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LEGAL NOTICEW r was M*esam cm Of tivimit ipoered wft. "er *Ah niteIfties, iu Ow Cowmi..ha. mr my~ perso sating esbohaft fs*A ~ i~

A. MaUmsy smuwaty or op'wmi;itom, exprmessd or I5pited. with resemct to the seve-racy, iemdtouml, or mweebwo *I the lairmatuam omuaised to hWe eort. or tha Me woof omr Afuarsdo. r--, mnd. or proceso Odmisod Is th report #uy mt lafrigoilhWMIy .w d rigbiet orS. AJmo may WtdUtae wift respeo td me oat.or for dawai resltpia from them el m Imsm'Uatioa, ftrs thr~od. or pmcss t isclosad in thia repoA*si ImedoO bAe. "pinmg. eg a bohl atd o Camsausom" icla.die my om-pke orat orsewt do Cos.i.m los, or em I - of muh ooustactor. tothe staset thatomch smle of omtrmmuqr of fte Coamiilm. or otnopyu of much centractorW p-ee.dOusmate or provdwe* "ccosio, tnyamatim pWafat" Iaa emuymmet or uetrmotwft s Comadmiom. or Us smploymnt with sofh oemetroir.

This report has been reproduced directly from the bestavailable copy.Printed in USA. Price $1.00. Available from the Clearing-house for Federal Scientific and Technical Information, Na-tional Bureau of Standards, U. S. Department of Commerce,Springfield, Virginia 22151.

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VUF 3016

PROJECT DRIBBLESALMON EVENT

VENT-GAS TREATMENT PLANT

D. Snoeberger and R. Heckman, Editors

Lawrence Radiation LaboratoryUniversity of CaliforniaLivermore, California

March 1966


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VENT GAS TREATMENT PLANTJ. Ackerman, R. Bundrick, J Cowles, V. DuVal, J. Grens,

R. Holzman, C. Hannon, J. Harrar, C. Morris, L. Rigdon,R, Heckman and D. Snoeberger

Lawrence Radiation Laboratory, University of CaliforniaLivermore, California

INTRODUCTION

As part of the Vela Uniform prog: am, Project Dribble was concernedwith the measurement of seismic signals generated by nuclear detonation ina salt dome. The principal objective of the project was a test of the decouplingtheory proposed by Latter et al. 1,2

In September 1962. after resumption of underground nuclear testing,Project Dribble was redefined. Certain technical responsibilities includingthe detailed design of the experiment, development of the technical programand execution of the on-site portion of the technical program were assignedto the Lawrence Radiation Laboratory through the Atomic Energy Commission.

The planned 5-kiloton detonation occurred October 22, 1964, in theTatum Salt Dome near Hattiesburg, Mississippi.

Technical objectives of the post-shot program for this event were to:I) Obtain samples of radioactive debris for yield determination.

iLatter, A. L. , E. LeLevier, E. Martinelli, and W. McMillan, "A Methodof Concealing Underground Nuclear Explosions, " J. Geophys. Research, 66,943-946 (1961).2Werth, G. , and P. Randolph, "Prepared Statement on the Theory ofDecoupling and the Status of Project Dribble, for the Joint Committee onAtomic Energy, Congress of United States, ' UCRL-7323, March 6, 1963. I.


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2) Sample the gas in the cavity to determine whether ridioactivematerial which might cause a public safety problem had escaped.

3) Examine the feasibility of re-use of the cavity for firing decouplednuclear shots. Measurements to be made included distributionof radioactivity, temperature, volume, geophysical logging, andtelevision survey.

4) Extract core from a second drill hole passing close to the cavityfor property measurements.

To accomplish this post-shot technical program, an assured means ofobtaining access to the cavity was required. Based on studies completed in1961 on the cost and engineering feasibility of the various means of assuringcavity access, it was decided that a vent-gas treatment facility was needed.This facility was to be connected to the post-shot drilling rig at the well headand was to remove radioactive particulates from the cavity effluents and controlrelease rate of gaseous radioactivity to meet public health safety standards.

Process engineering studies resumed in September 1962. The problemwas redefined with more stringent performance requirements added. Thenew requirements included the following points: The facility must removeradioiodine to eliminate any possible public safety problems. The releaserate for the noble gas fission products, xenon and krypton, must not exceedlimitations set by the limited test ban treaty, i. e., no detectable activitybeyond national borders. The plant must be removable before shot time andbe quickly reinstalled to prevent damage to the plant components by nuclearseismic shockwave. Absolute reliability and control of plant radioactivityreleases was to be accomplished by use of shut-off valves at the well head.


