ML20010H731

Research Program on Hydrogen Combustion & Control,Quarterly Progress Rept 4.

ML20010H731
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Site:	Sequoyah
Issue date:	09/16/1981
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t TENNESEE VALLEY AUTHORITY SEQUOYAH NUEEAR PIANT RESEARCH PROGRAM ON HYDROGEN COMBUSTION AND CON'IltOL QUARTERLY PROGRESS REPORT #4 SEPTEMBER 16, 1981-

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'8109290229 810922 PDR ADOCK 05000327

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o TABLE OF CONTENTS l I. Introduction f

II. Task Description, Schedule, and Status A. Industry Degraded Core (IDCOR) Program /TVA B. Electric Power Research Institute (EPRI)/TVA/ Duke /AEP C. Westinghouse /TVA/ Duke /AEP - CLASIX D. TVA/ Duke /AEP D.1 Catalytic Combustor D.2 Fogging D.3 Singleton Testing E. TVA E.1 Browns Ferry Probab!11stic Risk Assessment (Pickard, Lowe, and Garrick)

E.2 Sequoyah Full-Scale Safety and Availability Analysis (Keman Sciences Corporation)

E.3 Consequence Analysis E.4 Severe Accident Sequence Analysis (SASA)/(ORNL)

E.5 Ice Condenser Containment Code III. Appendices A. Program Details A.1 EPRI Program A.2 Singleton Testing B. Acurex Catalytic Combustor Final Report 2

I. Introduction

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This report is the fourth of a series of quarterly research summaries presented to the Nuclear Regulatory Commission (NRC) by the Tennessee Valley Authority (TVA) to satisfy the following condition of the Sequoyah Nuclear Plant units 1 and 2 operating licenses:

During the interim period of operation, TVA shall continue a research program on hydrogen control measures and the effects of hydrogen burns on safety functions and shall submit to the NRC quarterly reports on that research program.

These efforts are the-subject of the present series of reports.

The format of this report is designed to present in Section II an updated summary of the changes in scope, schedule, and status of each task as described in the first report with further f

technical details in appropriate appendices.

II. Task Description, Schedule, and Status The major emphasis of TVA's current research program is to discover, collect, and evaluate enough information about degraded core events and potential mitigations for their risk reduction to be able to justify tbo permanent hydrogen mitigation system (PHNS) selected for Sequoyah Nuclear Plant.

This permanent systra would satisfy the following condition of the operating licenses:

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For operation of the f acility beyond January 31, 1982, the Commission must confirm that an adequate hydrogen control system for the plant is installed and will perform its intended function in a manner that provides adequate safety nargins.

Table 1 is a schedule of activities necessary to meet this unit 1 licensing condition.

This section provides a sammary of each individual or group effort in which TVA is actively involved that is related to hydrogen conbustion and control, risk assessment, or overall degraded core ,tudies. Here, current updates of scope, schedule, and status of each effort are summarized with further details presented in the appendices.

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TABLE 1 s

IVA HYDROGDI MITIGATI0ri PROGRAM SCHEDULE 3/16/81 Srbeit quarterly report #2 to NRC*

4/1/81 Complete preliminary evaluation of conceptual designs 5/81 Submit resolution of IDIS equipment survivability to NRC 6/1/81

. Complete evaluation of conceptual designs Mid-81 Select PENS and submit preliminary information to NRC 6/16/81 Submit quarterly report #3 to NRC*

9/81

. Complete EPRI igniter development program 9/81

. Complete EPRI combustion studies 9/81 Complete EPRI H Control Studies 9/16/81 Submit quarterly report #4 to NRC*

9/81

. Complete final system design 11/81 Submit final safety analysis report to NRC 12/81

. Complete EPRI mixing studies 12/16/81 Submit quarterly report #5 to NRC*

1/31/82

. Receive NRC approval and removal of OL condition (22)D(2) 6/82

. Complete procurement of equipment l first

. Complete installation and testing refueling,each unit

• Quarterly reports will provide summary of progress made toward identified r.ilestone s.

