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Dynamic stability experimental/analytical program results on a multiple tube sodium heated steam generator model employing double wall tubes. [LMFBR]

Description: 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.
Date: January 1, 1983
Creator: Efferding, L.E.
Partner: UNT Libraries Government Documents Department

Preliminary thermal/hydraulic sizing calculations for duplex tube evaporator/superheater (interchangeable units). Revision 1

Description: This is a preliminry thermal/hydraulic report reflecting work under Subtask 6.2 of Ref. 1.1. This report is an extension of the previous thermal/hydraulic design report. Parts of this report have been transmitted to GE. The detailed design basis, listed by source, is given. Additional details are discussed.
Date: June 1, 1974
Creator: Waszink, R.P.; Hwang, J.Y. & Efferding, L.E.
Partner: UNT Libraries Government Documents Department

Evaluation of exposure conditions for the water-side corrosion test of a sodium heated steam generator evaporator model employing a duplex tube (2160 hours at critical heat flux - phase III SSGM tests). [LMFBR]

Description: This report describes the specialized corrosion test water steam loop, test procedures, test conditions, and test results. A complete water chemistry and thermal hydraulic performance history is given and evaluated for the Phase III test program. The movement of the dryout location and the heat flux variations in pre- and post-critical heat flux regions are documented and analyzed. On seven occasions during the course of the test program to date, the operating conditions drifted from the CHF reference Phase III operation in the dryout regime into the DNB regime. The corresponding corrosion mechanism experienced differing exposure conditions on these occasions. CHF sensitivity to this apparent drift behavior is evaluated.
Date: December 1, 1975
Creator: Waszink, R.P.; Hwang, J.Y. & Efferding, L.E.
Partner: UNT Libraries Government Documents Department

Infrared scanning of Hanford waste tank S-110 and interpretation of surface temperature variation

Description: An infrared scanner and data interpretation method was developed and applied for surface temperature mapping of heat generating nuclear waste tanks. A surface temperature map of a non-watch list tank (110-S) was selected for demonstration purposes because it displayed an irregular salt cake surface and contained an operable thermocouple tree that displayed a subsurface temperature gradient. The infrared scanner hardware was successfully operated in a tank environment and necessary data was gathered for application of a proposed data mapping and evaluation method.
Date: May 1, 1994
Creator: Efferding, L. E.
Partner: UNT Libraries Government Documents Department

Mitigation of Tank 241-SY-101 by pump mixing: Results of testing phases A and B

Description: A spare mixing pump from the Hanford Grout Program was installed in Hanford double-shell waste Tank 241-SY-101 on July 3, 1993, after being modified to take advantage of waste stratification. It was anticipated that pump mixing would prevent large episodic flammable gas releases that had been occurring about every 100-150 days. A cautious initial test plan, called Phase A, was run to find how the pump and tank would behave in response to very brief and gentle pump operation. No large gas releases were triggered, and the pump performed well except for two incidents of nozzle plugging. On October 21, 1993, the next test series, Phase B, began, and the pump was applied more aggressively to mix the tank contents and mitigate uncontrolled gas releases. Orienting the pump in new directions released large volumes of gas and reduced the waste level to a near-record low. Results of the entire period from pump installation to the end of Phase B on December 17, 1993, are presented in detail in this document. Though long-term effects require further evaluation, we conclude from these data that the jet mixer pump is an effective means of controlling flammable gas release and that it has met the success criteria for mitigation in this tank.
Date: March 1, 1994
Creator: Allemann, R. T.; Antoniak, Z. I.; Chvala, W. D.; Friley, J. R.; Gregory, W. B.; Hudson, J. D. et al.
Partner: UNT Libraries Government Documents Department