ML19323F365

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Forwards Comments on Draft Plan for long-range Water Reactor Research
ML19323F365
Person / Time
Issue date: 11/13/1979
From: Harold Denton
Office of Nuclear Reactor Regulation
To: Levine S
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML19323F361 List:
References
NUDOCS 8005280855
Download: ML19323F365 (30)
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NUCLEAR REGULATORY COMMISSION

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..y WASHINGTON,0. C. 20558 tiovembe' 13, 1979

.,. j MEMORANDUM FOR: Saul Levine, Director Office of Nuclear Regulatory Research FROM:

Harold R. Denton, Director Office of Nuclear Reactor Regulation

SUBJECT:

L0f1G-RANGE RESEARCH PLANS By memorandum dated August 1,1979, the EDO requested that the user Offices supply RES with a list of long-range research objectives.

My staff provided preliminary input to Dr. Tong to assist in the development of a draft plan for water reactor safety research (Enclosure 1). provides NRR coments on this draft plan. Enclosure 3 lists additional objectives that were either received too late to be included in Dr. Tong's draf t plan or that address topics in other program areas.

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Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

As stated 8005280

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L.llCl.O.S.u.t!E.l.

PLAN FOR WATER REACTOR SAFETY RESEAllCll Septenher 21, 1979 DiJectlyes A. Research Support B. Separate Efin as C. Loff Research D. Analysis Develoinent E. Fuel Behavior F. Metallurgy & Materials Branch Branch Branch 8ran(h Branc h Uranc h I. Accident Detection &

l.' Noise Analysis

1. In-pile
4. In-plie
1. In-pile I. IIDE Preventlun ll. Monitoring instrumentation instrumentation Instressentation ll, teak Detector instrumentation Application ill. Valve festing E 5eparate Ef fects fests I. 2DDD Tests
1. Semiscale Tests
1. 2D/3D Analysis
1. Clad and Fuel
8. Fracture itechanics for unJer-II. Secos=lary
11. lleet Transfer fests li. Blat Containment Studies
18. Environmental Ef fects standia.g &

Reliability study ill. Tue-phase Flow Analysts ll. Hydrogen Study on Materials hieling &

Tests lit. Bult lastability fil. Water Chemistry Reactor Iv. Sump lest Engineering Review 1.~5ysfem Evaluation

8. Fire protection I. LOIT lests
1. Intelligent $1mulator Tests & Reac-II. Ivallfl.ation Test

$1. Diagnostic tor Operation lit. Itanan Factor

& Control Display

/.

Research 111. System Analysis 47Aniliilcal a

Tool Develop-

1. Phe logical
1. Code Development
1. Fuel Code
1. Structure Code ment & Acci-Model evelopment ll. Code Assessment Development, dent Analy-lit. Code Application Assessatnt, &

sls Iv. Doppler Effect Application CAccide'nl Consequence Evaluation &

l. Fuel Damage C:ltigation Mechanism &

Threshold

18. Core Meltdonsi

&lndfcales had Fanch 6

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OBJECTIVES A. RESEARCH SUPPORT B. SEPARATE EFFECTS BRAi4CH BRAtiCH

1. ACCIDENT DETECTION &

PREVENTION 1.

NOISE ANALYSIS 1.

IN-PILE INSTRUMENTATION

11. MONITORING INSTRUMENTATION APPLICATION iii. VALVE TESTING
2. SEPARATE EFFECTS TESTS FOR UNDERSTANDING 1.

2D/30 TESTS 1.

SEMISCALE TESTS

& MODELING & REACTOR ii. SECONDARY RELIABILITY ii. HEAT TRANSFER TESTS ENGINEERING REVIEW STUDY fii. TWO-PHASE FLOW TESTS iv. SUMP TEST

3. SYSTEM EVALUATION TESTS

& REACTOR OPERATION &

i.

FIRE PROTECTION CONTROL RESEARCH

11. QUALIFICATION TEST iii. HUMAN FACTORS
4. ANALYTICAL TOOL DEVELOPMENT &

i.

