advanced fuel verification test project. This report describes the out-of pile hydraulic tests at CANDU-hot test loop for verification of CANFLEX fuel bundle. It is also describes the reactor thermal-hydraulic analysis for thermal margin and flow stability. The contents in this report are as follows; (1) Out-of pile hydraulic tests for verification of CANFLEX fuel bundle. (a) Pressure drop tests at reactor operation condition (b) Strength test during reload at static condition (c) Impact test during reload at impact load condition (d) Endurance test for verification of fuel integrity during life time (2) Reactor thermal-hydraulic analysis with CANFLEX fuel bundle. (a) Critical channel power sensitivity analysis (b) CANDU-6 channel flow analysis (c) Flow instability analysis. 61 figs, 29 tabs, 21 refs. (Author).

  12. Development of the advanced PHWR technology -Verification tests for CANDU advanced fuel-

    International Nuclear Information System (INIS)

    Jung, Jang Hwan; Suk, Hoh Chun; Jung, Moon Kee; Oh, Duk Joo; Park, Joo Hwan; Shim, Kee Sub; Jang, Suk Kyoo; Jung, Heung Joon; Park, Jin Suk; Jung, Seung Hoh; Jun, Ji Soo; Lee, Yung Wook; Jung, Chang Joon; Byun, Taek Sang; Park, Kwang Suk; Kim, Bok Deuk; Min, Kyung Hoh

    1995-07-01

    This is the '94 annual report of the CANDU advanced fuel verification test project. This report describes the out-of pile hydraulic tests at CANDU-hot test loop for verification of CANFLEX fuel bundle. It is also describes the reactor thermal-hydraulic analysis for thermal margin and flow stability. The contents in this report are as follows; (1) Out-of pile hydraulic tests for verification of CANFLEX fuel bundle. (a) Pressure drop tests at reactor operation condition (b) Strength test during reload at static condition (c) Impact test during reload at impact load condition (d) Endurance test for verification of fuel integrity during life time (2) Reactor thermal-hydraulic analysis with CANFLEX fuel bundle. (a) Critical channel power sensitivity analysis (b) CANDU-6 channel flow analysis (c) Flow instability analysis. 61 figs, 29 tabs, 21 refs. (Author)

  13. Safety analysis of the critical facility for AHWR and 500 MWe PHWR

    International Nuclear Information System (INIS)

    Pushpam, Neelima Prasad; Arvind Kumar; Srivenkatesan, R.

    2002-01-01

    Full text: The initiating event for the design basis reactivity accident is the uncontrolled moderator pump up at criticality. This uncontrolled pump up transient is considered to be the enveloping scenario and has been analysed for the reference core with AHWR fuel using point kinetics model. It is the most reactive core among the three with a small b value (core average b= 5.96 mk). The maximum pump rate in critical facility is limited to 300 litres/min which corresponds to the maximum rate of reactivity addition about 0.1 mk/sec. On any reactor trip 6 shut-off rods are inserted into the core along with partial moderator dumps. The reactor is provided with independent safety and regulating channels (SC and RC) to monitor reactor neutronic power and initiate trip at different power levels. After the reactor trips five of the six fast acting shut-off rods (maximum worth rod is unavailable) fall under gravity and at the same time moderator dump is initiated. We have considered shut off rods and moderator dump as two independent shutdown systems. The analysis shows that even if the reactor trips at the high power at 550 watt ignoring the earlier trips, the fuel temperature does not rise beyond 50 degC and the total energy released is less than 20 kW. We also analysed the transients due to uncontrolled withdrawal of absorber rod. In this case also we found that the fuel temperature became ∼54 degC and the total energy release was about 25 kW. The fuel can withstand this temperature. This shows that reactor is safe

  14. Implications of the Ontario government's white paper and competition strategies for Ontario's municipal electric utilities

    International Nuclear Information System (INIS)

    Wills, D.L.

    1998-01-01

    The strategies that Municipal Electric Utilities (MEU) should follow to deal with competition were discussed. North Bay Hydro is the 34th largest MEU out of 300 in Ontario but it serves only 23,000 out of 4 million electrical customers in Ontario. Therefore, the main strategy for municipal utilities to ensure their future would be to become part of an alliance and association like the MEA and the SAC - the Strategic Alliance for Competition and Customer Choice. Strong criticism was voiced regarding the contents of the recent Ontario Government White Paper for being vague with regard to electrical distribution and the role of MEUs in Ontario. It was suggested that it is vitally important that MEUs ally themselves with other stakeholders, to resist an Ontario Hydro monopoly, to make sure that prices stay low, to avoid excessive debt and bureaucratic inefficiency, be innovative, and consumer oriented and be prepared to anticipate events and conditions. 3 figs

  15. Design considerations, operating and maintenance experience with wet storage of Ontario Hydro's used fuel

    International Nuclear Information System (INIS)

    Frost, C.R.

    1989-01-01

    The characteristics of Ontario Hydro's fuel and at-reactor used fuel storage water pools (or used fuel bays) are described. There are two types of bay, known respectively as primary bays and auxiliary bays, used for at- reactor used fuel storage. Used fuel is discharged remotely from Ontario Hydro's reactors to the primary bays for initial storage and cooling. The auxiliary bays are used to receive and store fuel after its initial cooling in the primary bay, and provide additional storage capacity as needed. With on- power fueling of reactors, each reactor of greater than 500 MW(e) net discharges an average of 10 or more used fuel bundles to bay storage every full power day. The logistics of handling such large quantities of used fuel bundles (corresponding to about 300 te/year of uranium for a 4 unit station) present a challenge to designers and operators. The major considerations in used fuel bay design, including site- specific requirements, reliability and quality assurance, are discussed

  16. Post irradiation examination of tight fit garter springs from PHWR after 15 HOY of operation

    International Nuclear Information System (INIS)

    Dubey, J.S.; Shriwastaw, R.S.; Kumar, Ashwini; Shah, Priti Kotak; Rath, B.N.; Kumar, Sunil; Mishra, Prerna; Alur, V.D.; Mallik, G.K.; Anantharaman, S.

    2015-01-01

    Tight fit irradiated garter springs made of Zr-2.5Nb-0.5Cu, belonging to Pressurized Heavy Water Reactors (PHWRs), which had experienced 15 Hot Operation Years (HOY) of operation were subjected to visual, dimensional, metallographic examination and relevant mechanical tests such as stretch, crush and rolling-fatigue tests. The girdle wires, of these garter springs, made of Zr-2 were subjected to tension and bend tests. Methodology of the tests conducted and results of PIE are presented. Significance of the test results are discussed in view of its continued operation in reactor. (author)

  17. Ontario's new electricity market and the future of OPG

    International Nuclear Information System (INIS)

    Howes, H.

    2002-01-01

    The recent measures taken by Ontario Power Generation since 1998 to deregulate the electricity market in the province of Ontario are reviewed. The opening of Ontario's power market in May 2002 will oblige Ontario Power Generation to reduce its market share. The author reviewed the current status of the energy market in Ontario and noted a modest growth in demand. A significant portion of the energy supply is being provided by nuclear, fossil fuels and hydro energy. The challenge facing Ontario Power Generation is to stay competitive in the new deregulated market and to participate in the energy market in the United States. 6 figs

  18. Serological studies on the infection of dogs in Ontario with Borrelia burgdorferi, the etiological agent of Lyme disease

    Science.gov (United States)

    Artsob, Harvey; Barker, Ian K.; Fister, Richard; Sephton, Gregory; Dick, Daryl; Lynch, John A.; Key, Doug

    1993-01-01

    A serological study was undertaken to determine whether dogs in Ontario are being exposed to Borrelia burgdorferi, the etiological agent of Lyme disease. This study consisted of a survey of randomly selected dogs and testing of diagnostic submissions from candidate Lyme disease cases. The survey of 1,095 dogs, bled between January 1988 and August 1989, revealed a total of 65 (5.9%) enzyme-linked immunosorbent assay (ELISA) reactors, of which 22 had immuno-fluorescent antibody assay (IFA) titers ≥1:32. All but one of the IFA-positive and 10 of the ELISA-positive, IFA-negative sera were further tested by western blot. Eight western blot positive and three equivocal reactors were obtained. Three of the eight confirmed reactors had visited areas known to be endemic for Lyme disease, leaving five reactors that might have been infected in previously undocumented areas for B. burgdorferi activity in Ontario. Diagnostic submissions of sera from 223 dogs were received between August 1987 and February 1992. Test results revealed 21 (9.4%) IFA reactors, of which only six had significant titers (≥1:256) and were reactive by an immunodot Borrelia test. All six dogs had travelled to known Lyme endemic areas. Based on results obtained from this study, it seems likely that the agent of Lyme disease is not widespread in Ontario. PMID:17424284

  19. Meeting Ontario's electricity supply challenge

    International Nuclear Information System (INIS)

    Johnson, A.

    2004-01-01

    This paper presents a comparison between nuclear generation and other existing power generation, with particular reference to the natural gas industry. The aim of the paper was to present a rationale for an extensive nuclear restart in the near future in Ontario. An energy forecast was provided, generating capacity requirements were examined, with particular reference to requirements beyond conservation and renewable energy supplies. The cost effectiveness of nuclear rehabilitation was compared to combined cycle gas turbines (CCGT) in terms of capital and non-fuel costs. Future prospects of gas prices were discussed, as well as the possibilities of demand outstripping supply. CCGT costs were compared to nuclear rehabilitation in terms of overall electricity prices, including capital, non-fuel operating costs and fuel costs. Steps towards making the nuclear option a reality included a sustainable market environment; clear policy framework; a balanced energy mix; long term price certainty; and clear regulatory requirements. In was concluded that in order to regenerate its potential, the nuclear industry must demonstrate world class project management; fixed scope; fixed supplier prices; program commitment; guarantees; and realistic future production estimates. It was also concluded that nuclear restart and life extension was an extremely attractive option for consumers, offering long term stable competitive power, with fuel diversity and future reserves as well as zero greenhouse gas emissions and an optimization and use of existing facilities. Challenges in creating the right climate for nuclear rehabilitation were the difficulties in making the nuclear option attractive to investors as well as developing correct estimation of project times, costs, and scopes and allocation of project risks. tabs., figs

  20. Ontario Hydro 1982 annual report

    International Nuclear Information System (INIS)

    1983-05-01

    Due to the economic recession, primary electrical energy demand for the year failed to exceed that of the previous year for the first time since 1944. Actual demand was 100.8 billion kWh, 0.8 per cent below 1981. However, annual peak demand reached 18.1 million kW on January 18, an all-time high, and 5.4 per cent over January 1981. There were 104.1 billion kWh of electricity generated during the year, nearly equally from nuclear, coal, and water power. Nuclear generating units continued their outstanding performance. Bruce-3 completed a 494-day run at continuous power. NPD Generating Station celebrated 20 years of operation. Pickering B unit 5 started up and produced its first power. At Bruce A, a remote-controlled vehicle was used to remove damaged fuel to a shielded flask, completing the job in a short time with low staff radiation exposure. Bruce B construction progressed on schedule; while at Darlington, design and construction continued at a high level, with 1700 workers on site at year-end. Actual net income was $348 million, $38 million below forecast. Coal deliveries were 13.4 million Mg (23 per cent over 1981). Nuclear fuel deliveries to generating stations were 996 Mg (3 per cent over 1981). Agreements were negotiated for the supply of 5200 Mg of uranium concentrates during 1985-93. Nuclear fuel manufacturing contracts were awarded at lower prices than previously attained. Income totalling $163 million from electricity exports to the U.S.A. reduced overall cost of providing electricity to Ontario customers by 5.1 per cent. The Residential Energy Advisory Program surveyed 16,000 homeowners wishing to improve home energy efficiency. There were 20,000 residential customers who received grants to convert from oil to electric heating. Additional consumption resulting from these conversions is estimated at 280 million kWh

  1. Restructuring in Ontario : electricity sector reform

    International Nuclear Information System (INIS)

    Pospisil, S.

    2004-01-01

    Ontario's electricity reform strategy was outlined along with challenge facing Ontario's electricity supply and demand with particular focus on the issue of replacing coal-fired generation. According to reports by the Independent Electricity Market Operator, short-term reserve margins were higher in 2004 than they were in 2003 due to the return to service of some nuclear generating units and planned capacity additions. Ontario's long-term supply and demand situation was also examined. It was noted that lenders hesitate to finance the expansion of generation companies selling into the spot market. Many lenders are requiring that half of the project's output be sold in advance on contract. Other challenges include Ontario's aging generation infrastructure and rising energy prices. The presentation included graphs that compared electricity costs for residential and small business customers across various provinces and states. The main supply and conservation challenges revolve around the large investments required by 2020 to replace coal plants, retire nuclear plants and projected load growth. Ontario's current generation capacity is 154 TWh and the mix is represented by 40 per cent nuclear, 25 per cent coal, 25 per cent hydro, 8 per cent natural gas, 1 per cent oil, and 1 per cent biomass and other renewable energy sources. This paper also addressed the issue of coal generation and air pollution and emphasized the importance of looking at the broad externalities associated with air emissions. tabs., figs

  2. Marketing program for R2000 in Ontario

    International Nuclear Information System (INIS)

    Killins, B.L.

    1990-01-01

    In the Ontario new housing market, Ontario Hydro's goal is to reduce the demand for electricity, increase the utility's visibility in this market, and increase customer satisfaction. Analyses have demonstrated that it costs less to construct new houses according to R-2000 insulation standards than to install new power production and transmission facilities. Research has also shown that R-2000 houses have better air quality and energy efficiency than ordinary houses. Nevertheless, most home builders have little enthusiasm for R-2000 houses; the strictness of airtightness standards, the slowness of certification, excessive paperwork, and a lack of promised marketing support are cited as the reasons for this. Ontario Hydro and builders' associations have signed a cooperative agreement for certifying new houses with the object of self-financing the program. The program intends to see construction of 1,000 R-2000 houses in 1990. To carry out this objective, some elements have been added to Ontario Hydro's marketing program in order to make potential customers aware of the advantages of the R-2000 house. Field staff will receive rigorous training in order to prepare them for helping the diverse types of builders. A mail campaign, focusing on areas not served by natural gas where significant numbers of new houses are being built, intends to bring home builders and buyers together. In February 1990, Ontario Hydro signed agreements with four major housing manufacturers to construct a significant proportion of the R-2000 housing stock

  3. Darlington NGD valve packing program

    International Nuclear Information System (INIS)

    Spence, C.G.

    1995-01-01

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

  4. Evolution of new X and Y positioning system for 540 MWe PHWR fuelling machines - based on commissioning experience

    International Nuclear Information System (INIS)

    Gupta, Vivek; Vyas, A.K.; Gupta, K.S.; Rama Mohan, N.; Bhambra, H.S.

    2006-01-01

    In PHWR units, X and Y positioning system is provided to give feedback regarding the misalignment between end-fitting and Fuelling Machine (FM) Head during homing on process for carrying out the correction before clamping the Head. The existing design of X and Y Positioning System works by measuring the misalignment by sensing the tilt of the FM Head in X and Y direction caused by its mechanical interfacing with end-fitting as it is advanced in Z direction. The misalignment of Head is corrected by moving it in X and Y direction by X-fine and Y-fine drives, at Z pre-stop position. This correction is vital for achieving the satisfactory sealing of heavy water from channel at snout of FM Head with end fitting. During testing and commissioning trials, it was found that the end fitting of 540 MWe coolant channel assembly either tilts or bends due to the application of load by Fuelling Machines during the process of homing-on of FM Head. Due to this phenomenon, value of misalignment sensed by the Positioning System was considerably lower than the actual misalignment and consequently results in uncorrected misalignment. It was also observed that the high unbalanced moments caused by movement of heavier mass of B-ram in FM Head was further aggravating the misalignment problem. The problem, as an interim measure, was solved by optimising the loads acting on the end fitting to achieve the practically minimum possible uncorrected misalignment. However, to provide a lasting solution for this problem, a new X and Y Positioning System has been evolved. In this system, the misalignment between FM Head and end fitting is found by direct actuation of linear Variable Differential Transformer (LVDT) sensors by four separate alignment plates mounted on the snout. Further development to evolve a completely non-invasive technique using laser sensors has also been undertaken. This paper describes the problems encountered during commissioning of existing design of X and Y Positioning

  5. Lessons learned from Ontario wind energy disputes

    Science.gov (United States)

    Fast, Stewart; Mabee, Warren; Baxter, Jamie; Christidis, Tanya; Driver, Liz; Hill, Stephen; McMurtry, J. J.; Tomkow, Melody

    2016-02-01

    Issues concerning the social acceptance of wind energy are major challenges for policy-makers, communities and wind developers. They also impact the legitimacy of societal decisions to pursue wind energy. Here we set out to identify and assess the factors that lead to wind energy disputes in Ontario, Canada, a region of the world that has experienced a rapid increase in the development of wind energy. Based on our expertise as a group comprising social scientists, a community representative and a wind industry advocate engaged in the Ontario wind energy situation, we explore and suggest recommendations based on four key factors: socially mediated health concerns, the distribution of financial benefits, lack of meaningful engagement and failure to treat landscape concerns seriously. Ontario's recent change from a feed-in-tariff-based renewable electricity procurement process to a competitive bid process, albeit with more attention to community engagement, will only partially address these concerns.

  6. Assessing Ontario's Personal Support Worker Registry

    Directory of Open Access Journals (Sweden)

    Audrey Laporte

    2013-08-01

    Full Text Available In response to the growing role of personal support workers (PSWs in the delivery of health care services to Ontarians, the Ontario government has moved forward with the creation of a PSW registry. This registry will be mandatory for all PSWs employed by publicly funded health care employers, and has the stated objectives of better highlighting the work that PSWs do in Ontario, providing a platform for PSWs and employers to more easily access the labour market, and to provide government with information for human resources planning. In this paper we consider the factors that brought the creation of a PSW registry onto the Ontario government’s policy agenda, discuss how the registry is being implemented, and provide an analysis of the strengths and weaknesses of this policy change.

  7. Uranium and thorium deposits of Northern Ontario

    International Nuclear Information System (INIS)

    Robertson, J.A.; Gould, K.L.

    1983-01-01

    This, the second edition of the uranium-thorium deposit inventory, describes briefly the deposits of uranium and/or thorium in northern Ontario, which for the purposes of this circular is defined as that part of Ontario lying north and west of the Grenville Front. The most significant of the deposits described are fossil placers lying at or near the base of the Middle Precambrian Huronian Supergroup. These include the producing and past-producing mines of the Elliot Lake - Agnew Lake area. Also included are the pitchblende veins spatially associated with Late Precambrian (Keweenawan) diabase dikes of the Theano Point - Montreal River area. Miscellaneous Early Precambrian pegmatite, pitchblende-coffinite-sulphide occurrences near the Middle-Early Precambrian unconformity fringing the Lake Superior basin, and disseminations in diabase, granitic rocks, alkalic complexes and breccias scattered throughout northern Ontario make up the rest of the occurrences

  8. Ontario feed-in-tariff programs

    International Nuclear Information System (INIS)

    Yatchew, Adonis; Baziliauskas, Andy

    2011-01-01

    Recent feed-in-tariff (FIT) programs in Ontario, Canada have elicited a very strong supply response. Within the first year of their inception, the Ontario Power Authority received applications totaling over 15,000 MW, equivalent to about 43% of current Ontario electricity generating capacity. The overwhelming share of applications is for wind-power (69%) and solar photovoltaic (28%) generating facilities. Wind generation is being remunerated at 14-19 cents /kWh. Solar facilities receive from 40 to 80 cents /kWh. The initiative, which responds to Provincial legislation is administratively divided into applications for facilities exceeding 10 kW (the FIT program) and those less than or equal to 10 kW (the microFIT program). This paper describes the programs and their features, compares them to their predecessors in Ontario as well as to programs elsewhere, analyses the reasons for the very strong response, and assesses their efficacy and sustainability. - Research highlights: → Recent feed-in-tariff (FIT) programs in Ontario, Canada have elicited a very strong supply response. Within the first year, applications totaled over 15,000 MW, equivalent to about 43% of current Ontario electricity generating capacity. → Most projects are either solar or wind. → Likely causes of strong supply response-preferred system access and favorable, secure tariffs. (Wind generation is being remunerated at 14-19 cents /kWh. Solar facilities receive from 40 to 80 cents /kWh.) → Long term political sustainability of present program is in question.

  9. The potential of solar PV in Ontario

    International Nuclear Information System (INIS)

    McMonagle, R.

    2005-01-01

    Canada has lagged behind other industrialized nations in the growth of solar energy markets. Currently, over 78 per cent of the global market for solar energy is for grid-connected applications where power is fed into the electrical distribution network. Less than 3.5 per cent of the Canadian solar market is grid-connected. This report investigated the potential size of the photovoltaic (PV) market in Ontario given adequate support from both governments and utilities. The forecast was based on sustainable growth levels that the solar industry as a whole might maintain over an extended period of time. It was suggested that it is technically feasible to install over 3000 MW of PV in single, detached homes in the province, which could generate over 3200 GWh each year. If the right policy conditions were put in place, the technical potential for PV on all buildings in Ontario is over 14,000 MW by 2025, which would generate over 13,000 GWh annually. Support mechanisms such as the Advanced Renewable Tariff (ART) or Standard Offer Contracts (SOC) will enable the PV industry to build capacity. Future markets for PV include new homes, commercial buildings and the existing housing stock. With a properly designed system, it is forecasted that the deployment of PV by 2025 could result in the involvement of 400,000 homes with over 1200 MW of installed capacity and over 290 MW installed annually by 2025. Recommendations to Ontario Power Authority's (OPA) report supply mix report focused on the use of SOCs as the appropriate support mechanism to start building solar capacity in Ontario, as projections using SOCs would see Ontario following the growth patterns of other nations. It was concluded that the OPA report does not acknowledge the current growth rates of PV globally, nor does it fully consider the potential of PV in Ontario. 9 refs., 8 figs

  10. Comparative analysis of C A R A fuel element in argentinean PHWR Argentinas

    International Nuclear Information System (INIS)

    Brasnarof D; Marino, A. C; Florido, P. C; Daverio, H

    2006-01-01

    This paper presents an analysis of the thermal mechanical behaviour, fuel consumption and economical estimations of the CARA fuel element in the Atucha and Embalse nuclear power plants, compared with the present fuel performance.The present results show that the expect profit by the use of the CARA fuel element in our reactor guaranties the recovery of fund for its development. Likewise it reduces the number of spent fuel to be storage and treated [es

  11. Argentine criteria on nuclear safety and emergencies: their impact on the Argos PHWR 380 design

    International Nuclear Information System (INIS)

    Gonzalez, A. J.

    1988-01-01

    This paper describes first the safety criteria of the Argentine regulatory authority with emphasis on the probabilistic safety criteria based on a limitation of individual risks. Then, it is presented a discussion on emergency criteria in relation to evacuation and relocation measures. Finally, the paper briefly describes the design of an Argentine offer for a safer heavy water reactor where these criteria are applied. 9 figs., 1 tab., 46 refs. (author)

  12. Stress and fatigue analysis of fuelling machine housing of 500 MWe PHWR

    International Nuclear Information System (INIS)

    Dutta, B.K.; Ramana, W.V.; Kushwaha, H.S.; Kakodkar, A.

    1987-01-01

    One of the most appealing features of the Pressurised Heavy Water Reactors is the online refuelling capability. For this a fuelling machine is used. This machine opens a reactor channel by removing a seal plug and a shield plug and then does the necessary fuelling by pushing fuel bundles from a fuel magazine by rams. After necessary fuelling the machine closes the channel automatically. One of the most important parts of the fuelling machine is its pressure housing which becomes a part of the reactor channel during refuelling operation. It houses the fuel magazine, separators and rams. Beside channel pressure and other mechanical loads, the pressure housing experiences thermal transients during refuelling. The housing consists of two cylindrical shells having one end-closer in each. They are connected with each other by a large sized coupling. There are many holes on both the end-closers to accommodate ram movement, separators and magazine rive mechanisms. Some of these holes intersect with each other in the housing end-closers and hence end-closers are reinforced accordingly. This also makes the end-closers nonsymmetric. In the following sections the various analysis done to compute general stress distribution, stress concentration factors near to various holes, temperature transients during refuelling and also allowable fatigue cycles for pressure housing of fuelling machine for the proposed 500 MWe are described. (orig.)

  13. Stress and fatigue analysis of fuelling machine housing of 500 MWe PHWR

    International Nuclear Information System (INIS)

    Dutta, B.K.; Ramana, W.V.; Kushwaha, H.S.; Kakodkar, A.

    1987-01-01

    One of the most appealing features of the Pressurised Heavy Water Reactors is the online refuelling capability. For this a fuelling machine is used. This machine opens a reactor channel by removing a seal plug and a shield plug and then does the necessary fuelling by pushing fuel bundles from a fuel magazine by rams. After necessary fuelling the machine closes the channel automatically. One of the most important parts of the fuelling machine is its pressure housing which becomes a part of the reactor channel during refuelling operation. It houses the fuel magazine, separators and rams. Beside channel pressure and other mechanical loads, the pressure housing experiences thermal transients during refuelling. The housing consists of two cylindrical shells having one end-closer in each. They are connected with each other by a large sized coupling. There are many holes on both the end-closers to accommodate ram movement, separators and magazine drive mechanisms. Some of these holes intersect with each other in the housing end-closures and hence end-closures are reinforced accordingly. This also makes the end-closures nonsymmetric. In the following sections the various analysis done to compute general stress distribution, stress concentration factors near to various holes, temperature transients during refuelling and also allowable fatigue cycles for pressure housing of fuelling machine for the proposed 500 MWe are described

  14. Application of reliability methods in Ontario Hydro

    International Nuclear Information System (INIS)

    Jeppesen, R.; Ravishankar, T.J.

