Metallic Fuel Open Resources

Resources available in open liturature.

Contents

Technical Reports

Authors Title Publisher Year Report Number DOI EBR-II/FFTF Experiments
C.P. Cabell Summary description of the Fast Flux Test Facility Hanford Engineering Development Laboratory 1980 HEDL-400 10.2172/6032523
R.W. Hyndman, J.M. Allen, R.A. Call, E.W. Laird, M.R. Tuck, K.D. Tucker DESCRIPTION OF SOFTWARE FOR THE EBR-II DIGITAL DATA ACQUISITION SYSTEM Argonne National Laboratory 1970 ANL/EBR-33 10.2172/4023545
B.J. Toppel User's guide for the REBUS-3 fuel cycle analysis capability Argonne National Laboratory 1983 ANL-83-2 10.2172/6068571
K.L. Basehore, N.E. Todreas SUPERENERGY-2: a multiassembly, steady-state computer code for LMFBR core thermal-hydraulic analysis Pacific Northwest Laboratory 1980 PNL-3379 10.2172/5107861
A.M. Yacout, M.C. Billone Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data Argonne National Laboratory 2016 ANL-ART-76 10.2172/1418818 X419
A.M. Yacout, A. Oaks, W. Mohamed, K. Mo FIPD: EBR-II Fuels Irradiation & Physics Database,Untied States Argonne National Laboratory 2017 ANL-ART-124 10.2172/1480520 X419(X419A/B) X420(X420A/B) X421(X421A) X423(X423A/B/C) X435 X438 X425(X425A/B/C) X429(X429A/B) X430(X430A/B) X431(X431A) X432(X432A) X435(X435A/B) X438 X441(X441A) X447(X447A) X448(X448A) X449 X450 X451(X451A) X452(X452A) X453 X454 X455 X482(Z482A/B) X483(X483A) X484 X485 X486(X486A) X489 X492(X492A/B) X496 X501
T. Benoit, K. Mo, A. Yacout Quality Assurance Program Plan for SFR Metallic Fuel Data Qualification Argonne National Laboratory 2019 ANL/NE-16/17 10.2172/1524412
A.M. Yacout Legacy Metal Fuel Data Exploration for Commercial Scale-Up Argonne National Laboratory 2019 ANL/CFCT-C16144 10.2172/1496023
G.L. Hofman, M.C. Billone, J.F. Koenig, J.M. Kramer, J.D.B. Lambert, L. Leibowitz, Y. Orechwa, D.R. Pedersen, D.L. Porter, H. Tsai, A.E. Wright Metallic Fuels Handbook Argonne National Laboratory 2019 ANL-NSE-3 10.2172/1506477
W.J. Carmack Temperature and Burnup Correlated FCCI in U-10Zr Metallic Fuel Idaho National Laboratory 2012 INL/EXT-12-25550 10.2172/1055966 X419 X447
D.E. Janney, C.A. Papesch FCRD Transmutation Fuels Handbook 2015 Idaho National Laboratory 2015 INL/EXT-15-36520 10.2172/1239879
Seidel, B R;Walters, L C STATUS OF PERFORMANCE AND FABRICATION OF METALLIC U-Pu-Zr FUEL FOR THE INTEGRAL FAST REACTOR Argonne National Laboratory 1984 ANL-IFR-1 10.2172/707411
Cahalan, J E;Marchaterre, J F;Pedersen, D R;Sevy, R H PRELIMINARY SAFETY ASSESSMENT OF THE INTEGRAL FAST REACTOR CONCEPT Argonne National Laboratory 1985 ANL-IFR-3 10.2172/708173