PHENOMIN0 LOGICAL ACCIDENT ANALYSIS MODEL DEVELOPMENT

5. ACCIDENT CONSEQUENCE.

EVALUATION & MITIGATION

  • INDICATES LEAD BRANCH e

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OBJECTIVES C. LOFT RESEARCH D. ANALYSIS DEVELOPMENT BRANCH BRANCH

1. ACCIDENT DETECTION &

PREVENTION 1.

IN-PILE INSTRUMENTATION

2. SEPARATE EFFECTS TESTS FOR UNDERSTANDING i.

2D/3D ANALYSIS

& MODELING & REACTOR

11. BWR CONTAINMENT ANALYSIS ENGINEERING REVIEW iii. BWR INSTABILITY
3. SYSTEM EVALUATION TESTS

& REACTOR OPERATION &

i.

LOFT TESTS 1.

INTELLIGENT SIMULATOR CONTROL RESEARCH ii. DIAGNOSTIC DISPLAY iii. SYSTEM ANALYSIS

4. ANALYTICAL TOOL DEVELOPMENT &

i.

CODE DEVELOPMENT ACCIDENT ANALYSIS

11. CODE ASSESSMENT iii. CODE APPLICATION iv. DOPPLER EFFECT
5. ACCIDENT CONSEQUENCE EVALUATION & MITIGATION
  • INDICATES LEAD BRANCH i

03JECTIVES E. FUEL BEHAVIOR F. METALLURGY & MATERIALS BRANCH BRANCH

1. ACCIDENT DETEC' TION &

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PREVENTION 1.

IN-PILE INSTRUMENTATION 1.

NDE ii, LEAK DETECTOR

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2. SEPARATE EFFECTS TESTS FCR UNDERSTANDING 1.

CLAD AND FUEL STUDIES f.

FRACTURE MECHANICS

& MODELING & REACTOR

'i i. HYDROGEN STUDY ii. ENVIRONMENTAL EFFECTS ENGINEERING REVIEW iii. WATER CHEMISTRY ON MATERIALS

3. SYSTEM EVALUATION TESTS

& REACTOR OPERATION &

CONTROL RESEARCH

4. ANALYTICAL TOOL DEVELOPMENT &

i.

F!)EL CODE DEVELOPMENT, i.

STRUCTURE CODE ACCIDENT ANALYSIS ASSESSMENT & APPLICATION

5. ACCIDENT CONSEQUENCE EVALUATION & MITIGATION f.

FUEL DAMAGE MECHANISM &

THRESHOLD ii. CORE MELTDOWN

  • INDICATES LEAD BRANCH l---

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F rtw w

l 1.

ACCIDENT DETECTION AND PREVENTION A.

RESEARCILSUITORLBRANCll-NOISE DIAGNOSTICS FOR SAFETY ANALYSIS PERFORM A FEASIBILITY STUDY OF USING Tile 252 CF NOISE ANALYSIS FOR Tile DETERMINATION OF REACTIVITY (FY 1982)

IDENTIFICATION OF DEGRADED PLANT SITUATIONS AND DEVELOPENT OF APPROACilES AND PROCEDURES TO HANDLE Tile SITUATION (FY 198't)

CONTINUE AND COMPLETE Tile DEVELOPMENT OF AN AUTOMATIC SURVEILLANCE MONITORING SYSTEM FOR PLANT SIGNALS (FY 1983)

CONTINUE ANI) COMPLETE Tile DEVELOPENT OF A STABILITY PEASilREENT TECilN100E FOR i

DWRS (FY 1983)

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COMPLETE Tile FIELD MEASUREMENTS PROGRAM FOR LOOSE PARTS DETECTION (FY 1982)

CONTINUE AND COMPLETE Tile ASSESSMENT OF LEAK DETECTION METil0DS BY APPLYING NOISE DIAGNOSTIC TECllNIQUES TO AC0USTIC NOISE SIGNALS (FY 1982) 11.

f10NLIDRINE_ INSTRUMENTATION APPLICATION ASSESS Tile EFFICACY OF IMPROVED t10NITORING SYST'EPS (FY 1932)

DEVELOP INSTRUMENTATION IN SUPPORT OF IE RESII)EtlT INSPECTOR PROGRAM (FY 198'l) i

1.

