LM Boiling Review

8/8/2019 LM Boiling Review

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HIGH-TEMPERATURE L IQUID-METAL TECHNOLOGY REVIEW

A B i m o n t h l y T e c h n i c a l P ro g re s s R e v i e w

PREPARED UNDER THE AUSPICES OF SPECIAL TECHNOLOGY BRANCH,DIVISION OF REACTOR DEVELOPMENT AND TECHNOLOGY, USAEC

VOLUME 7 . NUMBER 1 FEBRUARY 1969

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B R O O K H A V E N N A T I O N A L L A B O R A T O R YA S S O C I A T E D U N I V E R S I T I E S , I N C

under contract w ith theUNITED STATES ATOMIC ENERGY COMMISSION


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DISCLAIMER

This report was prepared as an account of work sponsored by anagency of the United States Government. Neither the United StatesGovernment nor any agency Thereof, nor any of their employees,makes any warranty, express or implied, or assumes any legalliability or responsibility for the accuracy, completeness, orusefulness of any information, apparatus, product, or processdisclosed, or represents that its use would not infringe privatelyowned rights. Reference herein to any specific commercial product,process, or service by trade name, trademark, manufacturer, orotherwise does not necessarily constitute or imply its endorsement,recommendation, or favoring by the United States Government or anyagency thereof. The views and opinions of authors expressed hereindo not necessarily state or reflect those of the United StatesGovernment or any agency thereof.


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DISCLAIMER

Portions of this document may be illegible inelectronic image products. Images are producedfrom the best available original document.


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BNL 50170 (PR-37)(Propulsion Systems and Energy Conversion - TID-4500)

HIGH-TEMPERATURE LIQUID-METAL TECHNOLOGY REVIEW

A B im on th ly Techn ica l Progress R ev iew

P R E P A R E D U N D E R T H E A U S P I C E S O F S P E C IA L T E C H N O L O G Y B R A N C H ,D I V I S I O N O F R E A C T O R D E V E L O P M E N T A N D T E C H N O L O G Y , USAEC

V O L U M E 7 N U M B E R 1 F E B R U A R Y 1 9 6 9

L E G A L N O T I C EThis repor t was prepared as an account of Government sponsored work. N either the UnitedStates, nor the Commission, nor any person acting on behalf of the Commission:A, M akes any warrant y or representation , expressed or implied, with respect to the accu racy, completeness, or usefulness of the Information contained in this report, or that the useof any information, a pparatus, method, or proce ss disclosed in this repo rt may not infringeprivately owned rights; orB . Assum es any liabilities with respect to the use of, or lor damages resultin g from theuse of any information, apparatus, method, or process disclosed in this report.As used in the above, "perso n acting on behalf of the Com missio n" includes any e mployee or con tractor of the Commission, or employee of such co ntracto r, to the extent thatsuch employee or contractor of the Commission, or employee of such contractor prepares,dissem inates, or provides access to, any information pursuant to his employment or contractwith the Commission, or his employment with such contractor.

B R O O K H A V E N N A T I O N A L L A B O R A T O R YU P T O N , N E W Y O R K 1 1 9 7 3

STRIBUTION C IHIi UQCUWitNJ * UNU.


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L E G A L N O T I C EThis report was prepared as an account of Gov ernmen t sponsored work Neither theUnited States, nor the Commission, nor any pe rson ac ting on behalf of the CommissionA Mak es any w arran ty or representation, expressed or implied, with respect to theaccuracy, completeness, or usefulness of the information contained in this report, orthat the use of any information, app aratu s, meth od, or process disclosed in this reportmay no t infringe privately owned rights, orB Assumes a ny liabilities with respect to the use of, or for dam ages resulting fromthe use of any information, apparatus, method, or process disclosed in this reportAs used in the ab ove, "person acting on beh alf of the Com mission" includes any em ployee or contra ctor of the Commission, or employee of such contractor, to the extentthat such employee or contractor of the Commission, or employee of such contractorprepare s, disseminates, or provides access to, any information pursua nt to his employment or contract with the Commission, or his employment with such contractor

Pr in ted in the Uni t ed S ta t es o f Amer icaAvai l ab le f rom

C lear inghous e fo r Federa l Sc ien t i f i c and Techn ica l I n fo rmat ionN a t i o n a l B u r e a u o f S t a n d a r d s , U S D e p a r t m e n t o f C o m m e r c eSprmgf ie ld , Vi rg in ia 22151P r i c e I n d i v i d u a l P r i n t e d C o p y , | 3 0 0 , I n d i v i d u a l M i c r o f i c h eC o p y , SO 6 5 , A n n u a l S u b s c r i p t i o n R a t e f or P r i n t e d C o p i e s ,$15 00, Back Issues , $3 00 per copy


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FOREWORDThe purpose of the Hiqh-Temperature Liquid-Metal Technology Review is to provide up-to-date information on the various research and development programs in the United States in

the field of high-temperature liquid-metal technology. Themethod is to publish reviews prepared by members of the Department of Applied Science of the Brookhaven National Laboratoryon current topical and progress reports svibmitted by contracting organizations. When results and conclusions are reported,it is intended that the individual reviews become both summaries and critiques.The organizations currently submitting reports are thoseoperating under AEG, NASA, and Air Force contracts. A listof these organizations is given in the Appendix.The Review covers all phases of high-temperature liquid-metal technology, including materials development, corrosionand mass transfer, heat transfer, fluid dynamics, instrumentation, purification, component development, physical properties,thermodynamics, chemical analysis, and power systems. Thistype of information is pertinent to the AEG's fast breederdevelopment program and to the development of nuclear-Rankinepower systems for space vehicles.Monthly progress reports, owing to the usually small amountof new information contained in them, do not always receive individual treatment. The information in two or more such reportsis usually combined into a single review.Whenever an author feels that his report was not adequatelyor correctly represented in the Review, we would like to hearfrom him and would be happy to publish his letter in the nextissue, if he so wishes.Those organizations which regularly submit reports forcoverage in the Review automatically receive courtesy copiesof it directly from Brookhaven on date of issuance. All otherorganizations are required to follow the usual procedure ofsubscribing for them from the Clearinghouse for Federal Scientific and Technical Information, National Bureau of Standards,U. S. Department of Commerce, Springfield, Virginia.

O. E. DwyerTechnical Editor

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HIGH-TEMPERATURE LIQUID-METAL TECHNOLOGY REVIEWSUBJECT INDEX(Arabic numerals used below refer to review numbers)Physical Properties and Thermodynamics

798, 800Fluid Dynamics

799, 808Heat Transfer

798, 808, 810Materials Development, Corrosion, and Erosion

798, 799, 803, 810, 811Instrumentation

797, 799, 810, 8 12, 813Component Development

799, 801, 804, 805, 806, 8 07, 810System Studies .

810Chemistry and Chemical Analysis

798, 803, 809Fabrication Techniques

noneSafety

noneComponent Design

801

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TABLE OF CONTENTSReview No. Title Page

797 ULTRASONIC INSTRUMENTATION FOR DETECTION OF 1INCIPIENT BOILING IN LIQUID METALS, AeroprojectsIncorporated, West Chester, Penna., NYO-3622-20,July 1968

798 ARGONNE NATIONAL LABORATORY REACTOR DEVELOPMENT 2PROGRAM PROGRESS REPORT, Argonne National Laboratory, Argonne, Illinois, ANL-7527 , December19687 99 ARGONNE NATIONAL LABORATORY REACTOR DEVELOPMENT 4

PROGRAM PROGRESS REPORT, Argonne National Laboratory, Argonne, Illinois, ANL-7548 , January 1969800 THE SOLUBILITY OF OXYGEN IN LIQUID SODIUM: A 7RECOMMENDED EXPRESSION, Atomics International,Canoga Park, Calif., AI-AEC-12685, Nov. 1, 1968801 SODIUM TO STEAM HEAT EXCHANGER ELEMENTS AND 8RESEARCH Prelimin ary Steam Generator ConceptSelection Study, The Babcock & Wilcox Co ., Bar-berton, Ohio, BAW-1280-55, August 5, 1968802 BELLOWS SEALS FOR LIQUID METAL SYST EMS LITE RA- 9TURE SEARCH FOR FABRICATION AND OPERATIONAL EXPERIENCE, Battelle Memorial Institute, Richland,

Washington, BNWL-905, November 1968803 ANNUAL PROGRESS REPORT OF THE WORK SPONSORED BY 10THE SODIUM TECHNOLOGY AND THE FUELS AND MATERIALSBRANCHES, Brookhaven National Laboratory, Upton,

N.Y., BNL 50161 (T-526) for the report period ofJan. 1 to Dec. 31, 1968804 Space Programs Siommary 37-54, Vol. IllSU PPORT- 14ING RESEARCH AND ADVANCED DEVELOPMENT, Jet Propulsion Laboratory, Pasadena, Calif., 37-54, Vol. Ill,December 3 1, 1968805 LIQUID METAL ENGINEERING CENTER SEMIANNUAL TECHNI- 14GAL PROGRESS REPORT, Liquid Metal EngineeringCenter, Canoga Park, Calif.