    1985-01-01

    Ontario Hydro have established a reliability program in support of its substantial nuclear program. Application of the reliability program to achieve both production and safety goals is described. The value of such a reliability program is evident in the record of Ontario Hydro's operating nuclear stations. The factors which have contributed to the success of the reliability program are identified as line management's commitment to reliability; selective and judicious application of reliability methods; establishing performance goals and monitoring the in-service performance; and collection, distribution, review and utilization of performance information to facilitate cost-effective achievement of goals and improvements. (orig.)

  15. Sparking investment in Ontario's power generation industry

    International Nuclear Information System (INIS)

    Allen, J.

    2004-01-01

    This paper discusses the business strategy needed to spark investment in Ontario's power generation industry. It examines the process of decision making and investing in an uncertain environment. The paper suggests that any strategy based on one view of the future courts trouble and that strategic flexibility can prepare for what cannot be predicted. Finally the paper suggests that Ontario needs to create a stable policy and regulatory environment that allows investors to fulfill reasonable expectations and investors need to place bets that provide the flexibility to respond quickly to changing market conditions

  16. Ontario's standard offer programs: moving toward a cleaner energy future

    International Nuclear Information System (INIS)

    Shervill, P.

    2006-01-01

    The Ontario Standard Offer Program is designed to ensure reliable, long-term electricity supply for Ontario. The functional areas of the program are planning, conservation and supply sector development. The long-term plan is to create a self-sustaining electricity market in Ontario with 2700 MW renewable sources by 2010 including wind, waterpower, solar photovoltaic (PV) and biomass

  17. "Strengthening" Ontario Universities: A Neoliberal Reconstruction of Higher Education

    Science.gov (United States)

    Rigas, Bob; Kuchapski, Renée

    2016-01-01

    This paper reviews neoliberalism as an ideology that has influenced higher education generally and Ontario higher education in particular. It includes a discourse analysis of "Strengthening Ontario's Centres of Creativity, Innovation and Knowledge" (Ontario Ministry of Training, Colleges, and Universities, 2012), a government discussion…

  18. Opening Doors to Nursing Degrees: A Proposal from Ontario's Colleges

    Science.gov (United States)

    Colleges Ontario, 2010

    2010-01-01

    Ontario needs to expand nursing education options to improve access to the nursing profession, create better pathways amongst all nursing occupations, and build Ontario's capacity to meet the province's long-term nursing needs. Ontario's colleges are capable of playing a larger role within a long-term provincial strategy for sustaining and…

  19. Elasto-plastic finite element analysis of axial surface crack in PHT piping of 500 MWe PHWR

    International Nuclear Information System (INIS)

    Chawla, D.S.; Bhate, S.R.; Kushwaha, H.S.; Mahajan, S.C.

    1994-01-01

    The leak before break (LBB) approach in nuclear piping design envisages demonstrating that the pressurized pipe with a postulated flaw will leak at a detectable rate leading to corrective action well before catastrophic rupture would occur. This requires analysis of cracked pipe to study the crack growth and its stability. This report presents the behaviour of a surface crack in the wall of a thick primary heat transport (PHT) pipe of 500 MWe Indian PHWR. The line spring model (LSM) finite element is used to model the flawed pipe geometry. The variation of crack driving force (J-integral) across the crack front has been presented. The influence of crack geometry factors such as depth, shape, aspect ratio, and loading on peak values of J-integral as well as crack mouth opening displacement has been studied. Several crack shapes have been used to study the shape influence. The results are presented in dimensionless form so as to widen their applicability. The accuracy of the results is validated by comparison with results available in open literature. (author). 47 refs., 8 figs

  20. Comparison of safety margins for leak-before-break assessment of 500 MWe PHWR straight pipes: using contemporary techniques

    International Nuclear Information System (INIS)

    Rastogi, Rohit; Bhasin, Vivek; Kushwaha, H.S.

    1998-01-01

    The Leak Before Break (LBB) analysis of Primary Heat Transport (PHT) Piping of 500 MWe Indian PHWR is being performed using different well established techniques like R6 method (Nuclear Electric UK) and J-Tearing based methods (USNRC). These methods show that PHT piping has required safety margins and can be qualified for LBB. These analysis also showed that the piping has high fracture toughness and plastic collapse is the dominant mode of failure. To enhance the confidence in the results obtained from the above methods, further studies were done on the PHT piping. Procedures which predicted margins against plastic collapse were used. The analysis procedures used were Modified Limit Load Method, MPA Method (both from Germany), Moments Method (from Italy) and the Z-Factor method given in ASME Boiler and Pressure Vessel Code. The safety margins obtained from these analysis satisfied the LBB requirements. A table was generated which compared the safety margins obtained using all the above mentioned procedures. This report presents the results of this study. (author)

  1. Derivatization Ion Chromatography for the Determination of Monoethanolamine in Presence of Hydrazine in PHWR Steam-Water Circuits

    Directory of Open Access Journals (Sweden)

    Ayushi D.

    2011-01-01

    Full Text Available A simple, rapid and accurate method for the determination of monoethanolamine (MEA in PHWR steam-water circuits has been developed. MEA is added in the feed water to provide protection against corrosion while hydrazine is added to scavenge dissolved oxygen. The quantitative determination of MEA in presence of hydrazine was accomplished using derivatization ion chromatography with conductometric detection in nonsuppressed mode. A Metrosep cation 1-2 analytical column and a Metrosep cartridge were used for cation separation. A mixture of 4 mM tartaric acid, 20% acetone and 0.05 mM HNO3 was used as eluent. Acetone in the mobile phase leads to the formation of different derivatives with MEA and hydrazine. The interferences due Na+ and NH4 + were eliminated by adopting a simple pretreatment procedure employing OnGuard-H cartridge. The limit of detection limit of MEA was 0.1 μg mL−1 and the relative standard deviation was 2% for the overall method. The recovery of MEA added was in the range 95%–102%. The method was applied to the determination of MEA in steam generator water samples.

  2. CANDU reactor experience: fuel performance

    International Nuclear Information System (INIS)

    Truant, P.T.; Hastings, I.J.

    1985-07-01

    Ontario Hydro has more than 126 reactor-years experience in operating CANDU reactors. Fuel performance has been excellent with 47 000 channel fuelling operations successfully completed and 99.9 percent of the more than 380 000 bundles irradiated operating as designed. Fuel performance limits and fuel defects have had a negligible effect on station safety, reliability, the environment and cost. The actual incapability charged to fuel is less than 0.1 percent over the stations' lifetimes, and more recently has been zero

  3. Acoustic emission monitoring of leakage through seal-plug in PHWR systems

    Energy Technology Data Exchange (ETDEWEB)

    Jha, S K; Badgujar, B P; Goswami, G L [Bhabha Atomic Research Centre, Bombay (India). Atomic Fuels Div.; Patel, R J; Bhattacharya, S; Agrawal, R G [Bhabha Atomic Research Centre, Mumbai (India). Refuelling Technology Division

    1994-12-31

    Acoustic Emission (AE) technique is being developed as an in-service inspection tool for monitoring the leakage through seal-plugs in Pressurised Heavy Water Reactors (PHWRs). Time as well as frequency domain analysis have been utilised during the experiment carried out at Bhabha Atomic Research Centre (BARC) using test set up simulating the pressure and temperature conditions. The work involved were to determine the temperature profile on end-fitting, effect of pressure and temperature on leakage etc. This paper discusses various relationships like signal-level vs. pressure, frequency spectrum of signal, signal-level vs. leakage based on the above experimental work. (author). 4 refs., 6 figs.

  4. Development of modern CANDU PHWR cross-section libraries for SCALE

    International Nuclear Information System (INIS)

    Shoman, Nathan T.; Skutnik, Steven E.

    2016-01-01

    Highlights: • New ORIGEN libraries for CANDU 28 and 37-element fuel assemblies have been created. • These new reactor data libraries are based on modern ENDF/B-VII.0 cross-section data. • The updated CANDU data libraries show good agreement with radiochemical assay data. • Eu-154 overestimated when using ENDF-VII.0 due to a lower thermal capture cross-section. - Abstract: A new set of SCALE fuel lattice models have been developed for the 28-element and 37-element CANDU fuel assembly designs using modern cross-section data from ENDF-B/VII.0 in order to produce new reactor data libraries for SCALE/ORIGEN depletion analyses. These new libraries are intended to provide users with a convenient means of evaluating depletion of CANDU fuel assemblies using ORIGEN through pre-generated cross sections based on SCALE lattice physics calculations. The performance of the new CANDU ORIGEN libraries in depletion analysis benchmarks to radiochemical assay data were compared to the previous version of the CANDU libraries provided with SCALE (based on WIMS-AECL models). Benchmark comparisons with available radiochemical assay data indicate that the new cross-section libraries perform well at matching major actinide species (U/Pu), which are generally within 1–4% of experimental values. The library also showed similar or better results over the WIMS-AECL library regarding fission product species and minor actinoids (Np, Am, and Cm). However, a notable exception was in calculated inventories of "1"5"4Eu and "1"5"5Eu, where the new library employing modern nuclear data (ENDF/B-VII.0) performed substantially poorer than the previous WIMS-AECL library (which used ENDF-B/VI.8 cross-sections for these species). The cause for this discrepancy appears to be due to differences in the "1"5"4Eu thermal capture cross-section between ENDF/B-VI.8 and ENDF/B-VII.0, an effect which is exacerbated by the highly thermalized flux of a CANDU heavy water reactor compared to that of a typical

  5. Ontario Hydro's plan for used nuclear fuel

    International Nuclear Information System (INIS)

    Stevens-Guille, P.D.; Howes, H.A.; Freire-Canosa, J.

    1992-01-01

    A comprehensive plan for the management of used nuclear fuel has been published by Ontario Hydro. In this paper current practices are discussed and actions leading to disposal in a repository are outlined. Extended storage options are discussed should disposal be delayed

  6. Wind power and bats : Ontario guideline

    Energy Technology Data Exchange (ETDEWEB)

    McGuiness, F. [Ontario Ministry of Natural Resources, Peterborough, ON (Canada). Renewable Energy Resources; Stewart, J. [Ontario Ministry of Natural Resources, Toronto, ON (Canada). Wildlife Section

    2008-07-01

    None of the 8 species of bats in Ontario are considered as species at risk. However, all bats in Ontario are protected under the Fish and Wildlife Conservation Act. The Ontario Ministry of Natural Resources (MNR) is responsible for identifying significant wildlife habitat for bats, including hibernacula and maternity roosts. The MNR's role in wind development includes environmental assessments (EA) and surveys. The MNR bat guideline includes a summary of Ontario species, a literature review of research related to wind turbines and bats, and a review of methods for assessing and monitoring bats. Guideline development includes a bat working group responsible for obtaining data on risk factors and monitoring requirements. The MNR has determined that site selection is critical for minimizing potential impacts. Wind farm proponents can use MNR data, information, and maps for their site selection process. Information requirements include bat species data; habitat data; and meteorological data. The presence of risk factors results in a sensitivity rating. The MNR is also developing a site sensitivity mapping project in order to assist proponents in making siting decisions. All proposed sites are required to conduct pre-construction site surveys. Acoustic detectors and radar are used to determine bat activity at the site. Monitoring and mitigation strategies include selective wind turbine shutdown during key periods or weather conditions. tabs., figs.

  7. Measuring Social Capital in Hamilton, Ontario

    Science.gov (United States)

    Kitchen, Peter; Williams, Allison; Simone, Dylan

    2012-01-01

    Social capital has been studied by academics for more than 20 years and within the past decade there has been an explosion of growth in research linking social capital to health. This paper investigates social capital in Hamilton, Ontario by way of a telephone survey of 1,002 households in three neighbourhood groups representing high, mixed and…

  8. Poster - 27: Incident Learning Practices in Ontario

    Energy Technology Data Exchange (ETDEWEB)

    Angers, Crystal; Medlam, Gaylene; Liszewski, Brian; Simniceanu, Carina [The Ottawa Hospital Cancer Centre, Mississauga Halton/Central West Regional Cancer Center, Odette Cancer Centre, Cancer Care Ontario (Canada)

    2016-08-15

    Purpose: The Radiation Incident and Safety Committee (RISC), established and supported by Cancer Care Ontario (CCO), is responsible for advising the Provincial Head of the Radiation Treatment program on matters relating to provincial reporting of radiation incidents with the goal of improved risk mitigation. Methods: The committee is made up of Radiation Incident Leads (RILs) with representation from each of the 14 radiation medicine programs in the province. RISC routinely meets to review recent critical incidents and to discuss provincial reporting processes and future directions of the committee. Regular face to face meetings have provided an excellent venue for sharing incident learning practices. A summary of the incident learning practices across Ontario has been compiled. Results: Almost all programs in Ontario employ an incident learning committee to review incidents and identify corrective actions or process improvements. Tools used for incident reporting include: paper based reporting, a number of different commercial products and software solutions developed in-house. A wide range of classification schema (data taxonomies) are employed, although most have been influenced by national guidance documents. The majority of clinics perform root cause analyses but utilized methodologies vary significantly. Conclusions: Most programs in Ontario employ a committee approach to incident learning. However, the reporting tools and taxonomies in use vary greatly which represents a significant challenge to provincial reporting. RISC is preparing to adopt the National System for Incident Reporting – Radiation Therapy (NSIR-RT) which will standardize incident reporting and facilitate data analyses aimed at identifying targeted improvement initiatives.

  9. Ontario's Quality Assurance Framework: A Critical Response

    Science.gov (United States)

    Heap, James

    2013-01-01

    Ontario's Quality Assurance Framework (QAF) is reviewed and found not to meet all five criteria proposed for a strong quality assurance system focused on student learning. The QAF requires a statement of student learning outcomes and a method and means of assessing those outcomes, but it does not require that data on achievement of intended…

  10. The Status of Benthos in Lake Ontario

    Science.gov (United States)

    The benthic community of Lake Ontario was dominated by an amphipod (Diporeia spp.) prior to the 1990’s. Two dreissenid mussel species D. polymorpha (zebra) and D. bugensis (quagga) were introduced in 1989 and 1991 via ballast water exchange. D. bugensis was observed as deep as 85...

  11. Global warming: Towards a strategy for Ontario

    International Nuclear Information System (INIS)

    1990-01-01

    A discussion paper is provided as background to a proposed public review of a strategy for Ontario's response to global warming. Global warming arises from the generation of greenhouse gases, which come from the use of fossil fuels, the use of chlorofluorocarbons, and deforestation. Energy policy is the backbone of achieving climate stability since the burning of fossil fuels releases most of the greenhouse gases, mainly carbon dioxide. Canada is, by international standards, a very energy-intensive country and is among the world's largest emitters of carbon dioxide on a per capita basis. Ontario is the largest energy-using province in Canada, and fossil fuels represent over 80% of provincial energy use. A proposed goal for Ontario is to provide leadership in stabilizing atmospheric concentrations of the greenhouse gases, while minimizing the social, economic, and environmental costs in Ontario of adapting to global warming. A proposed first step to address global warming is to achieve reductions in expected emissions of the greenhouse gases, especially carbon dioxide, so that levels by the year 2000 are lower than in 1989. Current policies and regulations helping to reduce the greenhouse effect include some of the current controls on automotive emissions and the adoption by the provincial electric utility of targets to reduce electricity demand. New initiatives include establishment of minimum energy efficiency standards and reduction of peak-day electricity use. Action steps for future consideration are detailed in the categories of greenhouse gas emissions reductions, carbon dioxide absorption, and research and analysis into global warming

  12. Seven steps to an energy efficient Ontario

    International Nuclear Information System (INIS)

    2003-01-01

    The future of the electricity market in Ontario is examined in light of the recent debate concerning deregulation. This report focuses on measures that would have to be taken to ensure that there will be sufficient electricity available to serve the needs of Ontario. Increasing supply, or decreasing demand are discussed as the obvious answers to the problem at hand. The report concludes that: (1) mechanisms to encourage Demand Side Management and Demand Response have all but disappeared since the opening of the competitive electricity market in Ontario, (2) the current market structure does nothing to stimulate increased supply, nor does it encourage measures to reduce demand; as such, the result is an unsustainable situation. The report further concludes that Demand Side Management and Demand Response programs are essential components of the success of Ontario's evolving electricity market, and recommends programs that are designed and implemented in a manner that dovetail with parallel policies dealing with supply challenges. Seven essential elements of such a policy are discussed. These are: (1) vision and a clear set of goals for demand side management; (2) appropriate market drivers, principles and pricing incentives; (3) a central co-ordinating authority for managing demand side management; (4) appropriate implementation agents to manage programs and processes; (5) incentives to motivate change; (6) widespread education of the market; and (7) appropriate tactics to enable demand side management in sectors

  13. Poster - 27: Incident Learning Practices in Ontario

    International Nuclear Information System (INIS)

    Angers, Crystal; Medlam, Gaylene; Liszewski, Brian; Simniceanu, Carina

    2016-01-01

    Purpose: The Radiation Incident and Safety Committee (RISC), established and supported by Cancer Care Ontario (CCO), is responsible for advising the Provincial Head of the Radiation Treatment program on matters relating to provincial reporting of radiation incidents with the goal of improved risk mitigation. Methods: The committee is made up of Radiation Incident Leads (RILs) with representation from each of the 14 radiation medicine programs in the province. RISC routinely meets to review recent critical incidents and to discuss provincial reporting processes and future directions of the committee. Regular face to face meetings have provided an excellent venue for sharing incident learning practices. A summary of the incident learning practices across Ontario has been compiled. Results: Almost all programs in Ontario employ an incident learning committee to review incidents and identify corrective actions or process improvements. Tools used for incident reporting include: paper based reporting, a number of different commercial products and software solutions developed in-house. A wide range of classification schema (data taxonomies) are employed, although most have been influenced by national guidance documents. The majority of clinics perform root cause analyses but utilized methodologies vary significantly. Conclusions: Most programs in Ontario employ a committee approach to incident learning. However, the reporting tools and taxonomies in use vary greatly which represents a significant challenge to provincial reporting. RISC is preparing to adopt the National System for Incident Reporting – Radiation Therapy (NSIR-RT) which will standardize incident reporting and facilitate data analyses aimed at identifying targeted improvement initiatives.

  14. Ontario-U.S. power outages : impacts on critical infrastructure

    International Nuclear Information System (INIS)

    2006-01-01

    This paper described the power outage and resulting blackout that occurred on August 14, 2003 and identified how critical infrastructure was directly and interdependently impacted in Canada. The aim of the paper was to assist critical infrastructure protection and emergency management professionals in assessing the potential impacts of large-scale critical infrastructure disruptions. Information for the study was acquired from Canadian and American media reports and cross-sectoral information sharing with provincial and federal governments and the private sector. The blackout impacted most of the sources and means of generating, transmitting and distributing power within the area, which in turn impacted all critical infrastructure sectors. Landline and cellular companies experienced operational difficulties, which meant that emergency responders were impacted. Newspapers and the electronic media struggled to release information to the public. The banking and finance industry experienced an immediate degradation of services. The power outage caused shipping and storage difficulties for commercial retailers and dairy producers. A number of incidents were reported where only partially treated waste water was released into neighbouring waterways. The timing of the blackout coincided with the closures of workplaces and created additional difficulties on transportation networks. Many gas station pumps were inoperable. Police, fire departments and ambulance services experienced a dramatic increase in the volume of calls received, and all branches of the emergency services sector encountered transportation delays and difficulties with communications equipment. Nuclear reactors were also impacted. An estimated 150,000 Government of Canada employees were unable to report to work. Estimates have indicated that the power outage cost Ontario's economy between $1 and $2 billion. The outage negatively impacted 82 per cent of small businesses in Ontario. 170 refs., 3 figs

  15. Renewables without limits : moving Ontario to advanced renewable tariffs by updating Ontario's groundbreaking standard offer program

    International Nuclear Information System (INIS)

    Gipe, P.

    2007-11-01

    The Ontario Sustainable Energy Association (OSEA) promotes the development of community-owned renewable energy generation. It was emphasized that in order to achieve OSEA's original objectives of developing as much renewable energy as quickly as possible through community participation, changes are needed to Ontario's groundbreaking standard offer contract (SOC) program. This report examined the status of Ontario's SOC program and proposed changes to the program as part of the program's first two-year review. The report provided a summary of the program and discussed each of the program's goals, notably to encourage broad participation; eliminate barriers to distributed renewable generation; provide a stable market for renewable generation; stimulate new investment in renewable generation; provide a rigorous pricing model for setting the tariffs; create a program applicable to all renewable technologies; provide a simple, streamlined, and cost-effective application process; and provide a dispute resolution process. The program goals as developed by the Ontario Power Authority and Ontario Energy Board were discussed with reference to mixed results to date; simplicity; removing barriers; balancing targets with value to ratepayers; and building on the efforts of OSEA. Advanced renewable tariffs (ART) and tariff determination was also discussed along with ART's in Germany, France, Spain and Ontario. Inflation indexing; tariff degression; proposed new tariffs by technology; and other costs and factors affecting profitability were also reviewed. ref., tabs

  16. Ontario's Clean Air Action Plan : protecting environmental and human health in Ontario

    International Nuclear Information System (INIS)

    2004-01-01

    Ontario's Clean Air Action Plan was launched in June 2000 in an effort to improve air quality and comply with the Canada-Wide Standards for Particulate Matter and Ozone. This paper describes Ontario's approach to reducing smog. Smog-related air pollution is linked to health problems such as premature death, respiratory and heart problems. Smog also contributes to environmental problems such as damage to forests, agricultural crops and natural vegetation. The two main ingredients of smog are ground level ozone and particulate matter. In order to reduce the incidence of smog, the following four key smog-causing pollutants must be reduced: nitrogen oxides, volatile organic compounds, sulphur dioxide and particular matter. This paper includes the 2001 estimates for Ontario's emissions inventory along with Ontario's smog reduction targets. It was noted that approximately half of all smog in Ontario comes from sources in the midwestern United States. The province of Ontario is committed to replacing coal-fired power plants with cleaner sources of energy. It is also considering emission caps for key industrial sectors. The key players in reducing smog include municipalities, industry, individuals, the federal government and programs that reduce emissions in the United States. 3 figs., 8 tabs., 1 appendix

  17. Assessing the financial positions of Ontario`s new electricity companies

    Energy Technology Data Exchange (ETDEWEB)

    Connell, T. [Standard and Poor`s, Toronto, ON (Canada)

    1999-11-01

    This paper describes the methodology, including the criteria factors, comparable ratings and key credit issues used in assessing the financial positions of Ontario Power Generation Inc., and the Ontario Hydro Services Company. The rating criteria factors include both business factors (such as ownership structure, regulation, service area, operations, management, etc.,) and financial factors (e.g. financial policies and guidelines, recent financial performance, margin analysis, capital structure and borrowing plans, financial projections and sensitivities). Key credit issues include considerations of competitive dynamics, nuclear portfolio performance (for Genco), regulatory changes, cost control, capital spending program, retail business exposure, future financial performance. Comparisons are made with corresponding positions of comparable entities in Australia, Finland, New Zealand, the UK, and the USA. In the case of Ontario Power Generation Inc., the company is assessed to have significant advantages initially, but various uncertainties over the medium term warrant a more cautious view of the credit profile. For the Ontario Hydro Services Company the business risks appear to be low and moderate leverage entails a strong, stable credit profile. The overall assessment of the two companies is that while certain questions such as the workability and credibility of the new industry structure, the problem of stranded debt and questions about the liquidity of market participants remain unsolved, Ontario Power Generation Inc., and the Ontario Hydro Services Company ratings compare favorably with ratings of global industry peers.

  18. Development of the advanced PHWR technology -Design and analysis of CANDU advanced fuel-

    Energy Technology Data Exchange (ETDEWEB)

    Suk, Hoh Chun; Shim, Kee Sub; Byun, Taek Sang; Park, Kwang Suk; Kang, Heui Yung; Kim, Bong Kee; Jung, Chang Joon; Lee, Yung Wook; Bae, Chang Joon; Kwon, Oh Sun; Oh, Duk Joo; Im, Hong Sik; Ohn, Myung Ryong; Lee, Kang Moon; Park, Joo Hwan; Lee, Eui Joon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    This is the `94 annual report of the CANDU advanced fuel design and analysis project, and describes CANFLEX fuel design and mechanical integrity analysis, reactor physics analysis and safety analysis of the CANDU-6 with the CANFLEX-NU. The following is the R and D scope of this fiscal year : (1) Detail design of CANFLEX-NU and detail analysis on the fuel integrity, reactor physics and safety. (a) Detail design and mechanical integrity analysis of the bundle (b) CANDU-6 refueling simulation, and analysis on the Xe transients and adjuster system capability (c) Licensing strategy establishment and safety analysis for the CANFLEX-NU demonstration demonstration irradiation in a commercial CANDU-6. (2) Production and revision of CANFLEX-NU fuel design documents (a) Production and approval of CANFLEX-NU reference drawing, and revisions of fuel design manual and technical specifications (b) Production of draft physics design manual. (3) Basic research on CANFLEX-SEU fuel. 55 figs, 21 tabs, 45 refs. (Author).

  19. Ultrasonic measurement of gap between calandria tube and liquid injection shutdown system tube in PHWR

    International Nuclear Information System (INIS)

    Kim, Tae Ryong; Sohn, Seok Man; Lee, Jun Shin; Lee, Sun Ki; Lee, Jong Po

    2001-01-01

    Sag of CT or liquid injection shutdown system tubes in pressurized heavy water reactor is known to occur due to irradiation creep and growth during plant operation. When the sag of CT is big enough, the CT tube possibly comes in contact with liquid injection shutdown system tube (LIN) crossing beneath the CT, which subsequently may prevent the safe operation. It is therefore necessary to check the gap between the two tubes in order to confirm no contacts when using a proper measure periodically during the plant life. An ultrasonic gap measuring probe assembly which can be fed through viewing port installed on the calandria was developed and utilized to measure the sags of both tubes in a pressurized heavy water reactor in Korea. It was found that the centerlines of CT and LIN can be precisely detected by ultrasonic wave. The gaps between two tubes were easily obtained from the relative distance of the measured centerline elevations of the tubes. But the measured gap data observed at the viewing port were actually not the data at the crossing point of CT and LIN. To get the actual gap between two tubes, mathematical modeling for the deflection curves of two tubes was used. The sags of CT and LIN tubes were also obtained by comparison of the present centerlines with the initial elevations at the beginning of plant operation. The gaps between two tubes in the unmeasurable regions were calculated based on the measurement data and the channel power distribution

  20. Three-dimensional analyses of fluid flow and heat transfer for moderator integrity assessment in PHWR

    International Nuclear Information System (INIS)

    Yu, S.-O.; Kim, M.; Kim, H.-J.

