Published 1977 | Version v1
Report Restricted

PTA-1 computer program for treating pressure transients in hydraulic networks including the effect of pipe plasticity

Description

Pressure pulses in the intermediate sodium system of a liquid-metal-cooled fast breeder reactor, such as may originate from a sodium/water reaction in a steam generator, are propagated through the complex sodium piping network to system components such as the pump and intermediate heat exchanger. To assess the effects of such pulses on continued reliable operation of these components and to contribute to system designs which result in the mitigation of these effects, Pressure Transient Analysis (PTA) computer codes are being developed for accurately computing the transmission of pressure pulses through a complicated fluid transport system, consisting of piping, fittings and junctions, and components. PTA-1 provides an extension of the well-accepted and verified fluid hammer formulation for computing hydraulic transients in elastic or rigid piping systems to include plastic deformation effects. The accuracy of the modeling of pipe plasticity effects on transient propagation has been validated using results from two sets of Stanford Research Institute experiments. Validation of PTA-1 using the latter set of experiments is described briefly. The comparisons of PTA-1 computations with experiments show that (1) elastic-plastic deformation of LMFBR-type piping can have a significant qualitative and quantitative effect on pressure pulse propagation, even in simple systems; (2) classical fluid-hammer theory gives erroneous results when applied to situations where piping deforms plastically; and (3) the computational model incorporated in PTA-1 for predicting plastic deformation and its effect on transient propagation is accurate

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

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Additional details

Additional titles

Augmented title (English)
LMFBR

Publishing Information

Imprint Pagination
20 p.
Report number
CONF-770807--55

Conference

Title
4. international conference on structural mechanics in reactor technology.
Dates
15 - 19 Aug 1977.
Place
San Francisco, CA, USA.