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TABLE OF CONTENTSReview No. Title Page

806 AN ANALYTICAL AND EXPERIMENTAL INVESTIGATION OF 16TtJRBULENT FLOW IN BEARING FILMS, INCLUDING CON-VECTIVE FLUID INERTIA FORCES, Mechanical Technology Inc., Latham, New York, NYO-3930-2 andMTI-68TR80, Dec. 1968

807 LIQUID METAL BEARINGS TECHNOLOGY FOR LARGE, HIGH 17TEMPERATURE, SODIUM ROTATING MACHINERY, Mechanical Technology Inc., Latham, N. Y., NYO 3930-3and MTI-69TR1, Jan. 1969

808 STUDY OF THERMO-HYDRAULIC OSCILLATIONS IN BOIL- 18ING SYSTEMS EMPLOYING LIQUID METAL WORKINGFLUIDS, Mechanical Technology Inc., Latham, N.Y.,Tenth, Eleventh and Twelfth Monthly LetterProgress Reports, Nov., Dec. 1968 and Jan. 1969809 EVALUATION OF THE RESULTS OF A ROUND ROBIN ANALY- 19SIS FOR OXYGEN IN POTASSIUM AND SODIUM, LewisResearch Center, Cleveland, Ohio, NASA TN D-4971,December 1968810 SUMMARY OF IN-HOUSE LIQUID-METALS INVESTIGATIONS, 20Lewis Research Center, Cleveland, Ohio, Jan. 1968to March 1969811 NIOBIUM - 1% ZIRCONIUM BOILING-POTASSIUM FORCED- 26CIRCULATION LOOP TEST, Oak Ridge National Laboratory, Oak Ridge, Tenn., ORNL-4301, Dec. 1968812 ULTRASONIC THERMOMETRY FOR LMFBR SYS TEM SP has e I 27Report, Panametrics, Waltham, Mass., NYO-3906-4,Sept. 1968813 ULTRASONIC THERMOMETRY IN LMFBR SYSTEMS, Pana- 29metrics, Waltham, Mass., NYO-3906-5, Dec. 1968

Appendix AOrganizations Having Reports as Indi- 44cated by Review Numbers Covered in This and PreviousIssues of the Review

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REVIEW NO. 797ULTRASONIC INSTRUMENTATION FOR DETECTIONOF INCIPIENT BOILING IN LIQUID METALS

Sponsor: U. S. Atomic Energy CommissionContractor: Aeroprojects Incorporated, West Chester, Penna.Contract No.: AT(30-1)-3622Report No. : NYO-3622-20Report By: Herbert KartlukeReport Date: July 1968Reviews for Previous Two Years: 599,640,696,768,782This report describes the development of an instrument,based on ultrasonic principles for indicating the proximity toboiling in liquid-metal systems. The method is based on theprinciple that the acoustic power required to produce cavitationin the liquid decreases as the boiling condition is approached.

The instrument must therefore (a) deliver, through the liquidmetal containment, ultrasonic power to the liquid, (b) measurethis power, and (c) detect the start of cavitation.The acoustic conductors are inserted through the walls ofthe containment vessel by means of a hermetically sealable flange-type acoustic isolation mount. This mount was apparently developed by the contractor as part of an earlier effort that involvedthe development of an ultrasonic device for the detection ofincipient boiling in pressurized water systems.Initial experimental work in a static potassium system was

performed by the contractor at Oak Ridge. Subsequent work wasdone in both a static potassium cell and in a flowing sodiumsystem at the Mine Safety Appliance Research Corporation. Resultsin all cases verified that the acoustic power required to producecavitation decreased as the boiling condition was approached.However, tests in the flowing system exhibited less scatter, presumably because of improved thermal uniformity.The ultrasonic generator and the associated instrumentation are fully described in the report.The instrument described in this report measures the ultrasonic power required to initiate cavitation. It would seem that

the device is just another means for measuring subcooling, butit will not measure the superheat required to initiate boilingin its absence. It would appear that the primary effect of its


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presence in a system would be to minimize the superheat requiredto initiate boiling. In fact, it has been reported(1) that asimilar instrument was used to initiate and maintain stable boiling in potassium under conditions that normally produced liquidsuperheating and unstable and explosive boiling. A device ofthis sort might also have utility as a safety feature in a non-boiling system in that if the boiling point were accidentallyreached, boiling would be initiated with little or no superheat,thereby minimizing its effect.

In summing up, this reviewer feels that the device describedin this report cannot fulfill the function it was designed forany better than a pressure gage and thermocouple. However, itappears that it might possibly be useful for the applicationsdescribed above.(S. Kalish)

REVIEW NO. 798ARGONNE NATIONAL LABORATORYREACTOR DEVELOPMENT PROGRAM PROGRESS REPORT

Sponsor: U. S. Atomic Energy CommissionContractor: Argonne National Laboratory, Argonne, IllinoisContract No.: W-31-109-Eng-38Report No.: ANL-7527Report Coordinated By: L. B. Fosdick and A. GlassnerReport Date: December 1968Reviews for Previous Two Years: 584,585,600,601,602,623,624,644,645,662,663,681,682,697,699,700,719,720,737,738,757,758,771,772,783

(1) M. M. Yarosh - An Experiment Employing Ultrasonic Energyto Promote Boiling in Liquid Metals, Paper IIb-2 in Proceedings of the International Conference on the Safety of FastReactorsSept. 19-22, 1967. Edited by G. Denielou, Cada-rache, France.


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Influence of Dissolved Cesium, Antimony, Rubidium, and Gold inSodium on the Corrosion Behavior of Austenitic Stainless Steelp. 79)

Radioactive isotopes of these solute elements have beensuggested for use in the bond sodium of fuel elements in a sodium-cooled reactor to enable rapid detection of a cladding rupture.Capsules of type 304L stainless steel were loaded with 5- and10-mil-thick samples of the same material and reactor gradesodium containing 2% of either high-purity G s, Sb, Rb, or Au.The samples were then held at 650 G (in a rotating assembly)for 500 hr .

After testing, analysis showed that the sodium contained


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titration, indicating that a sodium compound (unaffected by thevariation in cold-trap temperature) was present in the residuewhich was not detectable by titration.Corrosion Inhibition by Dissolved Getters in Liquid Sodium (p. 104)

Dissolved getters in sodium are being investigated as ameans of controlling the oxygen activity. For example, CaO ismore stable than Na20, and consequently the Na-O-Ca system isbeing studied to determine its equilibrium free energy relationships. The apparatus for this work is under construction.Carbon Determination in Sodiimi (p. 104)

"A dry-combustion apparatus for the analysis of total carbon in sodium is being constructed. The method involves conversion of all the carbon in the sample to CO2 and analyzing theevolved gas by chromatography."I n c i p i e n t - B o i l i n g S u p e r h e a t s i n Na ( p . 128)

Pool-boiling experiments have indicated that an increase inoxygen content of the sodium slightly decreases the incipient-boiling superheat. Also, a theoretical study has indicated thatan increase in heat flux can produce either a decrease or increasein the incipient-boiling superheat, depending on the sequence ofevents between experimental runs as they affect inert-gas diffusion from the active cavities. No numbers are given, but atopical report will soon be issued on this work.(0. E. Dwyer)

Figure 1 in the Review corresponds to Figure III.B.l inthe original report.