    2002-01-01

    A CANDU reactor has the unique features and the intrinsic safety related characteristics that distinguish it from other water-cooled thermal reactors. If there is the loss of coolant accident (LOCA) and a coincident failure of the emergency coolant injection (ECI) system, the heavy water moderator is continuously cooled, providing a heat sink for decay heat produced in the fuel. Therefore, it is one of major concerns to estimate the local subcooling of moderator inside the calandria vessel under postulated accident in CANDU safety analyses. The Canadian Nuclear Safety Commission (CNSC), a regulatory body in Canada, categorized the integrity of moderator as a generic safety issue and recommended that a series of experimental works be performed to verify the safety evaluation codes for individual simulated condition of nuclear power plant, comparing with the results of three-dimensional experimental data. In this study, three-dimensional analyses of fluid flow and heat transfer have been performed to assess thermal-hydraulic characteristics for moderator simulation conducted by SPEL (Sheridan Park Experimental Laboratory) experimental facility. The parametric study has also carried out to investigate the effect of major parameters such as flowrate, temperature, and heat load generated from the heaters on the temperature and flow distribution inside the moderator. Three flow patterns have been identified in the moderator with flowrate, heat generation, or both. As the transition of fluid flow is progressed, it is found that the dimensionless numbers (Ar) and the ratio of buoyancy to inertia forces are constant. (author)

  1. Deregulation experiences in Alberta and Ontario

    International Nuclear Information System (INIS)

    Axford, D.

    2003-01-01

    A brief introduction of Nexen Chemicals, one of the largest producers of sodium chlorate in the world, was offered, and a map displaying its locations throughout the world was displayed. Nexen is one of Canada's largest independent oil and gas producers, while Nexen Marketing is involved in the marketing of natural gas in North America. In January 2001, the deregulated market opened in Alberta. High natural gas prices, generation shortages, high prices in California and an upcoming provincial election all combined to complicate the situation. A high degree of volatility characterized the market. A chart displaying weekly average Alberta power and gas prices from Jan 2002 to 13 Oct 2002 was shown. In Ontario, the market opened in May 2002, and the demand growth rate was in the 1 to 2 per cent range. The author indicated that approximately 20 per cent of homeowners in Ontario have signed deals with retailers, contrary to Alberta where very few have done so. A similar chart displaying weekly average Ontario power prices was presented. The issues in Ontario are: consistency in policy, increase market transparency, transmission / distribution price flexibility, overall transmission / distribution to industrial consumers high, and increasing costs of the system operator. In Alberta, the issues are: government intent, congestion management issues, and billing settlement errors that continue. The opportunities offered by a deregulated market include process responsiveness which is rewarded, the ability to look in forward prices when prices fit margin requirement, and gives companies the opportunity to participate in the development of the market. Various charts were also displayed to further illustrate the market in both Alberta and Ontario. figs

  2. Control chart analysis of data regarding 0.2% yield strength (YS) and percent total circumferential elongation (%TCE) for zircaloy clad tubes for PHWR and BWR fuels

    International Nuclear Information System (INIS)

    Yadav, M.B.; Singh, Hari; Vaidyanathan, S.; Sood, D.D.; Raghavan, S.V.; Bandyopadhyay, A.K.; Kulkarni, P.G.

    1992-01-01

    Zircaloy cladding tubes for PHWR and BWR fuels are manufactured and tested at Nuclear Fuel Complex (NFC), Hyderabad. Atomic Fuels Division is carrying out the quality assurance of the fuels on behalf of Nuclear Power Corporation (NPC). In this paper an attempt has been made to assess whether the quality of the clad tubes has met the requirements specified for the two mechanical properties of the tubes namely 0.2% yield strength and percent total circumferential elongation using control chart technique. For this purpose data for about 100 lots in each case were used. Process means and process standard deviations for these properties and the control limits for the corresponding control charts were estimated. The main findings are: (i) In case of PHWR tubes the production quality level with respect to 0.2% YS is higher, while that in case of %TCE is lower causing rejection of lots. On the other hand in the case of BWR tubes the production quality levels with respect to both the properties are higher than the required one. (ii) With respect to 0.2% YS, in case of BWR tubes a change in the pattern of distribution is detected beyond the lot serial no.47. However in case of PHWR tubes, though the data falls into two groups, no such pattern is seen. A modification in the acceptance/rejection criterion of the lot has been suggested. It is also pointed out that to have a correct picture of the total variation it is necessary to study the within tube variation. (author). 4 figs, 2 tabs

  3. Fracture toughness of irradiated Zr-2.5Nb pressure tube from Indian PHWR

    Science.gov (United States)

    Shah, Priti Kotak; Dubey, J. S.; Shriwastaw, R. S.; Dhotre, M. P.; Bhandekar, A.; Pandit, K. M.; Anantharaman, S.; Singh, R. N.; Chakravartty, J. K.

    2015-03-01

    Fracture toughness of irradiated Zr-2.5Nb alloy pressure tube, fabricated by the cold pilgering and stress relieving route, was evaluated using disk compact tension type specimens. These specimens were punched out from the irradiated pressure tube (S-07), which was in service for about 8 effective full power years of reactor operation in the Kakrapar Atomic Power Station-2 (KAPS-2). The tests were carried out remotely inside a lead shielded enclosure. Crack growth during the test was measured using the direct current potential drop technique. The irradiated pressure tube showed low fracture toughness at 25 °C. The fracture toughness increased with increase in temperature up to 250 °C but was practically unaffected with further increase in temperature up to 300 °C. This paper discusses the fracture behavior of irradiated Indian pressure tube material and compares it with other data available.

  4. Modelling of internal structure in seismic analysis of a PHWR building

    International Nuclear Information System (INIS)

    Reddy, G.R.; Vaze, K.K.; Kushawaha, H.S.; Ingle, R.K.; Subramanian, K.V.

    1991-01-01

    Seismic analysis of complex and large structures, consisting of thick shear walls, such as Reactor Building is very involved and time consuming. It is a standard practice to model the structure as a stick model to predict reasonably the dynamic behaviour of the structure. It is required to determine approximate equivalent sectional properties of Internal Structure for representation in the stick model. The restraint to warping can change the stress distribution thus affecting the centre of rigidity and torsional inertia, Hence, standard formulae does not hold good for determination of sectional properties of the Internal Structure. In this case the equivalent sectional properties for the Internal Structure are calculated using a Finite Element Model (FEM) of the Internal Structure and applying unit horizontal forces in each direction. A 3-D stick model is developed using the guidelines. Using the properties calculated by FEM and also by standard formulae, the responses of the 3-D stick model are compared. (J.P.N.)

  5. Assessment of the impact of fueling machine failure on the safety of the CANDU-PHWR

    International Nuclear Information System (INIS)

    Al-Kusayer, T.A.

    1982-01-01

    A survey of possible LOCA (Loss-of-Coolant Accident) initiating events that might take place for CANDU-PHWRs (Canadian Deuterium Uranium-Pressurized Heavy Water Reactors) has been conducted covering both direct and indirect initiators. Among the 22 initiating events that were surveyed in this study, four direct initiators have been selected and analyzed briefly. Those selected were a pump suction piping break, an isolation valve piping break, a bleed valve failure, and a fueling machine interface failure. These were selected as examples of failures that could take place in the inlet side, outlet side, or PHTS (Primary Heat Transport System) interfaces. The Pickering NGS (Unit-A) was used for this case study. Double failure (failure of the protective devices to operate when the process equipment fault occurs) and a triple failure (failure of the protective devices and the ECCS as well as the process equipment) were found to be highly improbable

  6. Plant life extension program for Indian PHWR power plants - Actual experience and future plans

    International Nuclear Information System (INIS)

    Sharma, M.B.; Ghoshal, B.; Shirolkar, K.M.; Ahmad, S.N.

    2002-01-01

    Full text: The Nuclear Power Corporation of India Limited (NPCIL) is responsible for design, construction and operation for all nuclear power plants in India. Currently, it has fourteen (14) reactor units under operation and another eight units are under various stages of planning and construction. India has adopted Pressurised Heavy Water Reactors (PHWRs) for the initial phase of its nuclear power program. In the earlier PHWRs zircaloy-2 has been used as coolant tube material. Subsequent studies and experience have shown their life to be considerably lower (about 10 full power years) than originally estimated. This meant that reactors at Rajasthan - 1 and 2 Madras - 1 and 2 Narora - 1 and 2 and Kakrapara-1 would require en-masse coolant channel replacement at least once in their lifetime. Subsequent reactors from Kakrapara-2 onwards would not need this en-masse coolant channel replacement as the coolant tube material has been upgraded to Zr 2.5% Nb. En-masse coolant channel replacement and other life extension work have been carried out successfully in Rajasthan Unit-2 (RAPS-2). Madras unit-2 (MAPS-2) has been shutdown since January 2002 and preparatory work for en-masse coolant channel replacement and plant life extension is in progress. This paper discusses in brief the experience of RAPS-2 in carrying out the above jobs as well as the strategies being adopted for MAPS-2. Since the coolant channel replacement work requires a plant outage of about 18 months, this opportunity is used to extend life of existing systems as well as upgradation work. This life extension and upgradation program is based on the results of detailed in service inspection, evaluation of performance of critical equipment, obsolescence and other strategic reasons. This paper discusses in detail some of the major areas of work done, for example introduction of supplementary control room, process control, computer based plant information and event analysis systems, provision of enhanced

  7. Radiometric determination of 90Sr in the dissolver solution of the spent PHWR fuel after its separation with solvent extraction and extraction chromatography

    International Nuclear Information System (INIS)

    Kulkarni, P.G.; Gupta, K.K.; Pant, D.K.; Bhalerao, B.A.; Gurba, P.B.; Janardan, P.; Changrani, R.D.; Dey, P.K.; Pathak, P.N.; Mohapatra, P.K.; Manchanda, V.K.

    2010-01-01

    A simple radiometric method for 90 Sr determination in the dissolver solution of the PHWR spent fuel has been developed.The method involves the quantitative separation of Sr from the associated actinides and other fission products by solvent extraction with 30% trialkylphosphine oxide (TRPO) -n-dodecane followed by extraction chromatography with XAD-7-Di-butylcyclohexano-18-crown-6 resin. The separation scheme yields quantitative recovery of 90 Sr and the separated 90 Sr was found to be radiochemically pure. 90 Sr was estimated by β-radiometry and the precision of the method at 5 mCi/mL level was 2% (RSD). (author)

  8. Benthic prey fish assessment, Lake Ontario 2013

    Science.gov (United States)

    Weidel, Brian C.; Walsh, Maureen; Connerton, Michael J.

    2014-01-01

    The 2013 benthic fish assessment was delayed and shortened as a result of the U.S. Government shutdown, however the assessment collected 51 of the 62 planned bottom trawls. Over the past 34 years, Slimy Sculpin abundance in Lake Ontario has fluctuated, but ultimately decreased by two orders of magnitude, with a substantial decline occurring in the past 10 years. The 2013 Slimy Sculpin mean bottom trawl catch density (0.001 ind.·m-2, s.d.= 0.0017, n = 52) and mean biomass density (0.015 g·m-2 , s.d.= 0.038, n = 52) were the lowest recorded in the 27 years of sampling using the original bottom trawl design. From 2011-2013, the Slimy Sculpin density and biomass density has decreased by approximately 50% each year. Spring bottom trawl catches illustrate Slimy Sculpin and Round Goby Neogobius melanostoma winter habitat overlaps for as much as 7 months out of a year, providing opportunities for competition and predation. Invasive species, salmonid piscivory, and declines in native benthic invertebrates are likely all important drivers of Slimy Sculpin population dynamics in Lake Ontario. Deepwater Sculpin Myoxocephalus thompsonii, considered rare or absent from Lake Ontario for 30 years, have generally increased over the past eight years. For the first time since they were caught in this assessment, Deepwater Sculpin density and biomass density estimates declined from the previous year. The 2013 abundance and density estimates for trawls covering the standard depths from 60m to 150m was 0.0001 fish per square meter and 0.0028 grams per square meter. In 2013, very few small (recruitment. Nonnative Round Gobies were first detected in the USGS/NYSDEC Lake Ontario spring Alewife assessment in 2002. Since that assessment, observations indicate their population has expanded and they are now found along the entire south shore of Lake Ontario, with the highest densities in U.S. waters just east of the Niagara River confluence. In the 2013 spring-based assessment, both the

  9. Serological studies on the infection of dogs in Ontario with Borrelia burgdorferi, the etiological agent of Lyme disease

    OpenAIRE

    Artsob, Harvey; Barker, Ian K.; Fister, Richard; Sephton, Gregory; Dick, Daryl; Lynch, John A.; Key, Doug

    1993-01-01

    A serological study was undertaken to determine whether dogs in Ontario are being exposed to Borrelia burgdorferi, the etiological agent of Lyme disease. This study consisted of a survey of randomly selected dogs and testing of diagnostic submissions from candidate Lyme disease cases. The survey of 1,095 dogs, bled between January 1988 and August 1989, revealed a total of 65 (5.9%) enzyme-linked immunosorbent assay (ELISA) reactors, of which 22 had immuno-fluorescent antibody assay (IFA) tite...

  10. Aspects on optimization of natural uranium fuel utilization in heavy water reactors

    International Nuclear Information System (INIS)

    1978-08-01

    This paper is dealing with a possibility to decrease the natural uranium consumption of CANDU PHWR using the once-through cycle. This possibility is based on the utilization of slightly enriched uranium. The optimal two-zone structure of a reactor using natural uranium is found out. The optimal criterium is the maximization of the burnup (equivalent to minimization of uranium requirements) with a constraint on power density radial uniformity factor. As regards the enriched uranium, the optimal enrichment and the two-zone structure of a reactor which minimizes the natural uranium requirement with constraints on uniformity factor and maximum burnup are established. Corresponding to a maximum burnup of 16,000 MWd/t and 1% enrichment, the natural uranium requirement is found to be 10% less than that of the natural uranium reactor

  11. A lead-before-break strategy for primary heat transport piping of 500 MWe Indian PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Chattopadhyay, J.; Dutta, B.K.; Kushwaha, H.S. [Bhabha Atomic Research Centre, Bombay (India)] [and others

    1997-04-01

    Leak-Before-Break (LBB) is being used to design the primary heat transport piping system of 500 MWe Indian Pressurized Heavy Water Reactors (IPHWR). The work is categorized in three directions to demonstrate three levels of safety against sudden catastrophic break. Level 1 is inherent in the design procedure of piping system as per ASME Sec.III with a well defined factor of safety. Level 2 consists of fatigue crack growth study of a postulated part-through flaw at the inside surface of pipes. Level 3 is stability analysis of a postulated leakage size flaw under the maximum credible loading condition. Developmental work related to demonstration of level 2 and level 3 confidence is described in this paper. In a case study on fatigue crack growth on PHT straight pipes for level 2, negligible crack growth is predicted for the life of the reactor. For level 3 analysis, the R6 method has been adopted. A database to evaluate SIF of elbows with throughwall flaws under combined internal pressure and bending moment has been generated to provide one of the inputs for R6 method. The methodology of safety assessment of elbow using R6 method has been demonstrated for a typical pump discharge elbow. In this analysis, limit load of the cracked elbow has been determined by carrying out elasto-plastic finite element analysis. The limit load results compared well with those given by Miller. However, it requires further study to give a general form of limit load solution. On the experimental front, a set of small diameter pipe fracture experiments have been carried out at room temperature and 300{degrees}C. Two important observations of the experiments are - appreciable drop in maximum load at 300{degrees}C in case of SS pipes and out-of-plane crack growth in case of CS pipes. Experimental load deflection curves are finally compared with five J-estimation schemes predictions. A material database of PHT piping materials is also being generated for use in LBB analysis.

  12. A lead-before-break strategy for primary heat transport piping of 500 MWe Indian PHWR

    International Nuclear Information System (INIS)

    Chattopadhyay, J.; Dutta, B.K.; Kushwaha, H.S.

    1997-01-01

    Leak-Before-Break (LBB) is being used to design the primary heat transport piping system of 500 MWe Indian Pressurized Heavy Water Reactors (IPHWR). The work is categorized in three directions to demonstrate three levels of safety against sudden catastrophic break. Level 1 is inherent in the design procedure of piping system as per ASME Sec.III with a well defined factor of safety. Level 2 consists of fatigue crack growth study of a postulated part-through flaw at the inside surface of pipes. Level 3 is stability analysis of a postulated leakage size flaw under the maximum credible loading condition. Developmental work related to demonstration of level 2 and level 3 confidence is described in this paper. In a case study on fatigue crack growth on PHT straight pipes for level 2, negligible crack growth is predicted for the life of the reactor. For level 3 analysis, the R6 method has been adopted. A database to evaluate SIF of elbows with throughwall flaws under combined internal pressure and bending moment has been generated to provide one of the inputs for R6 method. The methodology of safety assessment of elbow using R6 method has been demonstrated for a typical pump discharge elbow. In this analysis, limit load of the cracked elbow has been determined by carrying out elasto-plastic finite element analysis. The limit load results compared well with those given by Miller. However, it requires further study to give a general form of limit load solution. On the experimental front, a set of small diameter pipe fracture experiments have been carried out at room temperature and 300 degrees C. Two important observations of the experiments are - appreciable drop in maximum load at 300 degrees C in case of SS pipes and out-of-plane crack growth in case of CS pipes. Experimental load deflection curves are finally compared with five J-estimation schemes predictions. A material database of PHT piping materials is also being generated for use in LBB analysis

  13. Electricity market readiness plan : Ontario Energy Board

    International Nuclear Information System (INIS)

    2001-03-01

    This document informs electric power market participants of the Ontario Energy Board's newly developed market readiness plan and target timelines that local distribution companies (LDCs) must meet for retail marketing. The Ontario Energy Board's plan incorporates relevant independent market operator (IMO)-administered market milestones with retail market readiness targeted for September 2001. The market readiness framework involves a self-certification process for LDCs by August 10, 2001, through which the Board will be able to monitor progress and assess the feasibility of meeting the target timelines. For retail market readiness, all LDCs will have to calculate settlement costs, produce unbundled bills, provide standard supply service, change suppliers and accommodate retail transactions. LDCs must be either authorized participants in the IMO-administered market or become retail customers of their host LDC. Unbundled bills will include itemized charges for energy price, transmission, distribution and debt retirement charge. 1 tab., 1 fig

  14. An Outbreak of Foodborne Botulism in Ontario

    Directory of Open Access Journals (Sweden)

    Mona R Loutfy

    2003-01-01

    Full Text Available Botulism is a rare paralytic illness resulting from a potent neurotoxin produced by Clostridium botulinum. Botulism in Canada is predominately due to C botulinum type E and affects mainly the First Nations and Inuit populations. The most recent outbreak of botulism in Ontario was in Ottawa in 1991 and was caused by C botulinum type A. We report an outbreak of foodborne type B botulism in Ontario, which implicated home-canned tomatoes. The outbreak was characterized by mild symptoms in two cases and moderately severe illness in one case. The investigation shows the importance of considering the diagnosis of botulism in patients presenting with cranial nerve and autonomic dysfunction, especially when combined with gastrointestinal complaints; it also highlights the importance of proper home canning technique.

  15. Correlation between UO2 powder and pellet quality in PHWR fuel manufacturing

    International Nuclear Information System (INIS)

    Glodeanu, F.; Spinzi, M.; Balan, V.

    1988-01-01

    Natural uranium dioxide fuel for heavy water reactors has a series of very tightly controlled quality factors: Chemical purity, density and microstructures. Although the fabrication history may consistently affect the fuel quality, the quality factor mentioned above are function mainly of the quality of the powder used as raw material. As regards the fulfilment of the requirements for very high density of the pellets, it was found that in a definite technology the raw material plays the decisive part. Except for the powder sinterability, one found other important subtile parameters, such as the degree of agglomeration and structural homogeneity. The fuel microstructure, very important for in-serive performances of the fuel, is related to a great extent to some powder characteristics (homogeneity, sinterability). This is why much stress was laid on UO 2 power quality evaluation both by standard methods and non-conventional ones (agglomeration, microscopy, X-rays). Some of the characteristics defined by product specification, such as powder sinterability, should be better defined to guarantee the final product quality. (orig.)

  16. Evaluation of the shielding integrity of end-shields in PHWR type NPPs

    International Nuclear Information System (INIS)

    Sah, B.M.L.; Ramamirtham, B.; Kutty, B.S.

    1996-01-01

    In the new plants (Narora Atomic Power Plants (NAPP) onwards) relatively higher radiation fields exist on the north and south fuelling machine (FM) vault walls of the E1 100m accessible area passages. These fields were first noticed at NAPS-1 and subsequently at NAPS-2 and KAPS-1. Such surveys done at RAPS have indicated that the fields on these walls would come out to be quite low (only 1-2 mR/h) from sources other than that arising from 41 Ar contamination. RAPS/MAPS experience pointed to adequacy of shielding of the FM vault walls and sufficient overall shielding thickness of the end-shields. Further, radiometry tests of end-shields carried out at Kaiga and RAPP 3 and 4 indicated fairly satisfactory and uniform filling of balls. Hence, incomplete filling of water column of the end-shields due to any venting problem was suspected to be one possible reason for the observed high fields in NAPS and Kakrapar Atomic Power Station (KAPS). Since the presence of high radiation fields, both neutron and gamma, is of long-term concern, a special study/measurement of radiation levels on reactor face during high power operation was undertaken. In order to compare the shielding integrity of the older (RAPS/MAPS solid plate type shielding) and newer (NAPS/KAPS steel ball-filled type) end shields, these experiments were done at MAPS-2 and NAPS-2. (author). 2 refs., 2 tabs

  17. Development and validation of computer codes for analysis of PHWR containment behaviour

    International Nuclear Information System (INIS)

    Markandeya, S.G.; Haware, S.K.; Ghosh, A.K.; Venkat Raj, V.

    1997-01-01

    In order to ensure that the design intent of the containment of Indian Pressurised Heavy Water Reactors (IPHWRs) is met, both analytical and experimental studies are being pursued at BARC. As a part of analytical studies, computer codes for predicting the behaviour of containment under various accident scenarios are developed/adapted. These include codes for predicting 1) pressure, temperature transients in the containment following either Loss of Coolant Accident (LOCA) or Main Steam Line Break (MSLB), 2) hydrogen behaviour in respect of its distribution, combustion and the performance of proposed mitigation systems, and 3) behaviour of fission product aerosols in the piping circuits of the primary heat transport system and in the containment. All these codes have undergone thorough validation using data obtained from in-house test facilities or from international sources. Participation in the International Standard Problem (ISP) exercises has also helped in validation of the codes. The present paper briefly describes some of these codes and the various exercises performed for their validation. (author)

  18. Life cycle management at Ontario Power Generation

    International Nuclear Information System (INIS)

    Spekkens, P.

    2006-01-01

    This paper outlines the Life Cycle Management (LCM) program at Ontario Power Generation. LCM is carried out at different levels that includes components, systems, unit and fleet. A system involves cumulative effect of individual component aging. These components include steam generators, pressure tubes and feeders. A unit involves an overall unit aging strategy integrating all systems. At the fleet level, there is an optimal strategy for plant-level investments including end-of-life of a unit

  19. Interim report on nuclear power in Ontario

    International Nuclear Information System (INIS)

    1978-01-01

    An exhaustive report is presented on the implications of nuclear electric generation for Ontario's energy future. Such aspects as electrical demand and power planning, the CANDU fuel cycle, the nuclear debate, health, environmental and safety concerns, economics, social impacts and the status of the nuclear industry, uranium resources, ethical and political issues, nuclear weapons proliferation and plant security, and the regulation of nuclear power are dealt with in detail. (E.C.B.)

  20. CANDU reactor - supporting the nuclear renaissance

    International Nuclear Information System (INIS)

    Oberth, R.

    2010-01-01

    'Full text:' The CANDU reactor has proven to be a strong performer in both the Canada, with 22 units constructed in Ontario, New Brunswick and Quebec, as well as in Argentina, Korea, Romania and China where a further nine units are operating and two in the planning stage. The average lifetime capacity factor of the CANDU reactor fleet is 89%. The last seven CANDU projects in Korea, China, and Romania have been completed on budget and on schedule. CANDU reactors have the highest uranium utilization efficiency measures as electricity output per ton of uranium mined. The CANDU fuel channel design using on-power fuelling and a heavy water moderator enables flexible fueling options - from the current natural uranium option to burning uranium recovered from used LWR reactor fuel and even a thorium-based fuel. AECL and the CANDU reactor are poised to participate in the worldwide construction at least 250 new reactors over the next 20 years. (author)

  1. Ontario Hydro's operating experience with steam generators with specifics on Bruce A and Bruce B problems

    Energy Technology Data Exchange (ETDEWEB)

    Eatock, J W; Patterson, R W [Ontario Hydro, Toronto, ON (Canada); Dyck, R W [Ontario Hydro, Central Production Services Division, Toronto, ON (Canada)

    1991-04-01

    The performance of the steam generators in Ontario Hydro nuclear power stations is reviewed. This performance has generally been outstanding compared to world averages, with very low tube failure and plugging rates. Steam generator problems have made only minor contributions to Ontario Hydro nuclear station incapability factors. The mechanisms responsible for the the observed tube degradation and failures are described. The majority of the leaks have been due fatigue in the U-bend of the Bruce 'A' steam generators. There have been very few failures attributed to corrosion of the three tube materials used in Ontario Hydro steam generators. Recent performance has been deteriorating primarily due to deposit accumulation in the steam generators. Plugging of the broached holes in the upper support plates at Bruce 'A' has caused some derating of two units. Increases have been observed in the primary heat transport system reactor inlet temperature of several units. These increases may be attributed to steam generator tube surface fouling. In addition, several units have accumulated deep, hard sludge piles on the tube sheet, although little damage been observed. Recently some fretting of tubes has been observed at BNGSB in the U-bend support region. Remedial measures are being taken to address the current problems. Solutions are being evaluated to reduce the generation of corrosion products in the feedtrain and their subsequent transport to the steam generators. (author)

  2. Ontario Hydro's operating experience with steam generators with specifics on Bruce A and Bruce B problems

    International Nuclear Information System (INIS)

    Eatock, J.W.; Patterson, R.W.; Dyck, R.W.