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A. Industry Degraded Core (IDCOR) Program /TVA (identified in

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the first quarterly report as AIF proposal)

A.1 Scope No update necessary.

A.2 Schedule No update necessary.

A.3 Status The IDCOR Steering Committee has approved a two year technical program which began July 1,1981, and is scheduled to be completed July 1,1983.

The IDCOR program is currently on schedule and approximately 20 percent complete. The program has been divided up into 24 tasks:

Task 1: Safety Goal Evaluation Task 2: Ground Rules for Evainetion of Degraded Core Conditions Task 3: Selection of Dominant Sequences Task 4: Selection of Phenomenological Sequences Affecting Containment Task 5: Effects of Human Error on Dominant Accident Sequences -

Task 6: Risk Significance Profile for ESF sud Other Equipment Task 7: Baseline Risk Profile for Current 'seneration Plants Task 8: Effect of Post-TWI Changes on the Overall Risk Profile 6

._ _ . - . . _ . . _ , . . _ . _ . _ _ . _ _ _ _ _ . _ . _ _ - . . ~ . - _ . . _ . _ . . _ . - _ . _ _ _ - _ . . .~ .. . . _ . . . _ _ . . - _ .

o Task 9: Preventive Methods to Arrest Sequence of Events before Core Damage Task 10: Containment Structural Capability Task 11: Fission Product Liberation. Transport, and Inherent Retention Task 12: Hydrogen Generation and Burn Task 13: Hydrogen Burn Control Task 14: Steam Overpressure Phenomena (In-Vessel Containment)

Task 15: Core Debris Behavior and Coolability Task 16: Integrated Model Definition Task 17: Equipment Survivability in a Degraded Core Environment Task 18: Atmosphere sad Liquid Pathway Dose Task 19: Alternative Containment Systems Task 20: Core Retention Devices Task 21: Risk Reduction Potential Task 22: Safe Stable States Following Core Degradation Task 23: Integrated Containment Analyses Task 24: Operational Aspects for Accident Management and Control The finalized IDCOR program plan will be issued in the l

near future.

l Initial contacts for developing technology exchanges l

with Germany and France have been made.

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Technology for Energy Corporation (TEC), the IDCOR

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Program Manager, has prepared a list of potential contracts for this effort and is working toward issuing contracts for the early-start tasks on or around l November 1981.

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B. Electric Power Research Institute (EPRI)/TVA/Duks/AEP

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B.1 Scope The scope of the four EPRI research programs is unchanged. However, to facilitate the review of the program, we have in this revision consolidated the information we have about each project, its scope, description, and current status. We have included this latest information in the revised Appendix A.1.

The EPRI research program is carrently at a stage where testing is ongoing at all of the facilities.

B.2 Schedule EPRI's schedule which includes the latest progress for all four of the EPRI tests is shown in Figure II.B-1.

B.3 Status The revised Appendix A.1 includes the latest status for each of the four projects.

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C. Westinghouse /TVA/D2ko/AEP - CLASIX TVA, Duke, and AEP have purchased the CLASIX computer code from Westinghouse. As we reported in our third quarterly report, all modifications to the CLASIX code that were committed to earlier have been completed and the revised output provided to the NRC on June 1,1981. Presently, in-house analyses are being performed with CLASIX to address NRC concerns provided to the utilities in a letter from R.

L. Tedesco to H. G. Parris dated July 8,1981. These analyses are being performed with the version of CLASIX which includes structursi heat sinks, upper plenum model, and air return f an head flow curve.

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D. TVA/ Duke /AEP D.1 Catalytic Combustor D.1.1 Scope No update necessary.

D.I.2 Schedule No update necessary.

D.1.3 Status The final report was received by TVA/ Duke /AEP in late August, 1981. The report is contained in this document as Appendix B.

D.2 Fogging D.2.1 Scope No update necessary.

D.2.2 Schedule

' No update necessary.