ACCIDENT DETECTION AND PREVENTION A.

BESEARGl SUPPORT BRAN G (CONTINUED) lit.

VALVE TESTING

- PARTICIPATE IN IllDUSTRY FULL-SCALE VALVE TESTlHG AliD COOPERATIVE EFFORTS UNDER WAY WITil JAPAN AllD GERMANY ON VALVE TESTING (FY 1982) i

- ASSESS SAFETY / RELIEF VALVE OPERABILITY AND RELIABILITY INCLUDING FLOW DISOIARGE' RATE AliD SYSTEM STRUCTURAL' EFFECTS (FY 1983)

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2.

SEPAL'AIE EFFECTS lESTS FOR UllDERSTAllDlHG AliD MODELiliG AND REACTOR ENGINEERING REVIEW

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A.

RESEARCll SUPPORT BRANCil i.

2D/3D TESIS STUDY INTEGRAL MULTIDIMENSIONAL CORE AND DOWNCOMER llYDRAULIC BEllAVIOR DURING LATE BLOWDONW AND REFILL AND RCFLOOD (FY 198'l)

STUDY UPPER PLENUM DE-ENTRAINMENT AND FALL BACK (FY 1984)

PROVIDE INFORMATION ON llPPER PLENUM INJECTION (FY 198ti)

PROVIDE INFORMATI0fl ON INFLUENCES OF STEAM GENERATORS (DE-ENTRAINMENT, STORAGE, llEAT TRANSFER, HYDRAULIC LOADS) (FY 1984)

STUDY EFFECTS OF FLOW BLOCKAGE (FY 1983) ti.

SECONDARY SYSTEtLRELIARILITY STUDY PIIOVIDE EXPERT TECilNICAL ASSISTANCE TO NRR IN DEVELOPING SPECIFIC AND GENERAL LICENSillG SAFETY REQUIREMENTS (FY 1982) 2 ASSIST NRR IN RE-EXAMINING AUXILIARY SYSTEMS DESIGN CRITERIA BASED.ON STUDIES 0F B0P SYSTEM TRANSIENTS (FY 1982) l

.4

3.

SYSTEN EVALUAT10ll TESTS AliD REACTOR OPERATION AND CONTROL RESEARCil A.

RESEARClLSl!EEDRT BRANCll i.

ElRE PROTECTIDH C0llPLETE FULL-SCALE REPLICATION TESTS AND FIRE SUPPRESSION SYST.EM STUDIES (FY 1982)

OBTAIN DATA ON Tile EFFECTIVENESS OF SAFETY-RELATED EQUIPMENT (OTiiER THAN CABLE)

IN PERFORMING SAFETY FUNCTIONS WilEN SUBJECTED TO EXPOSURE FIRES (START FY 1981, COMPLETE FY 19811)

STUDY CORROSION OF STAGNANT FLUIDS IN FIRE PROTECTION SYSTEMS (START FY 1982, COMPLETE FY 1986)

II.

QUAllFICATION TESTING EVALUATION COMPLETE ASSESSMENT OF Tile VARIOUS OllALIFICATION TESTING METil0DOLOGIES (FY 1986)

DEVELOP OUALIFICATION METil0DOLOGY FOR QUALIFYING INSTRUMENTS TO E0LLOW Tile COURSE OF AN ACCIDENT (FY 1983)

DEVELOPMENT OF IMPROVED CONSTRUCTION MONITORING AND QUALITY CONTROL TESTING PROCEDURES TO ENSURE TilAT 111Gll QUALITY CONSTRUCTION IS BEING ACillEV'ED (FY 1983)

PROVIDE SUPPORT ON DEVELOPMENT OF ENVIRONMENTALLY INVULNERABLE IlYDRAULIC MOTOR DRIVES FOR IN-CONTAINMENT USE (FY 198ti)

ESTABLISil Tile MINIMUM ACCEPTABLE SAFETY AND RELIABIt.ITY REQUALIFICATION REbu FOR THI-2 EQUIPMENT Ill Tile PLANT (FY 1982)

3.