    1991-01-01

    The performance of the steam generators in Ontario Hydro nuclear power stations is reviewed. This performance has generally been outstanding compared to world averages, with very low tube failure and plugging rates. Steam generator problems have made only minor contributions to Ontario Hydro nuclear station incapability factors. The mechanisms responsible for the the observed tube degradation and failures are described. The majority of the leaks have been due fatigue in the U-bend of the Bruce 'A' steam generators. There have been very few failures attributed to corrosion of the three tube materials used in Ontario Hydro steam generators. Recent performance has been deteriorating primarily due to deposit accumulation in the steam generators. Plugging of the broached holes in the upper support plates at Bruce 'A' has caused some derating of two units. Increases have been observed in the primary heat transport system reactor inlet temperature of several units. These increases may be attributed to steam generator tube surface fouling. In addition, several units have accumulated deep, hard sludge piles on the tube sheet, although little damage been observed. Recently some fretting of tubes has been observed at BNGSB in the U-bend support region. Remedial measures are being taken to address the current problems. Solutions are being evaluated to reduce the generation of corrosion products in the feedtrain and their subsequent transport to the steam generators. (author)

  3. Interconnection issues in Ontario : a status check

    International Nuclear Information System (INIS)

    Helbronner, V.

    2010-01-01

    This PowerPoint presentation discussed wind and renewable energy interconnection issues in Ontario. The province's Green Energy Act established a feed-in tariff (FIT) program and provided priority connection access to the electricity system for renewable energy generation facilities that meet regulatory requirements. As a result of the province's initiatives, Hydro One has identified 20 priority transmission expansion projects and is focusing on servicing renewable resource clusters. As of October 2010, the Ontario Power Authority (OPA) has received 1469 MW of FIT contracts executed for wind projects. A further 5953 MW of wind projects are awaiting approval. A Korean consortium is now planning to develop 2500 MW of renewable energy projects in the province. The OPA has also been asked to develop an updated transmission expansion plan. Transmission/distribution availability tests (TAT/DAT) have been established to determine if there is sufficient connection availability for FIT application projects. Economic connection tests (ECTs) are conducted to assess whether grid upgrade costs to enable additional FIT capacity are justifiable. When projects pass the ECT, grid upgrades needed for the connection included in grid expansion plans. Ontario's long term energy plan was also reviewed. tabs., figs.

  4. Gas marketing strategies for Ontario producers

    Energy Technology Data Exchange (ETDEWEB)

    Walsh, P.R. [Energy Objective Ltd., London, ON (Canada)

    2000-07-01

    Activity in natural gas exploration and production in the province of Ontario has recently increased due to higher natural gas prices. This paper discussed the issue of how the gas from the new reserves should be marketed. A review of historical pricing and consumption patterns was also presented to better identify how prices of natural gas are determined in Ontario and to forecast the future demand for natural gas. The first trend of interest is the increased use of natural gas in generating electricity to meet cooling needs in the summer months. The second trend is the increase in gas consumption by the industrial sector resulting from increases in process load. Several marketing options are available to Ontario natural gas producers. They can market their gas to third parties at various trading points in the province or they can market it directly to Union Gas Limited, the local gas utility. This paper briefly described how a gas supply contract works with the union, how gas marketing agreement is conducted with a gas marketer, and how a gas marketing arrangement works with a consultant. Some of the pitfalls of marketing natural gas were also described and some recommended some strategies for selling natural gas in the future were presented. 7 figs.

  5. A fluvial mercury budget for Lake Ontario.

    Science.gov (United States)

    Denkenberger, Joseph S; Driscoll, Charles T; Mason, Edward; Branfireun, Brian; Warnock, Ashley

    2014-06-03

    Watershed mercury (Hg) flux was calculated for ten inflowing rivers and the outlet for Lake Ontario using empirical measurements from two independent field-sampling programs. Total Hg (THg) flux for nine study watersheds that directly drain into the lake ranged from 0.2 kg/yr to 13 kg/yr, with the dominant fluvial THg load from the Niagara River at 154 kg/yr. THg loss at the outlet (St. Lawrence River) was 68 kg/yr and has declined approximately 40% over the past decade. Fluvial Hg inputs largely (62%) occur in the dissolved fraction and are similar to estimates of atmospheric Hg inputs. Fluvial mass balances suggest strong in-lake retention of particulate Hg inputs (99%), compared to dissolved total Hg (45%) and methyl Hg (22%) fractions. Wetland land cover is a good predictor of methyl Hg yield for Lake Ontario watersheds. Sediment deposition studies, coupled atmospheric and fluvial Hg fluxes, and a comparison of this work with previous measurements indicate that Lake Ontario is a net sink of Hg inputs and not at steady state likely because of recent decreases in point source inputs and atmospheric Hg deposition.

  6. Ontario's energy crisis brings out conflicting visions

    International Nuclear Information System (INIS)

    Kishewitsch, S.

    2004-01-01

    Ontario's medium-term energy supply situation is discussed in light of the Ontario provincial government's insistence on phasing out coal-fired generation by 2007, and the somewhat longer term uncertainty about the aging nuclear fleet and the price tag associated with their overhauling or replacement. Centre to the discussion is the replacement of coal-fired plants by natural gas-fired generating plants, complicated by the fact is that there is already a surfeit of gas-fired plants sitting idle for lack of fuel available at an economically acceptable price. Recent statistics show that conventional gas supplies have already levelled off and unconventional sources, such as coalbed methane, and imports like LNG, are more abundant, but also significantly more expensive. The nuclear option is considered by knowledgeable insiders as a viable option for increased generation, although it is generally acknowledged as a serious public relations problem. The contributions of green power and cogeneration are also explored; the most optimistic estimates put the supply from this source at 50,000 GWh a year; less than the amount needed even in the absence of growth in demand. The overall conclusion is that Ontario's energy future can only be assured by aggressive pursuit of productivity improvements, financial and policy innovations, extensive use of cogeneration, strong development of renewables, energy conservation, efficiency, and demand management

  7. Gas marketing strategies for Ontario producers

    International Nuclear Information System (INIS)

    Walsh, P.R.

    2000-01-01

    Activity in natural gas exploration and production in the province of Ontario has recently increased due to higher natural gas prices. This paper discussed the issue of how the gas from the new reserves should be marketed. A review of historical pricing and consumption patterns was also presented to better identify how prices of natural gas are determined in Ontario and to forecast the future demand for natural gas. The first trend of interest is the increased use of natural gas in generating electricity to meet cooling needs in the summer months. The second trend is the increase in gas consumption by the industrial sector resulting from increases in process load. Several marketing options are available to Ontario natural gas producers. They can market their gas to third parties at various trading points in the province or they can market it directly to Union Gas Limited, the local gas utility. This paper briefly described how a gas supply contract works with the union, how gas marketing agreement is conducted with a gas marketer, and how a gas marketing arrangement works with a consultant. Some of the pitfalls of marketing natural gas were also described and some recommended some strategies for selling natural gas in the future were presented. 7 figs

  8. Reappraisal of the seismotectonics of southern Ontario

    International Nuclear Information System (INIS)

    Mohajer, A.A.

    1987-11-01

    The fundamental objectives of this study were to review and improve the seismological data base as an aid in more realistic evaluation of seismic hazard in southern Ontario. For this purpose, the following procedures have been undertaken: In the first stage, the types of errors in earthquake location files are identified, sources of uncertainties are discussed and a sensitivity analysis of the errors to different parameters is presented. In the second stage, a group location technique, Joint Hypocenter Determination (JHD), has been utilized to improve the locations of a group of 67 well-recorded events, mostly from the more active region near the Ottawa River and in western Quebec. The third stage, to relocate smaller and less reliably detected events in southern Ontario, utilized a nw algorithm, 'HYPOCENTER', which proved very efficient and flexible in the test runs for handling local explosion and natural events. A preliminary interpretation of the seismicity patterns in the study regions shows that earthquakes of magnitude 3 and larger tend to align along preferred seismic trends which may, in turn, be controlled by weakness planes in the Earth's crust. These inferred trends coincide with dominant northwesterly and northeasterly striking structural directions. For earthquakes smaller than magnitude 4 prior to 1970 and for microearthquakes (M<3) which occurred near the Lake Ontario shoreline, the detection coverage was not sufficient to conclusively discuss accurate locations and causative mechanisms

  9. Climate change impacts: an Ontario perspective

    International Nuclear Information System (INIS)

    Mortsch, L.

    1995-11-01

    Significant changes in the climate system which are likely to affect biophysical, social and economic systems in various ways, were discussed. Trends in greenhouse gas levels show that during the 20. century, human activity has changed the make-up of the atmosphere and its greenhouse effect properties. A pilot study on the impacts of climate change identified changes in the water regime such as declines in net basin supply, lake levels and outflows, as important concerns. These changes would have impacts on water quality, wetlands, municipal water supply, hydroelectric power generation, commercial shipping, tourism and recreation, and to a lesser extent, on food productions. Climate impact assessments suggest that world conditions will change significantly as a result. Those with less resources are likely to be most affected by climate change, and the impacts on other regions of the world will be more significant to Ontario than the direct impacts on Ontario itself. In an effort to keep pace with global changes, Ontario will have to limit emissions, conduct research in innovative technology and develop greater awareness of the risk of climate change. refs., tabs., figs

  10. Probabilistic integrity assessment of pressure tubes in an operating pressurized heavy water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Young-Jin; Park, Heung-Bae [KEPCO E and C, 188 Gumi-dong, Bundang-gu, Seongnam-si, Gyeonggi-do 463-870 (Korea, Republic of); Lee, Jung-Min; Kim, Young-Jin [School of Mechanical Engineering, Sungkyunkwan University, 300 Chunchun-dong, Jangan-gu, Suwon-si, Gyeonggi-do 440-746 (Korea, Republic of); Ko, Han-Ok [Korea Institute of Nuclear Safety, 34 Gwahak-ro, Yuseong-gu, Daejeon-si 305-338 (Korea, Republic of); Chang, Yoon-Suk, E-mail: yschang@khu.ac.kr [Department of Nuclear Engineering, Kyung Hee University, 1 Seocheon-dong, Giheung-gu, Yongin-si, Gyeonggi-do 446-701 (Korea, Republic of)

    2012-02-15

    Even though pressure tubes are major components of a pressurized heavy water reactor (PHWR), only small proportions of pressure tubes are sampled for inspection due to limited inspection time and costs. Since the inspection scope and integrity evaluation have been treated by using a deterministic approach in general, a set of conservative data was used instead of all known information related to in-service degradation mechanisms because of inherent uncertainties in the examination. Recently, in order that pressure tube degradations identified in a sample of inspected pressure tubes are taken into account to address the balance of the uninspected ones in the reactor core, a probabilistic approach has been introduced. In the present paper, probabilistic integrity assessments of PHWR pressure tubes were carried out based on accumulated operating experiences and enhanced technology. Parametric analyses on key variables were conducted, which were periodically measured by in-service inspection program, such as deuterium uptake rate, dimensional change rate of pressure tube and flaw size distribution. Subsequently, a methodology to decide optimum statistical distribution by using a robust method adopting a genetic algorithm was proposed and applied to the most influential variable to verify the reliability of the proposed method. Finally, pros and cons of the alternative distributions comparing with corresponding ones derived from the traditional method as well as technical findings from the statistical assessment were discussed to show applicability to the probabilistic assessment of pressure tubes.

  11. Design of an additional heat sink based on natural circulation in pressurized water reactors

    International Nuclear Information System (INIS)

    Frischengruber, Kurt; Solanilla, Roberto; Fernandez, Ricardo; Blumenkrantz, Arnaldo; Castano, Jorge

    1989-01-01

    Residual heat removal through the steam generators in Nuclear Power Plant with pressurized water reactors (PWR) or pressurized heavy water reactors (PHWR in pressured vessel or pressured tube types) requires the maintenance of the steam generator inventory and the availability of and appropriate heat sink, which are based on the operability of the steam generators feedwater system. This paper describes the conceptual design of an assured heat removal system which includes only passive elements and is based on natural circulation. The system can supplement the original systems of the plant. The new system includes a condenser/boiler heat exchanger to condense the steam produced in the steam generator, transferring the heat to the water of an open pool at atmospheric pressure. The condensed steam flows back to the steam generators by natural circulation effects. The performance of an Atucha type PHWR nuclear power station with and without the proposed system is calculated in an emergency power case for the first 5000 seconds after the incident. The analysis shows that the proposed system offers the possibility to cool-down the plant to a low energy state during several hours and avoids the repeated actuation of the primary and secondary system safety valves. (Author) [es

  12. IFPE/CNEA-MOX-RAMP, CNEA Power Ramp Irradiations with (PHWR) MOX Fuels

    International Nuclear Information System (INIS)

    Marino, Armando Carlos; Turnbull, J.A.

    2000-01-01

    Description: The irradiation of the first MOX nuclear fuel rods fabricated in Argentina began in 1986. These experiences were made in the HFR-Petten reactor, Holland. The six rods were fabricated in the a Facility (GAID-CNEA-Argentina). The first rod has been used for destructive pre-irradiation characterization in the KFK (Kernforschungszentrum Karlsruhe), Germany. The second one was a pathfinder for calibrating HFR systems in Petten. Two other rods included pellets doped with iodine. The first contained mostly CsI whilst the second contained elemental iodine. The concentration of iodine was intended to simulate a burn-up of 15000 MWd/ton(M). The power histories were defined from calculations performed with the BACO code. A 15 day cycle was assumed with a power history that induced PCMI during power cycling. The last high power period was maintained until stress corrosion cracking (SCC) was induced. Two further un-doped rods were used in a sub-program named BU15. Here a burn-up of 15000 MWd/ton(M) was achieved at a low power followed by a final power ramp for one of the rods. The ramp was similar to that used for the Iodine test. The HFR irradiation was conducted satisfactorily. The objective was to attempt a correspondence in behaviour between the doped rods and BU15 rods. PIE detected the presence of micro-cracks inside the cladding of the iodine doped rods. Ramping of the BU15 rod was interrupted when an increase of coolant activity was detected. After discharge, a visual inspection of the rod showed the presence of a small circular hole in the cladding. Additional PIE showed that the hole was due to a SCC failure

  13. Plant specific risk informed decision making -a vision for Indian PHWR

    International Nuclear Information System (INIS)

    Guptan, Rajee; Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

    2006-01-01

    The objective of Nuclear Power Plant (NPP) safety is to ensure and demonstrate that the risk from NPP to public and plant personnel is acceptably low. As a supplement to the deterministic approach, use of probabilistic techniques has been gaining grounds. Probabilistic Safety Assessment (PSA) is a popular international practice to calculate plant risk to the public, environment and plant personnel, in the event of an accident taking place in the plant. The risk posed by Nuclear Reactors to the Public at large is a very important issue in the public acceptance of a Nuclear Power Programme in any country. Risk Definition, generally accepted at present as the measure of possibility for an accidental event and severity of its effects to occur, simultaneously comprises both the probability (frequency) of potential damage occurrence and extent of this damage. NPCIL' s vision is to provide safe, reliable and cost effective energy to the nation by ensuring safe operation of the plants, limiting radiation exposure to plant personnel and public within prescribed limits. To achieve this vision our mission is to enhance the technical competency, resources and the awareness towards improved safety culture specific to Probabilistic Safety Assessment for applying PSA Studies to Risk Informed Decision making. This mission translates into the goal of completion of full scope PSA, with the co-operation and synergetic efforts of the Head quarters and Operating Station experts. NPCIL will then be self sufficient in applying Probabilistic Studies in Risk Informed Decision making to minimize risk and back fitting design changes to optimize the existing design and operating practices, thus providing for safe, reliable and cost effective energy to the nation. (author)

  14. Mental Health Consultation Among Ontario's Immigrant Populations.

    Science.gov (United States)

    Islam, Farah; Khanlou, Nazilla; Macpherson, Alison; Tamim, Hala

    2017-11-16

    To determine the prevalence rates and characteristics of past-year mental health consultation for Ontario's adult (18 + years old) immigrant populations. The Canadian Community Health Survey (CCHS) 2012 was used to calculate the prevalence rates of past-year mental health consultation by service provider type. Characteristics associated with mental health consultation were determined by carrying out multivariable logistic regression analysis on merged CCHS 2008-2012 data. Adult immigrant populations in Ontario (n = 3995) had lower estimated prevalence rates of past-year mental health consultation across all service provider types compared to Canadian-born populations (n = 14,644). Amongst those who reported past-year mental health consultation, 57.89% of Ontario immigrants contacted their primary care physician, which was significantly higher than the proportion who consulted their family doctor from Canadian-born populations (45.31%). The factors of gender, age, racial/ethnic background, education level, working status, food insecurity status, self-perceived health status, smoking status, alcohol drinking status, years since immigration, and age at time of immigration were significantly associated with past-year mental health consultation for immigrant populations. Ontario's adult immigrant populations most commonly consult their family doctor for mental health care. Potential exists for expanding the mental health care role of primary care physicians as well as efforts to increase accessibility of specialized mental health services. Integrated, coordinated care where primary care physicians, specialized mental health professionals, social workers, and community educators, etc. working together in a sort of "one-stop-shop" may be the most effective way to mitigate gaps in the mental health care system. In order to effectively tailor mental health policy, programming, and promotion to suit the needs of immigrant populations initiatives that focus on

  15. Lake Ontario benthic prey fish assessment, 2015

    Science.gov (United States)

    Weidel, Brian C.; Walsh, Maureen; Holden, Jeremy P.; Connerton, Michael J.

    2016-01-01

    Benthic prey fishes are a critical component of the Lake Ontario food web, serving as energy vectors from benthic invertebrates to native and introduced piscivores. Since the late 1970’s, Lake Ontario benthic prey fish status was primarily assessed using bottom trawl observations confined to the lake’s south shore, in waters from 8 – 150 m (26 – 492 ft). In 2015, the Benthic Prey Fish Survey was cooperatively adjusted and expanded to address resource management information needs including lake-wide benthic prey fish population dynamics. Effort increased from 55 bottom trawl sites to 135 trawl sites collected in depths from 8 - 225m (26 – 738 ft). The spatial coverage of sampling was also expanded and occurred in all major lake basins. The resulting distribution of tow depths more closely matched the available lake depth distribution. The additional effort illustrated how previous surveys were underestimating lake-wide Deepwater Sculpin, Myoxocephalus thompsonii, abundance by not sampling in areas of highest density. We also found species richness was greater in the new sampling sites relative to the historic sites with 11 new fish species caught in the new sites including juvenile Round Whitefish, Prosopium cylindraceum, and Mottled sculpin, Cottus bairdii. Species-specific assessments found Slimy Sculpin, Cottus cognatus abundance increased slightly in 2015 relative to 2014, while Deepwater Sculpin and Round Goby, Neogobius melanostomus, dramatically increased in 2015, relative to 2014. The cooperative, lake-wide Benthic Prey Fish Survey expanded our understanding of benthic fish population dynamics and habitat use in Lake Ontario. This survey’s data and interpretations influence international resource management decision making, such as informing the Deepwater Sculpin conservation status and assessing the balance between sport fish consumption and prey fish populations. Additionally a significant Lake Ontario event occurred in May 2015 when a single

  16. Proceedings of the Ontario Energy Association's 2004 annual conference

    International Nuclear Information System (INIS)

    2004-01-01

    The Ontario Energy Association (OEA) is a unique trade association that represents key participants in Ontario's converging natural gas and electricity industries. Its members include energy producers, transmitters, distributors, marketers, and retailers. This conference provided a forum to discuss the role of energy policy and energy conservation in promoting competitive and efficient gas and electricity markets in Ontario. The conference featured 15 presentations, of which 3 have been catalogued separately for inclusion in this database

  17. Advances in the manufacture of clad tubes and components for PHWR fuel bundle

    International Nuclear Information System (INIS)

    Saibaba, N.; Jha, S.K.; Chandrasekha, B.; Tonpe, S.; Jayaraj, R.N.

    2010-01-01

    Fuel bundles for Pressurized Heavy Water Reactors (PHWRs) consists of Uranium di-oxide pellets encapsulated into thin wall Zircaloy clad tubes. Other components such as end caps, bearing pads and spacer pads are the integral elements of the fuel bundle. As the fuel assembly is subjected to severe operating conditions of high temperature and pressure in addition to continual irradiation exposure, all the components are manufactured conforming to stringent specifications with respect to chemical composition, mechanical & metallurgical properties and dimensional tolerances. The integrity of each component is ensured by NDE at different stages of manufacture. The manufacturing route for fuel tubes and components comprise of a combination of thermomechanical processing and each process step has marked effect on the final properties. The fuel tubes are manufactured by processing the extruded blanks in four stage cold pilgering with intermediate annealing and final stress relieving operation. The bar material is produced by hot extrusion followed by multi-pass swaging and intermediate annealing. Spacer pads and bearing pads are manufactured by blanking and coining of Zircaloy sheet which is made by a combination of hot and cold rolling operations. Due to the small size and stringent dimensional requirements of these appendages, selection of production route and optimization of process parameters are important. This paper discusses about various measures taken for improving the recoveries and mechanical and corrosion properties of the tube, sheet and bar materials being manufactured at Nuclear Fuel Complex, Hyderabad For the production of clad tubes, modifications at extrusion stage to reduce the wall thickness variation, introduction of ultrasonic testing of extruded blanks, optimization of cold working and heat treatment parameters at various stages of production etc. were done. The finished bar material is subjected to 100% Ultrasonic and eddy current testing to ensure

  18. Development of organic tritium light technology at Ontario Hydro

    International Nuclear Information System (INIS)

    Mullins, D.F.; Krasznai, J.P.; Mueller, D.A.

    1992-01-01

    Tritium is a by-product of CANDU heavy water reactor operations and is the major contributor to internal dose for plant workers. The Darlington Tritium Removal Facility (DTRF) is decontaminating heavy water by removing tritium and storing it as a metal hydride. In view of the large tritium separation capacity, (24 MCi/a, 888 PBq/a). This paper reports that Ontario Hydro is interested in pursuing markets for the peaceful uses of tritium. One of these peaceful uses is in self-luminous lighting. The state of the art at present is a phosphor coated tube filled with tritium gas. However, safety considerations have restricted the use of these lights to outdoor or essential safety applications. Binding the tritium to a solid non-volatile matrix would increase the safety of tritium lights and allow the use of other phosphors, matrices and construction geometries. Solid, organic based tritium lights were produced using two different polymer matrices. While both these materials produced visible light, the intensity was low and radiolytic damage to the polymers was evident

  19. Conceptual design of a quasi-homogeneous pressurized heavy water reactor to be operated in the closed Th-U233 fuel cycle

    International Nuclear Information System (INIS)

    1979-06-01

    This paper deals with the heavy water reactor, which, from the neutron economy point of view, offers advantages over the light water reactor. Its capability to be fuelled with natural uranium has also been considered a desirable nuclear option by various countries with sufficient domestic uranium resources not wishing to be dependent on the import of enrichment and other fuel cycle services which, in addition, would draw on the foreign exchange reserves. Pressurized heavy water reactors have been designed and built according to two somewhat different versions. While the Canadian CANDU-PHWR concept uses pressure tubes in a nearly unpressurized moderator tank (calandria), the German development line takes advantage of the established and well proven LWR technology, and, thus, uses a pressure vessel design where coolant channels and the surrounding moderator are held at equal pressure. This pressure vessel type heavy water reactor which has been built on a commercial demonstration plant level at ATUCHA in Argentina is described in a companion paper where also a conceptual design for a 685 MWsub(e) PHWR is discussed

  20. An overview of the regulation of the activities of Eldorado Nuclear Limited in Port Hope, Ontario

    International Nuclear Information System (INIS)

    Smythe, W.D.

    1980-09-01

    Eldorado Nuclear Limited's operations at Port Hope, Ontario include both chemical and metallurgical processes involved in processing uranium in various forms. The plant processes natural uranium for both the domestic and export markets, and processes enriched uranium for the fuel in Canada's research reactors and for booster fuel for Candu reactors. The plant receives wastes from fuel fabrication plants and recycles them to recover uranium, and also produces wastes of its own. The Atomic Energy Control Board (AECB) is involved at all stages of this operation, as the agency responsible for nuclear materials management, safeguards, occupational health and safety, and safe disposal of wastes in all Canada's nuclear facilities. The AECB has also been involved in the clean up of contamination from the early days of operations in Port Hope

  1. Ontario Hydro experience in the identification and mitigation of potential failures in safety critical software systems

    International Nuclear Information System (INIS)

    Huget, R.G.; Viola, M.; Froebel, P.A.