Orechwa, Y;Khalil, H PERFORMANCE CHARACTERISTICS OF A PRELIMINARY 330 MWe METAL CORE DESIGN Argonne National Laboratory 1984 ANL-IFR-4 10.2172/707412
Su, S F;Sevy, R H UNPROTECTED L0SS-0F-FL0W ACCIDENTS - PERFORMANCE OF METAL FUEL Argonne National Laboratory 1985 ANL-IFR-5 10.2172/708174
Sevy, R H;Cahalan, J E AN ASSESSMENT OF FISSION-GAS-INDUCED TRANSIENT SWELLING IN METALLIC FUEL Argonne National Laboratory 1985 ANL-IFR-6 10.2172/708175
Robinson, W. R. POWER CALIBRATION EXPERIMENT FOR TREAT TEST M2 Argonne National Laboratory 1985 ANL-IFR-8 10.2172/708176
Bauer, T. H.;Morman, J. A.;Lo, R. K.;Robinson, W. R.;Wright, A. E.;Tentner, A. M. TREAT TESTS M2 AND M3: EXPERIMENT INFORMATION AND PRETEST ANALYSIS Argonne National Laboratory 1985 ANL-IFR-9 10.2172/708177
Wood, E. L.;Porter, D. L. FUEL/CLADDING COMPATIBILITY OF U-lOZr AND U-5Fs FUELS WITH ADVANCED ALLOY CLADDING MATERIALS Argonne National Laboratory 1985 ANL-IFR-13 10.2172/711868
Johnson, T R;Miller, W E;Burris, L CHARACTERISTICS OF HIGH LEVEL WASTES FROM A PYROCHEMICAL PROCESS Argonne National Laboratory 1985 ANL-IFR-16 10.2172/711820
Fenske, G R;Emerson, J E;Savoie, F E;Gebo, C H;Lautermilch, H;Johanson, E W DIRECT ELECTRICAL HEATING OF IRRADIATED EBR-II MARK-II DRIVER FUEL Argonne National Laboratory 1985 ANL-IFR-17 10.2172/712224
Robinson, W R;Lo, R K;Bauer, T H;Froehle, P H;Helenberg, H W;Morman, J A;Stanford, G S;Wright, A E IFR SAFETY TESTS M2 AND M3 IN TREAT: DATA AND ANALYSIS Argonne National Laboratory 1985 ANL-IFR-18 10.2172/712225
Pahl, R G;Lahm, C E;Hudman, G D TEST DESCRIPTION FOR THE INTEGRAL FAST REACTOR SUBASSEMBLIES X419, X420, AND X421 Argonne National Laboratory 1985 ANL-IFR-19 10.2172/711870 X419 X420
Hughes, T H FPIN2 ANALYSIS OF METAL FUELED PINS Argonne National Laboratory 1985 ANL-IFR-23 10.2172/712138
R.H Sevy QUASI-STATIC TRANSIENT ANALYSIS Argonne National Laboratory 1985 ANL-IFR-26 10.2172/712226
Gruber E.E.;Kramer J.M. GAS-BUBBLE GROWTH MECHANISMS IN THE ANALYSIS OF METAL FUEL SWELLING Argonne National Laboratory 1985 ANL-IFR-27 10.2172/712124
G.L. Hofman, L. Leibowitz, J.M. Kramer, M.C. Billone, J.F. Koenig Metallic fuels handbook Argonne National Laboratory 1985 ANL-IFR-29 10.2172/712317
Kramer, J M;Demaree, J D;Gruber, E E THE DYNAMICS OF AXIAL EXTRUSION OF METALLIC FUEL DURING OVERHEATING TRANSIENTS Argonne National Laboratory 1985 ANL-IFR-30 10.2172/711809
Porter, D L ZIRCONIUM MIGRATION IN METAL FUELS Argonne National Laboratory 1985 ANL-IFR-32 10.2172/712330
