ML22042A097

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Kairos Power LLC, Preliminary Safety Analysis Report
ML22042A097
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Site: Hermes File:Kairos Power icon.png
Issue date: 02/10/2022
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PreliminarySafetyAnalysisReport TheFacility

1.3 GENERALDESCRIPTIONOFTHEFACILITY 1.3.1 GeographicalLocation ThefacilityislocatedwithintheEastTennesseeTechnologyPark(ETTP)inOakRidge,Tennessee.Thefacility latitudeandlongitudeareprovidedinSection2.1.ThesitelocationisillustratedinFigure2.11.

1.3.2 PrincipalCharacteristicsoftheSite ThesiteconsistsofanarealocatedinthenorthwesternportionoftheHeritageCenterwithintheETTP (theETTPconsistsoftheHeritageCenter,siteofformeruraniumenrichmentoperations,andthe HorizonCenterIndustrialPark).ThepropertyisatthesiteoftheformerBuildingsK31andK33ofthe OakRidgeGaseousDiffusionPlant(ORGDP),whereuraniumenrichmentoperationsoccurredfrom1954 untilthemid1980s.Theoverallsiteisanapproximately185acre(74.8hectare)parcelthathadbeen usedasfarmlandpriortotheconstructionoftheORGDP.Thesitehassincebeenrestoredtoabrown fieldsitebyDOEandtheformerabovegradeportionsofthebuildingswereremoved.

ThesiteisentirelycontainedwithintheETTP,OakRidge,Tennessee.Thedominantlanduseinthesite areaisabrownfieldfromtheORGDPsite.OtheroperationsinthesiteareaareassociatedwithDOE facilities,ongoingconversionofformerDOEsitesforcommercialuse,andvariousindustrialactivities.

PrincipalcharacteristicsofthesitearefurtherdescribedinChapter2.

1.3.3 PrincipalDesignCriteria,OperatingCharacteristics,andSafetySystems 1.3.3.1 PrincipalDesignCriteria TheprincipaldesigncriteriaforthefacilityaredescribedinSection3.1.Theprincipaldesigncriteriafor thefacilityarebasedonthecriteriaincludedinKairosPowerTopicalReportKPTR003NPA (Reference1).

1.3.3.2 OperatingCharacteristics Thereactorisdesignedtoachieveareactorpowerof35MWth(designratedthermalpower)anda plannedoperationallicensedlifetimeof104years.ThereactorparametersareprovidedinTable4.11.

1.3.3.3 SafetySystems Thefacilityisafluoridesaltcooled,hightemperaturereactor.Thedesignofthereactorandfuelarediscussed indetailinChapter4.Theprimaryheattransportsystemandprimaryheatrejectionsystemare addressedinChapter5.ThesafetysystemclassificationisprovidedinTable3.61.

1.3.4 EngineeredSafetyFeatures Engineeredsafetyfeatures(ESF)areSSCsofthefacilitydesignedtomitigatetheconsequencesof postulatedevents.Forthenonpowerreactorfacility,theESFsarerelatedtothecontainmentoffission products,andthepassiveremovalofdecayheat.TheESFsaredescribedinChapter6.

1.3.5 Instrumentation,Control,andElectricalSystems Theinstrumentationandcontrol(I&C)systemmonitorsandcontrolsplantoperationsduringnormal operationsandplannedtransients.Thesystemalsomonitorsandactuatesprotectionsystemsinthe eventofunplannedtransients.TheI&Csystemiscomprisedoftheplantcontrolsystemandthereactor protectionsystem.TheI&CsystemisdiscussedinChapter7.

Theelectricalsystemprovidesthenormalandbackuppowertothefacility.Theelectricalsystemis discussedinChapter8.

KairosPowerHermesReactor 16 Revision0 PreliminarySafetyAnalysisReport TheFacility

1.6

SUMMARY

OFOPERATIONS AsnotedinSection1.1,thepurposeofthenonpowerreactorfacilityistotestanddemonstratethekey technologies,designfeatures,andsafetyfunctionsoftheKPFHRtechnologyanditsSSCs.Thefacility willalsoprovidedataandinsightsforthesafetyanalysistoolsandcomputationalmethodologiesused forthedesignandlicensingofaKPFHRcommercialpowerreactor.Themajorprogramstobe performedinthefacilitywillbeprovidedintheapplicationforanOperatingLicenseconsistentwith10 CFR50.34(b)(2).

