Dynamic stability experimental/analytical program results on a multiple tube sodium heated steam generator model employing double wall tubes. [LMFBR]
Experimental results are described of a test program which induced water/steam dynamic instability in the multiple tube circuits of a sodium heated, double-wall tube, steam generator model whose water/steam side is designed to operate under once-through conditions with exit superheat (457/sup 0/C/855/sup 0/F; 15.8 MPa/2290 psia). The instability thresholds were determined experimentally with off-nominal operation in order to establish the stability margin that exists with and without the damping orifice configuration employed at the inlet of each tube circuit. Two classes of experiments were performed; one with low magnitudes of water/steam mass velocity resulting in high exit superheat (Benson Cycle), and the other with high magnitudes of mass velocity and no bulk exit steam superheat (Sulzer Cycle). Analytical prediction of the instability inception conditions were compared with experiment and are included along with an evaluation of the applicability of the analysis method to plant scale stability evaluations.
- Research Organization:
- Westinghouse Electric Corp., Pensacola, FL (USA). Nuclear Components Div.
- DOE Contract Number:
- AC02-77ET37201
- OSTI ID:
- 5584739
- Report Number(s):
- CONF-831111-10; ON: DE84002738
- Resource Relation:
- Conference: ASME winter annual meeting, Boston, MA, USA, 13 Nov 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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