Tsai, H.;Neimark, L. A.;Billone, M. C.;Fryer, R. M.;Koenig, J. F.;Lehto, W. K.;Malloy, D. J. TEST DESIGN DESCRIPTION (TDD), VOLUME 1A, DESIGN DESCRIPTION AND SAFETY ANALYSIS FOR IFR-1 METAL FUELS IRRADIATION TEST IN FFTF Argonne National Laboratory 1986 ANL-IFR-33 10.2172/711873 X419 420 421
Strain, R. V.;Sanecki, J. E. METALLOGRAPHIC CHARACTERIZATION OF UNIRRADIATED U-Pu-Zr FUEL Argonne National Laboratory 1986 ANL-IFR-35 10.2172/711875
Hins, A. G. COMPATIBILITY OF U-Pu-Zr FUELS WITH ADVANCED CLAD ALLOYS: ONSET-OF-MELTING RESULTS Argonne National Laboratory 1986 ANL-IFR-36 10.2172/711876
Tilbrook, R W;Pedersen, D R;Thompson, D H;Ragland, W A LOCAL FAULT TOLERANCE OF METAL FUEL Argonne National Laboratory 1986 ANL-IFR-37 10.2172/711877 X419 X420 X421
Tsai, H;Koenig, J F SPECIAL HANDLING AND PREHEATING REQUIREMENTS FOR IFR-1 METAL FUEL EXPERIMENT IN FFTF Argonne National Laboratory 1986 ANL-IFR-39 10.2172/711878
Batte, G. L.;Wilkes, C. W. FINAL SAFETY ANALYSIS REPORT FOR THE IFR EXPERIMENTAL FUELS LABORATORY Argonne National Laboratory 1986 ANL-IFR-42 10.2172/712227
Dodds, N. E. TEST DESIGN DESCRIPTION VOLUME IB IFR-1 METAL FUEL IRRADIATION (AK-181) Argonne National Laboratory 1986 ANL-IFR-43 10.2172/712141
Dodds, N. E. TEST DESIGN DESCRIPTION VOLUME II, PART 1 IFR-1 METAL FUEL IRRADIATION TEST (AK-181) ELEMENT AS-BUILT DATA Argonne National Laboratory 1986 ANL-IFR-44 10.2172/712348
Fenske, G R;Emerson, J E;Savoie, F E;Johanson, E W FISSION GAS RETENTION AND AXIAL EXPANSION OF IRRADIATED METALLIC FUEL Argonne National Laboratory 1986 ANL-IFR-45 10.2172/712349
Liu, Y Y;Billone, M C THERMOELASTIC STRESSES IN U-Pu-Zr TERNARY ALLOY FUELS - AN ANALYTICAL INTERPRETATION OF RESULTS IN THE IFR LEAD IRRADIATION EXPERIMENTS Argonne National Laboratory 1986 ANL-IFR-49 10.2172/712394 X419
Gabor, J. D.;Purviance, R. T.;Aeschlimann, R. W.;Spencer, B. W. CHARACTERIZATION OF METAL FUEL FRAGMENTATION Argonne National Laboratory 1986 ANL-IFR-52 10.2172/712403
Leibowitz, L PHASE RELATIONS FOR FUEL-CLADDING INTERACTIONS Argonne National Laboratory 1986 ANL-IFR-54 10.2172/712838
Pahl, R G;Beck, W N;Hofman, G L;Lahm, C E;Villarreal, R POSTIRRADIATION EXAMINATIONS OF U-Pu-Zr" FUEL ELEMENTS FROM SUBASSEMBLIES X419 AND X419A Argonne National Laboratory 1986 ANL-IFR-55 10.2172/712836 X419 X419A
Gruber, E E THE STARS MODEL FOR FISSION-GAS BEHAVIOR: I. STEADY STATE BEHAVIOR Argonne National Laboratory 1986 ANL-IFR-58 10.2172/712886 X419 X420 X421
Crawford, D C;Porter, D L THE RELIABILITY OF UNTEMPERED END PLUG WELDS ON HT9-CLAD IFR FUEL ELEMENTS Argonne National Laboratory 1987 ANL-IFR-65 10.2172/713590
Kramer, J. M. ;Hughes, T. H.;Gruber, E. E. Validation of Models for the Analysis of the Transient Behavior of Metallic Fast Reactor Fuel Argonne National Laboratory 1987 ANL-IFR-66 10.2172/713690 X408