D.2.3 Status The testing at Factory Natual and Acurex on fogging was completed recently. Reports from both of these f acilities will be included in the next quarterly report.

D.3 Singleton Testing D.3.1 Scope In response to a request by the NRC to perform sustained (24 heur), low hydrogen concentration exposure tests on a glow plug, TVA has arranged to perform tests at TVA's Singleton Laboratories. A description of the tests is j

contained in Appendix A.2.

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D.3.2 Schedule Test Procedure Appreved 9-2-81 Shakedown Tests Complete 9-10-81 Testing Complete 9-21-81 Draft Test Report 9-28-81 Final Report 10-16-81 D.3.3 Status IVA's Singleton Laboratory is presently conducting tests as scheduled.

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E. TVA In addition to the preceding, TVA is independently pursuing other areas of degraded core studies which are outlined in this section.

E.1 Browns Ferry Nuclest Plant Probabilistic Risk Assessment (Pickard, Lowe, and Garrick)

E.1.1 Scope No update necessary.

E .1. 2 Schedule The study began 10/80.

Dates for najor milestones

. Data analysis and fault trees - 1/82

. Explant consequence model assessment - 7/81

. Seismic analysis reports - 9/81

. Event trees - 9/81

. Explant consequence analysis - 3/82

. Final report - 6/82 E.1.3 Status Tasks completed or presently underway:

. Event sequencre diagrams

. Event trees

. System quantitative analysis

. Maintenance and test data

. Seismic analysis

. External events analysis

. TVA code conversion 13

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Near ftture tasks;

. System quantitative analysis

. Containment analysis E.2 Sequoyah Nuclear Plant Full-Ssale Safety and 5

Availability Analysis (Kaman Sciences Corporation)

E.2.1 Scope No update necessary.

E.2.2 Schedule Phase I (preliminary availability assessment) 1/ 81 Phase II-A (preliminary safety assessment) 5/81 Phase II (final assessment) 6/82 E.2.3 Comprehensive system models have been developed for five systens (Auxiliary Feedwater, Main f eedwater, Safety Injection, Residual Heat Repaval, Ice Condenser)

Prelimir?ry models have been developed for all other systems which are included in the analysis.

Preliminar.v availability and safety assessments have been made.

E.3 Consequence Analysis E.3.1 Scope No update necessary.

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l s E.3.2 Schedule Evaluate MARCH / CORRAL 2 and KESS as to similitudes and differences in the prediction ut LWR Class 9 accident consequences 12/81 Comparison of postulated accident sequences for SQN using MARCH / CORRAL 2 and KESS 4/82 E.3.3 Status Completed training in use of MARG, CORRAL 2 and dose prediction codes 3/81 High probability accident sequences identified 4/81 Obtained CRAC2 computer program from Sandia 7/81

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E.4 Severs Accident Sequence Analysis (SASA)/(ORNL)

E.4.1 Scope No update necessary.

E.4.2 Schedule I. Browns Ferry Station Ulackout Analysis A. Complete Analysis of Blackout Sequence 4/81 B. Issue Draft Report 5/81 C. Completo Peer Review 8/81 D. Issue Final Report (NUREG) 10/81 II. Analyze pther BWR Sequences Identified by NRC/INEL A. Provide Accident Signatures for 8 BWR Sequences 10/81 B. Identify Sequences for Follow-on Detailed Analysis 11/81 15 l

C. Perfers asslysis of fciltro to isolato o s2311 break LOCA outside contabaent 1/82 E.4.3 Status 4/81 Completed analysis of Browns Ferry station blackout analysis 5/81 Issued draft report 8/81 Completed peer review 5/81 RELAP5 model completed for BFN-1 5/81 Draft report for BFN-1 station blackout completed 7/81 Completed the predicted station blackout fission product release and behavior study E.5 Ice Condenser Containment Code E.5.1 Scope No update necessary E.5.2 Schedule No update necessary E.5.3 Status Part I - No update necessary.

Part II - Comparison has been made between NONSTER and CLASIX for an S2 D event.