SYSTEM EVALUATI0ll TESTS AllD REACTOR OPERAT10H At!D CONTROL RESEARCll A.

RESEARCILSDEEDRT_BRANEll iii. IluMalLEACIDRS DEVELOP BETTER UNDERSTANDING 0F Til0SE IlUMAN FACTORS WillCil ARE IMPORTANT IN ENSURING TilAT Tile OPERATOR CAN FUNCTION EFFECTIVELY TO CONTINUE OFF-NORMAL EVENTS.

Tills Sil00LD BE REFLECTED IN CONTROL SYSTEM AND CONTROL ROOM DESIGNS (FY 1983)

DEVELOP llUMAN FACTORS INPUT T0 IMPROVE OPERATOR TRAINING FOR DEGRADED FLANT CONDITIONS (FY 1982)

C0f1PLETE Tile SAFETY-RELATED OPERATOR ACTION STUDY (FY 1983)

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l WAIDLREACTOR SAFETY RESEARQI PLAN 1.

ACCIDENT DETECTION AND PREVENTION B.

SEPARATE EFFECTS BRANCil I.

REACTOR INSTRUMENTATION PWR LIQUID LEVEL IN CORE

- IIEATED T.C.

- ULTRAS 0NICS

- SELF-POWERED NEUTRON DETECTOR PWR PRESSURIZER LEVEL

- ULTRASONIC SOUNDING j

STEAM GENERATOR BUBBLE (PRIMARY SIDE)

- GAMMA BEAMS i

- ULTRAS 0NICS NATURAL CIRCULATION FLOW MEASUREMENT

- IIEATED T.C.

- PULSED NEUTRON ACTIVATION e

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2. SEPARATE EFFECTS TESTS FOR UNDERSTAllDlHG AND MODELING AND REACTOR ENGINEERING RENEW B.

SEPARATE EFFECTS BRANCila 1.

SEMISCALE TESTS

- BLOWDOWN REFILL AND REFLOOD,llEAT TRANSFER DATA

- SMALL BREAK TEST DATA l

- THI-2 RELATED EXPERIMENTS 1

- Uill INTEGRAL SYSTEM TEST

- ECC BYPASS

- LOWER PLENUM V0IDING

- STEAM GEllERATOR llEAT TRANSFER.DURING REFLOOD II.

IIEAT TRANSFER TESTS

- BDilT (0RNL) FOR SMALL BREAK TRANSIEllT, POST-CllF llEAT TRANSFER; REWET (COMPLETED BY FY 1981)

- PWR FLECllT SEASET 01); SYSTEM EFFECT OF REFLCOD, BL'0CKAGE TESTS, j

GRID EFFECTS, STEAM GENERATOR TESTS (COMPLETEJ BY FY 1982)

- BLOWDOWN AND ECC (GE); BLOWDOWN llEAT TRANSFER AiB ECC BEHAVIOR T0 j

8 X 8 ButlDLE WITH SIMULATED ELECTRICAL RODS (FY 1982)

(

2.

SEPARATE EFFECTS TESlS FOR UNDERSTAl:DIt:G AllD MODEllllG AND REACTOR ENGINEERING REVIEW B.

SEPARATE EFFECTS BRANCll (CONTINUED) 111.

TWO PilASE FLOW TESTS

- STEAM WATER MIXING IN DOWNCOMER TO DETERMINE ECC BYPASS (BCL AND CREARE, FY 1980)

IV.

SUMP TEST (SANDIA)

- TO DETERMINE THE IlYDRAULIC BEllAVIOR OF RECIRCULATED COOLANT FROM CONTAINMENT

- INSULATOR DEBRIS EFFECT ON SUMP PUMP EFFICIENCY G

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li.

ANALYTICAL TOOL DEVELOPMENT AND ACCIDENT ANALYSIS 11 SEPARATE EFFECTS BRANCll 1.