Thereactorwillbeoperatedfora104yearlifetimeoverthefullrangeofpowertoevaluatethese aspectsofthetechnology.Theprocesssystemdesignsincludethenecessaryfeaturestomonitorand assessplantperformanceinsupportoftheseobjectivesasdescribedelsewhereinthisreport.The activationproductinventoryandfissionproductinventoryfromthenormaloperationofthefacilityand effluentreleasepathwaystotheenvironment,arediscussedinSection11.1andadescriptionofthe radiationsourcesforthefacilitywillbeprovidedintheapplicationforanOperatingLicenseconsistent with10CFR50.34(b)(3).

Ananalysisofpostulatedeventsfromoperationofthefacility,includingtheradiologicalconsequences ofunplannedreleases,isaddressedinChapter13.

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siteboundarywherethereactorsitemanagementhasdirectauthorityoverallactivitiesincluding exclusionorremovalofpersonnelandpropertyfromthearea.

TheEABiscoincidenttothesiteboundary.

TheLowPopulationZone(LPZ)is800metersfromthereactorasshowninFigure2.13.TheEmergency PlanningZone(EPZ)boundaryissetcoincidenttothesiteboundary.TheEPZisanareausedfor emergencyactivitiesintheeventofanemergency(Reference6).ThedosesattheEPZarebelowthe EnvironmentalProtectionAgency(EPA)ProtectiveActionGuide(PAG)Manualguidelinesforprotective action,asrecommendedbyANSI/ANS15.162015(R2020)andpursuanttoRegulatoryGuide2.6, EmergencyPlanningforResearchandTestReactors.Thisapproachisconsistentwiththeallowance forasmallerEPZin10CFR50,AppendixE.I.3.

2.1.2 PopulationDistribution Thissectionprovidespopulationdistributiondataforresidentandtransientpopulationsforthearea within5miles(8km)ofthecenterpointofthesiteforthefollowingyears(Reference9,Reference10):

Beginningoftherequestedlicenseperiod(2026)

Fiveyearsafterthebeginningoftherequestedlicenseperiod(2031)

Approximateendoftherequestedlicenseperiod(2036)

Estimatesandprojectionsofresidentandtransientpopulationsaroundthesitearedividedintofive distancebands(representedbyconcentriccircles).Thedistancesfromthecenterpointofthereactor are:0to0.5miles(0to0.8km),0.5to1mile(0.8to1.6km),1to2miles(1.6to3.2km),2to3miles (3.2to4.8km),and3to5miles(4.8to8km).Thedistancebandsarefurthersubdividedinto16 directionalsectors,eachcenteredononeofthe16compassdirectionsandconsistingof22.5degrees.

Foreachsegmentformedbythedistancebandsanddirectionalsectors,theresidentpopulationwas estimatedusingthemostrecentandcurrentlyavailabledecennialcensusyear(2010)(Reference9).The populationdataisusedintheenvironmentalmonitoringprogramdiscussedinChapter11.

2.1.2.1 ResidentPopulation Thedistributionoftheresidentpopulationfortheareawithin5miles(8km)ofthesiteisshownin Figures2.14toFigure2.178.Themapsillustratetown,city,andcountyboundaries.

Figure2.14showsthepopulationbyblockgroupusingthemostrecentandcurrentlyavailable decennialcensusyear(2010)withinthesite.Figure2.15alsoshowsthepopulationasof2010 decennialcensusbutdistributesthepopulationintofivedistancebandsbasedondistancefromthe centerpointofthereactor.Populationestimateswithineachquadrantandbandwerederivedfrom blockdata,asmallergeographicunitthanblockgroups,alsofromthe2010decennialcensus (Reference9).Todeterminethepopulationwithineachquadrantandband,apopulationdensitywas calculatedforeveryblockwithinthe5mileradius.Thepopulationwasrecalculatedbasedonthearea withinthequadrantsandbands.Foreachsegmentformedbythedistancebandsanddirectional sectors,thepercentageofeachblockareathatfalls,eitherpartiallyorentirely,withinthatsegmentwas calculatedusingthegeographicinformationsystemsoftwareknownasArcMap10.5.Theequivalent proportionofeachblockspopulationwasthenassignedtothatsegment.Ifportionsoftwoormore blocksfallwithinthesamesegment,theproportionalpopulationestimatesfortheblocksweresummed toobtainthepopulationestimateforthatsegment,asillustratedinTable2.11.