Both codes provide similar results showing multiple burns in the lower compartment and upper plenus. The CLASIX results are more conservative than those obtained from NONSTER.

Comparisons between NONS1ER results j 16

ced the Fenwat tost data sh nsd goad i agreement.

Part III -Plotting capability has been incorporated into the code. Other i

items remain the same as discussed in our first quarterly report.

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i APP 5DII A.I EPRI PROGRAM l

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AFFENDIX A.1 EPRI PROGRAM - TECHNICAL DETAILS 1.0 Introduction In order to justify installation of a permanent hydrogen mitigation system at Sequoyah Nuclear Plant, several questions concerning hydrogen management are being addressed. TVA, American Electric Power (AEP), and Duke Power have entered into a research effort with the Electric Power Research Institute (EPRI) to study hydrogen mitigation and control under degraded core accident conditions. The following is a description and status of that program to date.

1.1 Obtectives and Technical Insnes. This program is intended to meet the following limited objectives:

1. Determination of whether and when hydrogen can burn in l

postulated ice condenser accident environments resulting l from degraded core scenarios; i

2. Demonstration that if a hydrogen burn does occur, its ef fects will n*,t exceed the realistic survival capabilities of equipment and containment; and

3. Demonstration that ressonable control methods can provide adequate safety margins assuring the integrity of the containment and of key safety-related equipment.

Determination of the effects of hydrogen deflagrations on f

containment and equipment requires investigation of several questions, in particular:

a. What are the lower flammability limits undsr degraded 1

core accident conditions and how effective are thermal l

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ignition sourcess

b. What is the chae-ater of deflagrations in various geometries and how can the offects be sitigasads

c. What is the nature of Lydrogen mixing and distribution in Imrge compartmentalized volumes; and

d. What is the potential for the acceleration of deflagrations, or for flame propagation between compartments in turbulent mixtures.

1.2 Pronram Elamants. We feel the following projects will provide the information needed to satisfy the program obj e c tive s. The projects are related, and consist of.

1. Development and preliminary testing of thermal ignitors for a deliberate ignitior, system (AECL Thitoshell);

2. Peperiments and analyses on basic hydrogen combustion phenomena including the effects of steam, turbulence, and flame propagation between compartments (AECL Whitoshe11)s

3. Experiments on hydrogen control methods including water spray and fog (Acurez/ Factory Natual);

4. Measurement and analyses cf hydrogen mixing and

- distribution in a large compartmentalized volume (REDL- ! ).

Figure 1 shows time scales for the projects, including the test phase (solid line).

2.0 Dameristion of the Pronram Elements The four projects listed above will be accomplished at four facilities (ABCL Whitoshe11, Acurex, Factory Natual, and Hanford Engineering and 3evelopment Laboratory). The following is a description of each of the four projects and the f acilities they ,

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will use to meet their program objectives.

2.1 Innitar Davaloosent (AECL Thitenhall)

The interim distributed ignition system which TVA installed in September of 1980 in Sequoyah Nuclear Plant employs a diesel engine slow plug. The ability of this glow ping to ignite hydrogen at low concentrations under various environmental conditions of steam, pressure, humidity, water spray, and airflow across the igniter surface was demonstrated during the Fenwat test. The current EPRI program is designed to compare three thermal igniter types, including the glow plugs, for effectiveness under an expanded range of environmental conditions and to compilo data for comparison with the 1erger body of existing hydrogen combustien data.

This program will be accomplished at AECL Thitoshe11 in a 0.6 ft vessel which is approximately 12 inches high by 14 inches in diameter. Four types of thornst ignitors will be subjected to identical test conditions. The ignitors will be evaluated for their ability to ignite hydrogen in the range of 5 to 12 volume percent under various steam concentrations in the range of 0 to approximately 60 percent. The test will be conducted both wita and without fan-induced turbulence. The vessel will be instrumented 1

with f ast response thermocouples (10 microseconds) and l

pressure transducers (1 microsecond) tied into a computerized data acquisition system.

