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Fuel And Fuel Channel Assessment For Channel Flow Blockage Accidents In A 600 Mwe Candu Reactor
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Book Synopsis Fuel and fuel channel assessment for channel flow blockage accidents in a 600 mw(e) CANDU reactor by : Y. Ogniewicz
Download or read book Fuel and fuel channel assessment for channel flow blockage accidents in a 600 mw(e) CANDU reactor written by Y. Ogniewicz and published by . This book was released on 1983 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Themohydraulic assessment of a postulated channel flow blockage in a 600 mw(e) CANDU reactor by : Y. Ogniewicz
Download or read book Themohydraulic assessment of a postulated channel flow blockage in a 600 mw(e) CANDU reactor written by Y. Ogniewicz and published by . This book was released on 1983 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Loss-of-coolant Accident Analysis for Near Stagnation Flow in the Horizontal Fuel Channel of Candu Reactor by : Ahmet Durmayaz
Download or read book A Loss-of-coolant Accident Analysis for Near Stagnation Flow in the Horizontal Fuel Channel of Candu Reactor written by Ahmet Durmayaz and published by . This book was released on 1995 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In this thesis, a two-phase thermalhydraulic model has been developed inorder to investigate the near stagnation flow phenomena in the horizontal fuelchannel of a CANDU nuclear reactor following a postulated small break _loss-_of-çoolant-accident (LOCA) in the inlet feeder or inlet header. In this model, the unequal velocity unequal temperature (UVUT) modelis used in which the velocities and enthalpies (hence temperatures) for both liquidand vapor phases, void fraction and a common dynamic pressure are computed. Stratified smooth and dispersed bubbly flows are considered together for the near stagnation flow and dispersed bubbly flow is considered for the normal operating conditions of a CANDU reactor as the flow regimes. Geometrical configuration of a typically CANDU reactor fuel channel is considered. Thermodynamic andtransport properties of heavy water are also considered as functions of pressure and temperature. In the derivations of the conservation equations, all of the terms are area and time (ensemble) averaged. A fully implicit discretization method and a staggered grid control volume approach are applied in order to obtain an algebraic equation set from the governing differential conservation equations. Hvbrid scheme. in which central difference and upwind schemes are considered by turns depending on the value of Peclet number, is used while deriving the discretization equations. To solve the near stagnation flow problem by using this model, the IPSA algorithm (Inter-Phase Slip Algorithm) which was developed to solve the multi-phase flows originally is modified to give a solution for a horizontal channel which is full of single phase fluid in some part whereas it is full of two- phase fluid in the other part. A computer code that is called as the ANESTA ( Analysis for NEar STAgnation flow in the fuel channel of a CANDU reactor ) code has been developed. The model mentioned above is applied to both normal operating conditions and the near stagnation flow (LOCA) conditions by this code. A set of approximate functions for the fast calculation of the thermodynamic properties of heavy water (D20 ) has also been derived. For this aim, the data given in the steam tables for heavy water thermodynamic properties have been accurately and successfully fitted to the curves as functions of pressure and temperature in order to obtain some simple functions by usingthe least-square method.
