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Title: Development, construction, and use of pneumometric tubes for measurement of steam flow in the steam lines of PVG-1000 at NPP

Abstract

A system for the direct measurement of steam flow in steam lines after a steam generator, which utilizes a special design of pneumometric tubes and a computing unit that accounts for variation in steam pressure, has been developed to improve the quality of water-level regulation in the steam generators of VVER-1000 power-generating units in the stationary and transitional modes. The advantage of the pneumometric tubes consists in their structural simplicity, high erosion resistance, and absence of irrevocable losses during measurement of steam flow. A similar measurement system is used at foreign NPP. The measurement system in question has been placed in experimental service at the No. 3 unit of the Balakovo NPP, and has demonstrated its worthiness. This measurement system can also be used to determine steam flow in the steam lines of NPP units with VVER-1000 and VVER-440 reactors, and PBMK-1000 power-generating units.

Authors:
; ; ;  [1]
  1. FGUP 'Elektrogorsk Scientific-Research Center for NPP Safety' (Russian Federation)
Publication Date:
OSTI Identifier:
21072450
Resource Type:
Journal Article
Resource Relation:
Journal Name: Power Technology and Engineering (Print); Journal Volume: 41; Journal Issue: 3; Other Information: DOI: 10.1007/s10749-007-0033-0; Copyright (c) 2007 Springer Science+Business Media, Inc; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; CONSTRUCTION; DESIGN; EROSION; NUCLEAR POWER PLANTS; STEAM; STEAM GENERATORS; STEAM LINES; TUBES; WATER; WWER TYPE REACTORS

Citation Formats

Gorbunov, Yu. S., Ageev, A. G., Vasil'eva, R. V., and Korol'kov, B. M. Development, construction, and use of pneumometric tubes for measurement of steam flow in the steam lines of PVG-1000 at NPP. United States: N. p., 2007. Web. doi:10.1007/S10749-007-0033-0.
Gorbunov, Yu. S., Ageev, A. G., Vasil'eva, R. V., & Korol'kov, B. M. Development, construction, and use of pneumometric tubes for measurement of steam flow in the steam lines of PVG-1000 at NPP. United States. doi:10.1007/S10749-007-0033-0.
Gorbunov, Yu. S., Ageev, A. G., Vasil'eva, R. V., and Korol'kov, B. M. Tue . "Development, construction, and use of pneumometric tubes for measurement of steam flow in the steam lines of PVG-1000 at NPP". United States. doi:10.1007/S10749-007-0033-0.
@article{osti_21072450,
title = {Development, construction, and use of pneumometric tubes for measurement of steam flow in the steam lines of PVG-1000 at NPP},
author = {Gorbunov, Yu. S. and Ageev, A. G. and Vasil'eva, R. V. and Korol'kov, B. M.},
abstractNote = {A system for the direct measurement of steam flow in steam lines after a steam generator, which utilizes a special design of pneumometric tubes and a computing unit that accounts for variation in steam pressure, has been developed to improve the quality of water-level regulation in the steam generators of VVER-1000 power-generating units in the stationary and transitional modes. The advantage of the pneumometric tubes consists in their structural simplicity, high erosion resistance, and absence of irrevocable losses during measurement of steam flow. A similar measurement system is used at foreign NPP. The measurement system in question has been placed in experimental service at the No. 3 unit of the Balakovo NPP, and has demonstrated its worthiness. This measurement system can also be used to determine steam flow in the steam lines of NPP units with VVER-1000 and VVER-440 reactors, and PBMK-1000 power-generating units.},
doi = {10.1007/S10749-007-0033-0},
journal = {Power Technology and Engineering (Print)},
number = 3,
volume = 41,
place = {United States},
year = {Tue May 15 00:00:00 EDT 2007},
month = {Tue May 15 00:00:00 EDT 2007}
}
  • In order to analyze the benefits of the multidimensional hydrodynamic modeling capability of the RELAP5-3D system code for the VVER-1000 nuclear power plant (NPP), a three-dimensional (3-D) model of the core, downcomer, and lower plenum has been created to replace the NPP one-dimensional (1-D) counterparts in a complete plant model. This multidimensional model has been validated with plant operational data and other computer simulations of a thermal-hydraulic transient. The simulated transient considered was a large-break loss-of-coolant accident (LB LOCA).A validated, 1-D control model of the NPP, for the study of the effects of mixed oxide fuel, was modified to includemore » a standard fuel loading of UO{sub 2}. The development of the 3-D sections of the reactor vessel consisted of ensuring geometrical fidelity with the design of the modeled plant, the Balakovo Unit 4 NPP in Saratov, Russia. A stable operational steady state was obtained and the calculated plant conditions compared well with the design values of the Balakovo plant. Transient results verified that the simulated thermal-hydraulic conditions of the multidimensional model agreed well with both the control and analyses that have been performed separately from this study.It was found that the multidimensional model has shown a reduction in the calculated hot-spot peak-clad temperature (PCT) during the blowdown stage of a LB LOCA and an increase in PCT during the reflood stage. A preliminary uncertainty analysis of the PCT during blowdown stage was performed using a response surface method of the Code Scaling, Applicability, and Uncertainty Method and a significant number of relevant input variables. From the preliminary analysis, the PCT reduction during blowdown appears to be significant, but a further, more detailed analysis should be performed, along with an uncertainty analysis of the PCT during the reflood stage.The enhanced depiction of the flow patterns and temperature distributions in the transient situation allowed the user further understanding of the thermal-hydraulic conditions throughout the transient. The developed model proved to be suitable for analysis of the VVER-1000 plant, but to further the applicability of the model, a 3-D kinetics model of the neutronics and 3-D hydrodynamic models of the horizontal steam generators should be included.« less
  • Experiments were performed to determine the feasibility of using Pitot tubes for mass velocity measurements in steam-water flow. Such measurements are of interest in reactor safety studies. Results indicate that mass velocities calculated from the data adequately predict the actual mass velocities over the range studied.
  • An experimental heat-exchanger-type steam reformer containing eight full-sized tubes of catalyst was operated at low steam/carbon ratios up to the point of onset of carbon deposition. The following phenomena were investigated: the effect of carbon deposition on the distribution of the gas stream among the tubes, the effect of this distribution on the nonuniformity of temperature on the outer surface of the tubes, and the distribution of carbon deposition in the beds of catalyst. At steam/carbon ratios close to the onset of carbon deposition, the average pressure differential through the tubes rose at a rate of 0.1-0.5 kg/cm/sup 2/ .more » hr. The temperature at the bottom of the catalyst tubes varied about 10 /sup 0/C due to the deposition of carbon. Most of the carbon is deposited within about 1,000 mm from the top of the bed.« less