REVIEW NO. 7 99ARGONNE NATIONAL LABORATORYREACTOR DEVELOPMENT PROGRAM PROGRESS REPORT

Sponsor: U. S. Atomic Energy CommissionContractor: Argonne National Laboratory, Argonne, IllinoisContract No. : W-31-109-Eng-38


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Report No.: ANL-7548Report Coordinated By: L. B. Fosdick and A. GlassnerReport Date: January 1969Reviews for Previous Two Years: 584,585,600,601,602,623,624,644,645,662,663,681,682,697,699,700,719,7 20,737,738,7 57,7 58,771,772,783,798

Effect of Temperature and Strain Rate on the Fracture Mode ofType 304 Stainless Steel (p. 78)"The fracture surfaces of tensile specimens of Type 304stainless steel were studied by means of optical microscopy todetermine the effect of temperature and strain rate on the transition point from transgranular to intergranular failure. Thespecimen material came from the same heat as that used in theEBR-II control-rod thimble currently undergoing postirradiationexamination at ANL. The tensile test's were conducted at tem

peratures of 22, 450, 550, 650, and 750C and at strain ratesof 1, 10, 100, and 1000%/min."Preliminary results indicate that specimen failure occursby transgranular fracture at all strain rates up to 100%/minand at temperatures below 550G. At these strain rates, evidenceof intergranular fracture begins to appear at about 550C, andat 7 50 C the failure is entirely due to intergranuld.r fracture.At the highest strain rate of 1000%/min, evidence of failureby intergranular fracture does not appear until 650G, and at7 50G failure is again entirely due to intergranular fracture.In all tests the specimen had sustained a true uniform strainof 15 % at the start of the transition from transgranular to intergranular fracture."These results suggest that the intergranular-type fracturecould occur at lower values of true uniform strain and at temperatures below 550 G: at strain rates in the creep range (e


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Development of an Acoustic Detector for Boiling Inception (p. 98)In this project, the major problem in developing a high-temperature sensor is that of bonding the lithium niobate ceramiccrystal to stainless steel. During the report period, the sur

faces of two Z-cut crystals were coated with an organic-vehiclemetallizer and fired in an oxygen furnace. One of these wasbrazed with Au-Ni alloy to the container diaphragm on the frontcrystal face and to a stainless-steel acoustic backing on therear crystal face. With it, an ultrasonic test signal waselectrically detectable. However; alternative bonding methodsare also being investigated.Electron-Bombardment Heater Development (p. 101)

Fig. 2 shows the 7-pin electron-bombardment heater and theassociated test section that is being tested. Its operationhas been hindered by mechanical problems associated with theattachment of the thoriated-tungsten filaments to the electrodes,and steps are being taken that will presumably eliminate theproblem.

A second type of heater arrangement is being designed inwhich the pins are 1/4 in. in diameter rather than 3/8 in. and36 in. long rather than 24. Also, these new pins will havesingle filaments instead of double filaments.Liquid Fraction in Two-Phase Flow of Na (p. 117)

Liquid-fraction measurements were made for adiabatic two-phase flow of Na produced in a Na-flashing facility. The average liquid velocity in the two-phase region was measured withan electromagnetic flowmeter. Fig. 3 shows that the measurements agreed very well with the Lockhart-Martinelli correlationbased on air-water and steam-water data. The vapor quality, x,was calculated from the average liquid velocity data using atemperature obtained from the measured axial temperature profile. The agreement between the measured and predicted liquidvolume fractions shows once again that the hydrodynamic behaviorsof two-phase flows of liquid metals and ordinary liquids are .essentially the same. Similar results were observed by Baroczywith potassium.

(0. E. Dwyer)Figs. 2 and 3 in the Review correspond to Figs. III.C.land IV.A.3 in the original report.

(1) G. J. Baroczy, Chem. Eng. Progr. Symp. Ser. p . (1968).-6-


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REVIEW NO. 800THE SOLUBILITY OF OXYGEN IN LIQUID SODIUM:A RECOMMENDED EXPRESSION

Sponsor: U. S. Atomic Energy CommissionContractor: Atomics International, Canoga Park, Calif.Contract No.: AT(04-3)-701Report No. : AI-AEC-12685Report By: R. L. EichelbergerReport Date: November 1, 1968Reviews for Previous Two Years: noneThe solubility of oxygen in sodium as reported in ninepublications from eight laboratories was reviewed. A proposedset of criteria for inclusion of the data was developed, wherebyhalf the points were excluded. Five of the laboratories hadsome data which met the criteria. A recommended mathematical

expression from these data is given aslog^gS = 6.239 - 2447/T(K) ,

where S is the solubility of oxygen in weight ppm.Data from experiments where sodium was equilibrated or sampled in glass apparatus were excluded because of the possibilityof a sodium-glass reaction. Data derived by amalgamation analysis from sodium equilibrated at temperatures below 250C werealso excluded because of a possibility of a high analyticalblank. The result of the above criteria is that below 250C

the only data included are those obtained in one laboratoryutilizing the distillation technique. Unfortunately, therewas no distillation data above 340C to compare with the amalgamation results obtained in that region.Standard deviations of the constants for the above equation are not given but it does not appear justified to reportthe constants to more than three and possibly only two signifi

cant figures.(L. Newman)


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REVIEW NO. 801SODIUM TO STEAM HEAT EXCHANGER ELEMENTS AND RESEARCHPreliminary Steam Generator Concept Selection Study

Sponsor: U. S. Atomic Energy CommissionContractor: The Babcock & Wilcox Co., Power Generation Division,Barberton, OhioContract No. : AEGA T(ll -l)-1 280 ; B&W 596-3559-55Report No. : BAW-1280-55Report By: P. B. Probert, Project ManagerReport Period: Interim Report - Preliminary Steam GeneratorConcept Selection StudyReport Date: August 5, 1968Reviews for Previous Two Years: 590,603,649,705,724,759,774

The purpose of this project is to select the optimvim steamgenerator design for the Liquid-Metal Fast Breeder Reactor Program. A total of 96 possible designs were considered, and theyencompassed all feasible combinations of the following variables.1. Large units and modular units.2. Once-through, natural recirculation, and pumpedrecirculation.3. Drainable and undrainable bundles.4. Vertical and horizontal.5. Straight tube, U-tube, return bend, and helical coil.Each feasible design is discussed in the report and thereasons for the rejection of specific designs are presented.

Outline drawings of several designs are also included in thereport. As a result of the analysis, five alternatives and areference design were selected for further study. The selecteddesigns are:1. Modular, forced-recirculation, drainable, verticalstraight tube unit.2. Modular, once-through, drainable, vertical and horizontal straight tube units.3. Modular, once-through, drainable, horizontal, U-tubeunit.4. Large, once-through, drainable, vertical, return bendunit.5. Large, once-through, drainable, vertical, helical-coilunit.6. Large, once-through, undrainable, vertical, helical-coil unit (reference design).


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The sixth concept was selected as the reference designbecause of the large amount of analysis that is available fromthe prototype and full-size steam generator designs of thisconcept that have been performed by B&W.The planned analyses of these selected designs involve apreliminary analysis in which sizing calculations and preliminary arrangement drawings will be prepared and a design analysisthat will cover the work necessary to resolve important problems in sufficient detail to serve as a basis for cost estimatesand schedules. The program is outlined in the report.

(K. Hoffman)

REVIEW NO. 802BELLOWS SEALS FOR LIQUID METAL SYSTEMSLITERATURE SEARCH FOR FABRICATIONAND OPERATIONAL EXPERIENCE

Sponsor: U. S. Atomic Energy CommissionContractor: Battelle Memorial Institute, Pacific NorthwestLaboratory, Richland, WashingtonReport No.: BNWL-905Report By: R. C. AungstReport Date: November 1968Reviews for Previous Two Years: none

The control system for the Fast Test Reactor (FTR) willinclude bellows to isolate drive mechanisms from the sodiumvapor-inert gas mixture which covers the 1200F sodium pool inthe reactor vessel.To aid in the design of the bellows, a literature searchwas conducted by the Liquid Metals Information Center thatyielded 136 references, of which 26 were relevant and werereviewed in detail. It was found that the design of the requiredbellows is within the "state-of-the-art." Tentative specifications have been written that specify the material, grain size,mechanical properties, dimensions, temper, surface conditions,

welding configuration and procedure, leak testing and othertesting, and certification.


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This report is another example of the usefulness of theservices offered by the Liquid Metals Information Center.(S. Kalish)

REVIEW NO. 803ANNUAL PROGRESS REPORT OF THE WORK SPONSORED

BY THE SODIUM TECHNOLOGY AND THE FUELS AND MATERIALS BRANCHES*Sponsor: U. S. Atomic Energy CommissionContractor: Brookhaven National Laboratory, Upton, N.Y.Contract No.: AT30-2-Gen-16Report No .: BNL 50161 (T-526)Report Compiled By: John R. WeeksReport Period: January 1 to December 31, 1968Reviews for Previous Two Years: 684,741,742,760,787

The program includes studies of the 760 to ei5C corrosion behavior in sodium of materials for the LMFBR program,the mechanism of corrosion of materials in liquid sodium, andthe chemistry of liquid sodium solutions.Materials Testing Program

Thermal convection loops continue to be used to study thebehavior of a wide range of possible fuel-cladding materialsin sodium. Oxygen activity is controlled by one or more ofthe following techniques? cold-trapping, Zr hot-trapping, andMg or Li-gettering. Carbon activity is varied by using bothtype 321 and type 316 stainless steels as loop piping. In thealloys tested, the corrosion rate increases with the Ni + Crcontent of the alloy; the Co-base alloy S-1 corrodes the least,followed by stainless steel, and IN-800, which lost ~4 timesthe weight lost by S-1. The temperature dependence of the corrosion rates of all three alloys, however, is the same between700 and 760C, as shown in Fig. 4.