    1995-01-01

    Ontario Hydro has had experience in designing and qualifying safety critical software used in the reactor shutdown systems of its nuclear generating stations. During software design, an analysis of system level hazards and potential hardware failure effects provide input to determining what safeguards will be needed. One form of safeguard, called software self checks, continually monitor the health of the computer on line. The design of self checks usually is a trade off between the amount of computing resources required, the software complexity, and the level of safeguarding provided. As part of the software verification activity, a software hazards analysis is performed, which identifiers any failure modes that could lead to the software causing an unsafe state, and which recommends changes to mitigate that potential. These recommendations may involve a re-structuring of the software to be more resistant to failure, or the introduction of other safeguarding measures. This paper discusses how Ontario Hydro has implemented these aspects of software design and verification into safety critical software used in reactor shutdown systems

  2. 34. annual conference Ontario Petroleum Institute

    International Nuclear Information System (INIS)

    1995-01-01

    A total of 18 papers, dealing with a variety of issues relevant to the petroleum industry, such as marketing strategies, feasibility studies and exploration technologies, were combined in this volume of proceedings of the 34th annual conference of the Ontario Petroleum Institute. Some of the papers presented case studies of hydrocarbon reserves in North America, along with their depositional histories. Oil yields and resource potential of fractured reservoirs was the subject of some presentations. Studies of cores from drilling sites and complete stratigraphic columns of some oil fields were also presented. (Papers are paged individually). refs., tabs., figs

  3. The Ontario Energy Board's proposed new mandate

    International Nuclear Information System (INIS)

    Laughren, F.

    1998-01-01

    The Ontario Energy Board's proposed new mandate was reviewed. The role of the Board will be to regulate the monopoly delivery components of the electricity and natural gas industry and to smooth the transition to competition. The Board will monitor market performance and will encourage electricity and natural gas monopoly services to be compatible where possible. The Board will also assist local restructuring efforts when called upon do so and ensure that the marketplace operates efficiently and effectively. Gas marketers' licensing is scheduled to begin in early 1999. Licenses will also apply to the electric industry. The objectives of the proposed licensing, the regulatory requirements and the proposed regulatory approach are described

  4. Ontario Power Generation Nuclear: results and opportunities

    International Nuclear Information System (INIS)

    Dermarkar, F.

    2006-01-01

    This paper describes the accomplishments of Ontario Power Generation (OPG) Nuclear and outlines future opportunities. OPG's mandate is to cost effectively produce electricity, while operating in a safe, open and environmentally responsible manner. OPG's nuclear production has been increasing over the past three years - partly from the addition of newly refurbished Pickering A Units 1 and 4, and partly from the increased production from Darlington and Pickering B. OPG will demonstrate its proficiency and capability in nuclear by continuing to enhance the performance and cost effectiveness of its existing operations. Its priorities are to focus on performance excellence, commercial success, openness, accountability and transparency

  5. The Ontario Hydro mortality surveillance programme

    International Nuclear Information System (INIS)

    Anderson, T.W.

    1985-01-01

    The Ontario Hydro mortality surveillance programme was the first such study established in any group of radiation workers. Copies of annual reports are available to senior officials of both management and union and to members of the general public. Apart from an elevated Standardized Mortality Ratio in the 15.0 - 19.9 cSv range, there is no suggestion of any rising cancer death rate with increased lifetime radiation dose. It should be noted that employees who had left before pensionable age were not included in the study. Results of the study are presented in tabular form

  6. Design considerations and operating experience with wet storage of Ontario Hydro's irradiated fuel

    International Nuclear Information System (INIS)

    Frost, C.R.; Naqvi, S.J.; McEachran, R.A.

    1987-01-01

    The characteristics of Ontario Hydro's fuel and at-reactor irradiated fuel storage water pools (or irradiated fuel bays) are described. There are two types of bay known respectively as primary bays and auxiliary bays, used for at-reactor irradiated fuel storage. Irradiated fuel is discharged remotely from Ontario Hydro's reactors to the primary bays for initial storage and cooling. The auxiliary bays are used to receive and store fuel after its initial cooling in the primary bay, and provide additional storage capacity as needed. The major considerations in irradiated fuel bay design, including site-specific requirements, reliability and quality assurance, are discussed. The monitoring of critical fuel bay components, such as bay liners, the development of high storage density fuel containers, and the use of several irradiated fuel bays at each reactor site have all contributed to the safe handling of the large quantities of irradiated fuel over a period of about 25 years. Routine operation of the irradiated fuel bays and some unusual bay operational events are described. For safety considerations, the irradiated fuel in storage must retain its integrity. Also, as fuel storage is an interim process, likely for 50 years or more, the irradiated fuel should be retrievable for downstream fuel management phases such as reprocessing or disposal. A long-term experimental program is being used to monitor the integrity of irradiated fuel in long-term wet storage. The well characterized fuel, some of which has been in wet storage since 1962 is periodically examined for possible deterioration. The evidence from this program indicates that there will be no significant change in irradiated fuel integrity (and retrievability) over a 50 year wet storage period

  7. Managing an oak decline crisis in Oakville, Ontario: lessons learned

    Science.gov (United States)

    Peter A. Williams; John W. McNeil; Kurt W. Gottschalk; Robert A. Haack

    2013-01-01

    The town of Oakville, Ontario, is located along the north shore of Lake Ontario between Toronto and Hamilton. In the fall of 2002, significant oak (Quercus spp.) mortality was observed at Oakville's Iroquois Shoreline Woods Park, an environmentally significant forest remnant noted for its oak-dominated forests. Investigations suggested that oak...

  8. Cooperatives and the State: The Case of Ontario

    Directory of Open Access Journals (Sweden)

    Rachel Laforest

    2011-01-01

    Full Text Available In the early 2000s, the cooperative movement in Ontario came together in order to lobby its provincial government for active cooperative development support programs. Momentum was building for these types of programs. Already, many provincial governments had implemented active support programs in their jurisdiction. Despite having one of the largest cooperative sectors in Canada, Ontario was lagging behind. This article assesses the progress of the efforts of the Ontario cooperative movement to date. It details how the Ontario cooperative movement developed a sectoral identity for itself and framed its objectives in an effort to strengthen its relationship with the Ontario government. / Le mouvement coopératif en Ontario s'est rassemblé au début des années 2000 afin de faire pression sur le gouvernement provincial pour qu'il développe des programmes de soutient actif pour coopératives. Déjà plusieurs gouvernements provinciaux avaient mis en place de telles politiques. L'Ontario tardait malgré le fait qu'il avait un des plus grands secteurs coopératifs au Canada. Cet article examine le progrès qu'a connu le mouvement coopératif en Ontario dans ses efforts. Il décrit comment le mouvement coopératif a construit une identité sectorielle autour de laquelle il a pu ancrer ses demandes auprès du gouvernement ontarien.

  9. Colonoscopy resource availability and colonoscopy utilization in Ontario, Canada

    Directory of Open Access Journals (Sweden)

    Colleen Webber

    2017-04-01

    The availability of colonoscopy resources improved in Ontario between 2007 and 2013. However, the geographic variation in resource availability and findings that higher colonoscopy resource availability is associated with higher colonoscopy utilization suggest that certain areas of the province may be under-resourced. These areas may be appropriate targets for efforts to improve colonoscopy capacity in Ontario.

  10. Education Governance Reform in Ontario: Neoliberalism in Context

    Science.gov (United States)

    Sattler, Peggy

    2012-01-01

    This paper explores the relationship between neoliberal ideology and the discourse and practice of education governance reform in Ontario over the last two decades. It focuses on changes in education governance introduced by successive Ontario governments: the NDP government from 1990 to 1995, the Progressive Conservative government from 1995 to…

  11. Province of Ontario nuclear emergency plan. Pt. 1

    International Nuclear Information System (INIS)

    1986-06-01

    The Province of Ontario Nuclear Emergency Plan has been developed pursuant to Section 8 of the Emergency Plans Act, 1983. This plan replaces the Province of Ontario Nuclear Contingency Off-Site Plan (June 1980) which is no longer applicable. The wastes plan includes planning, preparation, emergency organization and operational responsibilities and policy

  12. Chemical aspects of hydrogen ingress in zirconium and zircaloy pressure tubes: ageing management of Indian PHWR coolant channels - determination of hydrogen and deuterium

    International Nuclear Information System (INIS)

    Sayi, Y.S.; Shankaran, P.S.; Yadav, C.S.; Ramanjaneyulu, P.S.; Venugopal, V.; Ramakumar, K.L.; Chhapru, G.C.; Prasad, R.; Jain, H.C.; Sood, D.D.

    2009-02-01

    Pressurized heavy water reactors (PHWRs) use zirconium and zirconium based alloys as clad and coolant tubes since its beginning. The first ever zircaloy-2 pressure tube failure occurred in 1983 at Ontario Hydro's Pickering Unit 2 in Canada which necessitated a thorough examination of causes of such failure. The failure was attributed to massive hydriding at the failed spot of pressure tube. Continuous usage of zirconium alloys could result in their hydrogen and deuterium pick-up leading to hydrogen/ deuterium embrittlement. The life of the zircaloy coolant channels is dictated by hydrogen/deuterium content and hence ageing management of the pressure tubes is essential for ensuring their trouble-free usage. It is desirable to have a sound knowledge on the chemical aspects of zirconium and zirconium based alloys metallurgy, the mechanistic principles of hydrogen ingress into the pressure tubes during in reactor service, and identifying suitable analytical methodologies for precise and accurate determination of hydrogen in wafer thin sliver samples carved out from insides of pressure tubes without causing any structural damage so that it can continue to remain in service. This is desirable so that the ageing management does not result in cost-escalation. This report is divided in to three main parts. The first part deals with the chemical aspects of zirconium and zirconium based alloy metallurgy, the mechanism of hydrogen pick-up and hydride formation in zirconium matrix. The second part describes various methodologies and their limitations, available for hydrogen/deuterium determination. The third part deals in detail, about the extensive investigations carried out at Radioanalytical Chemistry Division (RACD) in Radiochemistry and Isotope Group for establishing an indigenously developed hot vacuum extraction system in combination with quadrupole mass spectrometry for precise determination of hydrogen and deuterium in wafer thin sliver sample of zircaloy. The

  13. Reactor noise analysis applications in NPP I and C systems

    Energy Technology Data Exchange (ETDEWEB)

    Gloeckler, O. [International Atomic Energy Agency, Wagramer Strosse 5, A-1400 Vienna, Austria Ontario Power Generation, 230 Westney Road South, Ajax, Ont. L1S 7R3 (Canada)

    2006-07-01

    Reactor noise analysis techniques are used in many NPPs on a routine basis as 'inspection tools' to get information on the dynamics of reactor processes and their instrumentation in a passive, non-intrusive way. The paper discusses some of the tasks and requirements an NPP has to take to implement and to use the full advantages of reactor noise analysis techniques. Typical signal noise analysis applications developed for the monitoring of the reactor shutdown system and control system instrumentation of the Candu units of Ontario Power Generation and Bruce Power are also presented. (authors)

  14. 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

  15. Independent power and cogeneration in Ontario's new competitive electricity market

    International Nuclear Information System (INIS)

    Barnstable, A.G.

    1999-01-01

    The factors influencing the initial market pricing in the early years of Ontario's new electricity market were discussed with particular insight on the potential for near term development of independent power and cogeneration. The major factors influencing prices include: (1) no increase in retail prices, (2) financial restructuring of Ontario Hydro, (3) the Market Power Mitigation Agreement, (4) tighter power plant emissions standards, and (5) an electricity supply and demand balance. Generation competition is not expected to influence market pricing in the early years of the new electricity market. Prices will instead reflect the restructuring decisions of the Ontario government. The decision to have Ontario Power Generation Inc. (OPGI) as a single generator for Ontario Hydro's generation assets will ensure that average spot market pricing in the early market years will be close to a 3.8 c/kWh revenue cap

  16. Facing the facts: the suspension of a design requirement applicable to nuclear power reactor effluents

    International Nuclear Information System (INIS)

    Amado, Valeria; Biaggio, Alfredo; Canoba, Analia; Curti, Adriana

    2008-01-01

    A design requirement aimed at limiting the discharge of globally dispersed long-lived radionuclides released by nuclear power reactors was in force in Argentine since 1979 till recently. The practical results of such regulatory measure was the need to retain C-14 in the PHWR under construction, as well as in furniture heavy water reactors to be built in the country. This paper explains the basis of such requirement, which was formulated as a collective dose constraint per unit of energy generated, and the main assumptions that triggered it. The differences between the assumptions made at the time and the reality of nuclear power generation at the beginning of the 21 st century, as well as their implications in relation to the requirement are described, including the Suess effect and its impact in the total dose due to C-14. Finally, the facts that made no longer reasonable to keep in force the above mentioned requirement are presented. (author)

  17. Investigation of fluid flow in various geometries related to nuclear reactor using PIV system

    International Nuclear Information System (INIS)

    Kansal, A.K.; Maheshwari, N.K.; Singh, R.K.; Vijayan, P.K.; Saha, D.; Singh, R.K.; Joshi, V.M.

    2011-01-01

    Particle Image Velocimetry (PIV) is a non-intrusive technique for simultaneously measuring the velocities at many points in a fluid flow. The PIV system used is comprised of Nd:YAG laser source, CCD (Charged Coupled Device) camera, timing controller (to control the laser and camera) and software used for analyzing the flow velocities. Several case studies related to nuclear reactor were performed with the PIV system. Some of the cases like flow in circular tube, submerged jet, natural convection in a water pool, flow field of moderator inlet diffuser of 500 MWe Pressurised Heavy Water Reactor (PHWR) and fluidic flow control device (FFCD) used in advanced accumulator of Emergency Core Cooling System (ECCS) have been studied using PIV system. Theoretical studies have been performed and comparisons with PIV results are also given in the present studies. (author)

  18. Deregulation, privatization and the Ontario power failure

    International Nuclear Information System (INIS)

    2003-09-01

    The Canadian Union of Public Employees (CUPE) has examined the history of deregulation of the electricity industry in the United States and presents lessons that could be learned from the California electricity crisis, the collapse of Enron, and the massive blackout that occurred in August 2003 across Ontario and northeastern United States. Unlike the United States, Canada's electricity system is mostly publicly owned and operated. This report emphasized that the need for public investment in the electricity system is greater than ever, and offers suggestions on how to strengthen the Canadian electricity system. It examines the attempts made to deregulate and privatize the electricity system in Ontario, Alberta, New Brunswick and British Columbia and exposes the reality of price caps and the debt of public utilities. It demonstrates that privatization has failed to provide a safe, reliable, affordable and adequate supply of electricity. The report claims that profit-seeking power producers want to keep supply and demand in their favour to sell electricity at the highest possible price. In addition to emphasizing the need for public investment in the electricity system, this report emphasizes the need for Canadian electricity cooperation, with particular mention of the large energy supplies in Manitoba and Quebec. 37 refs

  19. Public perceptions of energy issues in Ontario

    International Nuclear Information System (INIS)

    2004-11-01

    In October 2004, the Environics Research Group conducted a telephone survey of 608 adult Ontarians to collect information on matters regarding energy; consumer confidence and protection; responsibilities of the Ontario Energy Board; and consumer information preferences. This report summarizes the key findings of the survey. According to the survey, the most important electricity and natural gas issue was identified as being price and cost issues, followed by reliability of supply, conservation, keeping utilities publicly owned, finding renewable sources of energy, and over-consumption. The survey revealed that Ontarians show much interest in conserving energy to save money, to protect the environment and ensure future energy supply, but they are generally sceptical that their interests are being protected on electricity and natural gas price issues. At least 9 in 10 Ontarians consider the tasks of the Ontario Energy Board to be important. The majority of Ontarians prefer to receive energy conservation information through the mail and from public regulators over a government department or a company. 10 tabs

  20. Ontario Energy Board 2005 survey of stakeholders

    International Nuclear Information System (INIS)

    2006-01-01

    A survey was conducted among members of the Ontario Energy Board's (OEB) various stakeholder groups in order to measure the Board's performance and to help the Board identify areas for improvement in the way it operates. The survey included telephone interviews with consumer groups, advocacy groups, the energy sector, electricity and gas distributors, financial organizations as well as other stakeholders. The topics addressed in the survey were key energy issues and priority issues; the perceived role of the OEB; the OEB strengths and weaknesses; the importance of various OEB functions; the overall performance of the OEB; an evaluation of OEB communication with industry and consumers; an evaluation of service quality; and, awareness and participation in regulatory policy initiatives. Respondents used a 10-point scale in their evaluation. This report presented the main findings and their interpretations. Major stakeholders identified electricity supply issues and the price of electricity as being the most important energy issues facing Ontario. This report also presented the detailed findings for questions regarding the lack of generator capacity, policy stability, the coal phase out program, electricity blackouts, conservation, electricity restructuring and investment. The major finding of the survey was an overall increase in satisfaction with the OEB's performance. It was suggested that the OEB can improve in timeliness and providing consumer information. The major areas of strength were found to be its professionalism in conducting hearings and the fairness of the Board's decisions and regulations. tabs

  1. Coal-fired electricity generation in Ontario

    International Nuclear Information System (INIS)

    2001-03-01

    This report examines coal-fired electricity generation in Ontario and recommends actions to be taken by the provincial government to protect the environment. The recommendations are also designed to assist in making decisions about the environmental safeguards needed for a competitive electricity industry. The report examines air emissions from coal-fired generating plants in the larger context of air pollution in the province; summarizes background information on key air pollutants; provides an individual profile of all coal-fired power stations in the province; and benchmarks Ontario's emissions performance by comparing it with 19 nearby U.S. jurisdictions. Current and proposed environmental controls for fossil fuel power generation in the province are elaborated. Options for maximizing environmental performance and the framework for strengthening environmental protection are reviewed. The report also contains a series of findings and recommendations which are deemed necessary before the moratorium imposed on the sale of coal-fired electricity plants imposed in May 2000, can be lifted. tabs., figs

  2. Operating experiences of reactor shutdown system at MAPS

    International Nuclear Information System (INIS)

    Kotteeswaran, T.J.; Subramani, V.A.; Hariharan, K.

    1997-01-01

    The reactors in Madras Atomic Power Station (MAPS), Kalpakkam are Pressurised Heavy Water Reactors (PHWR) similar to RAPS, Kota. The moderator heavy water is pumped into the calandria from dump tank to make the reactor critical. Later with the calandria level held constant at 92% FT, the further power changes are being done with the movement of adjuster rods. The moderator is held in calandria by means of helium gas pressure differential between top of calandria and dump tank located below. The shutdown of the reactor is effected by dumping the moderator water to dump tank by fast equalizing of helium gas pressure. In the revised mode of operation of moderator circuit after the moderator inlet manifold failure, the dump timing was observed to be more compared to the normal value. This was investigated and observed to be due to accumulation of D 2 O in the gas space above dump valves, which was affecting the helium equalizing flow. Also some of Indicating Alarm Meters (IAM) in protective system initiating the trip signals have failed in the unsafe mode. They have been modified to avoid the recurrence of the failures. (author)

  3. Dual pressurized light water reactor producing 2000 M We

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-15

    The dual unit optimizer 2000 M We (Duo2000) is proposed as a new design concept for large nuclear power plant. Duo is being designed to meet economic and safety challenges facing the 21 century green and sustainable energy industry. Duo2000 has two nuclear steam supply systems (NSSS) of the unit nuclear optimizer (Uno) pressurized water reactor (PWR) in a single containment so as to double the capacity of the plant. Uno is anchored to the optimized power reactor 1000 M We (OPR1000) of the Korea Hydro and Nuclear Power Co., Ltd. The concept of Duo can be extended to any number of PWRs or pressurized heavy water reactors (PHWR s), or even boiling water reactor (BWRs). Once proven in water reactors, the technology may even be expanded to gas cooled, liquid metal cooled, and molten salt cooled reactors. In particular, since it is required that the small and medium sized reactors (SMRs) be built as units, the concept of Duo2000 will apply to SMRs as well. With its in-vessel retention as severe accident management strategy, Duo can not only put the single most querulous PWR safety issue to end, but also pave ways to most promising large power capacity dispensing with huge redesigning cost for generation III + nuclear systems. The strengths of Duo2000 include reducing the cost of construction by decreasing the number of containment buildings from two to one, minimizing the cost of NSSS and control systems by sharing between the dual units, and lessening the maintenance cost by uniting NSSS. The technology can further be extended to coupling modular reactors as dual, triple, or quadruple units to increase their economics, thus accelerating the commercialization as well as the customization of SMRs. (Author)

  4. Conducted and radiated emission tests for fault tolerant power distribution system ECPS-100 developed for PHWR700MW C and I

    International Nuclear Information System (INIS)

    Das, Shantanu; Yadav, Ramnayan

    2016-01-01

    Electronics devices when designed to meet specific requirements, the designers do not generally envisage the amount of electromagnetic interference that this particular device may give as power line conducted noise and radiated noise. After the product is developed, the quantification of the same is carried out in certified EMI-EMC set-up to get these figures of conducted emissions (CE) and radiated emissions (RE), and its mitigation as per limits of the chosen standard. In the latest TM embodiment of Fault Tolerant Power Distribution System ECPS"T"M (Electronics Corporation Power Supply) developed for NPCIL (PHWR700MW plant) we carried out CE and RE tests and quantified the spectrum obtained for CE and RE, and mitigated them as per CISPR22 standards. In this short article we bring out the CE and RE results of the latest product ECPS, done at EMI-EMC Centre of ECIL Hyderabad. (author)

  5. Mechanical properties of Zr-2.5Nb pressure tube material manufactured employing forging routes for PHWR700 - Part 1: tensile behavior

    International Nuclear Information System (INIS)

    Bind, A.K.; Singh, R.N.; Sunil, Saurav; Chakravartty, J.K.; Ghosh, Agnish; Dhandharia, Priyesh; More, Nitin S.; Vijayakumar, S.; Chhatre, A.G.

    2012-01-01

    Tensile properties of Zr-2.5Nb alloy tubes produced employing forging to break the cast structure were evaluated by carrying out uni-axial tension test at temperatures between 25 and 325 degC and under strain-rate of 1.075 x 10 -4 /s for both longitudinal and transverse specimens. Both strength and elongation values were comparable for the samples obtained from front and back end of the tube. Transverse samples showed higher strength and lower uniform elongation values as compared to longitudinal samples. The yield strength of double forged material at 25 degC is higher than the PHWR700 specification of a maximum value of 586 MPa. (author)

  6. Status of fast reactor development in India (April 1996 - March 1997)

    International Nuclear Information System (INIS)

    Bhoje, S.B.

    1998-01-01

    India generated 395 TWh of electricity during, 4 April 1996 to March 1997. Oil import bill during the year was $9.3 billion. The operating performance of the thermal power reactors has considerably improved during the year and has enhanced the confidence level in nuclear energy in the government and the public. Construction of 4x220 MWe PHWR is continued at two locations. Start of construction of 2x220 MWe PHWR, 2x500 MWe PHWR and 2x1000 MWe WWER (Russian collaboration) and 500 MWe PFBR have been proposed in the IX Plan (1997- 2002). The 13 party coalition government is discussing the IX plan proposals in the power sector. Operation of FBTR at 10.5 MWt is continued The maximum fuel burnup reached is 32,000 MWd/t without any failure. Targeted burnup is 50,000 MWd/t. Post irradiation examination has been completed on one fuel subassembly taken out at 25,000 MWd/t. The performance of the fuel is very good. Turbine was rolled up to synchronous speed of 3000 rpm several times during the year and operation was found to be smooth. TG synchronisation with grid will be achieved during the reactor operation at 12.5 MWt, with the addition of fuel subassemblies in the core. All the activities related to the revision of conceptual design from 4 loop to 2 loop concept are almost complete for the 500 MWe Prototype Fast Breeder Reactor. The main options for the reactor are sodium coolant, pool type, MOX fuel, 2 primary sodium pumps, 2 secondary loops with 4 SG in each loop. The important design activities carried out during the year are plant dynamic studies, decay heat removal analysis, design of pump to grid plate pipe, scram and LOR parameters, location of secondary sodium pump in the secondary sodium circuit and design of fuel handling machines. Important experimental R and D work carried out during the year were testing of prototype primary sodium pump in water, operation of a large sodium test rig to study the heat and mass transfer in the cover gas, testing of dummy fuel

  7. New fuel advanced heavy water reactors

    International Nuclear Information System (INIS)

    Notari, Carla

    1999-01-01

    A redesign of the PHWR fuel element (FE) to be used in all Argentine nuclear power plants has been proposed elsewhere. This new FE presents several characteristics aimed to an improved in-core performance and economical benefits derived from the unification of most of the fabrication processes that today constitute two different production lines: one for Embalse nuclear power plant CANDU type fuel and another for Atucha I. Atucha I and Embalse, the two operating nuclear power plants in Argentina, are PHWR of different conception. Atucha I (357 M we) is of pressure vessel type and the fuel elements are full-length assemblies (530 cm of active length) with 36 uranium rods in the cluster and a support one in the outer ring. Embalse (648 M we) is a CANDU pressure tube reactor fuelled with the well known 37 rod / 50 cm length fuel bundles, twelve of which are loaded in each channel. The more relevant changes in the proposed design are an increased subdivision of the fuel material in 52 rods and a 100 cm long bundle. The combined features give the adequate channel pressure drop. The proposed CARA design shows a superior neutronic performance than the standard PHWR fuel elements currently used in Atucha I and Embalse nuclear power plants. A variant of the CARA FE consisting in the elimination of the central four rods, leaving 48 rods and a central free space, is strongly recommended because it saves materials (less uranium, less sheaths) with no loss of burnup. The central D 2 O zone allows a better utilization of the inner rods and compensates the diminished uranium loading. In Embalse no differences in core physics are expected except the beneficial decrease in linear power density. In Atucha I besides the lower power density, a higher exit burnup appears as a consequence of the higher uranium inventory. The exit burnup figures have been calculated with cell and reactor models and the result is that similar fuel management schemes as the proposed for Atucha I for the

  8. Proceedings of the Ontario Petroleum Institute's 48. annual conference : Ontario oil, gas and storage conference

    International Nuclear Information System (INIS)

    2009-01-01

    This conference discussed issues related to Ontario's petroleum industry and evaluated the province's potential hydrocarbon plays. Geological studies of interest to oil and gas operators were presented along with storage opportunities for hydrocarbons in underground formations. Regulatory issues related to the environmental impacts of oil and gas operations on soil and groundwater were reviewed, and various mitigation options for treating soils impacted by hydrocarbons were discussed. New technologies currently being used in Ontario's petroleum industry were presented together with various investment and exploration opportunities. An economic update of recent oil and gas activities in the region was also presented. The conference was divided into 7 sessions, and featured 17 presentations, of which 11 have been catalogued separately for inclusion in this database. tabs., figs.