Current Status The testing of the GM/AC model 7G glow plug has been l

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complet:d. Whitosho11 is carrostly testing a RAMA'e:rtridge heater and following that will test a TAYC0 coil heater.

2.2 Ewdroman Ca=hmation (AECL Thitashell)

The objectives of these tests are:

1. To provide inadamental understanding of H combustions 2

2. To establish comparison betwoon slow plus data and spark ignition data.

3. To study the effects of turbulence created by obstacles; and

4. To study the flame propagation between different concentrations of hydrogen.

In order to accomplish these objectives, the tests will be conducted in a 8-foot diameter, 220-cubic-foot sphere, and when necessary a connected 12-inch (id) pipe. The sphere has a design pressure of 1450 lbs/in . Both

. ihe sphere and the pipe are trace heated and insulated.

The vessel will be instrumented with fast response thermocouples (10 microseconds) and pressure transducers (1 microsecond) as well as ion probes from which flame speeds can be determined. This vessel, like the smaller vessel discussed in 2.1 above, will employ a canputerized data acquisition system. The vessel will also be equipped with two fans, the details of which are noted on Table 3, and provisions for gas sampling both before and af ter each testing using gas chromatography.

I The tests have been divided into four parts to study:

1. The lower fiammability limits in steam, I

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2. Laminar spherical deflagrations,

3. 'ae effects of turbulence on deflagrations, and

4. Propagation of deflagrations between connected volumes Current Status Whiteshell la proceeding with the test matriz outlined in tables 1 through 4. Preliminary results are being analyzed.

2.3 Hydromen Control Studies (Acurax/Factorv Natual)

The purpose cf these tests is to study the effects of sprays and fogs on hydrogen deflagratiras. This will be accomplished by studying the interrelationship between water droplet size, water concentration, and hydrogen concentrations in sus 11 scale tests at Factory Natual.

Based on the data obtained from Factory Natual, large scale tests will be conducted by Acurez to study the pressure suppressant effects of sprays and fogs on hydrogen i

i de fla gra tions.

2.3.1 Factory Natual Studies A schematic of the esperimental apparatus to be used is shown in Figure 2. The test vessel is a Plexiglass tube approximately 3-1/2 feet long and 6 inches id. Ile ignition source will be a spark igniter. Ionization probes will verify the presence of a flame during an ignition attempt. Thermocouples l

will measure the test vessel's atmosphere temperature.

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The current test matrix will provide data for droplet sizes in the range of 10-400 microns and water 5

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concentrations varying from 0-5 volums parecst. Tha hydrogen coneratration will be varied from 4-12 volume percent. These tests will provide information on conditions that produce inerting. From this data, spray droplet sizes with potential to reduce the t

maximum pressure from controlled burning will be selected for further study at the Acures test facility.

Current Status Factory Natual has completed their testing and provided input to the Acuren spray / fogging tests.

The Factory Natual final report will be forwarded to the NRC as soon as it is available.

2.3.2 Acurez Studies Figure 3 provides a flow diagram of the facility to be used. Vessel instrumentation is she,n in Figure

4. The vessel is approximately 17 feet high with a 7-foot id. The volume is 630 cubic feet.

Instrumentation includes pressure transducers, Type K th e rmocouple s , and ionization probes. Ignition will be by sp6tk and slow plugs. This will allow correlations to be made between the Factory Natual studies and postnisted conditions inside I containment.

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These tests will provide informatica ca tbo prosstro l

. i suppressant effects of fogs / sprays on hydrogen 1 defingration.

Current Status The Acurez tests will be complete by September 19, 1981.

2.4 Hydroaan Mixina and Distribution Studies (Hanford). The purpose of these tests is to qcsntify the degree of hydrogen mixing in a simulated ics condenser seemetry under accident conditions.

. Compartments will be built in the 30,000-cubic-foot containment system test f acility to simulate a simplified ice condenser conta8.nment Soometry (see Figures 5 and 6).