Book Synopsis CANDU 600 reactor fuel channel components : hydraulic losses by : M. Liska
Download or read book CANDU 600 reactor fuel channel components : hydraulic losses written by M. Liska and published by . This book was released on 1982 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Pressure drops in a CANDU 600 mw fuel channel in water and steam water flow preliminary analysis by : C. F. Forrest
Download or read book Pressure drops in a CANDU 600 mw fuel channel in water and steam water flow preliminary analysis written by C. F. Forrest and published by . This book was released on 1978 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Advanced fuel channel concepts for improved heat rejection under postulated accident conditions in CANDU reactors by : R. Dutton
Download or read book Advanced fuel channel concepts for improved heat rejection under postulated accident conditions in CANDU reactors written by R. Dutton and published by . This book was released on 1994 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1984 with total page 622 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis CANDU 600 fuel channels assessment of pressure tube failure at pickering a by : J. T. Dunn
Download or read book CANDU 600 fuel channels assessment of pressure tube failure at pickering a written by J. T. Dunn and published by . This book was released on 1984 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis CANDU 600 mw(e) large break loss-of-coolant/loss of class iv power analysis : a fuel and channel assessment by : L. Macdonald
Download or read book CANDU 600 mw(e) large break loss-of-coolant/loss of class iv power analysis : a fuel and channel assessment written by L. Macdonald and published by . This book was released on 1983 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A preliminary assessment of fuel-channel options for advanced CANDU. by : R. Dutton
Download or read book A preliminary assessment of fuel-channel options for advanced CANDU. written by R. Dutton and published by . This book was released on 1991 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Flow blockage channel rupture experiments : test 2 (fbcr2). by : J. Ramsay
Download or read book Flow blockage channel rupture experiments : test 2 (fbcr2). written by J. Ramsay and published by . This book was released on 1997 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The btf-105 experiment in the blowdown test facility is one of a series of experiments sponsored by the candu owners group (cog) to determine the release, transport and deposition of fission products from nuclear fuel under high-temperature transient conditions. the btf-105 experiment has been broken up into two tests: btf-105a and btf-105b. the btf-105a test is a precursor to the btf-105b test, which will generate fission product release data used to benchmark candu safety analysis codes. the btf-105a test will be used to assess instrumentation and procedures to be used during btf-105b, and to generate correlations between fuel sheath and fuel centreline temperatures. fission product release and transport data will also be obtained from low burnup fuel. the btf-105a test consists of a fuel stringer containing a single unirradiated instrumented zircaloy-clad uo2 fuel element. the assembly will be irradiated at a linear power of 50 kw/m for 10 days to establish an inventory of fission products in the fuel. following the soak irradiation, the stringer will be subjected to a coolant blowdown where the volume average temperature of the uo2 will rise to and be maintained at about 1600-1800 degrees c for about 10 minutes. the fuel element is predicted to fail during the ramp up to this temperature due to complete oxidation of the sheath. fission products released during the transient will be monitored by gamma spectrometers. following the test, the fuel stringer will be removed from the reactor and destructively examined in the crl hot cells. grab samples from inside the test section will also be removed and analyzed for fission products. this report presents an overall plan for the activities to be completed before, during and after the btf-105a blowdown test.
Book Synopsis Flow behaviour in a CANDU horizontal fuel channel from stagnant subcooled intial conditions by : M. Z. Caplan
Download or read book Flow behaviour in a CANDU horizontal fuel channel from stagnant subcooled intial conditions written by M. Z. Caplan and published by . This book was released on 1983 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :B. A. Cheadle Publisher :Chalk River, Ont. : Reactor Materials Division, Chalk River Laboratories ISBN 13 :9780660167206 Total Pages :17 pages Book Rating :4.1/5 (672 download)
Book Synopsis Assessment of the Integrity of KANUPP Fuel Channels by : B. A. Cheadle
Download or read book Assessment of the Integrity of KANUPP Fuel Channels written by B. A. Cheadle and published by Chalk River, Ont. : Reactor Materials Division, Chalk River Laboratories. This book was released on 1996 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A method for calculating CANDU fuel channel flow following inlet header stratification by : W. C. Bowman
Download or read book A method for calculating CANDU fuel channel flow following inlet header stratification written by W. C. Bowman and published by . This book was released on 1983 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Corrosion, hydriding and chemistry in annulus gas systems in the core of CANDU reactors by : D. R. Mccracken
Download or read book Corrosion, hydriding and chemistry in annulus gas systems in the core of CANDU reactors written by D. R. Mccracken and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of this study is to evaluate the relative impact of the design parameters on bundle uranium mass and sheath strain and to re-evaluate the basis for the limitation on bundle mass due to an increase in bundle subchannel cross-sections. bundle uranium mass is determined by parameters that in turn affect the sheath strain during operation. this might affect sub-channel flow areas and affect the chf-ccp. the bundle uranium mass was assessed with electres and resulting sheath strains estimated for a candu 6 fuel channel operating at overpowers just at the trip set point of the reactor (onset of sheath dryout), a 14% power increase. the electres fuel modeling code is used to determine the relative impact on sheath strain of the design parameters that control uranium mass, namely, pellet density, diametral clearance, axial gap, and pellet face geometry (chamfer, dish depth, and land width). a limitation was placed on bundle uranium mass by new brunswick power. this came from a ccp evaluation showing that a candu 6 reactor, fuelled with bundles having average masses greater than 19.25 kg u, would have a net positive sheath strain over a fuel channel at the power for the onset of dryout, and therefore a ccp penalty. the calculations were based on steady bundle powers, operating in a fuel channel at ccp to a burnup of 168 mw middle dot h/kg u. at this burnup the strain calculation included a 14% power boost. these are indeed very conservative assumptions with a view to maximizing calculated sheath strains, without regard for fuel defect probability. for comparison, this study has produced electres strain calculations for high power channel power histories representative of 8 bundle shifts, also with a 14% power boost, operating at dryout.