  9. Waste management practices in Ontario`s workplaces: An emerging industrial ecology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    Describes a study commissioned to evaluate employee attitudes and behaviours with respect to participation in workplace initiatives in waste diversion/reduction, to examine management initiatives related to waste diversion and reduction/recycling/reuse, and to report on Ontario Ministry of Environment & Energy activities related to industrial, commercial, and institutional (ICI) waste diversion activities. Linkages between management and employees, management and government, and ICI activities and government were also studied. The study methodology included a literature review, a series of interviews with key stakeholders, industry associations, and waste management companies, and a series of 12 case studies spanning major industrial sectors in Ontario. Issues addressed in the study include the factors that trigger waste diversion activities by ICI establishments, barriers to the initiation of waste diversion practices, and the social aspects of waste reduction/recycling/reuse practices.

  10. Cross currents : hydroelectricity and the engineering of northern Ontario

    Energy Technology Data Exchange (ETDEWEB)

    Manore, J.L. [Calgary Univ., AB (Canada)

    1999-05-01

    The history of hydroelectric development in northern Ontario was reviewed and analysed with special emphasis on the developments along the Mattagami and Abitibi Rivers. The objective was to examine the important factors that shaped modern hydroelectric development in Canada. System builders, the privately owned Nesbitt Thomson Company, the publicly owned Hydro Electric Power Corporation of Ontario and the eventual evolution of the single power system under Ontario Hydro are chronicled. Broad historical themes such as the technological impacts, regionalism, indigenous rights, plus environmental and economic issues are examined, in addition to an appreciation of the importance of electricity in the manufacturing sector of Ontario, the impact of hydroelectric development on the northern environment and on the northern First Nations, who rely on rivers for their subsistence. Until fairly recently, government policies and interpretations of law often excluded the recognition of Aboriginal uses of river systems, thereby limiting First Nations` peoples ability to practice traditional ways of life. In essence, the book is an account of how the northeastern power system in Ontario shaped the social, political and natural environments and how the development of northeastern power sources by southern power developers shaped the regional interactions between Ontario`s north and south. refs., figs.

  11. The Efficacy of Key Performance Indicators in Ontario Universities as Perceived by Key Informants

    Science.gov (United States)

    Chan, Vivian

    2015-01-01

    The Ontario Ministry of Education and Training's Task Force on University Accountability first proposed key performance indicators (KPIs) for colleges and universities in Ontario in the early 1990s. The three main KPIs for Ontario universities are the rates of (1) graduation, (2) employment, and (3) Ontario Student Assistance Program loan default.…

  12. 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...

  13. Feminism and women's health professions in Ontario.

    Science.gov (United States)

    Adams, Tracey L; Bourgeault, Ivy Lynn

    2003-01-01

    Historically, prevailing gender ideologies were an important element in both the exclusionary strategies employed by male occupational groups and the countervailing responses by female groups. The way in which evolving gender ideologies, and feminism in particular, influence the continuing struggle for greater status and recognition by female professions, however, remains to be fully explored. In this paper, we examine the impact and the role of feminism and feminist ideologies within three female professional projects: nursing, dental hygiene and midwifery in Ontario. We argue that feminism provides an ideology of opposition that enables leaders in these professions to battle against professional inequalities by laying bare the gender inequalities that underlie them. Framing their struggles in feminist terms, female professions also seek recognition for the uniquely female contribution they make to the health care division of labour. At the same time, there exists a tension between ideals of feminism and ideals of professionalism, that has the potential to undermine female professional projects.

  14. Ontario Hydro nuclear - challenges of the future

    International Nuclear Information System (INIS)

    Field, R.

    1996-01-01

    The challenges facing Ontario Hydro Nuclear (OHN), as understood at the time of the conference, are discussed. OHN had many strengths to build on in preparing for the competition ahead, including: extremely competitive production costs, strong technical capabilities, advantages of multiple units, environmental advantages favoring nuclear, strong public support, and improving station performance. Even with these advantages, OHN faced the difficult challenge of improving overall performance in the face of a large debt burden, coupled with the reinvestment demands of aging units at Pickering A and Bruce A. At the time of the conference, Bruce 2 had already been shut down, because the cost of retubing it and replacing its boilers could not be justified. The ''drive to nuclear excellence'' involves the simultaneous achievement of top performance in safety, reliability and cost; and to this end, changes were being made to reverse the trends indicated by disappointing ''peer reviews''

  15. Physician recruitment in Ontario Provincial Psychiatric Hospitals.

    Science.gov (United States)

    Draper, R; Galbraith, D; Frost, B

    1989-11-01

    Recruitment of Physicians/Psychiatrists to staff the Ontario Provincial Psychiatric Hospitals remains an ongoing problem despite the introduction of measures such as University Affiliation and Incentive Grants. Historically there has been heavy reliance upon Foreign Medical Graduates (GOFM's) who have been denied the possibility of professional mobility and advancement because of restrictive licences. Recent changes in regulations have severely restricted the recruitment of GOFM's. During 1987, details of all physicians employed in the provincial hospitals during the preceeding five years were entered into a computerized data base. This paper presents some initial analyses which indicate that Canadian graduates have provided low levels of service, especially outside major urban centres, quite insufficient to replace the GOFM's. These findings raise urgent social and professional concerns.

  16. Implementation plan for smart meters in Ontario

    International Nuclear Information System (INIS)

    2004-01-01

    This paper presents Ontario Energy Board's implementation plan to install 800,000 smart meters by December 31, 2007. The objective is to help consumers control their electricity bills through conservation and demand response. The three conditions that will change power consumption habits are price changes in response to demand and supply forces; the ability of consumers to see and respond to the price signals; and, a measurement of the response so that consumers get credit for their actions. This paper identifies the mandatory technical requirements for smart meters and the support operations of distributors. It sets priorities, identifies barriers and regulatory mechanisms for cost recovery. It also discusses options for ownership of the meters. 18 refs., 1 tab., 2 figs

  17. Oil heritage district : Lambton County Ontario

    Energy Technology Data Exchange (ETDEWEB)

    Shearer, W. [Wendy Shearer Landscape Architect, Kitchener, ON (Canada)

    2009-07-01

    This paper discussed a project conducted to assess the cultural heritage values of oil field equipment in Lambton County, Ontario. Oil was discovered in the region in 1858, after which a boom and bust cycle of exploration created a large rural-industrial landscape. The region now contains a unique collection of historic oil equipment. The region's industrial footprint is interwoven with village settlements, agricultural settlements, and a railway and road network linking the region to remote refineries. Oil wells in the region still operate using a jerker line system developed in the early twentieth century. The operational oil wells are subject to fluctuating oil prices and environmental protection requirements. The project presents a rare opportunity to place industrial heritage conservation directly in the hands of business operators and regulators, while also functioning as part of a living community. 2 figs.

  18. Ontario Hydro's integrated air management plan

    International Nuclear Information System (INIS)

    Kalvins, A.K.; Brown, D.; Camacho, F.; Howes, H.; Jantzi, B.; Lin, X.; Lui, P.; Melo, O.T.; Mortimer, W.P.; Reuber, B.

    1992-01-01

    Ontario Hydro is developing an integrated air management plan as a tool for comparing the environmental impacts of fossil-fuel power generation options. The goal is to relate equipment, location, emissions, and impacts and to identify the optimum way to manage the utility's fossil generation system in view of upcoming environmental regulations and public expectations. The eight steps of the plan are briefly described: definition of power generation scenarios (upgrading, conversion to natural gas, non-utility generation, alternative technologies); estimation of emissions for each generation and fuel option studied; identification of impact of air emissions on building materials, agriculture, forests, lakes, and fisheries; modelling of air emissions dispersion; quantification of damage to pollution receptors; quantification of full fuel cycle effects; and comparison of the scenarios. The scenario having the lowest overall environmental impact involved upgrading the existing fossil-fuel system with additional air emissions controls and two integrated gasification combined cycle plants. 9 refs., 3 figs., 3 tabs

  19. Ontario freight movement study: component two

    International Nuclear Information System (INIS)

    Hackston, D.; Lake, R.; Schwier, C.; Tardif, L.P.; English, G.; Bunting, M.

    1995-11-01

    The freight (cargo) transportation sector accounts for a major use of fossil fuels and contributes significantly to greenhouse gas emissions. A study was conducted to assess the prospects, in terms of CO 2 emission reduction, of alternatives to present freight distribution, especially alternatives involving the use of rail instead of truck. Statistical data for Ontario freight transportation were analyzed for fuel consumption, CO 2 emission and cost consequences. Railway fuel consumption was calculated for detailed routing descriptions using a model that computed route and service specific fuel use. The information was compared directly with truck fuel consumption. It was determined that shippers who needed quick, accurately timed shipments preferred trucking over rail, while price conscious shippers, or those with heavy loading commodities preferred rail. An important goal of the study was to identify the enormity of the challenges involved, and clarify the potential tradeoffs by showing different strategies, with respect to CO 2 reduction and related economic impacts. refs., tabs., figs

  20. Sulphate deposition by precipitation into Lake Ontario

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, R W; Whelpdale, D M

    1973-01-01

    Measurements of sulphate concentration in precipitation from individual snow storms of several hours duration in the western Lake Ontario region indicate that approximately 9-66 mg/M/sub 2/ of SO/sub 4//sup 2 -/ is being deposited into the lake per storm. This amount is up to several times more than daily average values over long periods found by other workers. Using a mean sulphate concentration of 4 mg/l and an annual accumulation of precipitation of 760 mm, the yearly sulphate deposition by precipitation is about 0.1% of the total mass of sulphate in the lake; however, more significantly, it is of the same order of magnitude as that discharged directly into the lake by industry.

  1. Forecasting Ontario's blood supply and demand.

    Science.gov (United States)

    Drackley, Adam; Newbold, K Bruce; Paez, Antonio; Heddle, Nancy

    2012-02-01

    Given an aging population that requires increased medical care, an increasing number of deferrals from the donor pool, and a growing immigrant population that typically has lower donation rates, the purpose of this article is to forecast Ontario's blood supply and demand. We calculate age- and sex-specific donation and demand rates for blood supply based on 2008 data and project demand between 2008 and 2036 based on these rates and using population data from the Ontario Ministry of Finance. Results indicate that blood demand will outpace supply as early as 2012. For instance, while the total number of donations made by older cohorts is expected to increase in the coming years, the number of red blood cell (RBC) transfusions in the 70+ age group is forecasted grow from approximately 53% of all RBC transfusions in 2008 (209,515) in 2008 to 68% (546,996) by 2036. A series of alternate scenarios, including projections based on a 2% increase in supply per year and increased use of apheresis technology, delays supply shortfalls, but does not eliminate them without active management and/or multiple methods to increase supply and decrease demand. Predictions show that demand for blood products will outpace supply in the near future given current age- and sex-specific supply and demand rates. However, we note that the careful management of the blood supply by Canadian Blood Services, along with new medical techniques and the recruitment of new donors to the system, will remove future concerns. © 2012 American Association of Blood Banks.

  2. A review of fast reactor programme in India - April 1992

    Energy Technology Data Exchange (ETDEWEB)

    Paranjpe, S R [Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu (India)

    1992-07-01

    There is no change in the basic policy for development of nuclear energy in India. Fast Breeder Reactors are required to be available commercially to supply increasing quantities of nuclear energy when the first phase programme of deployment of Pressurised Heavy Water Reactors would be reaching the limit imposed by indigenously available natural uranium. Based on presently proven reserves of economically exploitable uranium one cannot expect to support more than 10 to 15 million kilowatt of installed capacity of PHWRs. The immediate goal of the Fast Reactor Programme therefore, remains completion by 2002-2003 of the first 500 MWe Prototype Fast Breeder Reactor which will become the first reactor in the series of reactors to be built there afterwards. This will enable addition of one 500 MWe reactor each year even if the first phase of programme of PHWR is limited to 6.0 million kilowatt. The capital cost of installed kilowatt for FBRs is expected to be comparable to the capital cost per kilowatt for PHWRS. It is expected to launch the construction of PFBR in the next 2 or 3 years as soon as the over all economic condition shows some improvement. In the meantime, manufacturing development of important NSS components like Steam Generators, Sodium Pumps, Main Vessel and Inner Vessel has been initiated. Detailed designs of Control Rod Drive Mechanism (Primary) has been completed and contacts with the manufacturers are being established to identify the industry which would be entrusted with the responsibility of manufacturing the Control Rod Drive Mechanisms. Manufacturing technology for making cladding tubes of D9 stainless steel has been developed and significant progress has been made towards the production of hexagonal wrapper (i.e. Hex-Cans). Inclined Fuel Transfer Machine for loading and unloading the fuel from the Main Vessel has been designed and manufacturing of the prototype machine has been initiated. It is hoped that these steps will enable timely completion

  3. Cobalt-60 production in CANDU power reactors

    International Nuclear Information System (INIS)

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

    2002-01-01

    MDS Nordion has been supplying cobalt-60 sources to industry for industrial and medical purposes since 1946. These cobalt-60 sources are used in many market and product segments, but are primarily used to sterilize single-use medical products including; surgical kits, gloves, gowns, drapes, and cotton swabs. Other applications include sanitization of cosmetics, microbial reduction of pharmaceutical raw materials, and food irradiation. The technology for producing the cobalt-60 isotope was developed by MDS Nordion and Atomic Energy of Canada Limited (AECL) almost 55 years ago using research reactors at the AECL Chalk River Laboratories in Ontario, Canada. The first cobalt-60 source produced for medical applications was manufactured by MDS Nordion and used in cancer therapy. The benefits of cobalt-60 as applied to medical product manufacturing, were quickly realized and the demand for this radioisotope quickly grew. The same technology for producing cobalt-60 in research reactors was then designed and packaged such that it could be conveniently transferred to a utility/power reactor. In the early 1970's, in co-operation with Ontario Power Generation (formerly Ontario Hydro), bulk cobalt-60 production for industrial irradiation applications was initiated in the four Pickering A CANDU reactors. As the demand and acceptance of sterilization of medical products grew, MDS Nordion expanded its bulk supply by installing the proprietary Canadian technology for producing cobalt-60 in additional CANDU reactors. CANDU is unique among the power reactors of the world, being heavy water moderated and fuelled with natural uranium. They are also designed and supplied with stainless steel adjusters, the primary function of which is to shape the neutron flux to optimize reactor power and fuel bum-up, and to provide excess reactivity needed to overcome xenon-135 poisoning following a reduction of power. The reactor is designed to develop full power output with all of the adjuster

  4. Inequalities in Sport and Physical Activity Programs in Ontario Schools.

    Science.gov (United States)

    Macintosh, Donald

    1981-01-01

    Two recent studies of interschool sports and physical education in Ontario secondary schools examine the issues of differences in interschool sports participation as a reflection of socioeconomic background, gender of the participants, degree of participation, and school size.

  5. The effect of Ontario's transmission system policies on cogeneration projects

    International Nuclear Information System (INIS)

    Carr, J.

    1999-01-01

    The impact that the establishment of transmission tariffs would have on the viability of cogeneration projects in Ontario was discussed. The proposal to establish such tariffs on the basis of a 'postage stamp' rate would ensure that all electricity users have access to electricity at the same price. However, this would unfairly penalize short-haul transmission transactions and would possibly result in the inappropriate location of new generation facilities. Electricity users would ultimately be burdened with these inefficiencies. This presentation also discussed another public policy which proposes to determine what parts of the electricity system should have their costs recovered at postage stamp rates. The costs would include not only transmission charges but also distribution and generation costs. The restructuring of Ontario Hydro into the Ontario Power Generation Company (OPGC) and the Ontario Hydro Services Company (OHSC) and its impact on the cogeneration projects was also discussed

  6. Ontario: prostitution-related provisions of Criminal Code struck down.

    Science.gov (United States)

    Chu, Sandra Ka Hon

    2011-04-01

    In September 2010, the Ontario Superior Court of Justice held that three provisions of the Criminal Code dealing with prostitution violated sex workers' constitutional rights, were not in accordance with the principles of fundamental justice and must be struck down.

  7. 2001 USACE LRE Topobathy Lidar: Lake Ontario (NY)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — NOAA Office for Coastal Management received the 2001 Lake Ontario dataset with 2 separate metadata records in 2013 on a hard-drive device from the USGS Center for...

  8. Why we must move quickly to open Ontario's power market

    International Nuclear Information System (INIS)

    Brooks, J.

    2001-01-01

    This paper presented issues regarding the reform in Ontario's electricity sector and why the Independent Power Producer's Society of Ontario (IPPSO) believes it is necessary to open the electricity market in the province as soon as possible. The 400 members of IPPSO include developers, suppliers, consultants and various professionals working in the fields of co-generation, small hydro, biomass, wind energy and other technologies with a total generating capacity of about 1600 MW in Ontario. The government of Ontario recently announced four principles for implementing competition in the electricity sector which were protecting the consumers and offering choice, creating a strong business climate, protecting the environment, and supporting innovation and alternative energy development. This paper described the possible indicators of success in implementing these four principles and provided a historical perspective on the motivation for bringing in competition

  9. Full cost accounting for decision making at Ontario Hydro

    International Nuclear Information System (INIS)

    Plagiannakos, T.

    1996-01-01

    Ontario Hydro's approach to full cost accounting (FCA) was outlined in response to questions raised earlier, in another forum, regarding Ontario Hydro's views on FCA. FCA was defined as an evaluation framework (as opposed to an accounting system) which tries to account for the internal (private) as well as the external (environment and human health) costs and benefits and integrate them into business decisions. When the external impacts cannot be monetized, qualitative evaluations are used based on the damage costing approach, which Ontario Hydro prefers to the cost of control method recommended by its critics. In general, however, Ontario Hydro is not opposed to FCA in so far as it puts the Utility in a better position to make more informed decisions, improve environmental cost management, avoid future costs, enhance revenue, improve environmental quality, contribute to environmental policy, and contribute to sustainable development. 1 fig

  10. Fabrication of metallic fuel for fast breeder reactor

    International Nuclear Information System (INIS)

    Saify, M.T.; Jha, S.K.; Abdulla, K.K.; Kumar, Arbind; Mittal, R.K.; Prasad, R.S.; Mahule, N.; Kumar, Arun; Prasad, G.J.

    2012-01-01

    Natural uranium oxide fuelled PHWRs comprises of first stage of Indian nuclear power programme. Liquid metal fast breeder reactors fuelled by Pu (from PHWR's) form the second stage. A shorter reactor doubling time is essential in order to accelerate the nuclear power growth in India. Metallic fuels are known to provide shorter doubling times, necessitating to be used as driver fuel for fast breeder reactors. One of the fabrication routes for metallic fuels having random grain orientation, is injection casting technique. The technique finds its basis in an elementary physical concept - the possibility of supporting a liquid column within a tube, by the application of a pressure difference across the liquid interface inside and outside the tube. At AFD, BARC a facility has been set-up for injection casting of uranium rods in quartz tube moulds, demoulding of cast rods, end-shearing of rods and an automated inspection system for inspection of fuel rods with respect to mass, length, diameter and diameter variation along the length and internal and external porosities/voids. All the above facilities have been set-up in glove boxes and have successfully been used for fabrication of uranium bearing fuel rods. The facility has been designed for fabrication and inspection of Pu-bearing metallic fuels also, if required

  11. Construction management of Indian pressurized heavy water reactors

    International Nuclear Information System (INIS)

    Bohra, S.A.; Sharma, P.D.

    2006-01-01

    Pandit Jawaharlal Nehru and Dr. Homi J. Bhabha, the visionary architects of Science and Technology of modern India foresaw the imperative need to establish a firm base for indigenous research and development in the field of nuclear electricity generation. The initial phase has primarily focused on the technology development in a systematic and structured manner, which has resulted in establishment of strong engineering, manufacturing and construction base. The nuclear power program started with the setting up of two units of boiling light water type reactors in 1969 for speedy establishment of nuclear technology, safety culture, and development of operation and maintenance manpower. The main aim at that stage was to demonstrate (to ourselves, and indeed to the rest of the world) that India, inspite of being a developing country, with limited industrial infrastructure and low capacity power grids, could successfully assimilate the high technology involved in the safe and economical operation of nuclear power reactors. The selection of a BWR was in contrast to the pressurized heavy water reactors (PHWR), which was identified as the flagship for the first stage of India's nuclear power program. The long-term program in three stages utilizes large reserves of thorium in the monazite sands of Kerala beaches in the third stage with first stage comprising of series of PHWR type plants with a base of 10,000 MW. India has at present 14 reactors in operation 12 of these being of PHWR type. The performance of operating units of 2720 MW has improved significantly with an overall capacity factor of about 90% in recent times. The construction work on eight reactor units with installed capacity of 3960 MW (two PHWRs of 540 MW each, four PHWRs of 220 MW each and two VVERs of 1000 MW each) is proceeding on a rapid pace with project schedules of less than 5 years from first pour of concrete. This is being achieved through advanced construction technology and management. Present

  12. The world's reactors No. 82: Atucha II

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    Detailed information on Atucha II, a 745 MWe pressure-vessel PHWR, is presented in the form of a wall chart. Plant specifications and full colour cutaway drawings of the power station are included. (U.K.)

  13. Brief on nuclear emergency planning and preparedness in Ontario

    International Nuclear Information System (INIS)

    1987-01-01

    Ontario has an excellent conceptual plan to ensure the safety of its inhabitants in the event of a nuclear accident anywhere in the world. This plan still needs to be translated into tangible preparedness to deal with such an emergency. The province is confident that, with the assistance of Ontario Hydro, a high level of nuclear emergency preparedness will soon be established for the people of the province

  14. New rules for competition: Ontario to cap power plant emissions

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    The Ontario government through the Dept. of the Environment announced on November 16, 1999 that it would cut the emissions from Ontario coal burning power plants that cause acid rain and smog. This announcement was a much anticipated clarification of the government's plans to clean up the power industry since the enactment of the Electricity Competition Act more than one year past. The announcement signals the beginning of a public discussion process between government and stakeholders on the environmental rules for electricity generation in Ontario. The Ontario government is expected to release draft regulations for controlling coal burning power plant emissions in the near future. Consulations with stakeholders on the regulations, as well as the rules for disclosure and labeling, are anticipated to begin in a few months. The announcement set out four principles for environmental performance in the competitive electricity market. Anti-smog requirements will be included in the stringent environmental requirements to be built into Ontario's new, competitive electricity market. The strong measures which the government will put into place when the market opens later in 2000 include: (1) regulations to cut smog and acid gas emissions for all Ontario electricity generators on the grid - these regulations will include Ontario Hydro's voluntary nitrogen oxide limits; (2) emission performance standards to define maximum acceptable emission levels for all generators wanting to sell in the Ontario market; (3) a framework to support opportunities to make greater use of more efficient, environmentally responsible technologies; and (4) disclosure requirements to ensure that electricity consumers can understand the environmental implications of their purchasing decisions

  15. A survey of medical quality assurance programs in Ontario hospitals.

    OpenAIRE

    Barrable, B

    1992-01-01

    OBJECTIVE: To determine the prevalence and types of medical quality assurance practices in Ontario hospitals. DESIGN: Survey. SETTING: All teaching, community, chronic care, rehabilitation and psychiatric hospitals that were members of the Ontario Hospital Association as of May 1990. PARTICIPANTS: The person deemed by the chief executive officer of each hospital to be most responsible for medical administration. INTERVENTION: A questionnaire to obtain information on each hospital's use of cri...

  16. New directions in nuclear waste disposal in Ontario Hydro

    International Nuclear Information System (INIS)

    Nash, K.

    1996-01-01

    Ontario Hydro Nuclear has financial, environmental, safety and public acceptance business objectives which must be met to achieve long term sustainable success. Short term objectives of achieving nuclear excellence in safety, cost and production are vital to this success. Ontario Hydro's nuclear waste and decommissioning liabilities must be managed within these objectives. This paper outlines the financial environmental and societal considerations and responsibility framework for managing these liabilities. (author)

  17. Cancer mortality among immigrant populations in Ontario, 1969 through 1973.

    OpenAIRE

    Newman, A. M.; Spengler, R. F.

    1984-01-01

    Ontario is home to a sizeable, recently established immigrant population whose cancer mortality has until now remained unexamined. The province's six largest immigrant groups (British, Italian, German, Dutch, Polish and Soviet) were investigated to compare their cancer mortality experience with that prevailing in Ontario and in their countries of birth for the period 1969 through 1973. Standardized mortality ratios (SMRs) were computed from data from Statistics Canada and the World Health Org...

  18. The Financial Feasibility of Anaerobic Digestion for Ontario's Livestock Industries

    OpenAIRE

    Weersink, Alfons; Mallon, Shawn

    2007-01-01

    This report is an investigation of the financial feasibility of farm based anaerobic digestion investments under Ontario's Standard Offer Contract electricity prices. Using Ontario Ministry of Agriculture, Food and Rural Affairs (OMAFRA) Agricultural Anaerobic Digestion Calculation Spreadsheet (AADCS) anaerobic digestion inputs, outputs, cost and revenues were estimated and used to conduct a financial analysis on the feasibility of four sized farm base anaerobic digestion investments. The res...

  19. Cross currents : hydroelectricity and the engineering of northern Ontario

    International Nuclear Information System (INIS)

    Manore, J.L.