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It was recognized that an explosive mixture of gases might be presentin the post-shot cavity. To prevent any possibility of catastrophic failureof the plant components with subsequent radioactivity release, an air dilutionventuri was added at the plant inlet. The flow rate of cavity gas into thedilution venturi was controlled so that an explosive mixture was neverpossible beyond the dilution venturi. In addition, all the well head pipingupstream of the venturi was designed to contain any gas explosion that mightoccur.

Since drill back into the cavity might occur as early as D + 7 d-.ys, thefacility must be capable of handling the following fission pruduct activity mixedwith the gas: particulate - 4 X 105 curies; radioiodine - 8 X 105 curies; and

6 6radioxenon and krypton - 1 X 10 curies; or a total of 2.2 X 10 curies.GAS TREATMENT PROBLEM

Predictions of the chemical environment of an underground r.'iclearexplosion are very difficult; yet that is the problem with which we were facedin attempting to describe the feed conditions into our vent gas treatmentfacility. The design of the facility had to be sufficiently flexible to cover anypossible situation that could occur in the field. From test hole sample3, saltdome composition was estimated to be Ns-.Cl 91%, CaSO 4 8% , CO 0.015%, H 02 2


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3) SO 3 + H 2 0 - H- 2 2so42 NaC1 + H 2 S04----- 2 HCI + Na 2SO 4

4) H 2 +C O 2 CO + H 2 05) H 2 0 ( ) - H 0 (g)

The iron was present from the emplacement canister. There was an un-certainty in amount of salt melt to be produced by the nuclear detonationand therefore the amount of CaSO 4 available for reaction.

With these great uncertainties in the general chemical environment, weattempted to make predictions of the chemical state of the radioiodine. Thesepredictions indicated the most likely forms to be 12 and HI.

Predictions of the cavity volume produced further uncertainties inexpected pressures; cavity collapse would radically affect cavity pressureand temperature at the time of re-entry. With no collapse, the cavity temper-ature was estimated to be below the melting point of salt. The cavity pressuremight range from 10 atm ,o a partial vacuum, depending on which chemicalequilibrium prevailed.

With these considerations as background, we chose the following asdesign criteria for the facility: The problem was to release at controlled andsafe rate approximately 5.6 X 105 ft 3 of gas initially at a pressure of 10 atmo-spheres or less. Release was to begin one to four weeks after the shot, de-pending upon time required to drill the postshot well. The vented gas tem-perature would be at ground ambient temperature because of hcat transferto the earth and well casing during passage up the well. There might beenough hydrogen and oxygen present to constitute an explosive nixture,possibly in a detonation range. The gas was expected to be acidic, corrosive

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and saturated with water. It might carry suspended salt particles capableof plugging flow passages. Radioactivity was estimated to be a maximumof 4.0 curie per cubic foot of gas fed to the plant.

Later times of re-entry and bleed dowr would allow further decay ofradioact'ivity. Radioiodine activity, 11 3 3 , predominate.s after 10 days, butdecreases by a factor of 10 per month. Xenon activity falls off a little fasterbut krypton 85 activity predominates over those of xenon and iodine afterroughly three months, contributing approximately a total of 200 curies.

A controlled release of the cavity gas these further effects were ex-pected: Excess water vapor would condense on the wall or on cold salt,dissolve salt, and return to the cavity. This process might continue byreflux. There may be a net beneficial effect in separation of gases andparticulates by this "wetted wall column." There might be problems withsalt plugging in the well.

Radioactive particulates and iodine were to be removed from the ventedgas; xenon and krypton were to be dispersed in the atmosphere.

The release rate was limited to allowable rates for iodine, xenon andkrypton as determined by publc safety and limited test ban treaty considera-tion. It was important to complete bleed down in as short a time as possibleto minimize cost and degradation of data for the post shot programs.

Pre-operational tests with radioactive iodine were made in July 1964.The plant was removed to avoid shock d&.mage, then reinstalled after thetest detnation. Operational use began in February 1965, and continuedintermittently through May 1965. Figure I shows the plant piped to the re -entry well late in the operational period. The plant is now in caretakerstatus pending development of requirements in connection with re-use of thecavity for further experiments.


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Prior to the actual detonation the decision was made to delay start ofpost-shot drill back for 60 days to accomplish additional technical require-ments for the detection program. Because of this delay a large fraction ofradioactivity decayer', and the cavity cooled to 2040 C. At the time of cavitypenetration, the cavity was found to be under a partial vacuum of 313 millibars.