PilEN0MENGLOGIGAL MODEL DEVELOPMENT

- IIEAT TRANSFER FOR SLOW BREAK TRANSIENT (ORllL, H AND INEL)

INCLUDING llEAT TRANSFER TO WET STEAM, DRY STEAM, LEVEL SWELLING

- POST-CllF llEAT TRANSFER, INCLUDING FILM BOILING', TRANSITION BOILING AND REWET (0RNL, INEL, LElllGil BY FY 1981)

- CONDENSATION IN PARALLEL STEAM 0F WATER AND STEAM (NWU, FY 1981)

-VAPORGENER4TIONRATEANDCONDENSATIONRATEINdlSPERSEDFLOW (BNL AND NWU, BY FY 1981)

- TWO PilASE FLOW INSTEAMGENERATOR (EIT, FY 1982) INCLUDING MULTI-CllANNEL EFFECT, NATURAL CIRCULATION LOOP

- PilASE DISTRIBUTION AND PilASE SEPARATION IN VARIOUS CilANNEL i

GE0 METRY (RPI, FY 1981)

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ANALYTICAL TOOL DEVELOPMENT AND ACCIDENT ANALYSIS B.

SEPARATE EFFECTS BRANCll (CONTINUED)

- PARALLEL CllANNEL EFFECT IN BWR (RPI, FY 1981)

- TWO FLUID MODEL (ANL, FY 1980)

- DROPLET FLOW PROFILES IN END BOX AND IN BLOCKED BUNDLE (SUNY FY 1981) 1 e

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1. ACCIDENT DETECTION AND PREVENTION C. LOFT RESEARCil BRANCil l

1.

IN-PILE INSTRUMENTAT10!(

  • COMPARISON OF EX-CORE IN CilAMBERS CLAD TilERM0C00PLES USED IN LOFT AND RECORDED COOLANT TilERM0000PLES DURING CORE UNC0VERIES TO ASSESS GUIDE TUBE TilERM0C00PLES THEIR VALUE IN MEASURING CORE SELF-POWEP,tD NLUTION DETECTORS UNC0VERY DURING ACCIDENT CONDITIONS LIQUID LEVEL TRANSDUCERS j

'LIQUIDSUBC00LINGMETERN0WDEVELOPEDAilDOPERATIONALINLOFT "FOLLOWING NRR AND OTHER NRC ASSESSMENTS OF IN-CORE INSTRUMENTATION CONSIDERED USLful TO LWRS, INSTALL AND TEST INSIT THOSE CONTENDERS FOR LWR INSTALLATION.

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3.

SYSTEM EVALUATION TESTS AND REACTOR OPERATION AND CONTROL RESEARCll C.

LOFT RESEARCil BRANCll r.

LOFT TESTS LOFT TESTS IN FY 80

  • COLD-LEG SMALL BREAKS - L3-1 CONTINUED DEPRESSURIZATION (11/79)

L3-2 IIANGUP AT INTERMEDIATE PRESSURE (2/80)

L3-2 REPRESSURIZATION (7/80)

L3-4 STUCK OPEN RORV (S/80)

  • Il0T-LEG SMALL BREAKS.- L3-5 PRIMARY COOLANT PUMP 0FF (3/80)

- L3-6 PRIMARY COOLANT PUMP DN (3/80)

  • OPERATIONAL TRANSIENT - L6-1 STEAM LINE BREAK (S/80)

L6-2 LOSS OF PCS FLOW (7/80) t LONG TERM

  • COMPLETE LARGE BREAK POWER ASCENSION SERIES
  • INTERMEDIATE BREAKS

" ADDITIONAL SMALL BREAKS AND AN0MALOUS TRANSIENTS e

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9 3.

SYSTEM EVALUATION TESTS AND REACTOR OPERATION AND CONTROL RESEARCll C.