    1999-01-01

    The history of hydroelectric development in northern Ontario was reviewed and analysed with special emphasis on the developments along the Mattagami and Abitibi Rivers. The objective was to examine the important factors that shaped modern hydroelectric development in Canada. System builders, the privately owned Nesbitt Thomson Company, the publicly owned Hydro Electric Power Corporation of Ontario and the eventual evolution of the single power system under Ontario Hydro are chronicled. Broad historical themes such as the technological impacts, regionalism, indigenous rights, plus environmental and economic issues are examined, in addition to an appreciation of the importance of electricity in the manufacturing sector of Ontario, the impact of hydroelectric development on the northern environment and on the northern First Nations, who rely on rivers for their subsistence. Until fairly recently, government policies and interpretations of law often excluded the recognition of Aboriginal uses of river systems, thereby limiting First Nations' peoples ability to practice traditional ways of life. In essence, the book is an account of how the northeastern power system in Ontario shaped the social, political and natural environments and how the development of northeastern power sources by southern power developers shaped the regional interactions between Ontario's north and south. refs., figs

  20. Canada's reactor exports

    International Nuclear Information System (INIS)

    Morrison, R.W.

    1981-01-01

    A brief sketch of the development of Canada's nuclear exports is presented and some of the factors which influence the ability to export reactors have been identified. The potential market for CANDUs is small and will develop slowly. The competition will be tough. There are few good prospects for immediate export orders in the next two or three years. Nonetheless there are reasonable opportunities for CANDU exports, especially in the mid-to-late 1980s. Such sales could be of great benefit to Canada and could do much to sustain the domestic nuclear industry. Apart from its excellent economic and technical performance, the main attraction of the CANDU seems to be the autonomy it confers on purchasing countries, the effectiveness with which the associated technology can be transferred, and the diversification it offers to countries which wish to reduce their dependence on the major industrial suppliers. Each sales opportunity is unique, and marketing strategy will have to be tailored to the customer's needs. Over the next decade, the factors susceptible to Canadian government action which are most likely to influence CANDU exports will be the political commitment of the government to those reactor exports, the performance established by the four 600 MWe CANDUs now nearing completion, the continuing successful operation of the nuclear program in Ontario, and the co-ordination of the different components of Canada's nuclear program (AECL, nuclear industry, utilities, and government) in putting forth a coherent marketing effort and following through with effective project management

  1. Application of the dose limitation system to the control of carbon-14 releases from heavy-water-moderated reactors

    International Nuclear Information System (INIS)

    Beninson, D.; Gonzalez, A.J.

    1982-01-01

    Heavy-water-moderated reactors produce substantially more carbon-14 than light-water reactors. Applying the principles of the systems of dose limitation, the paper presents the rationale used for establishing the release limit for effluents containing this nuclide and for the decisions made regarding the effluent treatment in the third nuclear power station in Argentina. Production of carbon-14 in PHWR and the release routes are analysed in the light of the different effluent treatment possibilities. An optimization assessment is presented, taking into account effluent treatment and waste management costs, and the collective effective dose commitment due to the releases. The contribution of present carbon-14 releases to future individual doses is also analysed in the light of an upper bound for the contribution, representing a fraction of the individual dose limits. The paper presents the resulting requirements for the effluent treatment regarding carbon-14 and the corresponding regulatory aspects used in Argentina. (author)

  2. Development of in-situ laser cutting technique for removal of single selected coolant channel from pressurized heavy water reactor

    International Nuclear Information System (INIS)

    Vishwakarma, S.C.; Upadhyaya, B.N.

    2016-01-01

    We report on the development of a pulsed Nd:YAG laser based cutting technique for removal of single coolant channel from pressurized heavy water reactor (PHWR). It includes development of special tools/manipulators and optimization of laser cutting process parameters for cutting of liner tube, end fitting, bellow lip weld joint, and pressure tube stubs. For each cutting operation, a special tool with precision motion control is utilized. These manipulators/tools hold and move the laser cutting nozzle in the required manner and are fixed on the same coolant channel, which has to be removed. This laser cutting technique has been successfully deployed for removal of selected coolant channels Q-16, Q-15 and N-6 of KAPS-2 reactor with minimum radiation dose consumption and in short time. (author)

  3. The power control system of the Siemens-KWU nuclear power station of the PWR [pressurized water reactors] type

    International Nuclear Information System (INIS)

    Huber, Horacio

    1989-01-01

    Starting with the first nuclear power plant constructed by Siemens AG of the pressurized light water reactor line (PWR), the Obrigheim Nuclear Power Plant (340 MWe net), until the recently constructed plants of 1300 MWe (named 'Konvoi'), the design of the power control system of the plant was continuously improved and optimized using the experience gained in the operation of the earlier generations of plants. The reactor power control system of the Siemens - KWU nuclear power plants is described. The features of this design and of the Siemens designed heavy water power plants (PHWR) Atucha I and Atucha II are mentioned. Curves showing the behaviour of the controlled variables during load changes obtained from plant tests are also shown. (Author) [es

  4. A data base for PHW reactor operating on a once-through, low enriched uranium-thorium cycle

    International Nuclear Information System (INIS)

    Lungu, S.

    1984-04-01

    The study of a detailed data base for a new once-through uranium-thorium cycle using low enriched uranium (4 and 5,5% wt. U-235) and distinct UO 2 and ThO 2 fuel channels has been performed. With reference to a standard 638 MWe CANDU-type PHWR with 380 channels, evaluation of economics, fuel behaviour and safety has been performed. The Feinberg-Galanin method (code FEINGAL) has been used for calculation of axial flux distribution. All parameters have been provided by LATREP code following up the irradiation history. Economical assessment has shown that this fuel cycle is competitive with the natural uranium fuel cycle for 1979-based values of the parameters. Fuel behaviour and safety features modelling has shown that core behaviour of the uranium-thorium reactor under abnormal and accident conditions would be at least as good as that of the standard natural uranium reactor

  5. Ontario Business Survey Program on energy : impacts of power failure on Ontario businesses

    International Nuclear Information System (INIS)

    2003-01-01

    The Ontario Chamber of Commerce conducted a survey for its members between August 19-23, 2003 to determine the impact of the massive power failure that took place on August 14, 2003. This paper presents the results of the survey which are based on a total of 929 respondents across Ontario. The primary businesses that participated in the survey were: manufacturing, service, technology, commercial, retail, automotive, steel, forestry, and resource businesses. 78 per cent of the respondents replied that the power disruption had a negative impact on their business. 48 per cent of the respondents were without power for 11-24 hours. 65 per cent of the businesses did not have a blackout contingency plan in place, but 63 per cent responded that they will likely develop a plan for future power failures. The survey also asked business members how they would rate the federal, provincial and municipal government's response to the emergency. The participants ranked the top 3 actions that governments can take to prevent future outages as follows: (1) review possible changes to the interconnected grid system, (2) ensure sufficient supply within Ontario, and (3) invest in alternative forms of energy such as solar and wind power. Other recommendations were to implement a sliding scale of energy pricing to reflect the true cost of energy. It was suggested that tax incentives should be offered to encourage energy conservation and the use of alternative energy sources. 2.6 per cent of the respondents suggested that excess energy should not be sold to neighbouring jurisdictions. 1 tab., 6 figs

  6. Expanding exports, increasing smog : Ontario Power Generation's and Hydro One's strategies to continue coal-fired electricity generation in Ontario

    International Nuclear Information System (INIS)

    Gibbons, J.

    2002-06-01

    The production of coal-fired electricity increased by approximately 150 per cent in Ontario between 1995 and 2000. As a result, the smog-causing emissions generated by the five coal-fired power plants operated by Ontario Power Generation caused an increase in smog and worsened air quality in the province as well as affecting air quality as far afield as the Atlantic provinces. Between 2002 and 2005, it is expected that the Pickering and Bruce nuclear plants will be returned to service, making the electricity generated by the coal plants surplus to Ontario's needs. Increasing this surplus are the planned natural gas generating stations. Ontario Power Generation is planning on using this surplus to export it to the United States rather than phasing out its reliance on coal. The increase in exports to the United States Northeast and Midwest is planned with Hydro One, already busy increasing its transmission capacity to the United States by 1,000 megawatt (MW). This plan involves laying 975 MW submarine cable from the Nanticoke Generating Station (operated by Ontario Power Generation) under Lake Erie to Pennsylvania, Ohio, or both states. At the moment, the exports are constrained by the government emissions limits imposed by the Ontario government on sulphur dioxide and nitrogen oxides. This constraint could be removed if Ontario Power Generation decides to pay further for pollution controls for sulphur dioxide and nitrogen oxides at its coal stations. Unfortunately, increasing the exports would also result in emissions increases for 28 other uncapped pollutants such as lead, mercury and arsenic. The author recommended that the Ontario government ban non-emergency coal-fired electricity exports to improve air quality in the province. refs., 8 figs

  7. Market Myths and Facts - the Ontario Context

    Energy Technology Data Exchange (ETDEWEB)

    Dorey, S.

    2007-07-01

    The world has learned much about electricity markets and what they can and can't do over the past few years, but some myths persist. Why they persist is a subject for those who study politics, interests and influence. This paper provides a perspective on myths which have affected the reliable and economic delivery of electricity to customers, particularly with respect to transmission. Hydro One effectively provides the transmission network for the Province of Ontario, Canada. As Hydro One is a wires company, the paper is not intended to address the issues which affect the generation or conservation sectors of the industry, except where they directly relate to the wires. The proposition of this paper is that electricity transmission is best treated as an essential public good. Transmission as a market participant and a traded commodity has generally not worked with respect to assuring that the system continues to be developed to meet the basic need of customers for reliable and affordable electricity. (auth)

  8. Three new bachelors of photonics in Ontario

    Science.gov (United States)

    Nantel, Marc; Beda, Johann; Grevatt, Treena; Chebbi, Brahim; Jessop, Paul; Song, Shaowen

    2004-10-01

    After the introduction in 2001 of community college programs at the Photonics Technician/Technologist levels, the need to cover the photonics educational space at the undergraduate level was addressed. In the last year, three very different new undergraduate degrees in photonics have started to develop in Ontario. These programs are presented in this paper. The Honours B.Sc. in Photonics at Wilfrid Laurier University (Waterloo) will develop a strong understanding of the theory and application of photonics, with practical hands-on exposure to optics, fibre optics, and lasers. This program benefits from the particularity that the department offering it combines both Physics and Computer Science. At McMaster University, the Engineering Physics program will provide students with a broad background in basic Engineering, Mathematics, Electronics, and Semiconductors, as well as an opportunity to pursue Photonics in greater depth and to have that fact recognized in the program designation. The Niagara and Algonquin College Bachelor of Applied Technology in Photonics program is co-op and joint between the two institutions. Emphasis is placed on the applied aspects of the field, with the more hands-on experimental learning taking precedence in the first years and the more advanced theoretical subjects following in the latter years.

  9. Fuel string supporting shield plug (f3sp) for Ontario Hydro - Bruce NGSA

    Energy Technology Data Exchange (ETDEWEB)

    Henry, P T [Canadian General Electric Co. Ltd., Peterborough, ON (Canada)

    1997-12-31

    A reactor `power pulse` problem was identified for the Ontario Hydro Bruce generating stations. On a postulated inlet header break, the fuel strings in a large number of channels could relocate toward the upstream end, resulting in a power pulse. The solution adopted for Bruce GSA is to change the direction of fuelling, from against the flow, to fuelling with the flow. In this revised fuelling scheme, given a postulated inlet header failure, the fuel bundle with the highest burnup would relocate into the reactor core and introduce a negative reactivity during the accident. However, this fuelling configuration results in a highly irradiated fuel bundle residing in the most downstream position against the latch. The latch supports only the outer ring of elements, not the end plate. A resulting high stress on the end plate coupled with high levels of hydrogen and deuterium may result in Zr hydride assisted cracking in the end plate during hot shutdown conditions. (In fuelling against flow, this is not a problem, since the latch supported bundle is not irradiated and has only low levels of hydrogen and deuterium.) A fuel string supporting shield plug (f3sp) which supports the bundle end plate has been developed as a solution to the fuel bundle end plate cracking problem. It would replace the existing outlet shield plug in all channels. This paper will describe the f3sp design, associated fuel handling, operation and qualification for reactor use. (author). 8 figs.

  10. Fuel string supporting shield plug (f3sp) for Ontario Hydro - Bruce NGSA

    International Nuclear Information System (INIS)

    Henry, P.T.

    1996-01-01

    A reactor 'power pulse' problem was identified for the Ontario Hydro Bruce generating stations. On a postulated inlet header break, the fuel strings in a large number of channels could relocate toward the upstream end, resulting in a power pulse. The solution adopted for Bruce GSA is to change the direction of fuelling, from against the flow, to fuelling with the flow. In this revised fuelling scheme, given a postulated inlet header failure, the fuel bundle with the highest burnup would relocate into the reactor core and introduce a negative reactivity during the accident. However, this fuelling configuration results in a highly irradiated fuel bundle residing in the most downstream position against the latch. The latch supports only the outer ring of elements, not the end plate. A resulting high stress on the end plate coupled with high levels of hydrogen and deuterium may result in Zr hydride assisted cracking in the end plate during hot shutdown conditions. (In fuelling against flow, this is not a problem, since the latch supported bundle is not irradiated and has only low levels of hydrogen and deuterium.) A fuel string supporting shield plug (f3sp) which supports the bundle end plate has been developed as a solution to the fuel bundle end plate cracking problem. It would replace the existing outlet shield plug in all channels. This paper will describe the f3sp design, associated fuel handling, operation and qualification for reactor use. (author). 8 figs

  11. 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

  12. 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.

  13. 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.

  14. 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

  15. Nuclear fuel element design and thermal-hydraulic analysis of Wolsung-1, 600 MWe CANDU-PHWR (Part II)

    International Nuclear Information System (INIS)

    Suk, H.C; Lee, J.C.; Suh, K.S.; Yuk, K.E.; Whang, W.; Park, J.S.; Eim, J.S.; Bang, K.H.; Eim, M.S.; Rim, C.S.

    1982-01-01

    The main objective of the present thermal hydraulic analysis is to determine the thermal hydraulic characteristics of Wolsung-1 600 MWe CANDU-PHW reactor under normal operation. This is to verify and expedite the development of the nuclear fuel design and fabrication as well as the management. The computer program package developed for the stated objective are DOD81, CANREPP, PLOC81 and COBRA-CANDU. (Author)

  16. Is there a future for coal in Ontario?

    International Nuclear Information System (INIS)

    Davies, G.

    2004-01-01

    This PowerPoint presentation examined the efficacy of a governmental decision in 2003 to close all Ontario coal stations by 2007. Coal currently represents one quarter of Ontario's energy and capacity. Projected supply and demand gaps for Ontario were presented for up to 2020. Ontario's supply options were outlined. It was noted that between $30 and $40 billion in investment in the electricity sector will be needed over the next 10 to 15 years. It was observed that closing coal plants may reduce pollution by 6 per cent at a cost of $2 billion. More than half the smog affecting Ontario comes from the United States, while much of the remaining half is caused by transportation emissions. Details of energy strategies related to coal in the United States were discussed. New coal power plant technologies include supercritical combustion; advanced air pollution control; circulating fluidized bed combustion and integrated coal gasification combined cycles. Coal power plant performance criteria were presented. Various research programs in the United States were reviewed, and roadmap performance targets were presented. It was concluded that high prices and uncertainty for natural gas fired options may reinforce views on the need to rethink coal closures. A strategy was recommended in which Ontario pursued economic options for reducing emissions across all sectors. New investments in latest and best technology for emissions reduction in Ontario's coal-fired stations were recommended, as well as a North American agreement on clean air, and increased Canadian participation in U.S. technology development efforts for clean coal and zero emissions plants by 2025. tabs., figs

  17. An assessment of the waterside corrosion and hydrogen pick-up in the zircaloy-2 pressure tubes of PHWR

    International Nuclear Information System (INIS)

    Sah, D.N.

    1992-01-01

    In view of the deleterious effect of hydriding on the operating life of zircaloy-2 pressure tubes in PHWRs there is an urgent need for the assessment of the status of the pressure tubes with respect to corrosion and hydrogen pick-up in the operating PHWRs. A model has been developed for analysing the waterside corrosion and hydrogen pick-up in the zircaloy-2 pressure tubes under reactor operating conditions. This model predicts the axial profiles of oxide layer thickness and hydrogen pick-up in the pressure tubes as a function of the operating time of the reactor. The prediction of hydrogen pick-up by the model in the F-10 pressure tube of RAPS-I have been found to be in good agreement with the measured value of hydrogen content. This report gives a brief description of the model and its predictions on the present status of hydrogen pick-up in the pressure tubes of lead reactor RAPS-II. (author). 6 refs., 5 figs., 2 tabs

  18. 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

  19. 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

  20. Probability safety assessment activities in India for new and advanced reactors

    International Nuclear Information System (INIS)

    Guptan, R.; Ghagde, S.G.; Nama, R.; Varde, P.V.; Vinod, G.; Arul, J.; Solanki, R.B.

    2012-01-01

    This paper discusses, in brief, the salient features of the Level 1 PSA for New and Advanced reactors in India. The features of Level 1 PSA for new reactors are being discussed through a case study of 540 MWe twin unit (comprises of Unit 3 and 4) PHWRs at TAPS. The reactors uses Heavy water moderator and pressurized heavy water coolant, natural uranium fuel and horizontal pressure tubes. The major feature of PSA of advanced reactors is also discussed through the specific issues that were encountered during PSA modeling of AHWR (Advanced Heavy Water Reactor) and 700 MWe PHWR. The results of the PSA indicate that a fairly high level of redundancies exists in TAPS-3 and -4 design. It is recommended that staggered testing philosophy should be adopted especially for Emergency Core Cooling System, to reduce the probability of common cause failure among the motorized valves. It is also recommended to emphasize the importance of Small Break LOCA in general and their consequences in the licensing process of the plant operators

  1. Heat wave generates questions about Ontario's generation capacity

    International Nuclear Information System (INIS)

    Horne, D.

    2005-01-01

    Concerns regarding Ontario's power generation capacity were raised following a major blackout which occurred in August 2003. Power demand reached 26,170 MW during the weeks leading to the blackout, forcing the Independent Electricity System Operator (IESO) to ask residents to reduce electricity use during the day. The grid operator had also issued a forecast that Toronto could face rolling blackouts during times of heavy power demand. Ontario power consumption records were set in June and July of 2003 due to a heat wave, with hourly demand exceeding 25,000 MW on 53 occasions. Ontario was forced to import up to 3,400 MW (13 per cent of its power needs) from neighbouring provinces and the United States. During that period, the price of power had risen sharply to over 30 cents a kilowatt hour, although household consumers were still charged in the 5 to 10 cent range per kilowatt hour. However, it was noted that taxpayers will eventually bear the cost of importing power. The IESO noted that importing electricity is cheaper than the generation available in Ontario and that it is more economical to import, based on the market clearing price of all generators. In 2004, the IESO purchased 6 per cent of their electricity from the United States. That figure is expected to increase for 2005. Ontario generators produced 26.9 million MWh more in the summer of 2005 than during the same period in 2004 to meet electricity demand levels. It was noted that although importing power presently meets peak demand, the IESO agrees there is a need for new generation within Ontario. In addition to restarting Ontario's Pickering and Bruce nuclear facilities, more than 3,300 MW of new gas-fired generation is under construction or approved, and more than 9,000 MW are in various stages of approval. This paper discussed the effect of high energy costs on industry and Ontario's ability to meet future electricity demand in comparison to neighbouring jurisdictions. Issues regarding grid maintenance

  2. Ontario hydro's aqueous discharge monitoring program

    International Nuclear Information System (INIS)

    Mehdi, S.H.; Booth, M.R.; Massey, R.; Herrmann, O.

    1992-01-01

    The Province of Ontario has legislated a comprehensive monitoring program for waterborne trace contaminants called MISA - Municipal Industrial Strategy for Abatement. The electric power sector regulation applies to all generating stations (Thermal, Nuclear, Hydraulic). The program commenced in June, 1990. The current phase of the regulation requires the operators of the plants to measure the detailed composition of the direct discharges to water for a one year period. Samples are to be taken from about 350 identified streams at frequencies varying from continuous and daily to quarterly. The data from this program will be used to determine the scope of the ongoing monitoring program and control. This paper discusses the preparation and planning, commissioning, training and early operations phase of the MISA program. In response, the central Analytical Laboratory and Environmental staff worked to develop a sampling and analytical approach which uses the plant laboratories, the central analytical laboratory and a variety of external laboratories. The approach considered analytical frequency, sample stability, presence of radioactivity, suitability of staff, laboratory qualifications, need for long term internal capabilities, availability of equipment, difficulty of analysis, relationship to other work and problems, capital and operating costs. The complexity of the sampling program required the development of a computer based schedule to ensure that all required samples were taken as required with phase shifts between major sampling events at different plants to prevent swamping the capability of the central or external laboratories. New equipment has been purchased and installed at each plant to collect 24 hour composite samples. Analytical equipment has been purchased for each plant for analysis of perishable analytes or of samples requiring daily or thrice weekly analysis. Training programs and surveys have been implemented to assure production of valid data

  3. Investigating Summer Thermal Stratification in Lake Ontario

    Science.gov (United States)

    James, S. C.; Arifin, R. R.; Craig, P. M.; Hamlet, A. F.

    2017-12-01

    Seasonal temperature variations establish strong vertical density gradients (thermoclines) between the epilimnion and hypolimnion. Accurate simulation of vertical mixing and seasonal stratification of large lakes is a crucial element of the thermodynamic coupling between lakes and the atmosphere in integrated models. Time-varying thermal stratification patterns can be accurately simulated with the versatile Environmental Fluid Dynamics Code (EFDC). Lake Ontario bathymetry was interpolated onto a 2-km-resolution curvilinear grid with vertical layering using a new approach in EFDC+, the so-called "sigma-zed" coordinate system which allows the number of vertical layers to be varied based on water depth. Inflow from the Niagara River and outflow to the St. Lawrence River in conjunction with hourly meteorological data from seven local weather stations plus three-hourly data from the North American Regional Reanalysis govern the hydrodynamic and thermodynamic responses of the Lake. EFDC+'s evaporation algorithm was updated to more accurately simulate net surface heat fluxes. A new vertical mixing scheme from Vinçon-Leite that implements different eddy diffusivity formulations above and below the thermocline was compared to results from the original Mellor-Yamada vertical mixing scheme. The model was calibrated by adjusting solar-radiation absorption coefficients in addition to background horizontal and vertical mixing parameters. Model skill was evaluated by comparing measured and simulated vertical temperature profiles at shallow (20 m) and deep (180 m) locations on the Lake. These model improvements, especially the new sigma-zed vertical discretization, accurately capture thermal-stratification patterns with low root-mean-squared errors when using the Vinçon-Leite vertical mixing scheme.

  4. Selling from Ontario into the U.S. midwest

    International Nuclear Information System (INIS)

    Green, B.

    2002-01-01

    The market structure of the Midwest Independent System Operator (MISO) for the electric power grid was described with reference to physical bilateral markets, multi-control areas, and MISO services such as security coordination, congestion management, billing, generator interconnections, tariff administration, energy imbalance, market monitoring, and electronic scheduling. The drivers impacting MISO development include MISO-PJM-SPP common market initiative, the FERC Standard Market Design initiative, the integration of alliance companies with MISO, and the division of functional responsibilities between RTOs and ITCs. The characteristics of the Michigan market were described, along with participation in the midwest (Ohio and Michigan) wholesale and retail markets. It was noted that in order for Ontario to sell to the midwest, the Ontario market design would need a successful export bid each hour to get power out of the province. Sales of ancillary services from Ontario-based generation are not permitted in the initial Ontario market design. Energy and transmission is currently bundled in Ontario tariffs. 1 fig

  5. Selling from Ontario into the U.S. midwest

    Energy Technology Data Exchange (ETDEWEB)

    Green, B. [Ontario Power Generation Inc., Toronto, ON (Canada)

    2002-07-01

    The market structure of the Midwest Independent System Operator (MISO) for the electric power grid was described with reference to physical bilateral markets, multi-control areas, and MISO services such as security coordination, congestion management, billing, generator interconnections, tariff administration, energy imbalance, market monitoring, and electronic scheduling. The drivers impacting MISO development include MISO-PJM-SPP common market initiative, the FERC Standard Market Design initiative, the integration of alliance companies with MISO, and the division of functional responsibilities between RTOs and ITCs. The characteristics of the Michigan market were described, along with participation in the midwest (Ohio and Michigan) wholesale and retail markets. It was noted that in order for Ontario to sell to the midwest, the Ontario market design would need a successful export bid each hour to get power out of the province. Sales of ancillary services from Ontario-based generation are not permitted in the initial Ontario market design. Energy and transmission is currently bundled in Ontario tariffs. 1 fig.

  6. The Ontario Psychosocial Oncology Framework: a quality improvement tool.

    Science.gov (United States)

    Li, Madeline; Green, Esther

    2013-05-01

    To overview the newly developed Psychosocial Health Care for Cancer Patients and Their Families: A Framework to Guide Practice in Ontario and Guideline Recommendations in the context of Canadian psychosocial oncology care and propose strategies for guideline uptake and implementation. Recommendations from the 2008 Institute of Medicine standard Cancer Care for the Whole Patient: Meeting Psychosocial Health Needs were adapted into the Ontario Psychosocial Oncology (PSO) Framework. Existing practice guidelines developed by the Canadian Partnership against Cancer and Cancer Care Ontario and standards developed by the Canadian Association of Psychosocial Oncology are supporting resources for adopting a quality improvement (QI) approach to the implementation of the framework in Ontario. The developed PSO Framework, including 31 specific actionable recommendations, is intended to improve the quality of comprehensive cancer care at both the provider and system levels. Important QI change management processes are described as Educate - raising awareness among medical teams of the significance of psychosocial needs of patients, Evidence - developing a research evidence base for patient care benefits from psychosocial interventions, and Electronics - using technology to collect patient reported outcomes of both physical and emotional symptoms. The Ontario PSO Framework is unique and valuable in providing actionable recommendations that can be implemented through QI processes. Overall, the result will be improved psychosocial health care for the cancer population. Copyright © 2012 John Wiley & Sons, Ltd.

  7. Facing the challenges of nuclear power at Ontario Power Generation

    International Nuclear Information System (INIS)

    Howes, H.

