scholarly journals 30 MEGAWATT HEAT EXCHANGER AND STEAM GENERATOR FOR SODIUM COOLED REACTOR SYSTEM. VOLUME III. MATERIAL AND WELDING SPECIFICATIONS

1962 ◽  
Author(s):  
Not Given Author
Keyword(s):  
Heat Exchanger ◽  
Steam Generator ◽  
Reactor System ◽  
System Volume

ASME Section III Stress Analysis of a Heat Exchanger Tubesheet With a Misdrilled Hole and Irregular or Thin Ligaments

2013 ◽  
Author(s):  
Enrique Gomez ◽  
Roberto Ruiz ◽  
Robert M. (Con) Wilson
Keyword(s):  
Heat Exchanger ◽  
Stress Analysis ◽  
Steam Generator ◽  
Companion Paper ◽  
Flat Plates

A stress analysis is described for a nuclear steam generator tubesheet with a thin or irregular ligament associated with a mis-drilled hole using the rules of ASME B&PV Section III and Non-Mandatory Appendix A, Article A-8000 for Stresses in Perforated Flat Plates. The analysis demonstrates the proper application of the NB-3200 rules for this special application with discussion of the differences between an actual tube hole deviation from what is assumed in ASME Appendix A. This is a companion paper to “Technical Justification Supporting Operation with a Tube Installed in a Mis-Drilled Hole of a Steam Generator Tubesheet”.

Eliminating Thermoacoustic Oscillations in Heat Exchanger and Steam Generator Systems

1999 ◽  
Vol 121 (4) ◽  
pp. 444-452 ◽  
Author(s):  
F. L. Eisinger
Keyword(s):  
Heat Exchanger ◽  
Temperature Gradient ◽  
Steam Generator ◽  
Critical Value ◽  
Duct Systems ◽  
Furnace Burner ◽  
Thermoacoustic Oscillations

Systems comprised of hot and cold components containing gaseous fluids may be subject to thermoacoustic oscillations if the temperature gradient between the two components exceeds a critical value. An evaluation of the Sondhauss-type and the Rijke-type thermoacoustic oscillations in combined turbine/heat exchanger/duct systems and furnace/burner systems will be presented. Parameters which will reduce or eliminate the likelihood of thermoacoustic oscillations in such systems are identified and discussed in this paper.

Natural Circulation and Creep Damage Analyses of Severe Accident for a Typical PWR Plant

2009 ◽  
Author(s):  
Osamu Kawabata ◽  
Masao Ogino
Keyword(s):  
Steam Generator ◽  
Natural Circulation ◽  
Reactor Core ◽  
Creep Damage ◽  
Reactor Vessel ◽  
Reactor System ◽  
Severe Accident ◽  
Steam Generator Tube ◽  
Hot Gas ◽  
Core Meltdown

When the primary reactor system remain pressurized during core meltdown for a typical PWR plant, loop seals formed in the primary reactor system would lead to natural circulations in hot leg and steam generator. In this case, the hot gas released from the reactor core moves to a steam generator, and a steam generator tube would be failed with cumulative creep damage. From such phenomena, a high-pressure scenario during core meltdown may lead to large release of fission products to the environment. In the present study, natural circulation and creep damage in the primary reactor system accompanying the hot gas generation in the reactor core were discussed and the combining analysis with MELCOR and FLUENT codes were performed to examine the natural circulation behavior. For a typical 4 loop PWR plant, MELCOR code which can analyze for the severe accident progression was applied to the accident analyses from accident initiation to reactor vessel failure for the accident sequence of the main steam pipe break which is maintained at high pressure during core meltdown. In addition, using the CFD code FLUENT, fluid dynamics in the reactor vessel plenum, hot leg and steam generator of one loop were simulated with three-dimensional coordinates. And the hot gas natural circulation flow and the heat transfer to adjoining structures were analyzed using results provided by the MELCOR code as boundary conditions. The both ratios of the natural circulation flow calculated in the hot leg and the steam generator using MELCOR code and FLUENT code were obtained to be about 2 (two). And using analytical results of thermal hydraulic analysis with both codes, creep damage analysis at hottest temperature points of steam generator tube and hot leg were carried out. The results in both cases showed that a steam generator tube would be failed with creep rupture earlier than that of hot leg rupture.

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