Bauer, T. H.;Lo, R. K.;Rhodes, E. A.;Wright, A. E.;Robinson, W. R.;Froehle, P. H.;Stanford, G. S. UPDATE OF SAFETY TESTING IN TREAT ON U-5Fs FUEL: DATA FROM TEST M4 AND COMBINED ANALYSIS OF TESTS M2, M3, AND M4 Argonne National Laboratory 1987 ANL-IFR-69 10.2172/713744 X408
Hudman, G. D.;Keiser, D. D.;Porter, D. L. EX-REACTOR TESTING FOR CARBON LOSS FROM HT9 CLADDING IN THE PRESENCE OF HETAL FUELS Argonne National Laboratory 1987 ANL-IFR-70 10.2172/713759 X425
Dodds, N. E. TEST DESIGN DESCRIPTION VOLUME II, PART I MFF-1 AND MFF-1A METAL FUEL IRRADIATIONS (HF168 AND HF169) ELEMENT AS-BUILT DATA Argonne National Laboratory 1987 ANL-IFR-72 10.2172/713773
Wilkes, C. W.;Batte`, G. L.;Tracy, D. B.;Griffiths, V. EBR-II FUEL SLUG CASTING EXPERIENCE Argonne National Laboratory 1987 ANL-IFR-73 10.2172/713795 X419 X420 X421 X425
Leibowitz, L.;Veleckis, E.;Blomquist, R. A. REVIEW OF THE PHASE EQUILIBRIA AND THERMODYNAMICS OF BINARY AND TERNARY SYSTEMS COMPOSED OF IFR FUEL COMPONENT METALS (U, Pu, and Zr) AND NITROGEN Argonne National Laboratory 1987 ANL-IFR-78 10.2172/713925
Mueller, C. J. UNCERTAINTIES IN INHERENT SHUTDOWN OF GENERIC UNPROTECTED LOSS-OF-FLOW AND TRANSIENT OVERPOWER EVENTS IN INNOVATIVE DESIGNS Argonne National Laboratory 1987 ANL-IFR-80 10.2172/713938
Pahl, R G;Beck, W N;Sanecki, J E POSTIRRADIATION EXAMINATION OF THE HT9 CLAD FUEL TEST X425 AT 2.9% BURNUP Argonne National Laboratory 1987 ANL-IFR-81 10.2172/713968 X425
H. H. Hummel and P. A. Pizzica STUDIES OF PREFAILURE FUEL EXTRUSION IN METAL FUEL PINS WITH EXTRUS Argonne National Laboratory 1988 ANL-IFR-85 10.2172/714106 X419 X419A
Robinson, W R;Bauer, T H POWER COUPLING IN TREAT M-SERIES: NEW EXPERIMENTAL RESULTS FROM M7CAL AND UPDATED ANALYSES Argonne National Laboratory 1988 ANL-IFR-86 10.2172/714162
Wei, T. Y. C. INHERENCY CONTROL STRATEGIES Argonne National Laboratory 1988 ANL-IFR-88 10.2172/714473
Gruber, E. E.;Kramer, J. M. ANALYSIS OF FISSION-GAS BEHAVIOR WITH THE STARS CODE: STEADY-STATE IRRADIATION OF U-Pu-Zr FUEL PINS Argonne National Laboratory 1988 ANL-IFR-90 10.2172/714488 x419 X420 X421
Gabor, J D;Purviance, R T;Aeschlimann, R W;Spencer, B W REACTOR MATERIAL DEBRIS FORMATION SCOPING TESTS Argonne National Laboratory 1988 ANL-IFR-91 10.2172/714482
Pelton, A D;Leibowitz, L CALCULATION OF THE LIQUIDUS AND SOLIDUS IN THE PLUTONIUM-URANIUM-ZIRCONIUM SYSTEM Argonne National Laboratory 1988 ANL-IFR-93 10.2172/714489
Veleckis, E;Leibowitz, L;Blomquist, R A Thermal Conductivity of 304 Stainless Steel and U-11.4 wt % Zr Alloy between 600 and 1200 K Argonne National Laboratory 1988 ANL-IFR-94 10.2172/714505