On the basis of pre-operaaonal performance tests and the actual operatingexperience, we feel that we successfully designed and built a vent gas treat-ment facility whose performance exceeded our original design specifications.The desired flexibility was demonstrated by our ability to support a 'Vide varietyof down-hole operations that resulted from actual conditions found in the field.However, our ability to predict the chemical environment of a.i undergroundnuclear explosion leaves something to be desired. We recognized ourignorance in this area and by use of a very conservative design we did conducta post-shot technical program successfully without endangering the publib:safety or violating the limited test ban treaty.

DESCRIPTION OF PROCESS AND PLANTThe process is a remotely operated gas scrubbing and filtering system

with charcoal adsorption units incorporated with the filters. It is sized to3 3take up to 200 ft /min of cavity gas mixed with 2000 ft /min of air to dilute

nydrogen. Effluent gas is discharged from a 150-foot stack after mixing with20,000 cfm of additional air. Liquid wastes from the scrubbers are st din four 25,000-gal tanks for later disposal. Figure 2 shows the sutdown,flow control and main process units,

i Well HeadWell ,The well head includes the cavity gas shut-off valves. There are six,two in series plus a sampling valve on each of the two connections to the plant.Io w oncin otepat


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These valves ate remotely operable. They are designed to fail to a closedposition and will close automatically on loss of electric power or failure ofthe process equipment.

Flow Control and DilutionFlow control valves, adjacent to the well, limit flow to rates based on

the hydrogen dilution requirement or radioactivity release limit. The venturiserves to dilute cavity gas to below the lower explosive limit for hydrogen andprovide suction for faster flow at low cavity pressures. Equipment workingpressure ratings are 3000 psig prior to dilution and 150 psig after dilution.

Gas ScrubbersThe two scrubbers, in series, are a venturi-type and an impingement

plate type. Their purposes are to remove particulates, protecting the filtersfrom excess loading, and remove iodine. The scrubbing liquid is aqueoussodium hydroxide.Filter Adsorbers

Each of three units installed in parallel consist.3 of an activated charcoalbed with an "absolute" type filter preceding and following. A prefilter isused with each to avoid caustic damage to the glass fiber media of the highefficiency filters. These are modified Cambridge Filter Company C. B. R.,units. Their purpose is to remove particulates carrying radioactivity andto adsorb radioiodine. One of the three is a reserve unit.

StackThe stack is 150 feet high, clearing local trees and hills by 50 to 100 feet.

A stack blower adds air at 20,000 ft 3/min for local dilution. All effluent andcontaminated tank vent gas is discharged through the stack,

Chemical Biological Radiological.


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Laboratory Trailer

A gas chromatograph provides feed gas analysis by sample pipe orbottle. Scrubbing solution analysis is provided by "auto analyzer" and pHand density instruments.

PREOPERATIONAL TESTSDuring the course of the project increasing emphasis was placed on

removal of radioactive ;odine. Although quantities and the compounds ofiodine to be expected in the gas were not predictable, tests with a probableform, I2' were made using 1-131 as a gamma tracer. Results were excellent.The removal factor for the combined scrubbers and charcoal beds was 4 X

510OPERATION OF FACILITY

This period began on February 26 , 1965. It can be divided roughlyinto three phases: 1) a standby period prior to cavity penetration (Feb. 26 toMar. 3); 2) an operation period during which the greatest part of actual ventgas treatment took place (Mar. 4 to Mar. 13); 3) a continuing period of stand-by and occasional operation (Mar. 14 onward).

A summary of operational experience follows:

1. Cleaning of air drilling returnsA crossover line was installed from the drill rig "blooie line" into the

plant 10-inch process gas line. This system allowed the plant to provideprotection against spreading of radioactive salt dust and release of radiogasencountered in the final stages of drilling. Drilling returns were diverted


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This was done on penetration drilling into the cavity and later while drillingfor cores below the cavity.

2. Vent gas treatmentThe true operating phase began at cavity penetration, early on March

4. A pressure measurement shortly after penetration showed 0.8-inch Hgvacuum, so no immediate attempt was made to bleed off cavity gas.

Gas sample bottles and temperature measuring instruments were loweredinto the cavity, and the plant gas chromatography unit analyzed a sample ofthis gas. This important findings were that the gas was primarily air, withCO 2 the primary additional constituent. Both H2 and SO2 were present, butin concentrations too low to be of concern in operations.