Book Synopsis Soatic report on overview of fuel channel problems by : D. Dasgupta
Download or read book Soatic report on overview of fuel channel problems written by D. Dasgupta and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: A chf look-up table, applicable for both the loss-of-regulation (lor) and loss-of-coolant (loc) accident conditions, has been derived for a string of horizontal, candu-type, 37-element bundles. the bundle-chf look-up table is primarily based on the chf table for tubes and the correction factors accounting for the differences in geometry (between tubes and bundles) and in channel orientation (between vertical and horizontal flows). experimental results of chf in bundles are subsequently used to improve the accuracy of the table. the table-chf values have been adjusted to provide a correct and smooth parametric trend. within the ranges of experimental data, the prediction accuracy of the chf look-up table for bundles is excellent: rms errors are 4.6 percent for the data from the 6-m uniformly heated bundles, 5.8 percent from the 3-m uniformly heated bundles, 7.4 percent from the 1-m uniformly heated bundles and 6.8 percent for the initial dryout data from the 6-m non-uniformly heated bundles. predictions from the chf look-up table for bundles have also been compared against the bundle chf results obtained with freon-12, using the h2o/f-12 modelling parameters. these freon chf tests covered a range of mass flux from 1200-7450 kg.m-2.s-1 (water equivalent conditions). the overall rms error for four separate horizontal bundle-chf tests is 6.33 percent and for five vertical bundle-chf tests it is 5.09 percent. outside the ranges of the data base, the effect of flow stratification has been accounted for in the bundle-chf table by employing a semi-empirical correction factor which is obtained from a balance of turbulent force and gravitational forces. at conditions corresponding to stratified smooth or stratified wavy flow, the table values are equal to zero.
Book Synopsis Assessment of fuel channel inspection needs 1994 to 2000 by : A. Jeffs
Download or read book Assessment of fuel channel inspection needs 1994 to 2000 written by A. Jeffs and published by . This book was released on 1991 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: A number of different types of procedures are used in the operation of a nuclear power plant [1], including emergency operating procedures (eops) or abnormal incident manuals (aims), maintenance procedures, testing procedures, operating manuals (oms), field procedures, etc. oms are used for normal plant conditions or when minor incidents occur. in general, there is a separate om for each system in the plant [2]. instructions for performing manual tasks in the plant are contained in field and maintenance procedures. transients that could affect plant or public safety are known as abnormal incidents and require the use of eops. since the accident at three mile island, increased emphasis has been placed internationally on the development of eops to mitigate plant upsets. plants are becoming increasingly complex and require many volumes of procedure instructions to allow operation under all conditions. the amount of information has grown to the point where an automated means of referencing this knowledge would be beneficial. recent advances in technology have prompted research to develop computer tools to assist operations staff [3]. this report reviews recent developments in the field of computerized plant operating procedures in all aspects of the procedure lifecycle. in particular, the evolution of procedure resentation from paper-based manuals to computer systems is described and a classification scheme is proposed to categorize levels of procedure automation. the results of a literature survey are given to describe current work by institutions around the world, and the three prototype presentation systems developed by aecl research are outlined.