Figures2.16,and2.17,and2.18showthepopulationestimatesfor2026(thebeginningofthelicense period);and2031(5yearslater),and2036(approximateendofthelicenseperiod).Projectionsare basedoncountyestimatesforRoaneandMorganCountiesderivedfromtheBoydCenterforBusiness

KairosPowerHermesReactor 23 Revision0 PreliminarySafetyAnalysisReport SiteCharacteristics

andEconomicResearch,Tennesseesstatedemographer(Reference9).Thebasisoftheprojection methodwastheapplicationofagrowthratederivedfromthecountyprojectionstothe2010decennial censusblockdata.Thegrowth(orloss)ratewasdeterminedbycalculatingtheactualyearlypercent changeoftheestimatedpopulationgrowth(orloss)forRoaneandMorgancountiesasprojectedbythe statedemographer.Thesameannualrateswerethenappliedtothebaseyearof2010foreachcounty, whichwasthemostrecentdecennialcensusdataavailable,andprojectedforwardfortheyears2026, and2031,and2036.Thesamerateswereusedtoprojectpopulationchangesineachdistance/direction segmentineachcounty.

Tables2.11and2.12showthehistoricalpopulationfor2010andtheprojectedresidentpopulationfor theyears2026,and2031,and2036thatfallwithinthedistancebandsforRoaneandMorgancounties (Reference9,Reference10).

AsshowninFigure2.12,thenearestpermanentresidencetothereactorisaresidencelocated0.7 milesawaytothenorthwest.Figure2.13demonstratesthatthenearestresidentisoutsidetheLPZ.

2.1.2.2 TransientPopulation Transientpopulationsaretemporaryorseasonalpopulationsresidinginthearea,suchasinlodging accommodations,dormitories,orclassroomsonacollegecampus.Accordingtotheresultsofthe GoogleEarthdesktopresearch,therearenoschoolsorlodgingfacilitieswithin5miles(8km)ofthesite.

Thus,therearenotransientpopulationsinthearea.

2.1.3 References

1. EnvironmentalSystemsResearchInstitute(ESRI),TennesseeMap.2021.
2. U.S.DepartmentofEnergy(DOE)OakRidgeEnvironmentalManagementProgram,ETTPfactsheet.

2019.Retrievedfrom https://www.energy.gov/sites/default/fil es/2019/01/f58/ETTP%20fact%20sheet_0.pdf.

3. OakRidgeOfficeofEnvironmentalManagement,EastTennesseeTechnologyPark.Website:

https://www.energy.gov/orem/cleanupsites/easttennesseetechnologypark.

4. Parr,P.D,andHughes,J.F.,OakRidgeReservationPhysicalCharacteristicsandNaturalResources, OakRidgeNationalLaboratory,ORNL/TM2006/110.September2006.
5. U.S.DepartmentofEnergy(DOE),EnvironmentalMonitoringPlanfortheOakRidgeReservation, DOE/ORO2227/R5.October2012.
6. ANSI/ANS15.162015(R2020),EmergencyPlanningforResearchReactors.
7. U.S.GeologicalSurvey(USGS),ElevationsforSiteBuildings,2021.
8. NotUsed.
9. USCensusBureau,2010CensusBlockMaps.2010.Retrievedfrom https://www.census.gov/geographies/referencemaps/2010/geo/2010censusblockmaps.html.
10. TennesseeStateDataCenter,BoydCenterPopulationProjections,PopulationProjectionsfor TennesseeCounties20192070.October22,2019.Retrievedfrom https://tnsdc.utk.edu/estimatesandprojections/boydcenterpopulationprojections/.

