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Title: OPERATION AND ANALYSIS OF A 3000 KW LIWUID METAL MODEL STEAM GENERATOR

Abstract

A 3000-kw(thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania under the cognizance of Atomics International. The steam generator was fabricated of 2-1/4%Cr -- l%Mo steel and consisted of an evaporator, moisture separator, and superheater. Two configurations of the steam generator were tested and each was tested in a different portion of the teat program. The first configuration included a superheater and a natural- circulation evaporator, and was tested mainly to demonstrate the practicality of designing and operating a liquid sodium-heated stea m generator. The second configuration tested incorporated the sa me superheatsr and evaporator heat transfer tube bundle, but a new "kettle" type evaporator shell with integral moisture eliminator and a new evaporator core tube bundle were installed. The second configuration was tested mainly for the purpose of proving the feasibility of the design for application to similar fullscale steam generators for the Hallun Nuclear Power Facility, each of 84,500 kw(thermal) capacity. A two-tube model superheater of 5%Cr--1/2%Mo and a trace of Ti in the heat transfer tubing was also installed and testsd in the loop during the test program of the second configuration of the modelmore » steam generator. It was tested mainly for the purpose of evaluating this material for superheater application. Both configurations were operated at steady state and various transient conditions during their respective teat programs. The cumulative operating time totaled 8451 hours, 4926 hours of which were applicable to the testing of the natural-circulation unit and the remainder to the kettletype unit. Over-all heat transfer coefficients determined by analysis of the model steam generator on an analog computer ranged from 1032 Btu/hr- deg F-ft/sup 2/ at startup to 850 Btu/ hr- deg F-ft/sup 2/ at the end of the operating period for the naturalcirculation unit. The heat transfer coefficient at startup for the kettle-type unit could not be readily determined due to a thermocouple fault during initial operations. It was, however, estimated to be approximately 860 Btu/hr- deg F-ft/sup 2/ at startup. The coefficient decreased to nominally 755 Btu/ cients were also determined using the analytical techniques as applied to the natural-circulation unit. The superheater heat transfer coefficient at startup was 206.5 Btu/hr- deg F-ft/sup 2/ and was obseved at the end of 8541 hours of operation to be approximately 170 Btu/hr- deg F-ft/sup 2/ with a minimum at one point of approximately 100 Btu/hr- ft/sup 2/ due to excessive carryover of boiler water solids. Except for a steam- tothird-fluid leak attributed to a manufacturing error, which occurred 250 hours after initial startup, the integrity of the steam generator was maintained throughout the test program without incident. The two-tube model superheater was removed from the test loop after 2460 hours of operation and examined. No deleterious effects were found. Operating problems with respect to the steam generator were virtually non-existent except for excessive pressure drops that occurred on the steam side of the superheater. These excessive pressure drops were attributed to carried-over boiler water solids which deposited in the superheater, eventuaily causing the flow passages to become plugged. This problem was eliminated in the latter stages of the test program by changing the boiler water treatment from solid chemicals to volatile chemicals using hydrazine and morpholine. (auth)« less

Authors:
Publication Date:
Research Org.:
Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
OSTI Identifier:
4049000
Report Number(s):
NAA-SR-4884
NSA Number:
NSA-15-015282
DOE Contract Number:  
AT(11-1)-GEN-8
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ANALOG SYSTEMS; CHROMIUM ALLOYS; COMPUTERS; CONFIGURATION; GENERATORS; HEAT TRANSFER; HNPF; LIQUID METALS; MOLYBDENUM ALLOYS; POWER; SODIUM; STAINLESS STEELS; STEAM; SUPERHEATING; TESTING; TITANIUM; TUBES

Citation Formats

Webster, L.J. ed. OPERATION AND ANALYSIS OF A 3000 KW LIWUID METAL MODEL STEAM GENERATOR. United States: N. p., 1961. Web.
Webster, L.J. ed. OPERATION AND ANALYSIS OF A 3000 KW LIWUID METAL MODEL STEAM GENERATOR. United States.
Webster, L.J. ed. 1961. "OPERATION AND ANALYSIS OF A 3000 KW LIWUID METAL MODEL STEAM GENERATOR". United States.
@article{osti_4049000,
title = {OPERATION AND ANALYSIS OF A 3000 KW LIWUID METAL MODEL STEAM GENERATOR},
author = {Webster, L.J. ed.},
abstractNote = {A 3000-kw(thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania under the cognizance of Atomics International. The steam generator was fabricated of 2-1/4%Cr -- l%Mo steel and consisted of an evaporator, moisture separator, and superheater. Two configurations of the steam generator were tested and each was tested in a different portion of the teat program. The first configuration included a superheater and a natural- circulation evaporator, and was tested mainly to demonstrate the practicality of designing and operating a liquid sodium-heated stea m generator. The second configuration tested incorporated the sa me superheatsr and evaporator heat transfer tube bundle, but a new "kettle" type evaporator shell with integral moisture eliminator and a new evaporator core tube bundle were installed. The second configuration was tested mainly for the purpose of proving the feasibility of the design for application to similar fullscale steam generators for the Hallun Nuclear Power Facility, each of 84,500 kw(thermal) capacity. A two-tube model superheater of 5%Cr--1/2%Mo and a trace of Ti in the heat transfer tubing was also installed and testsd in the loop during the test program of the second configuration of the model steam generator. It was tested mainly for the purpose of evaluating this material for superheater application. Both configurations were operated at steady state and various transient conditions during their respective teat programs. The cumulative operating time totaled 8451 hours, 4926 hours of which were applicable to the testing of the natural-circulation unit and the remainder to the kettletype unit. Over-all heat transfer coefficients determined by analysis of the model steam generator on an analog computer ranged from 1032 Btu/hr- deg F-ft/sup 2/ at startup to 850 Btu/ hr- deg F-ft/sup 2/ at the end of the operating period for the naturalcirculation unit. The heat transfer coefficient at startup for the kettle-type unit could not be readily determined due to a thermocouple fault during initial operations. It was, however, estimated to be approximately 860 Btu/hr- deg F-ft/sup 2/ at startup. The coefficient decreased to nominally 755 Btu/ cients were also determined using the analytical techniques as applied to the natural-circulation unit. The superheater heat transfer coefficient at startup was 206.5 Btu/hr- deg F-ft/sup 2/ and was obseved at the end of 8541 hours of operation to be approximately 170 Btu/hr- deg F-ft/sup 2/ with a minimum at one point of approximately 100 Btu/hr- ft/sup 2/ due to excessive carryover of boiler water solids. Except for a steam- tothird-fluid leak attributed to a manufacturing error, which occurred 250 hours after initial startup, the integrity of the steam generator was maintained throughout the test program without incident. The two-tube model superheater was removed from the test loop after 2460 hours of operation and examined. No deleterious effects were found. Operating problems with respect to the steam generator were virtually non-existent except for excessive pressure drops that occurred on the steam side of the superheater. These excessive pressure drops were attributed to carried-over boiler water solids which deposited in the superheater, eventuaily causing the flow passages to become plugged. This problem was eliminated in the latter stages of the test program by changing the boiler water treatment from solid chemicals to volatile chemicals using hydrazine and morpholine. (auth)},
doi = {},
url = {https://www.osti.gov/biblio/4049000}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {2}
}

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