LOFT RESEARCll BRANCll (CONT'D)

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11. DIAGNOSTIC DISPLAY BEING INSTALLED IN LOFT 2 USES: - STUDY EFFECTIVENESS.IN DETECTING PROBLEM ANNUNCIATING, ADVICE TO OPERATOR, AND PREVENTING ACCIDEllT

- STUDY MEANS OF PRESENTING INFORMATION TO OPERATE DU' RING A) NORMAL OPERATING CONDITIONS B) COURSE OF AN ACCIDENT SEQUENCE (EARLY RESULTS EXPECTED LATE '80) 111. SYSTEM ANALYSIS

  • APPLY LOFT TEST RESULTS TO ASSESS AND DEVELOP LOCA AND TRANSIENT CODES

-

  • IN PLANNING A TEST,BEST ESTIMATE ANALYSIS COULD IDENTIFY BEHAVIOR AT VARIANCE WITil TilAT EXPECTED.

Tills SERVES NOT ONLY TO ASSESS ATYPICALITIESINLOFT,SUTALSOBRINGSATTENTIONTOUNANTICIPATED BEllAVIOR IN LWRs.

1 I

2.

SEPARATE EFFECTS TESTS FOR UNDERSTANDING AND MODEUNG, AND REACTOR ENGINEERING REVIEW 11.

ANALYSIS _DEVELOPliERLDRAN0l i,

2D/3D ANALYSIS PROVIDE COMPUTER MODELS TO DESCRIBE MULTIDIMENSIONAL EFFECTS OF BLOWDOWN, REFILL AND REFLOOD PLUS DE-ENTRAINMENT AND FALLBACK (FY 1984)

PROVIDE PRETEST PREDICTIONS AND POST-TEST ANALYSES OF 2D/3D TESTS (FY 1984) ii.

BWR CONTAINHERLANALYSIS_

PROVIDE IMPROVED ANALYTICAL MODELS FOR BWR CONTAINMENT RESPONSE (FY 1983) 111. BWR INSTABILITY DEVELOPANALYTICALMODELTOANALYZESTABillTYOFBWRS(FY1983) g 8

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l 3.

SYSTEl1 EVALUATION TESTS AND REACIOR OPERATION AND CONTROL RESEARCil D.

ANALYSIS DEVELOPBEMLBRANDL I

i i.

IHIELLl6ENT SillulAIDRS DEVELOP INTELLIGENT SIMULATOR TO ASSESS PROBABILITY OF ACCIDENT OCCURRENCE (FY 1986) i I

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11.

ANALYTICAL TOOL DEVELOPMENT AND ACCIDENT ANALYSIS D.

ANALYSIS _ DEVELOPMENT BIIANCll

  • i.

CODE _DEVEL0EMENL DEVELOP STEAM GENERATOR CODES AND MODELS (FY 1980)

DEVELOP A BWR-LOCA BEST ESTIMATE COMPUTER CODE (FY 1982) 4 DEVELOP Ulli AND UPI MODELS (FY 1981)

PROVIDE ANALYTICAL TOOLS FOR A FAST CALCULATING CAPABILITY TO ANALYZE ALL l

POSTULATED REACTOR SYSTEM TRANSIENTS (FY 1985)

ESTABLISil A COMPUTER MODEL INPUT DATA BANK (FY 1984)

PROVIDE FOR REACTOR PilYSICS C01)E ACQUISITION, IMPROVEENT, CllECK00T AND l

ASSESSMENT (FY 1984)

EDDE_ASSESSHEMI 11.

COMPLETE ASSESSENT OF LOCA AND TRANSIENT CODES (FY 1986)

COMPLETE ASSESSENT OF BEACON USING NEW SUBCOMPARTENT TEST DATA (FY 1983)

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11.

ANALYTICAL TOOL DEVELOPifNT AND ACCIDENT ANALYSIS D.

ANALYSIS DEVEl0PMENT BRANCll (CONTINUED) gli. CODE APPLICATIDH ANALYZE EFFECTS OF ECCS LOCATION AND INJECTION TIME STUDY ATWS PROVIDE ASSISTANCE TO NRR IN APPLICATION OF CODES TO LICENSING ISSUES iv.