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Figure2.18:ResidentPopulationDistribution-2036

Sources:Reference1,Reference9,Reference10

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2.3.1.14 ClimateChange Whileclimaticconditionschangeovertime,suchchangesarecyclicalinnatureonvarioustimeand spatialscales.Thetiming,magnitude,relativecontributionsto,andimplicationsofthesechangesare generallymorespeculative,evenforspecificareasorlocations.Further,themostextremeprojected changesarefortimescalesmuchlongerthantheapproximate410yearplannedoperationperiodfor theHermesreactor.

Projectedchangesaregenerallysmallcomparedtonaturalvariation.Generalpredictionsofglobalor UnitedStatesclimaticchangesexpectedduringtheperiodofreactoroperationareuncertainandare onlyapplicableonamacroclimaticscale.Becausethemaximumdataspanavailablewasusedinthe severeweatheranalysis,accuratesevereweatherphenomenahavebeenprovidedbasedonbest availablehistoricaldata.Projectionsoffuturesevereweatherconditionsatthesitearehighlyuncertain atbest,basedoncurrentunderstandingandmodelingofglobalclimatechange.Predictionsprovidedby theU.S.GeologicalSurvey(USGS)(Reference34)varyconsiderably.Forexample,onemodel(theBNU ESMmodel)givesasummermaximumtemperatureincreasefromapproximately89°Fto93°Fwitha standarddeviationofapproximately3°Fovertheperiodof2025through2049.

TheSouthernClimateImpactsPlanningProgramisaclimatehazardsresearchprogramwhosemissionis tohelpTennesseeresidentsincreasetheirresiliencyandlevelofpreparednessforweatherextremes nowandinthefuture.Theirresearch(Reference35)providesroughlyconsistentpredictionsrelativeto theUSGSofaveragetemperatureincreasesbetween2010and2100of48°F.Thisclimateprediction alsoindicatesmoreextremeprecipitationeventsthatcouldhaveaneffectonthethreatofflooding potentialingeneral.

TheORR,locatedinRoaneandAndersonCountiesineastTennesseeabout25mi(40km)westof Knoxville,ismanagedbytheDOE.ORRissuesAnnualSiteEnvironmentalReports(ASERs),availableat https://doeic.science.energy.gov/ASER/.AppendixBofthemostrecentASER(for2019)containsa substantialreviewoftheregionalclimatefortheORR,includingadiscussionofclimatechangetrendsin SectionB.1.

Althoughthelongtermclimatetrendfrommultiplesourcesindicatesamoderateincreaseinthe averagetemperatureandpossibilityofextremeprecipitationevents,asstatedabove,throughtheend ofthe21stcentury,thetimescaleoftheHermeslicensingperiodisaminorfractionofthisprojection period.

2.3.2 LocalMeteorology 2.3.2.1 LocalMeteorologicalDataOverview TheHermesReactorFacility(ReactorFacility)islocatedatthesoutheastportionofthesiteofthe formerK33buildingoftheEastTennesseeTechnologyPark(ETTP)complex.Sincethe1940s,thissite hasbeenunderthejurisdictionoftheAtomicEnergyCommission(AEC),whichbecametheDepartment ofEnergy(DOE)forthisfunction.Inthelate1940s,attherequestoftheAEC,theUnitedStatesWeather Bureauconducted,forthefirsttime,ameteorologicalsurveyoftheOakRidge,Tennessee,areato providedetailedinformationregardingwindflowpatternsandotherfactorstodeterminedispersionof radioactivecontaminants(Reference36).Thisstudyledtotheestablishmentofanextensivenetworkof meteorologicaltowersandforecastcapabilitythatisstillinexistencetoday.Amorerecentstudyofthe meteorologicalpatternsintheORNLareawascompletedin2011(Reference37).Thenetworkof meteorologicalobservationsprovidesastrongbasisfortheonsitemeteorologicaldataneededforthe siteaswellasthereactorfacility.

KairosPowerHermesReactor 251 Revision0 PreliminarySafetyAnalysisReport ReactorDescription

HeavyloadconsiderationsareaddressedinSection9.8.4,CranesandRigging.Thesefeatures demonstratecompliancewithPDC4.