Bauer, T. H.;Cahalan, J. E.;Dunn, F. E.;Fenske, G. R.;Gabor, J. D.;Gruber, E. E.;Hughes, T. H.;Kalimullah;Kramer, J. M.;Miles, K. J.;Pedersen, D. R.;Spencer, B. W.;Tentner, A. M.;Tilbrook, R. W.;Wright, A. E. METALLIC FUEL SAFETY ASSESSMENT Argonne National Laboratory 1989 ANL-IFR-102 10.2172/10200877
Bauer, T H;Kramer, J M;Tilbrook, R W;Goldman, A J A PROGRAM TO RESOLVE THE SAFETY IMPLICATIONS OF FUEL DAMAGE IN THE OPERATION OF ADVANCED METAL-FUELED REACTORS Argonne National Laboratory 1989 ANL-IFR-103 10.2172/10200876 X441
Tsai, H.; Savoie, F. E.; Kelman, L. R.; Jackson, W. D. COMPATIBILITY OF LOW-BURNUP U-lOZr FUEL WITH HT9 CLADDING AT ELEVATED TEMPERATURES Argonne National Laboratory 1989 ANL-IFR-104 10.2172/714570 X425
Leibowitz, L.;Hins, A. G.;Strain, R. V.;Tsai, H.;Hofman, G. L. COMPATIBILITY OF U-Pu-Zr ALLOY FUEL WITH STAINLESS STEEL CLADDING Argonne National Laboratory 1989 ANL-IFR-109 10.2172/714609
Koenig, J F;Lell, R M Prediction of Temperature in an Uncooled EBR-II Subassembly Heated by Fission Product Decay Argonne National Laboratory 1989 ANL-IFR-110 10.2172/714610
Rhodes, E A;Stanford, G S;Regis, J P Fuel Motion in TREAT Tests M5F1, M5F2, M6, and M7: Preliminary Analysis of Hodoscope Data Argonne National Laboratory 1989 ANL-IFR-112 10.2172/714612
Herzog, JP; Miles, KJ SASSYS ANALYSIS OF FISSION GAS RELEASE FROM HIGH-BURNUP SUBASSEMBLIES IN EBR-II Argonne National Laboratory 1989 ANL-IFR-118 10.2172/974661 X421
Bauer, T. H.;Robinson, W. R.;Holland, J. W.;Rhodes, E. A.;Wright, A. E. FIRST OVERPOWER TESTS OF METALLIC IFR FUEL IN TREAT: DATA AND ANALYSIS FROM TESTS M5, M6, AND M7 Argonne National Laboratory 1989 ANL-IFR-124 10.2172/714655 X419 X419A X420 X421
Dodds,N.E.; Henslee,S.P. SODIUM BOND DEFECT INVESTIGATIONS Argonne National Laboratory 1990 ANL-IFR-131 10.2172/1548400 X429
Gabor, J. D.;Purviance, R. T.;Cassulo, J. C.;Charak, I.;Novick, V. J. INVESTIGATION OF CADMIUM COMBUSTION POTENTIAL Argonne National Laboratory 1990 ANL-IFR-133 10.2172/714682
Vilim, R. B. A MEASUREMENT-BASED METHOD FOR PREDICTING MARGINS AND UNCERTAINTIES FOR UNPROTECTED ACCIDENTS IN THE INTEGRAL FAST REACTOR CONCEPT Argonne National Laboratory 1990 ANL-IFR-135 10.2172/714694
Wigeland, R. A.;Turski, R. B.;Lo, R. K. RELATIVE PERFORMANCE OF METALLIC FUEL AND OXIDE FUEL DURING UNPROTECTED ACCIDENT CONDITIONS IN A 3500 MWth POOL-TYPE LMR Argonne National Laboratory 1990 ANL-IFR-136 10.2172/714700
Tsai, Hanchung;Wang, Da-Yung;Savoie, F E;Hins, A G FUEL/CLADDING COMPATIBILITY IN LOW-BURNUP U-26Pu-10Zr/HT9 FUEL AT ELEVATED TEMPERATURES Argonne National Laboratory 1991 ANL-IFR-152 10.2172/714936 X430 X430A