The first appreciable quantity of gas vented from the cavity occurredof March 6, following pressurization of the cavity to one-half atmospherepositive pressure with drilling compressors for purposes of cavity volumemeasurements. This gas was released through the rossover pipe installedfor drilling returns, which allowed flows at approximately 1000 cfm. Cyclicflow pulses, with a period of about 30 to 60 seconds, were observed duringbleeding off of the gas. These may have been caused by a reflux water leg,which also may have been responsible for closing the hole with a salt plug.

Activity release was very low. The maximum release rate of radio-active rare gas is estimated at less than 200 millicuries/minute. Approximately30 curies of rare gas, mostly Kr5, were released in the initial bleed downof the 300,000 cubic feet of ai r added for cavity volume measurement. Dueto dilution by the stack blower, 5 microcuries per cubic foot was the maximumconcentration in effluent gas. 1131 was so slight as to be detectable only withdifficulty.


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The second and final major release of cavity gas was from the flushingoperation. This was a procedure to reduce the concentration of radio-active gas to such a level that treatment of vent gases would no longer berequired. Three cavity volumes of air were pumped into the cavity andbled off, reducing residual gas to 40 microcuries per cubic foot rare gasradioactivity.

Release rate was a maximum of 50 millicuries per minute early in theoperation, and declined slightly. Total release was approximately 50 curies,primarily Kr 8 5 .

3. Downhole operations supportRegulated flows of nitrogen and air and slight suctions were provided

to the well on demand to assist in the use of well logging instruments andtelevision cameras. Cavity pressures were decreased to just below atmosphericpressure to establish downdrafts during insertion and removal of drillingequipment and instruments.

Repeated use of plant equipment was made to test by pressurization andpressure decay measurement for communication between well and cavity. Thedilution venturi suction was used to speed up final stages of gas pressurebleed down for the time saving benefit.

Suction of gas downward from the well head was used to reduce gashazards on the rig floor when unsealed insertions or removals were necessary.

CONCLUSIONS GAINED FROM OPERATIONAL EXPERIET&CEThe experience gained from the design and operation of this unique

vent gas treatment facility has initiated a number of research and developmentstudies to overcome many of the process engineering problems uncovered.


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We are actively studying methods of arresting detonation waves.Solution of this problem would eliminate necessity of air dilution, with asubsequent decrease in size of processing equipment capacity by an orderof magInitude.

From the measured performance of the charcoal scrubbers, we believemuch of the radioiodine released was present as organic compounds possiblyCH 3 I. We have completed studies on improving the performance of charcoaladsorption beds for the removal of CH 3 1. We are now studying new analyticaltechniqucs which will allow us to determine the chemical state of iodine infuture field experiments.

Basic studies of the chemical nature of an undergound nuclear explosionare underway. We plan to use computer calculation tenchiques and laboratoryscale experimen ts, as well as actual field experiments involving undergroundnuclear detonations.

With the results obtained from these basic studies, we expect to be ableto make better predictions of inlet feed streams and to design more ccmpact,higher performance vent gas treatment plants in the future.


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TECHNICAL AND SAFETY PROGRAM REPORTS SCHEDULED FOR ISSUANCEB1 AGENCIES PARTICIPATING IN PROJECT UIBBE

SAFETY REPORTSAgency Report No. Subject or TitleUSWB V'F.*120O Weather and lurface Radiation Prediction

ActivitiesU[PHS VUF-O121 Final Report of Off-site SurveillanceUS3M VUF-1O02 Pre and Post-Shot Safety Inspection of Oil

and Ga s Facilities Near Project DribbleUSGS VUF-1023 Analysis of Geohydrology of Tatum Salt DomeUSGS VUF-IO24 Analysis of Aquifer ResponseREECo VU?-1025 On-Site Health and Safety ReportRFB, Inc. VUF-IO26 Analysis of Dribble Data on Ground Motion

and Containment - Safety ProgramH-NSC VUF-1027 ,round-;.ater SafetyFAA VUF-1028 Federal Aviation Agency Airspace AdvisoryH&N VUF-1029 Summary of Pre and Post-Shot Structural

Survey ReportsJAB VUF-I030 Structural Response of Residential-Type TestStructures in Close Proximity to an UndergroundNuclear Detonat ionJAB VUF-1031 Structurel Response of Tall Industrial andResidential Structures to an Underground

Nuclear Detonat ion.NOTE: Th e Seismic Safety data will be included in the USC&GSTechnical Report VUF-3OI4