Corecoolingismaintainedthroughthedesignofthereactorvesselandthereactorvesselinternals.As describedinSection4.3.1.2,thevesselandvesselinternalsdefinethecoolantflowpath.Topreclude degradationtothevesselduetocorrosionofthestainlesssteel,thereflectorblocksandthevesselare baked(i.e.,heateduniformly)toremoveresidualmoisturepriortocomingintocontactwithcoolant.

Thereflectors,whichactasaheatsinkinthecore,arespacedtopreventtheformationoftensileand bendingstressesandaccommodatethermalexpansionandhydraulicforcesduringnormaloperation andpostulatedevents.Thegapsbetweenthegraphiteblockssupportcoolantflowtothereflectorthus maintainingacoolablecoregeometryandprecludingreflectordegradationbyoverheating.Maintaining acoolablecoregeometryandadequatecoolantflowthroughthecoreensuresthevesselwall temperatureisbelowdesignlimitswhichpreventvesselfailure.Dynamicbehaviorofthereactor,its support,anditsinternalsareanalyzedanddesignedtoensurevesselintegrityandcoregeometryare maintainedinadesignbasisearthquaketoadegreesufficienttoensurepassiveheatremoval.The vessel,aspartofthereactorcoolantboundary,ensuresthecontainmentofradionuclidesbyensuring thecoolantisconfinedandtheTRISOparticlesinthefuelpebblesareprotectedfromdamage.These featuresdemonstrateconformancetoPDC10.

TodemonstratecompliancewithPDC14,thereactorvesselisfabricated,erected,andtestedsoasto haveanextremelylowprobabilityofleakage,rapidlypropagatingfailure,andgrossrupture.Thereactor vesselmaterialsandweldmetalwillbequalifiedforuseasdescribedinKairosPowertopicalreport MetallicMaterialsQualificationfortheKairosPowerFluorideSaltCooledHighTemperatureReactor, KPTR013P(Reference3).The316HSSofthereactorvesselasfabricatedandtestedinaccordance withReference1standardshasahighfracturetoughnessatreactoroperatingconditions,thusreducing thelikelihoodofcrackpropagation.Thedesignofthereactorvesselandvesselinternalssupporta410 yearoperatinglifetime.Thisisaccomplishedbyoperatingthereactorvesselwithintheasdesigned operationalandtransientconditionstressesandbymonitoringforchanges(e.g.,irradiationand thermallyinduceddegradation,corrosion,creep)tothereactorvesselduringinserviceinspectionand testing.TheRVSSreactorvesselbottomheadinterfaceisdesignedtoallowaccessforweldinspections.

Thereactorvesseltopheadsupportsinserviceinspectionofattachmentsandpenetrations.

Thereactorvesselshellandbottomheadmaintainacoolantpathwayforcoolingthereactorcoreand ensuresubmergenceoffuelpebblesinthecore.Thereactorvesselisfabricated,erected,andtestedin accordancewithReference1asaClassAcomponenttoaccountforthermalandphysicalstressesduring normaloperationandpostulatedevents.Thevesselisfabricatedfrom316HSSbasemetalandER1682 weldmetalusingagastungstenarcweldingprocess.Reference1providesforweldmentstressrupture factorsuptoatemperatureof650°CforER1682weldmetalwith316Hbasemetal.Testingprovides stressrupturefactorsupto816°Cforweldmaterialwith316Hbasemetal(Reference3).Theplant controlsystemwilldetectleakagefromthereactorvesselandcatchbasinsareusedtodetectleaksin nearbycoolantcarryingsystems.ThesefeaturesdemonstratecompliancewithPDC30.

Reactorvesselstressrupturefactorsaredeterminedupto816°Ctoencompasstransientconditions.

Thestressrupturefactorsaredeterminedbyacreeprupturetestonthevesselbasematerialwithweld metalunderthegastungstenarcweldingprocess.Thevesselprecludesmaterialcreep,fatigue,thermal, mechanical,andhydraulicstresses.Theleaktightdesignofthereactorvesselheadminimizesairingress intothecovergasandprecludescorrosionoftheinternals.Thehightemperature,highcarbongrade 316HSSofthecorebarrelandreflectorsupportstructurehavehighcreepstrengthandareresistantto radiationdamage,corrosionmechanisms,thermalaging,yielding,andexcessiveneutronabsorption.

