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Author : A. O. Banas
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Thermal model of the CANDU fuel channel assembly and its implementation in the assert-iv code written by A. O. Banas and published by . This book was released on 1990 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : K. Hedges
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Future CANDUs influence the present written by K. Hedges and published by . This book was released on 1995 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The chan series of experiments was designed to provide data and understanding to assess the capability of various fuel channel codes to model the thermal-chemical behaviour of a candu fuel channel during accident conditions. the experiments were specifically designed to observe the exothermic zirconium-steam reaction. the analysis of the first experiment led to the question of flow distribution (subchannel-mixing) within the experimental bundle. the experimental bundle contained spacer plates along its length to maintain the bundle geometry throughout the experiment. the spacer plates constricted the flow in some subchannels thus forcing cross flow and mixing between adjacent subchannels. knowledge of the amount of subchannel steam cross flow is important for accurate predictions of hydrogen production from the zr-steam reaction during the experiment. the chan flow characterization facility (cfcf) was constructed to assist in understanding the influence of the spacer plates on the flow patterns within the experimental fuel channel. the 28-element bundle geometry allowed observation of flow patterns in less than half the bundle subchannels, therefore, the overall flow patterns within the bundle could not be determined without the aid of a modelling tool. the assert-pv (version-2 revision-6 modification-mod125) subchannel code was used as a tool to assist in the understanding of the overall flow patterns in the facility. this technical note describes the cfcf and the assert-pv model of the facility. it documents measurments taken in configuration 1 of the facility and compares assert-pv estimates to those measurements. assert-pv predictions of the flow patterns that exist in the chan experiments are presented and a recommendation for the use of a "partial-mixed" flow mixing assumption is made.
Author : J. T. Rodgers
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book A model for thermal analysis of a CANDU fuel channel following a LOCA with delayed ECC flow written by J. T. Rodgers and published by . This book was released on 1978 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : G. E. Gillespie
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Thermal behaviour of a CANDU-phw reactor fuel channel containing nearly stagnant steam written by G. E. Gillespie and published by . This book was released on 1982 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Ahmet Durmayaz
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (85 download)
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.
Author : P. M. Mathew
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Thermal conductivity of CANDU steam generator tubing alloys written by P. M. Mathew and published by . This book was released on 1997 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.
Author :
Publisher :
ISBN 13 :
Total Pages : 346 pages
Book Rating : 4.3/5 (91 download)
Download or read book INIS Atomindeks written by and published by . This book was released on 1995 with total page 346 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : V. Q. Tang
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Chan ii : a computer program predicting fuel channel thermal behavior in a typical CANDU- phw reactor core following a loss-of-coolant accident written by V. Q. Tang and published by . This book was released on 1981 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : M. B. Carver
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Application of the assert subchannel code to variations in fuel channel geometry and flux profiles written by M. B. Carver and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. J. Dutton
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Chanmod - a simple dynamic model of a CANDU-phw fuel channel written by R. J. Dutton and published by . This book was released on 1985 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : E. J. Muller
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Technical specification : fuel channel installation requirements, qinshan CANDU project, units 1 and 2 written by E. J. Muller and published by . This book was released on 1998 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : V. S. Krishnan
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Stability of natural-circulation flow in a CANDU-type fuel channel written by V. S. Krishnan and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Chf and post-chf tests were performed in water at 9.7 mpa using two vertical test assemblies having identical, internally heated annular flow channels, one heated directly, the other indirectly. experiments were conducted to determine the effect of the characteristics of these methods of heating on chf and post-chf heat transfer. for the range of the test conditions investigated, the results show that the direct and indirect heaters have similar chf performance. at heat fluxes above chf and mass fluxes of 2.0 and 3.5 mg.s sup(-1).m sup(-2), the indicated maximum wall temperatures of the heaters were similar, but at the highest mass flux of the tests, 5.0 mg.s sup(-1).m sup(-2), the indrrect heater had lower indicated maximum wall temperatures than the direct heater for a given heat flux above chf. a chf prediction method for vertical annuli based on a two-phase annular flow theory is presented. this model, which considers droplet entrainment, deposition and evaporation in the annular flow regime, assumes dryout to occur when the liquid film flow on the inner rod approaches zero. the chf predictions were in good agreement with the experimental results. in general, the model under-predicted chf at low inlet subcoolings and over-predicted chf at high inlet subcoolings. the error trend is consistent with that of the chf prediction models of other researchers.
Author :
Publisher :
ISBN 13 :
Total Pages : 1180 pages
Book Rating : 4.:/5 (89 download)
Download or read book Government Reports Announcements & Index written by and published by . This book was released on 1987 with total page 1180 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : J. C. Kiteley
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Application of the assert-4 subchannel code to a CANDU-PHWR pressure tube break scenario written by J. C. Kiteley and published by . This book was released on 1988 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : T. Qian
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Response-time requirements for resistance temperature detectors in CANDU stations written by T. Qian and published by . This book was released on 1997 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.
Author : Daniel Morgan
Publisher :
ISBN 13 :
Total Pages : 191 pages
Book Rating : 4.:/5 (661 download)
Download or read book A Thermomechanical Model of CANDU Fuel written by Daniel Morgan and published by . This book was released on 2007 with total page 191 pages. Available in PDF, EPUB and Kindle. Book excerpt: A fundamental code for predicting CANDU nuclear fuel thermomechanical behaviour in normal operating conditions was developed with the use of the Comsol Multiphysics finite element modelling environment. The code predicts the thermal response of the fuel, fuel thermal expansion, irradiation-induced densification, fission product swelling, fission gas release, and elastic and plastic deformation of the fuel and cladding. The evolution of the fuel-to-clad gap was predicted using the overall deformation of the fuel and sheath. The code was able to predict the behaviour of fuel under normal operating conditions and has been benchmarked against the industry-standard ELESTRES-IST fuel performance code.
Author : Z. Bilanovic
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Electron energy deposition in CANDU reactor fuel channels : a modelling study using mcnp and sandyl computer codes written by Z. Bilanovic and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