TECMNICAL REPORTS

Agency Report No. Subject or TitleSL VTJF-3012 Free-Field Particle Motions from a Nuclear

Explosion in Salt - Part ISRI VUF-3013 Free-Field Particle Motions from a NuclearExplosion in Salt - Part IIUSC&3S VUF-3014 Earth Vibration from a Nuclear Explosion ina Salt DomeUED VJF-3015 Compressional Velocity and Distance MeasurementsIn a Salt Dome

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IAL uF-3016 Vant-G.s Treatment PlantIAL PNE-300e 0 Response of Test Structures to Ground Motionfro an Underground Nuclear ExplosionSRI VF-3017 Feasibility of Cavity Pressure and TemperatureMeasurements fo r a Decoupled Nuclear ExplosionILL VUF-3OI8 Backround Engineering rata and Summary ofInstrumentation for a Nuclear Test in SaltWES VUF-3019 Laboratory Desig and Analyses and Field Controlof Grouting Mixtures Employed at a Nuclear Testin SaltILL VUF-30O0 Geology and Physical and Chemical Properties of

the Site fo r a Nuclear Explosion in SaltE VTF-J2 Timing and Firing

This report number wa s assigned by SAN

In addition to the reports listed above as scheduled fo r issuance by the ProjectDRIBBLE test organization, a number of papers covering interpretation of the SAI4ONdata are to be submitted to the American Geophysical Union for publication. Asof February 1, 1965, the list of these papers consists of the following:Title Author(s) Agency(s)Shock Wave Calculations of Salmon L. A. Rogers LRLNuclear Decoupling, Full and Partial D. W. Patterson IRLCalculation of P-Wave Amplitudes for D. L. Springer andSalmon W. D. Hurdlow LRLTravel Times and Amplitudes of Salmon J. N. Jordan USC&GSExplosion W. V. Mickey AFTACW. Helterbran UEDDetection, Analysis and Interpretation A. Archambeau andof Teleseismic Signals from the Salmon E. A. Flinn SDCEventEpicenter Locations of Salmon Event E. Herrin and Smi

J. Taggart USC&GSTh e Post-Explosion Environment Resulting D. E. Ravson andfrom the Salmon Event S. M.Hansen LMeasurements of the Crustal Structure in D. H. WarrenMississippi J. H. HealyW. H. Jackson USGSAll but the last paper in the above list will be read at the annual meeting ofthe American Geophysical Union in April 1965.

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LIST OF ABBREVIATIONS ?tM TECHNICAL AGENCIES

BK LTD hrringer Research Limited RFB, INC. R. F. Beers, Inc.Rexdale, OntarioCanada Alexandria, VirginiaERDL Engineering Research SDC Seismic D&+A CenterDevelopment laboratory Alexandria, VirginiaFort Belvoir, Virgnia EG&G Edgerton, Germeshausen &I Grier, Inc.FAA Federal Aviation 4Ency Crier, Nc.Los Angeles, CaliorniaGIMRADA U. S. Army Geodesy, Intelni- SL Sandia laboratoryAlbuquerque, New Mexicogence and Msapping Research

and Development Agency SMU Southern Methodist UniversityFort Belvior, Virginia Dalls, TexasX-NSC Hazleton-Nuclear ScienceCroainSRI Stanford Research InstituteCorporation MnoPrClfri

Palo Alto, California Menlo Park, CaliforniaH&O, INC Holmes & Narver, Inc. TI Texas Instruments, Inc.Los Angeles, California Dallas, Texas"Las VegLs, UA United AircraftII Isotopes, Inc. El Segundo, California

Weatwood, Ne w Jersey NUED United Electro Dynamics, Inc.MTEK Itek Corporation Pasadena, CaliforniaPalo Alto, CaliforniaI ,']E4 U. S. Bureau of Mines

JAB John A. Blume & Associates Washington, 25, D. C.Research DivisionSat Francisco, California USC&GS U. S. Coast and GeodeticSurveyIR L Lawrence Radiation laboratory Las Vegas, NevadaLivermore, California USGS U. S. Geologic SurveyNRDL U. S. Naval Radiological Denver, ColoradoDefense Laboratory

San Francisco, California USPHS U. S. Public Health ServiceLas Vegas, NevadaREECo Reynolds Electrical &Engineering Co., Inc. USWB U. S. Weather Bureau

Las Vegas, Nevada Las Vegas, Nevada

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PROJECY DRIBBLE.

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vuf 3016 Salmon Event

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