DOPPIER EFFECT PERFORM ACCURATE DETAILED STUDY OF Tile' INTERFACE EFFECT OF FISSION PRODUCTS WITil Tile MAIN RES0 NANCE ABSORBERS OF 00 FUEL (FY 19s3) 2 lg e

1.

ACCIDENT DETECTION.AND PREVENTION

~

E.

FUEL BEllAVIOR BRANCil i.

IN-PILE INSTRUMENTATION PBF & LOFT INSTRUMENTATION FUEL TEMPERATURE CLADDING TEMPERATURE FUEL PIN LENGTil FUEL PIN GAS PRESSURE e

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2.

SEl'ARAIE EFFECTS TESIS FOR UtIDERSTANDING At!D F.0DELIN0 AND REACTOR ENGINEERING REVIEW E.

, FUEL BEllAVIOR BRANCil i.

CLAD & FUEL STUDIES STRESS RUPTURE PROPERTIES OF IRRADIATED CLADDING (1982)

CYCLIC LOADING OF CLADDING DURING OPERATION (1986)

- MULTI-ROD BURST TESTING (1982)

FISSION GAS RELEASE AND GAP CONDUCTIVITY AT 111 611 BURNUP (1982)

FUEL RELOCATION EXPTS - IIALDEN (1982)

EXAMINE TMI FUEL (1983) iI.

IIYDP.0 GEN PROGRAM (1983)

RAD 10 LYSIS SAMPLING & ANALYSIS DETONATIONLIMITS DETONATION PRESSURES IlYDR0 GEN SOURCES FROM C0ATINGS & CORROSION IlYDR0 GEN llANDLING; E.G., EFFECTIVENESS OF VENTING, DEPRESSURIZATION, ETC..

III.

WATER CHEMISTRY (1983)

CORRELATION OF FISSION PRODUCTS IN COOLANT SAMPLES TO CONDITION OF FUEL IMPROVED SAMPLING & AtiALYSIS METil0DS.

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11.

ANALYTICAL TOOL DEVELOPMENT AND ACCIDENT ANALYSIS E.

FUEL BEllAVIOR BRANCil i.

FUEL CODE DEVELOPMENT ASSESSMENT & APPLICATION MAINTAIN AND ASSESS EXISTING CODES (FRAP; FRAPCON).

INCORPORATE RESULTS FROM NRU &'ESSOR.

DEVELOP MODELS FOR SEVERE FUEL DAMAGE, INCORPORATE RESULTS FROM PBF.

e l

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I.

So ACCIDENT CONSEQUENCE EVALUATION ANI) HillGA110fl

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E.

EUEL_DEllAYIllILERANCil" 1.

EUELilAMF;E_lifilARISMS_AND._IllPESil0LIl PBF:

SEVERE-DAMAGE TESTING (1980) o DAMAGE MECllANISMS, o

ROD-TO ROD INTERACTIONS, o

POST-TEST C00 LABILITY PBF:

INDIVIDUAL EXPERIMENTS TO FILL LICENSING NEEDS o

RIA, o
LOCA, o
PCM, o A0T.

NRU:

FULL-LENGTH BUNDLE IIEAT-UP TESTS 0983)

ESSOR:

SMALL AND LAPGE BREAK FUEL DM1 AGE TESTS (1986)

NRU OR SGilWR:

SEVERE-DAMAGE TESTING OF FULL LENGTil BUNDLES AT C0ftERCIAL ENRICllMENT it. CORE MELTDOWN STEAM EXPLOSION ENERGY CONVEP.SION AT LARGE SCALE-(1982)

MOLTEN CORE / CONCRETE INTERACTIONS CORCON CODE (1982) i FISSION PRODUCT TRANSPORT CODE VERIFICATION AT LARGE SCALE (198E)

IMI FISSION PRODUCT RELEASE IN PRIMARY SYSTEM AND CONTAINf1ENT (1982)

FISSION PRODUCT SOURCE TERMS FOR SEVEP.ELY DAMAGED FUEL (1986)

FISSIONPRODUCTRELEASEFROMFUELDEFECTSDURINGPOWERRAMPS(1986)

L ACCIDENT DETECTION AND PREVENTION F.