Co-base alloys are being studied as potential high temperature fuel-cladding materials for an LMFBR because of theirincreased strength at 750C. A series of new alloys is beingdeveloped containing 2 to 3% Ti which have 800C mechanicalproperties comparable to those of the stainless steels at 650C.Division of Reactor Development and TechnologyUnited States Atomic Energy Commission

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Forced circulation loop tests have shown that the corrosion rates of the Co-base alloys HA-25 and UMGO-51 are muchless affected by an increase in the oxygen level from 4 to 12ppm than are the corrosion rates of stainless steels as seenin Figure 5. X-ray fluorescence and metallographic observations suggest deposition of iron occurs on the surface of theGo-base alloy specimens when the oxygen level in the Na is 12ppm but not when it is 4 ppm as seen in Fig. 6. A comparisonof the BNL corrosion data on the stainless steels with thosefrom the UK RML and GEAP shows good agreement at comparableoxygen levels and velocities as seen in Fig, 7,The corrosion of refractory metal alloys is being studiedin a forced circulation loop with both hot- and cold-trap capabilities for controlling oxygen, A 2000 hr test was completedunder Zr-hot-trapped conditions (


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log^ (ppm Fe) = 7.05-5730/T(K)

The chemical activity of oxygen in Na held in a stainless-steel system is found to be buffered by one or more substancespresent in or on the stainless-steel surface. Further experiments in an oxidized Zr beaker containing 2 grams of a mixtureof Cr and Cr20_ powders confirmed that Cr is the probable buffering agent, and that, at 500G, the buffered activity in thepresence of Cr and Cr20o powders corresponds to that of a Na-17ppm oxygen binary solution.

For this work, the CU-CU2O reference electrodes in thecommercial electrochemical oxygen meters are replaced by a liquid Na-Na20 reference electrode, in which there is always excesssolid Na20 present to saturate the sodium. The measured potentials of this electrode at temperatures above 375G against Nacontaining known amounts of oxygen yield the equation for thesolubility of oxygen in Na:log^Q(ppm O) = 6.55-2600/T(K) .

There is an apparent inflection in the potential-temperaturecurve at 375C, which is possibly due to a phase change in solidNa20 at this temperature.Work is complete on studies of the reaction of HCl withNa and Na-Ba.solutions. The reaction occurs in two stages: thefirst produces H- and NaCl or BaCl2 and is controlled by processes of a physical nature, and the second is the reaction ofNa with the H2 produced.There is an interaction of hydrogen and oxygen in liquidNa at 400C which reduces the oxygen activity at constant oxygenconcentration, as observed by following the electrochemicalpotential of oxygen during reaction of the Na with H2 gas. Thereaction of CO with Na at 200G occurs in three stages: aninduction period in which a film forms on the Na, a rapid absorption stage in which the metal surface appears to be clear, anda second stage of negligible reaction rate in which the surfaceremains apparently clean.Construction of the Na chemistry loop was completed in 1968.It is currently undergoing shakedown runs.

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Electrochemical Techniques for Sodium ChemistryThe electrical conductivity of UNC Th02-Y202 meter tubeswas determined over a range of oxygen pressure from air to verydry hydrogen and at temperatures from 200 to 800C- The results

are shown in Fig. 10, The predominant conduction mechanismwas concluded to be ionic in the oxygen pressure range fromair to lO"- *-* atm at temperatures from 300 to a50C, To extendthe measurements to oxygen pressures corresponding to


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REVIEW NO. 804Space Programs Suirnnary 37-54, Vol , IIISUPPORTING RESEARCH AND ADVANCED DEVELOPMENT

Sponsor: National Aeronautics and Space AdministrationContractor: Jet Propulsion Laboratory, Pasadena, Calif,Contract No.: NAS 7-100Report No.: 37-54, Vol . IllReport Section By: D. G. Elliott, D. J. Cerini, and L. G. HaysReport Period: For the Period October 1 to November 30, 1968Report Date: December 31, 1968Reviews for Previous Two Years: 606,628,629,706,727 ,744,761,789,790Liquid-Metal MHD Power Conversion

The NaK-N.^ model induction generator was checked in the no-flowmode. Core losses were greater than those anticipated; otherwise, thegenerator performed as expected.The theory of the separation probe that will measure the lithium

level in the separator was checked against experimental values obtainedwith Dow-Therm as a stand-in.(J. Powell)

REVIEW NO. 805LIQUID METAL ENGINEERING CENTERSEMIANNUAL TECHNICAL PROGRESS REPORT

Sponsor: U. S. Atomic Energy CommissionContractor: Liquid Metal Engineering Cent er, Canoga Park, Calif.Contract No.: AT(04-3)-700Report No.: LMEG-69-1Report By: O. J. Foust et al.Report Period: July to December 1968Reviews for Previous Two Years: 607,631,677,69 1,729,730,7 48,762

This report summarizes the activities of the Liquid Metal Engineering Center during the first half of fiscal year 196 9. There are 16 majorprojects. Summaries on the following four are taken from the SUMMARYportion of the report and are considered appropriate for inclusion here.Sodium Pump Seal Test Program

"Preliminary System Design Descriptions for both oil-type and gas-type seal test facilities were approved after their revision. The described facilities can subject seals to operational and environmental conditions within the ranges expected to be encountered in actual LMFBR pumpservice. Means are provided to determine operating characteristics ofseals under various controlled and measured levels of these conditions.

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Project plans currently anticipate facility usage in the testof five seals: two for proposed 60,000-gpm LMFBR prototypepump designs, a third as-yet-unspecified design for a 60,000-gpm size pump, the PNL/FFTF pump, and a proposed one from anexisting pump design."Facility design modifications were resolved that resultedfrom new seal design information received from the pump studycontractors. These included addition of supplemental coolingfor the drive motor of one test rig and replacement of torquetransducers with another type to improve accuracy. A bearingspindle and support housing reinforcement assembly will be addedto eliminate flexibility revealed by load deflection measurements. Discrepancies of the test vessels were corrected byrework; the vessels were received and installed. Assembly ofthe test rigs was continued. Negotiations for the procurementof test seals were also continued.

Sodiimt Pump Bearing Test Program"A two-step program for development of radial bearings forLMFBR sodium pumps was instituted. The first part of the program involves testing of a prototype bearing for the FFTF primarysodium pump followed by tests of bearing designs developed bythe Large Sodium Pump Study contractors. Use of existing surplus equipment to compress the schedule and reduce costs isplanned.

Precision Mechanisms in Sodium"A detailed technical management plan to ensure meetingprogram objectives was developed, A literature search documenting information published since 1950 on mechanical devicesoperating in sodium environments was compiled and published,A similar document pertaining to operational experience withmechanical devices at various sodium-cooled reactor installations is being prepared,"Sliding wear tests were conducted with 8 2 material combinations in high-temperature liquid and sodium vapor. Theresultant wear rates are presented with some correlations interms of a "dimensionless wear coefficient" and the square ofthe hardness ratio for the particular material combinations.

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The cobalt base - nickel base alloy combinations appear to bethe best performers on the basis of tests completed. For thematerial and test parameters under investigation, frictionalheating effects appear to have a minimal contribution to thewear process."A journal bearing test plan has been prepared outlininga comprehensive test program to evaluate bearing performancecharacteristics in 900 to 1200F liquid sodium and sodium vapor.Materials selected for these tests include Hastelloy-C, Stelliteand -6B, Star-J, TZM, Inconel-718, K-95, and K-801.

Steam Generator and Intermediate Heat Exchanger PerformanceEvaluation"Test conditions are being established for a 2000-hr steady-state run of the Alco IHX and the Alco/BLH steam generator.This extended-run test is to be performed under reduced load

and less-than-rated temperature and pressure conditions."The capability of available computer codes to evaluatedetailed pressure and thermal stresses in the region of a tube-sheet has been demonstrated. Only steady-state conditions havebeen programmed to date, but the codes are capable of obtaining transient solutions as well."Additional studies have been performed to define the tube

vibration problem in the Alco IHX. There is evidence of vibrational impacting over an incompletely defined primary sodiumflow range. The severity and potential effect of this problemhave not yet been fully evaluated."