McKnight, R. D. VALIDATION OF THE REBUS-3/RCT METHODOLOGIES FOR EBR-II CORE-FOLLOW ANALYSIS Argonne National Laboratory 1991 ANL-IFR-153 10.2172/714933 X444
Wright, A. E.;Liu, Y. Y.;Holland, J. W.;Bauer, T. H. PERFORMANCE ANALYSIS AND CHECKOUT OF THE WHOLE PIN FURNACE SYSTEM Argonne National Laboratory 1991 ANL-IFR-154 10.2172/714939 X425
INTEGRAL FAST REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD July-September 1991 Argonne National Laboratory 1991 ANL-IFR-155 10.2172/714938 X425C X430B X431A X432A X435 X436 X437 X438 X441 X448 X449 X450 X451 X481 X483 X484 X485 X486X489 X492 X501 X512
Heineman J.B; Lottes,P.A; Pedersen, D.R;Stewart,R.R; Tessier, J.H. Experimental and Analytical Studies of Passive Heat Removal Systems for Advanced LMRs Argonne National Laboratory 1991 ANL-IFR-156 10.2172/1543441
INTEGRAL FAST REACTOR PROGRAM ANNUAL PROGRESS REPORT FY 1991 Argonne National Laboratory 1992 ANL-IFR-169 10.2172/7117033 X425 X441 X441A X447 X482B X492
INTEGRAL FAST REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD January-March 1992 Argonne National Laboratory 1992 ANL-IFR-170 10.2172/1546709 X419B X420B X421A X423C X425C X427A X429BX430B X431A X432A X435 X435A X436 X437 X438 X441A X447A X448 X448A X449 X450 X451 X452A X453 X454 X455 X481 X482 X483 X483A X484 X485 X486 X489 X492 X X492A X501 X502 X503
Gay, E. C.;Miller, W. E.;Battles, J. E.;Laidler, J. J. CRITICALITY HAZARDS CONTROL DURING METAL FUEL ELECTROREFINING Argonne National Laboratory 1992 ANL-IFR-171 10.2172/10197576
Yacout, A. M.;Orechwa, Y. ANALYSIS OF CLADDING STRAIN DATA FROM THE LEAD IFR TEST SUBASSEMBLY X425 Argonne National Laboratory 1992 ANL-IFR-172 10.2172/10197598 X425
INTEGRAL FAST REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD April-June 1992 Argonne National Laboratory 1992 ANL-IFR-174 10.2172/10197615
INTEGRAL FAST REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD July-September 1992 Argonne National Laboratory 1992 ANL-IFR-178 10.2172/10197801 X502 X503 X510 X512
Tzanos, C. P. PREDICTIONS OF RVACS SENSITIVITY TO WIND EFFECTS VIA COMMIX CALCULATIONS Argonne National Laboratory 1993 ANL-IFR-181 10.2172/10197912
Hill, D. J.;Ragland, W. A.;Roglans-Ribas, J. SUMMARY REPORT OF THE EBR- I I .PROBABILISTIC RISK ASSESSMENT ANALYSIS OF THE RISK FROM INTERNAL AND EXTERNAL EVENTS AT EBR-11 Argonne National Laboratory 1993 ANL-IFR-182 10.2172/10197915
Vilim, R. B. THE PASSIVE RESPONSE OF A METAL FUELED POOL-TYPE REACTOR TO THE CHILLED INLET ACCIDENT Argonne National Laboratory 1993 ANL-IFR-183 10.2172/10197940