    1999-01-01

    Nuclear power represents a major portion of Ontario Power Generation's generation mix and it will be the bedrock upon which we build a successful, competitive company. Our nuclear units offer many environmental and economic benefits, the one most relevant to this meeting is their significant contribution to the relatively low carbon intensity of Ontario's and Canada's electricity supply. In recent weeks, we have listened with great interest to the endorsement by our federal Minister of the Environment of nuclear technology as a means of reducing global warming. But endorsements of this type alone are not sufficient to ensure that nuclear remains an acceptable option for managing greenhouse gas emissions. Without public acceptance and support, the entire nuclear investment is endangered. At OPG we face three challenges to building this public support: we must continue to improve our safety margins and operating performance; we must continue to improve the environmental performance at our stations; and we must increase our community outreach. Today I would like to focus on the last two challenges and the actions that we are taking to maintain our social and environmental 'licence to operate.' But before I describe these initiatives, I will tell you about: the new company - Ontario Power Generation; the changes in store for Ontario's electricity sector; and our greenhouse gas emissions - the legacy from Ontario Hydro. (author)

  8. Electricity market price volatility: The case of Ontario

    International Nuclear Information System (INIS)

    Zareipour, Hamidreza; Bhattacharya, Kankar; Canizares, Claudio A.

    2007-01-01

    Price volatility analysis has been reported in the literature for most competitive electricity markets around the world. However, no studies have been published yet that quantify price volatility in the Ontario electricity market, which is the focus of the present paper. In this paper, a comparative volatility analysis is conducted for the Ontario market and its neighboring electricity markets. Volatility indices are developed based on historical volatility and price velocity concepts, previously applied to other electricity market prices, and employed in the present work. The analysis is carried out in two scenarios: in the first scenario, the volatility indices are determined for the entire price time series. In the second scenario, the price time series are broken up into 24 time series for each of the 24 h and volatility indices are calculated for each specific hour separately. The volatility indices are also applied to the locational marginal prices of several pricing points in the New England, New York, and PJM electricity markets. The outcomes reveal that price volatility is significantly higher in Ontario than the three studied neighboring electricity markets. Furthermore, comparison of the results of this study with similar findings previously published for 15 other electricity markets demonstrates that the Ontario electricity market is one of the most volatile electricity markets world-wide. This high volatility is argued to be associated with the fact that Ontario is a single-settlement, real-time market

  9. Solar and the future of Ontario's electricity supply

    International Nuclear Information System (INIS)

    McMonagle, R.

    2005-01-01

    The potential contribution of solar energy to Ontario's electricity supply was evaluated in this PowerPoint presentation. Only 3.5 per cent of Canada's photovoltaic (PV) systems are connected to the electricity grid. However, 47 per cent of all homes in Ontario have the potential to install 3 kW PV arrays, and the solar industry has the potential to achieve growth rates of between 50 to 75 per cent, with medium term sustainable growth estimated at 30 to 40 per cent annually. The benefits of grid-connected solar energy include employment and wealth creation in Ontario; reductions in peak demand; and improved grid efficiency. It was noted that the price of solar PV is declining. Various market niches for solar energy technologies were outlined, and the targeting of early adopters was recommended as a first market for PV growth. An overview of the value of PV build-ups in California was presented, as well details of international tariffs and rates. A 10 year program leading to the installation of 15,000 PV systems or 40 MWp of installed capacity in Ontario by 2015 was outlined, as well as a plan for solar financing. It was concluded that priming the market now will mean that solar will be prepared to contribute to Ontario's supply during the 2015-2025 period, when its price will be competitive. refs., tabs., figs

  10. Ontario pharmacists' crisis over Bill 16: A missed opportunity?

    Science.gov (United States)

    Rosenthal, Meagen; Austin, Zubin; Tsuyuki, Ross T

    2012-01-01

    In 2010, the Ontario government brought forward Bill 16, which, among other things, removed pharmacists' professional allowances. While many would disagree with this unilateral action by the Ontario government, it also could have served as a crisis for change towards patient-centred care. We sought to examine the response of the pharmacy profession in Ontario to this crisis as it relates to the vision outlined in the Blueprint for Pharmacy. We systematically examined publicly available responses to Schedule 5 of Ontario's Bill 16 during the period from April to June 16, 2010. A rapid textual analysis of the data using tag or word clouds and a qualitative content analysis were performed on all of the data collected. The rapid textual analysis revealed that the most frequently used terms were "pharmacist," "pharmacy" and "professional allowances"; the least used were "layoffs," "service cuts" and "patient care." Content analysis revealed 4 themes: the desire to maintain the status quo of practice, a focus on the business of pharmacy, pharmacy stakeholders' perceptions of government's attitude towards the profession and changes to patient services. It is notable that patient care was almost completely absent from the discussion, a reflection that our profession has not embraced patient-centred care. This also represents a missed opportunity - a crisis that could have been used to move the profession towards the Blueprint's vision. We thought that the Blueprint had already achieved this consensus, but the Ontario experience has shown that this may not be the case.

  11. Emission trading in Ontario : Understanding and managing compliance risk

    Energy Technology Data Exchange (ETDEWEB)

    White, A. [Mirant Canada Energy Marketing ltd., Toronto, ON (Canada)

    2002-07-01

    Mirant is one of the top five American energy marketer of power and gas, with more than 20,700 megawatts (MW) of electric generating capacity worldwide, of which 13,600 is in North America. The author presented a chart displaying nitrogen oxide emissions in Ontario, followed by another chart with the emissions of sulphur dioxide also in Ontario. The emission targets for the power sector were reviewed, as were the nitrogen oxide emission limits from 2002 to 2010. The major features of the Ontario legislation were discussed, covering allowance allocation, unlimited banking and limited provisions for credit. Ontario fossil capacity was reviewed, followed by emission allowance allocation. The issues and risks for Independent Power Producers were discussed. They included the emission rate compared to that of the competition, how much the facility was run last year and how much you expect to run it next year, the possibility of buying allowances or credits and at what cost. Looking to the future, the government of Ontario has announced bold actions on industry emissions. The initiatives include consultations, emission limits for both nitrogen oxide and sulphur dioxide from all major industrial emitters, and tighter province-wide targets and timelines for nitrogen oxide and sulphur dioxide. refs., tabs., figs.

  12. Staff report on Ontario gas distributor service quality regulation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-29

    This report provides the basis for consultation regarding a framework for building principles and minimum standards regarding service quality measures for gas distributors. It begins with a general overview of current concerns expressed by Ontario natural gas consumers regarding service quality. Customer complaints logged with the Ontario Energy Board between 2003 and 2004 include common issues such as slow telephone response time, failure to obtain regular meter reads, inaccurate billing, long payment processing times, long reconnection times, long new connection times, and slow response to emergencies. This report also presents the historical experience in Ontario's energy sector regarding performance monitoring of services within an incentive based rate making framework for electricity and gas distributors. The Ontario Energy Board's Natural Gas Forum report reveals that a service quality framework would ensure that cost saving initiatives are not implemented at the expense of customer service or safe operation of the distribution system. Although the Board intends to implement a service quality framework, it will not include direct financial incentives. Rather, it will monitor service quality performance and utilities will be subject to a compliance process. A brief summary was also included of service quality regulations in the electricity sector and in other jurisdictions such as Australia, the United Kingdom, Pennsylvania, and Alberta. A list of issues that remain to be addressed before implementing a framework in Ontario was then presented. 2 appendices.

  13. Emission trading in Ontario : Understanding and managing compliance risk

    International Nuclear Information System (INIS)

    White, A.

    2002-01-01

    Mirant is one of the top five American energy marketer of power and gas, with more than 20,700 megawatts (MW) of electric generating capacity worldwide, of which 13,600 is in North America. The author presented a chart displaying nitrogen oxide emissions in Ontario, followed by another chart with the emissions of sulphur dioxide also in Ontario. The emission targets for the power sector were reviewed, as were the nitrogen oxide emission limits from 2002 to 2010. The major features of the Ontario legislation were discussed, covering allowance allocation, unlimited banking and limited provisions for credit. Ontario fossil capacity was reviewed, followed by emission allowance allocation. The issues and risks for Independent Power Producers were discussed. They included the emission rate compared to that of the competition, how much the facility was run last year and how much you expect to run it next year, the possibility of buying allowances or credits and at what cost. Looking to the future, the government of Ontario has announced bold actions on industry emissions. The initiatives include consultations, emission limits for both nitrogen oxide and sulphur dioxide from all major industrial emitters, and tighter province-wide targets and timelines for nitrogen oxide and sulphur dioxide. refs., tabs., figs

  14. Fifteen years of radioactive waste management at Ontario Hydro

    International Nuclear Information System (INIS)

    Carter, T.J.; Rao, P.K.M.

    1985-01-01

    Ontario Hydro is a large Canadian utility producing 84% (7394 MWe) of the Nuclear Electricity generated in Canada. The low- and intermediate-level radioactive wastes generated by the Ontario Hydro program are currently being managed at the Bruce Nuclear Power Development with various volume reduction, packaging and interim storage systems. Ontario Hydro also owns and operates a radioactive waste transportation system. Studies are in progress for final disposal of these wastes in a suitable geology in Ontario. Since its inception in 1971, Ontario Hydro's radioactive waste management program has evolved into providing a full fledged radioactive waste management capability to the utility's two nuclear generation centres at Pickering and Bruce, and later in the decade, to Darlington. This paper summarizes the various developments in this program; highlights the major facilities both in-service and planned to be built; reviews the experiences gained over fifteen years of in-house waste management; and discusses the proposed reorientation towards ultimate disposal of these wastes. 2 refs., 8 figs., 1 tab

  15. Overview of surgery for oral cavity cancer in Ontario.

    Science.gov (United States)

    Eskander, Antoine; Irish, Jonathan; Gullane, Patrick; Gilbert, Ralph; de Almeida, John R; Freeman, Jeremy; Giuliani, Meredith; Urbach, David R; Goldstein, David P

    2016-07-01

    The pupose of this study was to describe variations in incidence and resection rates of patients with oral cavity squamous cell carcinoma (SCC) in Ontario. All oral cavity SCCs in Ontario between 2003 and 2010 were identified from the Ontario Cancer Registry. Incidence and resection rates along with variations in care were compared by sociodemographic factors and Ontario health regions. The 8-year incidence rates for oral cavity SCC was 21.3 per 100,000 with variations by sex, age group, neighborhood income, and community size. Seventy-four percent of patients underwent an oral cavity cancer resection, of which 91% were at a regional head and neck cancer center. Variations in resection rates existed by region of residence and treatment. Oral cavity cancer incidence rates vary by sex, age, neighborhood income, community size, and health region. Resection rates vary by age and health region. Oral cavity cancer care is highly regionalized in Ontario. © 2015 Wiley Periodicals, Inc. Head Neck 38: 1113-1118, 2016. © 2015 Wiley Periodicals, Inc.

  16. 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.)

  17. Reactor decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1984-01-01

    A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

  18. 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

  19. 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

  20. 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.)

  1. Measles Outbreak with Unique Virus Genotyping, Ontario, Canada, 2015.

    Science.gov (United States)

    Thomas, Shari; Hiebert, Joanne; Gubbay, Jonathan B; Gournis, Effie; Sharron, Jennifer; Severini, Alberto; Jiaravuthisan, Manisa; Shane, Amanda; Jaeger, Valerie; Crowcroft, Natasha S; Fediurek, Jill; Sander, Beate; Mazzulli, Tony; Schulz, Helene; Deeks, Shelley L

    2017-07-01

    The province of Ontario continues to experience measles virus transmissions despite the elimination of measles in Canada. We describe an unusual outbreak of measles in Ontario, Canada, in early 2015 that involved cases with a unique strain of virus and no known association among primary case-patients. A total of 18 cases of measles were reported from 4 public health units during the outbreak period (January 25-March 23, 2015); none of these cases occurred in persons who had recently traveled. Despite enhancements to case-patient interview methods and epidemiologic analyses, a source patient was not identified. However, the molecular epidemiologic analysis, which included extended sequencing, strongly suggested that all cases derived from a single importation of measles virus genotype D4. The use of timely genotype sequencing, rigorous epidemiologic investigation, and a better understanding of the gaps in surveillance are needed to maintain Ontario's measles elimination status.

  2. Hydrogen and fuel cell research networking in Ontario

    Energy Technology Data Exchange (ETDEWEB)

    Peppley, B.A. [Queen' s-RMC Fuel Cell Research Centre, Kingston, ON (Canada)

    2009-07-01

    This presentation reviewed the activities of the Ontario Fuel Cell Research and Innovation Network since its launch in 2006. Funded by the Ontario Ministry of Research and Innovation, the project involves 17 academic researchers from 8 universities and is supported by 8 industrial partners. The group of researchers has made progress in supporting the developing fuel cell industry in Ontario and in Canada. Their work has the potential to help deploy the province's automotive-oriented manufacturing sector in directions that address the issues of clean air and climate change. New initiatives in the development of hydrogen and fuel cell technologies are instrumental in expanding this network to leverage new business activities in the post financial crisis period. These activities are expected to result in economic benefits for job and economic growth.

  3. Ontario Hydro at the millennium : has monopoly's moment passed?

    International Nuclear Information System (INIS)

    Daniels, R.J.

    1996-01-01

    This volume is a collection of 10 papers presented at a conference in which the challenges of restructuring the electric power industry in Ontario were discussed. Legal experts, policy makers, economists and stakeholders in the industry presented their views regarding the future of the industry in Ontario. The implications of privatization were discussed. There was general agreement on the need for some industry de-integration and privatization. However, agreement on the exact nature of the approach to take was more divided. For example, opinion was divided on what the logical endpoint of industry restructuring should be i.e. wholesale or retail competition. Also contentious was the question of what portion of Hydro's generating assets should be sold off to private enterprise if Hydro's generation and transmission assets are unbundled. Opinions were also divided about the environmental consequences of nuclear energy. Significant differences of opinion were evident concerning the privatization of Ontario Hydro's nuclear assets. refs., tabs., figs

  4. 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.)

  5. 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)

  6. 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

  7. Tritium resources available for fusion reactors

    Science.gov (United States)

    Kovari, M.; Coleman, M.; Cristescu, I.; Smith, R.

    2018-02-01

    The tritium required for ITER will be supplied from the CANDU production in Ontario, but while Ontario may be able to supply 8 kg for a DEMO fusion reactor in the mid-2050s, it will not be able to provide 10 kg at any realistic starting time. The tritium required to start DEMO will depend on advances in plasma fuelling efficiency, burnup fraction, and tritium processing technology. It is in theory possible to start up a fusion reactor with little or no tritium, but at an estimated cost of 2 billion per kilogram of tritium saved, it is not economically sensible. Some heavy water reactor tritium production scenarios with varying degrees of optimism are presented, with the assumption that only Canada, the Republic of Korea, and Romania make tritium available to the fusion community. Results for the tritium available for DEMO in 2055 range from zero to 30 kg. CANDU and similar heavy water reactors could in theory generate additional tritium in a number of ways: (a) adjuster rods containing lithium could be used, giving 0.13 kg per year per reactor; (b) a fuel bundle with a burnable absorber has been designed for CANDU reactors, which might be adapted for tritium production; (c) tritium production could be increased by 0.05 kg per year per reactor by doping the moderator with lithium-6. If a fusion reactor is started up around 2055, governments in Canada, Argentina, China, India, South Korea and Romania will have the opportunity in the years leading up to that to take appropriate steps: (a) build, refurbish or upgrade tritium extraction facilities; (b) extend the lives of heavy water reactors, or build new ones; (c) reduce tritium sales; (d) boost tritium production in the remaining heavy water reactors. All of the alternative production methods considered have serious economic and regulatory drawbacks, and the risk of diversion of tritium or lithium-6 would also be a major concern. There are likely to be serious problems with supplying tritium for future

  8. Analysis of fuel handling system for fuel bundle safety during station blackout in 500 MWe PHWR unit of India

    Energy Technology Data Exchange (ETDEWEB)

    Madhuresh, R; Nagarajan, R; Jit, I; Sanatkumar, A [Nuclear Power Corporation of India Ltd., Mumbai (India)

    1997-12-31

    Situations of Station Blackout (SBO) i.e. postulated concurrent unavailability of Class Ill and Class IV power, could arise for a long period, while on-power refuelling or other fuel handling operations are in progress with the hot irradiated fuel bundles being anywhere in the system from the Reactor Building to the Spent Fuel Storage Bay. The cooling provisions for these fuel bundles are diverse and specific to the various stages of fuel handling operations and are either on Class Ill or on Class II power with particular requirements of instrument air. Therefore, during SBO, due to the limited availability of Class II power and instrument air, it becomes difficult to maintain cooling to these fuel bundles. However, some minimal cooling is essential, to ensure the safety of the bundles. As discussed in the paper, safety of these fuel bundles in the system and/or for those lying in the liner tube region of the reactor end fitting is ensured, during SBO, by resorting to passive means like `stay-put`, `gravity- fill`, `D{sub 2}0- steaming` etc. for cooling the bundles. The paper also describes various consequences emanating from these cooling schemes. (author). 6 refs., 2 tabs., 8 figs.

  9. Analysis of fuel handling system for fuel bundle safety during station blackout in 500 MWe PHWR unit of India

    International Nuclear Information System (INIS)

    Madhuresh, R.; Nagarajan, R.; Jit, I.; Sanatkumar, A.

    1996-01-01

    Situations of Station Blackout (SBO) i.e. postulated concurrent unavailability of Class Ill and Class IV power, could arise for a long period, while on-power refuelling or other fuel handling operations are in progress with the hot irradiated fuel bundles being anywhere in the system from the Reactor Building to the Spent Fuel Storage Bay. The cooling provisions for these fuel bundles are diverse and specific to the various stages of fuel handling operations and are either on Class Ill or on Class II power with particular requirements of instrument air. Therefore, during SBO, due to the limited availability of Class II power and instrument air, it becomes difficult to maintain cooling to these fuel bundles. However, some minimal cooling is essential, to ensure the safety of the bundles. As discussed in the paper, safety of these fuel bundles in the system and/or for those lying in the liner tube region of the reactor end fitting is ensured, during SBO, by resorting to passive means like 'stay-put', 'gravity- fill', 'D 2 0- steaming' etc. for cooling the bundles. The paper also describes various consequences emanating from these cooling schemes. (author). 6 refs., 2 tabs., 8 figs

  10. Proceedings of the Ontario Petroleum Institute's 46. annual conference : Ontario oil and gas conference

    International Nuclear Information System (INIS)

    2007-01-01

    This conference provided a forum for industry leaders and researchers to discuss issues related to Ontario's oil and gas industry. Economic profiles of the oil, gas, and salt resource industries were presented along with issues related to underground storage and abandoned oil wells. New technologies designed to improve production efficiency were also presented with particular reference to issues related to climate change and global energy needs. Other topics of discussion included gas storage facilities, the environmental impacts of the oil and gas industry, and issues related to site security. The conference was divided into 5 sessions. Two thesis award papers were also presented along with a keynote address that provided an overview of the petroleum industry's economic outlook. The conference featured 16 presentations, of which 3 have been catalogued separately for inclusion in this database. tabs., figs

  11. The short-term impact of Ontario's generic pricing reforms.

    Directory of Open Access Journals (Sweden)

    Michael R Law

    Full Text Available Canadians pay amongst the highest generic drug prices in the world. In July 2010, the province of Ontario enacted a policy that halved reimbursement for generic drugs from the public drug plan, and substantially lowered prices for private purchases. We quantified the impact of this policy on overall generic drug expenditures in the province, and projected the impact in other provinces had they mimicked this pricing change.We used quarterly prescription generic drug dispensing data from the IMS-Brogan CompuScript Audit. We used the price per unit in both the pre- and post-policy period and two economics price indexes to estimate the expenditure reduction in Ontario. Further, we used the post-policy Ontario prices to estimate the potential reduction in other provinces.We estimate that total expenditure on generic drugs in Ontario during the second half of 2010 was between $181 and $194 million below what would be expected if prices had remained at pre-policy level. Over half of the reduction in spending was due to savings on just 10 generic ingredients. If other provinces had matched Ontario's prices, their expenditures over during the latter half of 2010 would have been $445 million lower.We found that if Ontario's pricing scheme were adopted nationally, overall spending on generic drugs in Canada would drop at least $1.28 billion annually--a 5% decrease in total prescription drug expenditure. Other provinces should seriously consider both changes to their generic drug prices and the use of more competitive bulk purchasing policies.

  12. Future changes of temperature and heat waves in Ontario, Canada

    Science.gov (United States)

    Li, Zhong; Huang, Guohe; Huang, Wendy; Lin, Qianguo; Liao, Renfei; Fan, Yurui

    2018-05-01

    Apparent changes in the temperature patterns in recent years brought many challenges to the province of Ontario, Canada. As the need for adapting to climate change challenges increases, the development of reliable climate projections becomes a crucial task. In this study, a regional climate modeling system, Providing Regional Climates for Impacts Studies (PRECIS), is used to simulate the temperature patterns in Ontario. Three PRECIS runs with a resolution of 25 km × 25 km are carried out to simulate the present (1961-1990) temperature variations. There is a good match between the simulated and observed data, which validates the performance of PRECIS in reproducing temperature changes in Ontario. Future changes of daily maximum, mean, and minimum temperatures during the period 2071-2100 are then projected under the IPCC SRES A2 and B2 emission scenarios using PRECIS. Spatial variations of annual mean temperature, mean diurnal range, and temperature seasonality are generated. Furthermore, heat waves defined based on the exceedance of local climatology and their temporal and spatial characteristics are analyzed. The results indicate that the highest temperature and the most intensive heat waves are most likely to occur at the Toronto-Windsor corridor in Southern Ontario. The Northern Ontario, in spite of the relatively low projected temperature, would be under the risk of long-lasting heat waves, and thus needs effective measures to enhance its climate resilience in the future. This study can assist the decision makers in better understanding the future temperature changes in Ontario and provide decision support for mitigating heat-related loss.

  13. The long-term outlook for nuclear capacity in Ontario

    International Nuclear Information System (INIS)

    Archinoff, G.H.

    1979-04-01

    This report derives three estimates of long-term nuclear growth in Ontario for use in strategy studies of alternate nuclear fuel cycles. The low and high estimates encompass the full range of possible long-term nuclear growth rates. The middle, or base growth, estimate represents the nuclear growth pattern which seems at the present time most likely to occur. For the base growth estimate, nuclear capacity in Ontario reaches 31 GWe in 2000, grows to 175 GWe by 2060, and then remains constant. For the high growth estimate, the capacity in 2000 is 33 GWe, and climbs continuously to 833 GWe by the year 2100. (auth)

  14. Exposure of Ontario workers to radiofrequency fields from dielectric heaters

    International Nuclear Information System (INIS)

    Bitran, M.E.; Nishio, J.M.; Charron, D.E.

    1992-01-01

    As part of a program to assess and reduce the exposure of Ontario workers to non-ionizing radiations, stray electric and magnetic fields from 383 dielectric heaters were measured in 71 industrial establishments from 1988 to 1990. This represents a population of over 800 workers potentially exposed to radiofrequency (RE) electromagnetic fields. Electric and magnetic field strengths at the head, waist, and thigh levels of the operators, corrected by duty cycle, are presented for the different heater types surveyed. Worker exposure data and compliance with Ontario radiofrequency exposure guidelines are discussed. (author)

  15. Ontario Power Authority district energy research report : final report

    International Nuclear Information System (INIS)

    2010-02-01

    This paper presented an analysis of the technical and economic characteristics of district energy in Ontario. The market context for district energy was evaluated, and institutional issues that may influence the future development and operation of district energy systems in Ontario were explored. Technical, economic, and environmental analyses of district energy based on different neighbourhood sizes, types, and district energy systems were presented. Three case studies were included to demonstrate real world district energy applications. A set of interviews conducted with representatives of the province's district energy supply chain was also provided in order to provide a framework for district energy opportunities and challenges within the province. 22 tabs., 16 figs.

  16. A demand/supply and price outlook for electricity in Ontario

    International Nuclear Information System (INIS)

    Dalton, J.

    2004-01-01

    This paper presents the demand/supply and price outlook for electricity in Ontario. The paper examines the near term outlook, critical demand and supply issues, the projected Ontario demand/supply balances and finally concludes by looking at the challenges for Ontario's new market structure

  17. Natural gas in 1927: Petroleum in 1927: The oil and gas fields of Ontario. Annual publication

    Energy Technology Data Exchange (ETDEWEB)

    Harkness, R B

    1930-12-31

    This annual report presents figures for gas consumption in Ontario, gas wells and their production, and leakage. It includes licenses issued for the year and logs of wells. Information is also given on oil production in Ontario, petroleum refining and petroleum imported into Ontario.

  18. Compendium of Statistical and Financial Information: Ontario Universities, 2000-01.

    Science.gov (United States)

    Council of Ontario Universities, Toronto.

    This compendium presents data on various aspects of the Ontario University System, Canada. It is a companion to the Financial Report of Ontario Universities, the annual series of volumes prepared under the auspices of the Council of Financial Officers-Universities of Ontario (COFO-UO). This compendium contains supplementary information that helps…

  19. Compendium of Statistical and Financial Information: Ontario Universities, 2001-02.

    Science.gov (United States)

    Council of Ontario Universities, Toronto.

    This compendium presents data about aspects of the Ontario University System, Canada. It is a companion to the "Financial Report of Ontario Universities," the annual series of volumes prepared under the auspices of the Council of Financial OfficersUniversities of Ontario (COFO-UO). The Compendium contains supplementary information on…

  20. Opening Doors to Nursing Degrees: Time for Action. A Proposal from Ontario's Colleges

    Science.gov (United States)

    Colleges Ontario, 2015

    2015-01-01

    This report argues that Ontario must expand the educational options for people who want to become registered nurses (RNs). It argues that the change Ontario requires is to authorize colleges to offer their own high-quality nursing degrees. Until 2005, about 70 per cent of Ontario's RNs were educated at colleges. Today, tens of thousands of RNs who…