(Authors)

REVIEW NO. 806AM ANALYTICAL AND EXPERIMENTAL INVESTIGATION

OF TURBULENT FLOW IN BEARING FILMS,INCLUDING CONVECTIVE FLUID INERTIA FORCES

Sponsor: U. S. Atomic Energy CommissionContractor: Mechanical Technology Inc., Latham, New YorkContract No. : AT(30-1)-3930Report No. : NYO-3930-2 and MTI-68TR80

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Report By: A. J. Smalley, J. H. Vohr, V. Castelli andC. WachmannReport Date: December 1968Reviews for Previous Two Years: 732

This is the first topical report of the program on "LiquidMetal Bearings Technology for Large, High Temperature, SodiumRotating Machinery." A major aim is to extend the developedturbulent lubrication theory to include fluid inertia effectsand to verify by test the resultant analytical techniques. Ananalysis was developed that involves the direct numerical solution of the simultaneous equations representing conservation ofmomentum and fluid continuity. It was incorporated into a computer program and applied to pad bearings. The results werethen compared with experimental measurements made on a 12-in,-diam, four-pad, shrouded step bearing using silicone fluidsas a lubricant. A comprehensive description of the analysis,as well as graphically depicted comparisons between program andtest data are presented.

Tests were run with the bearing operating in the viscousand turbulent-inertial flow regimes at eccentricities of 0 and0.5. The mean discrepancies between predicted and measuredvalues of bearing peak pressure and integrated pressure profileswere found to be 8% or less. This is considered to be withintolerable limits, thereby verifying the analysis. An investigation of inertial and turbulent effects on pressure profile,peak pressure, and pressure-recovery factor was made and isreported herein.

(K. Hoffman)

REVIEW NO. 807LIQUID METAL BEARINGS TECHNOLOGY FOR LARGE,HIGH TEMPERATURE, SODIUM ROTATING MACHINERY

Sponsor: U. S. Atomic Energy CommissionContractor: Mechanical Technology Inc., Latham, N. Y.Contract No. : AT(30-l)-3930Report No.: NYO 3930-3 and MTI-69TR1Report By: E. B. Arwas, L. Hoogenboom, C. Kissinger, F. K.Orcutt, and W. D. Waldron

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Report Date: January 1969Previous Reviews: 792The progress made in the various tasks of this program,for the period August to October 1968, is reported.(a) The theore tical analysis of turbu lent- flow lubrica

tion, including the effects of fluid convective inertia, wascompleted. A comprehensive description of this work is presented in NYO 3930-2.

(b) The preparation of a bearing design handbook was begu n,with cal culations to optimize shrouded step beari ng configurations for operation with low-viscosity lubricants under highlevels of turbulence.

(c) An in-house development of an inductance-type proxi mitytransducer was initiated when it beca me apparent that comm ercially available units could not withs tand eleva ted tempera turetesting. The development of a capacitance-type, film-pressuretransducer for operation in high-tempe rature sodium was completed.A sample prob e is bei ng subjected to fatigue tes ting .

(d) The design of the bea rin g test rig is proc eed ing withthe preparatio n of component detailed drawings now under way .

Speci ficat ions for the two pro bes and the bea rin g test rig,as wel l as a flowsheet of test rig, are includ ed.

(P. Bezler)

REVIEW NO. 808STUDY OF THERMO-HYDRAULIC OSCILLATIONS IN BOILIN G

SYSTEMS EMPLOYING LIQUID METAL WORKING FLUIDSSponsor: National Aeronauti cs and Space Administrati onContra ctor: Mechani cal Technology Incorporated, Latham, N. Y.Contract No.: NASW-1705Report No s. : Tenth, Eleventh, and Twelfth Monthly LetterProgress ReportsReports By: J. H. Vohr and S. V. MansonReport Dat es: Novem ber, Decemb er, and JanuaryReports for Previous Two Ye ars : 750,763,79 1

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This is primarily an analytical study and the main objective is to investigate the thermal-hydraulic behavior of forcedflow of liquid metals in once-through boilers. Expressionsare being developed for net-vaporization rates in bubbly-,annular-, and fog-flow regimes. In the bubbly-flow regime, therapid rate of growth of the bubbles in superheated liquid callsfor a nonequilibrium treatment, and for this the expression ofTheofanous et al.^ ' for the growth rate of vapor bubbles isbeing used. In addition, the number and size distributions ofthe bubbles must yet be considered. The net vaporization ratein annular flow is assumed to take place under equilibrium conditions, which makes the analysis straightforward; and the governing differential equation is presented. The net vaporizationrate in fog flow is another nonequilibrium phenomenon, and littlework has yet been done on it.

In the case of large incipient-boiling superheats, thebubbly-, annular-, fog-flow sequence is replaced by the generation of a large vapor void, which grows in all available directions. In this situation, a "shock-wave" model of void propagation is being analyzed, and some of the basic momentum andheat transfer equations are given. Eventually it is hoped tobe able to predict the probability of a vapor void and its ratesof growth in the upstream and downstream directions.(O. E. Dwyer)

REVIEW NO. 809EVALUATION OF THE RESULTS OF A ROUND ROBINAJSTALYSIS FOR OXYGEN IN POTASSIUM AND SODIUM

Sponsor: National Aeronautics and Space AdministrationContractor; Lewis Research Center, Cleveland, OhioReport No.: NASA TN D-4971Report By: Glenn R. Zellars and Charles A. BarrettReport Date: December 1968Reviews for Previous Two Years: none

(1) "A Theoretical Study of Bubble Growth in Constant and Time-Dependent Pressure Fields," by T. Theofanous, L. Biasi,H. S. Isbin, and H. Fauske, to be published in ChemicalEngineering Science .

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This IS a report on the results of a round robin analysisof the determination of oxygen in sodium and potassiiom whichwas conducted in mid-1965. Each of 17 participating laboratories utilized their own method of analysis, in most cases theamalgamation technique, in some the vacuum distillation, andin one a neutron activation method.

The mean value obtained for oxygen in sodium was 10.7 ppmwith a standard deviation of 4.70 ppm; the value in potassiumwas 14.7 with a standard deviation of 5.08. The data showedsignificant variance in addition to experimental error. Analysis of variance performed on a selected set of results for thesame nominal experimental conditions indicated that the majorsource of variation was a lack of reproducibility among laboratories for sodium, and within laboratories for potassium.The results were not consistent enough to come to any conclusions as to other possible sources of error.This round robin was conducted nearly four years ago. Muchhas been learned since that time, and consequently the delayedpublication of these results is mainly of historical interest.As an outcome of this round robin, a second one was planned andhas already been conducted whereby the participating laboratories were all required to use a prescribed amalgamation technique.

(L. Newman)

REVIEW NO. 810SUMMARY OF IN-HOUSE LIQUID-METALS INVESTIGATIONS

(A special summary report to the editor)Sponsor: National Aeronautics and Space AdministrationContractor: Lewis Research Center, 21000 Brookpark Road,Cleveland, OhioForwarded By: Joseph P. JoyceReport Period: January 1968 to March 1969Reviews for Previous Two Years: 708,728

The report is reproduced below in its entirety:

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Accelerated Cavitation Damage FacilityA vibratory apparatus was used to subject the cobalt-base alloy, L-605,to cavitation damage in sodium at it-00, 800 and 1200 F. Cover gaspressures were varied from 1 to 4 atmospheres at each temperature.Increasing pressure increased the cavitation damage at each test temperature. Damage was greatest at the 800 F test temperature for allpressures. A volume loss rate contour diagram was constructed to showcavitation damage in terms of the combined temperature and pressureof the sodium.This information was covered in the following published paper:1. Young, Stanley G.; and Johnston, James R.: Effect of Temperatureand Pressure on Cavitation Damage to a Cobalt-Base Alloy in Sodium.NASA TM X-52555. (To be presented at T2nd Annual Meeting of theAmerican Society for Testing and Materials, Atlantic City, NewJersey, June 22-26, I969.)