METALLURGY AND MATERIALS RESEARCll BRANCH i.

N0NDESIR(ICTIVE EXAMINAIl0K

- AC0USTIC EMISSION FOR MONITORING WELDING (1980)

AC0USTIC EMISSION FOR ON-LINE MONI'.JRING PRIMARY SYSTEM COMPONENTS (1982)

IMPROVED EDDY CURRENT INSPECTION TECHNIQUES TO CHARACTERIZE FLAWS IN STEAM GENERATOR TUBING (1981)

IMPROVED ULTRASONIC FLAW CilARACTERIZATION (SAFT-UT) FOR ISI 0F PRESSURE B0UNDARY (1981)

NEW ISI TECllNIQUES-(INTERNAL FRICTION FOR ON-LINE MONITORING 0F PRESSURE B00NDARY)(1982)

(NEW METil0D0 LOGY FOR DETERMINING RESIDUAL STRESSES ) (1983) i IMPROVED ULTRASONIC FLAW DETECTION (198's)

11. LEAK DETECTION RELIABLE, lilGil-SENSITIVITY ON-LINE LEAK DETECTION FOR PRIMARY SYSTEM COMPONENTS (1983) 1 F

i

SEPARATE EFFECTS TESTS FOR UNDERSTANDING AND MODELING, AND REACTOR ENGINEERING REVIEW 2.

l l

F.

!ETALLURGLANILMIERIAlS RESEMOLIllBN01 1

I.

DMCIllRE MECllANIG ELASTIC-PLASTIC TEST METil0DS FOR DUCTILE STEELS (1980)

STRUCTURAL INTEGRilY OF DEGRADED PIPING (1981)

REEVALUATION OF CRITERIA FOR PIPING SYSTEM DESIGN AND OPERATION (1981) l VALIDATION OF.EFM AND E/P ETil0D0 LOGY FOR ACCIDENT ANALYSIS (1982) i THERHAL SHOCK 4

i

' STEAM LINE BREAK DATA BASE FOR TillCK-SECTION lilGH-STRENGTH STEELS (1986)

EVALUATIO!! 0F NEW WELDING AND FABRICATION PROCESSES (1984)

STRESS INTENSITY ANALYSIS ETil0DS FOR COMPLEX CRACK FRONTS (1984) ii. ENY1RONENIAL EFFECTS j

ENVIRONMENTALLY ENilANCED CRACK GROWTil RATES (1983) i I

FRACTURE T00GilNESS OF IRRADI ATED VESSEL STEEL AND ELDS (1981)-

ECilANISMS OF CORROSION AND DEGRADATION OF STEAM GENERATORS (1985) 1 f

ETil0DS FOR PREDICTING D0SIMETRY AND EMBRITTLEMENT FROM SURVEILLANCE (1984)

ENVIRONENTAL ECilANISMS OF STRESS CORROSION CRACKING I

BWR PIPING (1984)

}

PWR FEEDWATER PIPING (1984)

STEAM GENERATOR TUBES (1984)

EFFECTS OF llYDR0 GEN ON STRUCTURAL INTEGRITY (1981)

ANNEALING TO MITIGATE IRRADIATION EMBRITTLEMENT (1981)

11.

ANALYTICAL TOOL DEVELOPENT AND ACCIDENT ANALYSIS F.

EIALLURGY AND MAIERIAlS RESEARCILBRANCll i.

STRUCTURE ANALYSIS Ell 10D VAllDATION OF TEARING INSTABILITY METil0D FOR STRUCTURAL ANALYSIS

- PIPING (1981)

- PRESSURE VESSELS (1983)

PROBABILISTIC METil0D0 LOGY FOR PIPE BREAKS (1982)

COMPUTER-INTERACTIVE PIPING SYSTEM DESIGN AND OPERATION EVALUATION CAPABILITY (1985)

PROBABILISTIC EVALUATION OF FLAW DETECT 10th AND STRUCTURAL IMPLICATIONS (19811)

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4 e

t ENCLOSURE 2 l

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