The tests will then be performed with scaled hydrogen and steam flows based on average release rates obtained from the MARCH computer code. Hydrogen concentrations and temperatures at various spatial locations will be measured 1

as a function of time. Other measurements to be taken l

include water / vapor concentrations, and convective gas flow t

patterns in a few key locations. Testing will be restricted f

by safety regulations to use of only 4-volume percent hydrogen since the vessel is located la a building which houses other experiments. Identical tests will be run with i

l both helium and hydrogen, and a correlation between the two will be obtained to allow the majority of the tests to be 1

run with bellum.

Status The Hanf ord test matrix is included as table 5 to this I

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report. Hanford has prepared a detailed description of the similarity modeling used in this portion of the EPRI testing l

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pts tam. The report is in draf t stage at this time and will ,

be presented to the NRC when finalized.

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TABLE 1 Test Natrix for Whitenhall Emner4=anta

1. Extent of Remation of Lean N11tures Eyd %4 %g Innition 1-3 5.0 0 botton 4,5 6,5 0 botton

. 6 8.0 0 botton 7-9 5.0 15 botton 10,11 6.5 15 botton 12 8.0 15 botton 13,14 6.5 30 botton 15 8.0 30 botton 16 6.5 0 center 17 6.5 15 center 18 8.5 0 top 19 8.5 30 top Note: Steam concentrations are in the process of heAng revised upward to address current NRC concerns.

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TABLE 2

2. Laminar Scherical Deflamrations Exo. # 15, 1R,2 Ianition 1 10 0 center 2 20 0 center 3 30 0 center 4 42 0 center 5 10 10 center 6 20 10 center 7 30 10 center 8 42 10 center 9 10 20 center 10 20 20 conter 11 30 20 center 4

12 42 20 center 13 10 30 center 14 20 30 center 15 30 30 center 16 42 30 center 17 14 0 botton 18 20 0 botton Note: Steam concentrations are in the process of being revised upward to address current NRC concerns.

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TABLE 3

3. Effect of Fana and O'n a t ac im a Ex. # 5R, ig,Q Fan Sneed Gratina Innition 1 6 0 50% No botton 2 6 0 100% No bottom 3 7 0 100% No botton 4 6 0 0 Yes botton 5 7 0 0 Yes botton 6 7 0 100% Yes botton 7 14 0 100% No center 8 20 0 100% No center 9 14 0 0 Yes center 10 20 0 0 Yes center Fan Partienlars Gratina Partienlara blade tip diameter: 16 in. type: 1/4' perforated plate air deflectors hole size: 1: dia.

max. speed  : 1800 rpm blocked area: 50%

max. flow rate  : 1500 cfm spacing: 2 plates placed 3

horizontally at 2.6 and 5.3 (sphere vol = 220 ft feet from the bottom of the No. of fans  : 2 sphere continuously variable speed 11

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TABLE 4

4. Schere and Protrudina Pine Exn. #  % Q Innition 1 8 0 sphere-center 2 20 0 sphere-center 3 8 0 pipe-end 4 20 0 pipe-end 5 Sp/6s O pipe-center 6 10p/6s O pipe-center P " PiPo s = sphere 12

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i TABLE 5 f H MIXING TEST MATRIX 2

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Initial

Recirc. He or H2 Source Steam Low.r

Test Cont. Flow Source Flow Rate Gas Flow Cont Gas Geometry 4

No. Gas (CFM) Source Gas (1b/ min) Temp.(*F) '(1b/ mini Temp. (*F) ___(*)

HM-P1 Air 0 --- --- 0 --- ---

85 300 HM-P2 Air 3700 --- ---

0 --- ---

85 300 j HM-P3 Air 0 --- ---

0 --- ---

150 300 HM-P4 Air 3700 --- ---

0 --- ---

150 300 HM-1 Air 0 Jet-I He-Steam 0.9 300 27 150 300

HM-2 Air 0 Jet-I He-Steam 1.8 300 54 150 300 i HM-3 Air 3700 Jet-I He-Steam 0.9 300 27 150 300 i I