Other recent published papers utilizing the same equipment included:2. Young, Stanley G.: Cavitation Damage of Stainless Steel, Nickel,and an Aluminum Alloy in Water for ASTM Round Robin Tests. M S ATM X-I6TO, October I968,3. Young, Stanley G.; and Leonard, L.: Effect of Ultrasonic Vibrationon Precipitation Hardening of Steels and Superalloys. NASA TN (infinal stages of printing).Alkali-Metal Heat-Transfer FacilityThe 600 kW, refractory-metal, boiling test facility is presently deactivated. Data from over 800 hours of operation are included in aforthcoming NASA Technical Note entitled "Tests of Sodium Boiling in aSingle-Tube-in-Shell Heat Exchanger Over the Range 1720 to 1980 F(1210 to 1360 K ) . "Space Radiator and Condenser FacilityThe 150 kW facility is presently deactivated. The final test for whicha Technical Note is being written, determined the extent of liquidsuperheat (or liquid tension) that occurs in the throat of an adiabaticventuri to be used as a boiler tube inlet device for flow stabilizationand vapor initiation. The test was run with potassium over the range1190 to llH0 F (915 to 1070 K ) .Seal StudiesExperimental and theoretical studies continue at a low level of effort.There is no reportable new progress at this time.Bearing StudiesStability tests were conducted with I.5 inch diameter, I.5 inch longhydrodynamic journal bearings in water at 80 F (300 K ) , at speeds to12,000 rpm. It was possible to use water instead of sodium because of

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the viscosity and density similarities between the two fluids. Goodagreement existed between stability data obtained in water and insodium for the same herringbone configuration on the journal, indicatingthat water can be used instead of sodium for bearing stability investigations. Plain bearings were run at various clearances with threedifferent journals: (l) a partially grooved herringbone journal having20 groove-ridge pairs; (2) a fully grooved herringbone journal having20 groove-ridge pairs; and (3) a partially grooved herringbone journalhaving ii0 groove-ridge pairs. No significant differences in the zeroload threshold of stability were measured among the three differentconfigurations of herringbone grooved journal bearings tested. Theoreticalanalysis for herringbone-groove joirrnals predicts a larger range ofstable operation than was observed experimentally.The following NASA report has been published describing these tests indetail:1. Schuller, F. T.; Fleming, D. P.; and Anderson, J. A.: ExperimentsOn The Stability of Water Fabricated Herringbone Groove JournalBearings.Part I - Theoretical Considerations and Clearance Effects.NA SA TN D-4883, Nov. I968.Part II - covers the effect of configuration and groove to ridgeclearance ratio of herringbone-groove bearings on stability(should be available June I969).SNAP-8 Test SystemFollowing completion of the boiler endurance test in November 1967^the Lewis SNAP-8 test facility was shut down for extensive modificationsin preparation for a system dynamic test program. The following components were replaced: electric NaK heater, boiler, and turbinealternator. In addition, the NaK-cooled parasitic load resistor wasremoved and a large amount of primary NaK-loop and mercury-loop pipingwas replaced. A change was also made in the routing of the auxiliarystart-loop piping in order to keep pace with the current SNAP-8 design.Extensive changes were made in the instrumentation and recording systemin order to improve its accuracy and dynamic response.Operation of the system was resumed in October I968. Steady-statemapping of the NaK-to-NaK auxiliary start-loop heat exchanger was accomplished and performance mapping of the mercury boiler was initiated.However, the compact electric NaK heater being used as a reactorsimulator electrically failed in January 1969> This heater has beenreplaced with a larger, more conservatively designed electric heater.Also, a NaK leak through the shell of the auxiliary start-loop heatexchanger was observed. The shell was replaced with one having athicker wall. Test operations are once again being resumed. The dynamicsprogram will mainly investigate startup and shutdown transients.Reports published between January 1, I968 and March 1969 are asfollows:1. Thollot, P. A.; Block, H. B.; and Jefferies, K. S.: ExperimentalInvestigation of Reactor-Loop Transients During Startup of aSimulated SNAP-8 System. NASA TN D-k^k6, May I968.

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2. Soeder, R. H.; Curreri, J. S.; and Macosko, R. P.: Performance ofa Maltitube Single-Pass Counterflow NaK-Cooled Mercury Rankine-CycleCondenser. NASA TM X-15^+8, April I968.

3. Albers, J. A.; Soeder, R. H.; and Thollot, P. A.: Design-PointPerformance of a Double-Containment Tantalum- and Stainless-SteelMercury Boiler for SNAP-8. NASA TN D-i+926, Dec. 1968.

h. Valerino, A. S.; Wood, J. C ; and Reznik, J. F.: SNAP-8 SimulatorLoop Mechanical Design. NASA TM X-I515, I968.5. Deyo, J. N.; and Wintucky, W. T.: Instrumentation of a SNAP-8Simulator Facility. NASA TM X-I525, I968.6. Block, H. B.; Kruchowy, R.; and Gallagher, J. D.: Performance ofthe SNAP-8 Fabrication and Coolant Subsystem. NASA TM X-1731, I968.7. Macosko, R. P.; Hanna, W. T.; Gorland, S.; and Jefferies, K. S.:Performance of An Experimental SNAP-8 Power Conversion System.NASA m x-1732, 1968.8. Asadourian, A. S.; Frye, R. J.; Macosko, R. P.; and Vernon, R. W.:Results on Endurance Tests of a SNAP-8 Turbine Alternator Assembly.NASA TM X-17 +1, I968.9. Gorland, S.; Hecker, T. P.; and Lottig, R. A.: Performance andEvaluation of Two Liquid-Metal Pumps for NaK Service. NASA TM X-I765,1968.

10. Gorland, S.; Lottig, R. A.; and Hecker, T. P.: Performance andEvaluation of a Liquid-Metal Pump for Mercury Service. NASA TM X-I766,1968.

Liquid-Metal InstrumentationAnalytical studies and development work in the areas of quality, flow-rate, pressure, and temperature measurements in liquid-metals have beenundertaken.1. Quality Measurement

Studies of quality measurement included analysis of calorimetrictechniques, a two-phase flow measurement technique, and a sonicvelocity measurement technique. These studies are reported in thefollowing publication:a. Nyland, Ted W.: Analysis of Three Liquid-Metal QualityMeasuring Techniques. NASA TN 'D-k03Q, June I967.

2. Flowrate MeasurementThe effort in the study of liquid-metal flowrate measurements consists of an analytical study of a d.c electromagnetic flowmeterwith a static transverse magnetic field. The purpose of this studyis to improve the accuracy of flowrate measurements by considering

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such effects as distortion of the velocity profile by the staticmagnetic field and the entrance and exit effects at the edges ofthe magnetic field. A numerical analysis of the velocity profiledistortion effect is nearly complete. It covers a range of Hartmannnumbers up to 200, wall-to-fluid conductivity ratios from zero(the insulated pipe wall case) to 2.0 and outside-to-inside diameterratios from I.05 to I.35. Results Indicate that the velocityprofile distortion effect is greatest at the higher Hartmann numbersand at the lower values of conductivity and diameter ratios, andmay be as much as 7 percent.

3. Pressure MeasurementThe development of a liquid-metal pressure transducer has been basedon the requirements of a flat frequency response up to 200 Hz andoperation in 1500 F sodium. A bellows is used as the pressureelement and a miniature quartz load cell is used for readout. Aconcentric tube system, 6 inches long, connects the load cell tothe bellows. Testing on this transducer is complete and a report isin preparation.The performance of commercial strain gage pressure transducerssuitable for use with liquid-metal has been measured for 1300 hoursat 260 C (533 K ) . The most significant effect of the time andtemperature was .a zero drift of approximately 2 percent of fullscale. This work is reported in a technical note which will bereleased soon:a. Lewis, Ralph D.: Performance of Commercial Unbonded StrainGage-Type Absolute Pressure Transducers at 260 C. (Finalstages of printing.)

h. Temperature MeasurementAn experiment to determine the thermoelectric drift of some nobleand refractory metal thermocouples at 24-00 F (1590 K ) and fortimes up to 10,000 hours has been conducted in air, argon, andvacuum environments. Photomicrographs and solids mass spectrometer analysis are being prepared on selected thermocouple samples.A second test involving noble metal thermocouples at 2350 F(1563 K ) in a vacuum environment for 3700 hours has also beencompleted. Spark emission spectroscopy, photomicrograph, andelectrical resistivity measurements are being made on sample wirespecimens.