Vesselfluencecalculations,asdescribedinSection4.5,confirmadequatemarginrelativetotheeffects

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inspection,thepebblesaredirectedforreinsertionintothecore,ortopebblestorageforremovalfrom thecirculatingpebbleinventory,basedoninspectionresults.

9.3.1.5 PebbleInspection AnautomatedinspectionsystemprovidesinformationtotheprocessingportionofthePHSSfor determiningpebblehealth.Thisincludesinspectionofthephysicalconditionofthepebblefor unacceptablewearordamage,identifyingmoderatorandfuelpebbles,aswellasanevaluationofthe burnupofthefuelrelativetoamaximumburnuplimitusingtheburnupmeasurementsensor(BUMS).

Theburnupmeasurementisdonebymeansofagammaspectrometer.Furtherdetailspertainingto inspectionsforwearanddamagewillbeprovidedwiththeapplicationforanOperatingLicense.

9.3.1.6 PebbleInsertion Pebblesarereceivedfromtheprocessingsystemandplacedinabufferstorageuntilrequiredfor reinsertion.Thepebblebufferstorageissizedandorientatedtopreventacriticalconfiguration.

Individualpebblesarefedintothestepfeederinsertionmachinefromthispebblebufferstorageas showninFigure9.32.Thepebblesareinsertedintothetopofthereactorvesselhead,thenpushed throughtheinsertionlineandenterthereactorcoreviatheinvesselfuelingchuteatthebottomofthe core(seeSection4.3).Thereisasingleactiveinsertionlineintothevessel.

9.3.1.7 PHSSInertGasBoundary ThecomponentsofthePHSSaredesignedtomaintainaninertgasboundaryoutsideofthereactor vesselforpebblehandling.Thefunctionoftheinertgasenvironmentistopreventabsorptionof moistureandoxygenintopebblesforpebblehandlingduringnormaloperations.Theinertgasboundary withinthePHSS(seeFigure9.32)iscreatedbyamechanicalstructurethatenclosesthe aforementionedcomponentswithpenetrationsformotorshafts,storageoutlets,inspectionviewport, datachannels,electricalpower,andpebblesfromtheoffheadconveyancemechanismandfor insertion.Portionsoftheinertgasboundarythatareadjacenttopersonnelaccessareashavethe appropriateradiationshielding.

9.3.1.8 PebbleStorage Pebblestorageisprovidedforpebbledebris,damagedpebbles,spentfuel,andendoflifemoderator pebbles.Thestorageportionofthesystemiscomposedofastainlesssteelstoragecanisterand transporterdevice.Individualstoragecanistersaresizedtoholdapproximately1,9002,100pebbles.

Thedimensionsofthecanisterandquantityofpebblesaresizedtomaintainanoncriticalconfiguration.

Atransporterdeviceisusedtotransfercanisterstoeitherthespentfuelstorageareaduringnormal operationorthefullcoreoffloadareaintheeventofaperiodicmaintenancefullcoreoffloadoran emergentfullcoreoffload.

9.3.1.8.1 SpentFuelStorage Spentfuelisdischargedfromserviceinthecoreundernormaloperatingconditions,placedinsealed storagecanisters,andmovedtothespentfuelstorageareaasshowninFigure9.32.Theinitialstorage areaisacoolingpooldesignedtoholdspentfuelcanisterswhilethedecayheatofthepebblesdrops.

Thepoolisdesignedtolimitradiationexposuretopersonnel.Aftercoolinginpoolstorage,thecanisters aremovedtoaconcretestoragebaywithradiationshieldingandforcedaircooling.Thepoolisactively cooledbytheCCWSusinganinpoolheatexchanger.WaterisrecirculatedinthepoolbytheSFCSand makeupwaterisprovidedbythetreatedwatersystem(seeSection9.7.2).Thepoolandconcrete storagebayaredesignedtopreventacriticalconfiguration.Thestoragebayissizedsizingissufficientto storespentfuelandmoderatorpebblesgeneratedduringthe410yearoperatinglifetimeofthereactor.