HM-4 Air 3700 Jet-I He-Steam 1.8 300 54 150 300 HM-5 N 700 Jet-I H2-Steam 0.9 300 54 150 300 l

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HM-6 Air 3200 Jet-III He-stea. 0.55 400 TBD 150 300 HM-7 Air 3200 He-steam TBD

? Jet-III 1.1 400 150 300

! *HM-8 Air 3700 Jet-II He-Steam 1.8 300 54 ISO 300

• HM-9 Air 3700 Jet-II He-Steam 1.8 300 54 150 360

• HH-10 Air 0 Jet-II He-Steam 1.8 300 54 150 360 NOTES: 1.

• Lowest priority tests.

2. Jet I and Jet II are high velocity jets.

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! 3. Jet III is a low velocity jet.

TBD - To Be Determined

. HYDR 0 GEN COMBUSTION AND MANAGEMENT PROGRAM * .

FIGURE I 1982 SCALE 11/1 1/1 -

5/1 7/1 9/1 3/1 (1033 FT ) 11/1 1/1 IGNITER DEVELOPMENT 0.001 )

(WHITESHELL/

HYDROGEN CONTROL STLIDIES 0.6 (ACUREX)

HYDROGEN COMBUSTION STUDIES 0.2 (AECL, WHITESHELL)

HYDROGEN MIXING STUDIES 30 (HEDL-W) .

• 4/81

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FIGURE 4 e

G

. . . . . . _ . . - - . . - . . . . . . -- -. - t t , . ~ . _ . _ - , . _

%,QIII Annular Test Compartment

/

12 5 ft Rad.

h air 5 ft. Rad. air %

f

- air "iF Corrugated Steel  %

Culvert

\

/ \ I f

U / \ '

/ \ STF Vessel Wall j

\

Geometry Removable Plywood Walls o g .

Wall r/ yes no Wall V . yes no Jet I yes no Notes:

Jet II yes yes 1. Jet I, Jet II & Diffuse III Diffuse' are to be used in separate III yes no test.

2. Removable walls -------

Section A-A Figure 5 CSTF Plan for g Mixing Tests i

d CSTF V' "' 1

=

25 ft.

l

$2 N r Air 2

o Plywood Recirculating

• M # No Deck " Gas B:.oter to afl/ plecu:n O u yent, "

i 6 i

N r Air N

• 2 2 w

• d 10ft. Air N u y

,A e 3

" ^ -

Annular }f-l- .

Test Co=pe.rt=ent

, 777 Jet supplygh;.l'. a' n

j it 1'

l  :

d Cerrugated '

d Steel Culvert v_ _- '

v Notes:

I. Jet I4 cation 1. Figure not to scale II. Jet Location 2. Configuration has same dias.

III. Diffuse Location to lower ec.p. ht. ratio as plant crane wall diam to em:p. ht. .

Figure 6 CSTF View for H Mixing Tests 2

..m

APPENDIX A.2 SINGLETON TEST 1VA is conducting tests with the General Motors (GM) glow plug in order to determine the effects of lean (0-4 v/o) hydrogen mixtures for sustained durations (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) on the ability of the igniter to subsequently perform its intended functica.

The test consists of establishing baseline data by repeatedly energizing the glow plug and recording the voltage, current, surface temperature, and the time required for the surface tempercture to stabilize. This baseline data will be used to evaluate the effects of lean hydrogen mixtures on the glow plug. After establishing the baseline data, the heating element portion of the glow plus will be enclosed in a container in which the hydrogen concentration shall be maintained at a maximum of four percent for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The igniter will be energized, and the surf ace temperature and the atnosphere temperature in the vicinity of the plug monitored.

Af ter the -exposure test, the igniter shall be subjected to an acceptance test consisting of comparing the current, the surface temperature, and the time for the surface temperature to stabilize with the baseline data established before the test. Following the completion of the acceptance test, a metallographic examination shall be performed on the igniter.

.The results of these tests should be available by the middle of i l

October 1981.

13 l

_ _ . _ _ .,