Materials Support Programs1, Alkali-Metal Purification and Analysis

A procedure was devised for the isolation and recovery of alkali-metal reaction products in an uncontaminated state. Separation ofthe reaction product from excess alkali metal is accomplished byvacuum distillation. All recovery operations are carried out inhigh-vacuum or inert gas atmospheres. Two typical examples of the

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application of this method are: (a) the recovery of potassiumtantalate (KoTaOi ) from the potassium-tantalum-oxygen reaction, and(b) the recovery of potassium monoxide (K2O) from the potassium-oxygen reaction. Reaction products were identified by both X-raydiffraction and chemical analyses. This work is reported in:a. Gahn, Randall F.: Technique for Recovery of Alkali-MetalReaction Products. NASA TN D-U310, January I968.Effects of Environment on Interstitial Contamination oi RefractoryMetalsSticking probabilities for oxygen on columblum and dilute columbium-zirconium alloys were derived from ratios of oxygen absorption ratesto their corresponding oxygen fluxes. Oxygen test pressures werevaried fran 10"' to 10"5 torr over temperatures between 1158 and1373 K. Absorption rates were derived from a pressure-drop techniqueand fluxes were derived from constant pressure measurements. Reactionkinetics, as well as test method characteristics, were considered.This work is reported in:a. Barrett, Charles A.: Absorption Rate Sticking Probabilitiesfor Oxygen on Columblum and Dilute Columblum-Zirconium Alloys.NASA TN D-if885, November 1968.List of Publications since January 1, I968The following is a complete listing of reports from the LiquidMetals Section that have been published since January 1, I968:a. Gahn, Randall F.: Technique for Recovery of Alkali-MetalReaction Products. NASA TN D-I+310, January I968.b. Rosenblum, Louis; Scheuermann, Coulson; Barrett, Charles; andLowdermilk, Warren: Mechanism and Kinetics of Corrosion ofSelected Iron and Cobalt Alloys in Refluxing Mercury^ NASATN D-4i 50, April I968.c. Bowles, Kenneth J.: Vapor Pressure of Potassium to 2170 K.NASA TN D-1+535, May I968.d. Vary, Alex: A Radiator Concept Based on Capillary Retention ofLiquid. NASA TN D-i


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REVIEW NO. 811NIOBIUM - 1% ZIRCONIUM BOILING-POTASSIUMFORCED-CIRCULATION LOOP TEST

Sponsor: U. S. Atomic Energy CommissionContractor: Oak Ridge National Laboratory, Oak Ridge, Tenn.Contract No.: W-7405-eng-26Report No. : ORNL-4301Report By: D. H. Jansen et al.Report Date: December 1968Reviews for Previous Two Years: noneThis report gives a carefully documented account of theconstruction of,'and operating experience with, a forced-circulation boiling-potassiimi loop. The loop, built of niobium -

1% zirconium alloy, was designed to test simulated turbineblade specimens for possible use in potassium Rankine systems.The report gives clear descriptions of loop design, loop operating characteristics, and test results.Fig. 12 presents a schematic diagram of the test system.The test section consisted of three stages of nozzles and simulated turbine blades. The nozzles were designed to providepotassium vapor over the quality range of 83 to 9 7 % and temperature range of 1860 to 1260F. The simulated turbine bladespecimens were of niobium - 1% zirconium alloy. The preheater,boiler, and dryer sections of the primary loop were heated with

radiant clam-shell furnaces using tantalum resistors.The authors report that loop operation was characterized byperiods of complete stability followed by periods of severe temperature and pressure fluctuations associated with unstableboiling. During unstable periods, the test section outlet temperature underwent rapid changes of as much as 500F, with corresponding boiler pressure fluctuations of as much as 70 psi.The authors state that the cause of this instability was mostlikely associated with the problem of high nucleation superheatthat has been found to be characteristic of the alkali metals.Because unstable operating conditions prevailed for KAO% of the

operating time, it was not possible to obtain an unequivocalanalysis of the corrosion and erosion results. One of the majoruncertainties was the extent of liquid carry-over from the boilerto the test section specimens during unstable flow conditions.It was reasoned that this subjected the blade specimens to wetvapor conditions that were more severe than design conditions,but were not quantitatively definable. The report does give

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tables and figures illustrating results of metallographic andchemical analyses of various portions of the loop and of thetest blade specimens. From this evidence, the authors note thefollowing qualitative conclusions:(a) Evidence of a chrome-rich layer on the second-stageblade specimen indicated that the presence of a few stainless-steel components was sufficient to provide chromium transport,even though the components presented only limited surface areaat relatively low temperatures. The test specimens generallyindicated only minor damage, in spite of the rather severe operating conditions.(b) Some oxygen transfer from the potassium to the niobium -1% zirconium alloy was observed, with the greatest transfer inthe hotter loop regions.(c) An excessive increase in tubing diameter at the driersection indicated that the creep characteristics of the testalloy may be a problem for operation near 2000F.

(J. C. Chen)Fig, 12 in the Review corresponds to Fig. 1 in the originalreport.

REVIEW NO. 812ULTRASONIC THERMOMETRY FOR LMFBR SYSTEMSPhase I Report

Sponsor: U. S. Atomic Energy CommissionContractor: Panametrics, 221 Crescent Street, Waltham, Mass.Contract No.: AT(30-1)-3906Report No. : NYO-3906-4Report By: S. S. Fam, L. C. Lynnworth, and E. H. CarnevaleReport Date: September 1968Reviews for Previous Two Year s: 795This report summarizes the results of the first phase ofa program whose ultimate aim is the development of thermometers,based on ultrasonic principles, for use in liquid-metal-cooledreactor systems. The intent is to develop a system for monitoring fuel, cladding, and coolant temperatures.

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The proposed system is similar to that of a previous NASApr og ra m' ^ in which an ultrasonic system was developed for measuring local temperatures up to 4800F (to an accuracy of 50F)for one hour in the core of a nuclear rocket engine (see Figure 13)"This system exploits the temperature depndence of soundvelocity in refractory metal wir es. The system is basicallycomprised of four parts: transducer, lead-in, sensor, and anelectronic instrument. The transducer consists of a coil woundaround a suitable magnetostrictive wire (usually a nickel alloy).The coil is pulsed, thus producing an elastic strain in thewire...which is reflected and/or transmitted according to thegeometry and materials used in the line... Of particular interestare the reflections emanating from the beginning and end of thesensor element, the time interval between which is a measure ofits average temperature. This time interval is automaticallymeasured and digitally displayed... Since extensional and tor

sional waves propagate at speeds proportional to the square rootof Youngs' modulus, E, and to the modulus of rigidity, G, respectively, it is necessary to consider all the possible mechanismsby which the environment may affect these moduli."The authors mention the advantages that thin-wire ultrasonic thermometers have over other temperature-measuring systems.The ultrasonic sensor consists of a single wire, such as pure Re,and is therefore not subject to the calibration shifts, whichin thermocouples are due to diffusion of one leg into another.In addition, the small thermal mass of wire sensors results inless error due to internal heat generation from radiation.The sensor materials that have been found suitable are, Refor the fuel (f5000F) and type 304 SS for the coolant and cladding

{Ril200F) . Lead-in wire is of 304 SS and will be placed in protective sheaths (304 SS) for acoustic isolation. In the reactorcore the Ra sensor will be placed in a suitable protective sheath.Ta or W/Re may be used with UO fuels and W/Re may be used withU02/PuO^ fuels.A complete system was successfully tested under simulatedconditions which included: sensor temperatures up to j5000F;lead length of 50 ft, 20 ft of which were at temperatures up to

(1) Lynnworth, L. C. and Carnevale, E. H. "Ultrasonic Temperature Measuring Device," Final Report NASA CR-72339 , Aug. 1967.

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i:1200F; lead wire transmission through feedthroughs capableof containing vapor pressures of 100 psi ; and operation withthe lead wire containing typical bends.

Recommendations for Phase II of the program include theinstallation of the system constructed for Phase I in a selectedliquid-metal nuclear reactor facility to measure in-core temperatures. Radiation effects, if any, could then be checked.(S. Kalish)

Pig. 13 in the Review corresponds to Fig. 1 in the originalreport.

REVIEW NO. 813ULTRASONIC THERMOMETRY IN LMFBR SYSTEMS

Sponsor: U. S. Atomic Energy CommissionContractor: Panametrics, 221 Crescent Street, Waltham, Mass.Contract No .: AT(30-1)-3906Report No .: NYO-3906-5Report By: S. Fam, L. C. Lynnworth, and E. H. CarnevaleReport Period: September to December 1968Report Dat e: December 1968Reviews for Previous Two Years: 795, 812

(See Review No. 812)This is the first quarterly progress report in Phase II ofa program whose purpose is to develop an ultrasonic thermometrysystem for use in liquid-metal fast-breeder-reactor cores. Thetopical report covering Phase I of the program is reviewed inthis issue.The objective of Phase II of the program is to test the system developed in Phase I in a liquid-metal-reactor facility.During this report period, arrangements were made for system testing at the Oak Ridge Research Reactor, where temperatures up to j5000F can be maintained in a radiation field oflO-"- n/cm^sec (fast) and R^IO-*-^ n/cm^-sec (thermal). Apparently,the test will be run in conjunction with a GE experiment whose

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purpose is to test the compatibility of W/Re sheaths with UOj-PUO2 mixed oxide fuel. The tests are scheduled for mid-March1969.Room-temperature sound-velocity measurements were made onthree Re-Os alloy samples. However, further tests involvingthermal cycling and annealing are required in order to determinethe effect of composition on sound velocity.