KairosPowerHermesReactor 925 Revision0 PreliminarySafetyAnalysisReport AccidentAnalysis

13.2 ACCIDENTANALYSISANDDETERMINATIONOFCONSEQUENCES 13.2.1 MaximumHypotheticalAccident 13.2.1.1 MethodologyandInputs ThecalculationofthedoseconsequencesoftheMHAusesthesourcetermmethodsfordesignbasis accidentspresentedinReference1.Section13.1.1providestheMHAnarrativeandassumptions.This sectionprovidesahighlevelsummaryofthemethodsusedandtheinputstothecalculation.

TheevaluationoftheMHAdoseconsequencesfirstidentifiesandaccountsforthesourcesofMARand thebarrierstorelease.Eachbarrieristhenevaluatedforareleasefractiontoprovidedose consequencesattheexclusionareaandlowpopulationzoneboundaries.

ThefoursourcesofMARandtheassociatedbarrierstoreleaseintheMHA:

TRISOfuelinthereactorcore o Barriers:TRISOlayers,Flibe,andgasspace Circulatingactivity o Barriers:Flibeandgasspace StructuralMAR o TritiumretainedbygraphiteandinFlibe Barriers:Graphitegrains(fornonFlibetritium)andgasspace o Argon41retainedinclosedgraphitepores Barriers:GraphiteporesandGasspace Section13.1.1describesseveralnonphysicalconditionsthatarehypothesizedtoensureabounding MHA:

Pretransientdiffusionofradionuclidesfromthefuelinthereactorcoreisneglected:This conservatismisachievedintheevaluationbyassumingthatthefullradionuclideinventoryofthe fuelisavailableforreleaseattheinitiationoftheMHA.Thecirculatingactivityisstillassumedtobe atanupperboundlevel.Therefore,anyMARoriginatinginthefuelthatcontributestothe circulatingactivityiseffectivelydoublecounted.

Hypotheticaltemperaturehistoriesareappliedtothetransient:thehypotheticaltemperature historiesappliedtotheMHAisprovidedinFigure13.21.Thesetemperaturessetanupperlimitfor thefigureofmerittemperaturesinthepostulatedevents.

ThegasspaceisnotcreditedforconfinementoftheradionuclidesthatreleasefromtheFlibefree surface:radionuclidetransportinthegasspacebarrierismodeledusingtheconservativebuilding transportandoffsitedispersionmethodsdescribedinReference1.

Conservative,unfiltered,groundlevelreleases:thegasspacetransportevaluationassumesa conservativeleakagerateforthereactorbuildingthatreleasestheentirevolumewithina2hour windowtoavoidcreditingthebuildingasaconfinementstructure.Thedispersionevaluation assumesnoradionuclidesarefilteredafterthebuildingtransportisevaluatedtoavoidtakingcredit foranyradionuclidefilteringthatcouldoccurintheHVACsystem.

Initialtritiuminventoriesarecalculatedforanassumed50MWthcorethatoperatesatawithan assumed100%capacityfactorovertenyears.Loweroperatingpowersresultinalowertritium productionrateandlowercapacityfactorsallowforthegraphitegrainstoexperiencetimeperiods oftritiumdesorptioninsteadofsorption.

Aboundingvesselvoidfractionof0.1isassumedtofacilitatethereleaseoflowvolatilityspeciesin thevesselviabubbleburst.

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15.2 FINANCIALABILITYTOOPERATETHEKAIROSPOWERFACILITY KairosPowerexpectstoapplyforaClass104licenseper10CFR50.21(c)(fortesting,research,and developmentactivities),andreceipt,possessionanduseofsourcematerialunder10CFR40,byproduct materialunder10CFR30,andspecialnuclearmaterialunder10CFR70.KairosPowerfinancial projectionsassumea410yearoperatingperiodforthenonpowerreactorfacility.

KairosPowerhasreasonableassuranceofobtainingthenecessaryfundstocoverestimatedfacility operationcostsfortheperiodofthelicense.Operatingcostsforthefacilitywillbecoveredbysustained privateinvestmentfromKairosPowerinvestors,withpotentialsupplementsfromotherfunding sources.Estimatesofthetotalannualoperatingcostsforeachofthefirstfiveyearsofoperationofthe facilitywillbeprovidedwiththeapplicationforanOperatingLicenseconsistentwith10CFR50.33(f)(2).

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