(S. Kalish)

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Cathode leads (split molybdenum rod)

Conductor and leaf spring(molybdenum)

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A i r , V acu u m V en tD I S Cburstdss'y _ pressureM v a l v eu s e

B a c k -

T es t sec t i o n( l - i n sch . - 4 0 s t a i n l ess s t ee l )Mixer

S t e a mJ l i F l o w m e t e r_T '

T S t e a m Tlo r P u mpF i g u r e 3

W a t e r

^

R eser vo i r

Sonic-Velocity Test Apparatus. The pressuresat the four points above the test section aremeasured by quartz transducers.(Review No. 799)

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100

u 0 I

EFFECT OF TEMPERATURE ONCORROSION OF THREE ALLOYSIN lOCC DIFFUSION COLDTRAPPED SODIUM FLOWING AT~ 0 I ft /sec THERMAL CONVECTION'7-154(316 STAINLESS STEEL)

ONi-6 5Mo

IN-800Fe-2ICo-32Ni

960 980 1000 1020 1040 1060 1080I O V T (K)

Figure 4(Review No. 803)

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6I 4I 2

I 6I 4I 2

~ i I I I \ rHAYNES 25

INITIA L WT % 3 Fe"74 W

1 ^ r

. 304 S S IN IT IA L WT %- 68 Fe

0 2 4 6 8 10 12EXPOSURE TIME WEEKS

( R e v i e w N o . 8 0 3 )F i g u r e 6 - X - r a y F l u o r e s c e n c e R e s u l t sFCL-1

- 3 6 -


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10T E M P , X

7 6 0 7 1 0 6 5 0

1 1 1C O M P A R I S O N O F C O R R O S IO N R A T E SO F S T A I N L E S S S T E E L S v sRECIPROCAL TEMPERATURE -

0. 1

\ UK DATA\ 25 ppmO

a 32 1 S.S.0 3 0 4 S.S. M A N Y A L L O Y S

101 0 "

T , K

F i g u r e 7( R e v i e w N o , 8 0 3 )

- 3 7 -


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2 0

I 0

_ N i SOLU BIL ITY in No

T~ N i ( p p m ) = 0 0 0 4 6 T ( C ) - l 4 0

!

1

11

1J.1

1

TJ -

1

T11

\" 1I T

1 1-L 111

1

^

1

1

1

1

T -11

""""'^ 111

11

14 0 0 4 5 0 5 0 0

TEMPE RATURE , C5 5 0 6 0 0

Figure 8 - Solubility of Nickel inSodium as a Functionof Temperature(Review No. 803)

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10.

1.0

.1

;

I

0

"1 1 '

>

A F T E R 0 A D D IT I O N0 4 8 6 C 5 5 0 C

A F T E R 0 G E T T E R I N G


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T c7 0 0 6 0 0 5 0 0 4 0 0

Xo

10 r

10= ^

10" ^

10 "

1 rT h O j -

FROMUNC OXYGEN METER TUBE^ LENGTH 5 40 5 cm- 'AREA

R= RESISTANCE(T= CONDUCTIVITYa- IR A

ACTIVATION ENERGY =2 7 , 2 0 0 k c a l / m o l e

300 250 200T

DATA REPORTE D ''aBY /BATES /

D - A I R' ' - H E L I U M 5 p p ni O jo -DRY HYDROGEN

J \ I \ I \ I I I LI 2 14 16- L X l o 'T -K

2 0 2 2

( R e v i e w N o . 8 0 3 )Figure 10 - The Resistance of ThO--

15 wt % Y2O as aFunction of Temperature andOxygen Pressure

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5 10 15 20 25 3 0OXYGEN CONCENTRATION ppm

(Review No. 803)Figure 11 - The Variation of the Rateof Oxygen Uptake by

Uranium With OxygenConcentration

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DRYER

SURGETANK

LIOUID-Ng-COOLEDTRAP

Figure 12Schematic of Loop Test System,

(Review No . 811)

VACUUM CHAMBER

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T R A N S M I T / R E C E I V E U N I TWITH DIGITAL DISPLAY OFTRANSIT T IME IN SENSOR

TO DAMPING PADORT O S E CO N D L E A D - I NAND SENSOR

U L T R A S O N I C P U L S ET R A N S I T T I M EIN SENSOR

HIGH TEMPERATUREE N V I R O N M E N T

Figure 13Schematic of automatic measurement of pulse transit time in sensor,

(Review No. 812)

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Brookhaven National Laboratory9,16,32,49,79,180,366,472,684,741,742,760,787,803Columbia University73,344,519Consolidated Controls Corporation250,278,323,367,397,435,473,495,520Electro-Optical Systems, Inc.1,85Fairchild Stratos Corp., StratosDivision167General Electric Company

3,11,22,26,27,50,51,52,72,73,7475, 98,100,101,158,159,160,161,162,187,188,189,190,191,192,219,220,221,222,223,224,233,234,235,251,252,253,254,255,256,257,291,292,293,294,295,303,304,324,325,345,346,347,348,368,398,418,436,437,438,439,474,475,476,477,478,496,497,498,543,544,545,566,591,604,605,650,651,652,670,671,67 2,685,686,725,726,775,788

Geoscience Ltd.8,23,165,166,225,258,326,349,369,399,479,626,673Hydronautics Inc.107,132,164,260,370,419,546,567,593,653,743Jet Propulsion Laboratory80,97,547,568,606,627,628,629,

674,687,706,707,727,744,761,789,790,804Liquid Metal Engineering Center607,630,631,676,677,688,689,690,691,709,729,730,745,746,747,748,762,776,777,805

Los Alamos Scientific Laboratory2,15,20,99,155,156,201,262,279,305,327,372,400,441,480,499,550,569,570Marquardt Corporation521,551Massachusetts Institute of Tech.6,25,39,40,86,119,171,228,263,328,522,552,608,731,749Mechanical Technology Inc.329,373,374,401,592,710,732,763,791,792,806,807,808MSA Research Corporation

21,53,54,55,68,69,81,89,109,110,153,154,184,185,186,204,205,206,207,227,264,265,266,267,280,281,282,283,306,330,331,332,350,351,375,376,402,403,420,421,422,455,456,457,500,501,523,524,525,553,594,609,610,63 2,654,678,679,692,711NASA-Lewis Research Center

17,60,84,157,261,371,502,548,549,675,708,728,809,810

Oak Ridge National Laboratory58,90,91,95,284,298,377,378,404,423,526,633,655,656,712,733,751,7 52,764,765,778,793,794,811Panametrics795,812,813Philco Corporation

527,595,611,634Pratt and Whitney Aircraft

14,28,47,48,62,148,149,175,285,286,333,352,379,380,405,406,458,459,460,461,481,482,503,528

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Rocketdyne (A Division of NorthAmerican Aviation)7,24,59,76,196,236,270,353,381

San Fernando Laboratory382,422,504,529,530,554,713Southwest Research Institute38,271,307,334,383,424,443,571Stanford Research Institute753Sundstrand Aviation34,63,108,134,193,242,287Tapco (A Division of Thompson

Ramo Wooldridge)5,121Temple University (Research Inst.)

596Thermo Electron Engineering Corp.181Thompson Ramo Wooldridge, Inc.4,13

United Nuclear78,290,462,483,505,531,555,556,572,573,597,635,657,658,680,693,714,734,754,766,779,796U. S. Naval Research Laboratory35,104,105,226,268,269,354,463University of Michigan

18,19,31,43,44,45,46,70,71,87,120,135,136,146,176,177,178,179,215,216,217,218,230,231,232,272,288,308,309,310,355,356,3 57,384,385,386,387,407,408,409,425,444,445,484,506,532,533,534,557,574,575,576,598,659,745

University of Washington200Westinghouse Electric Corp.10,111,112,113,114,137,138,139,140,182,183,209,210,273,274,311,388,426,446,447,485,507,508,535,577,578,612,613,614,636,660,694,755

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