Sevy, R. H. SUDDEN LOSS OF FLOW IN AN INTEGRAL FAST REACTOR Argonne National Laboratory 1993 ANL-IFR-184 10.2172/10197949
INTEGRAL FAST REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD October-December 1992 Argonne National Laboratory 1993 ANL-IFR-185 10.2172/10197965 X419B X420B X421A X423 X423C X425 X425C X427A X429B X430 X430B X431A X432A X435 X435A X436 X437 X438 X441 X441A X444 X447A X448 X448A X449 X450 X451 X452A X453 X454 X455 X481 X482 X483 X483 A X484 X 485 X486 X489 X492 X X492A X501 X502 X503
Tentner, A M;Kalimullah, SAS4A ANALYSIS OF THE M7 METAL FUEL TREAT EXPERIMENT Argonne National Laboratory 1993 ANL-IFR-186 10.2172/10197962
Reifman, Jaques;Vitela, Javier ARTIFICIAL NEURAL NETWORK TRAINING WITH CONJUGATE GRADIENTS FOR DIAGNOSING TRANSIENTS IN NUCLEAR POWER PLANTS Argonne National Laboratory 1993 ANL-IFR-189 10.2172/10198077
Yang, W. S. RCT - A CODE TO RECONSTRUCT PIN POWER AND BURNUP CHARACTERISTICS . . FROM NODAL CALCULATIONS IN HEXAGONAL'GEOMETRY Argonne National Laboratory 1993 ANL-IFR-192 10.2172/10198080
Chang, Y I;Walters, L C;Laidler, J J;Pedersen, D R;Wade, D C;Lineberry, M J INTEGRAL FAST REACTOR PROGRAM ANNUAL PROGRESS REPORT FY 1992 Argonne National Laboratory 1993 ANL-IFR-202 10.2172/10181235 X441 X447
INTEGRAL FAST REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD April-June 1993 Argonne National Laboratory 1993 ANL-IFR-205 10.2172/10198352 X419B X420B X421A X423C X425 X425C X427A X429B X430 X430B X431A X432A X435A X436 X437 X438 X441 X441A X447A X448A X449 X450 X451A X452A X453 X454 X455 X481 X482 X483 A X484 X 485 X486A X486 X489 X492B X492A X501 X510 X521
Hayes, S L SAFE: A COMPUTER CODE FOR THE STEADY-STATE AND TRANSIENT THERMAL ANALYSIS OF LMR FUEL ELEMENTS Argonne National Laboratory 1993 ANL-IFR-221 10.2172/140916 X447 X447A
Vilim, R. B.;Aumeier, S. E. ASSESSMENT OF NONOBTRUSIVE METHODS FOR VERIFYING DEMONSTRABLY SAFE REACTOR RESPONSE Argonne National Laboratory 1994 ANL-IFR-224 10.2172/10199827
Hayes, Steven L.;Pahl, Robert G.;Crawford, Doug C. TEST DESIGN DESCRIPTION AND POSTIRRADIATION EXAMINATION OF THE HT9 ADVANCED DRIVER FUEL TEST (X430) Argonne National Laboratory 1994 ANL-IFR-225 10.2172/1644685 X430
Robinson, W. R.;Bauer, T. H. THE M8 POWER CALIBRATION EXPERIMENT (M8CAL) Argonne National Laboratory 1994 ANL-IFR-232 10.2172/1130413
Morris, E. E.;Tentner, A. M. ANALYSIS OF SEVERE ACCIDENT ENERGETICS IN METALLIC-FUELED,LIQUID METAL COOLED REACTORS Argonne National Laboratory 1994 ANL-IFR-235 10.2172/10200225
Gruber, E. E.;Hughes, T. H. EXPERIMENTAL DETERMINATION OF THE HIGH-TEMPERATURE INTERMEDIATE-TIME MECHANICAL PROPERTIES OF ALLOY HT9 Argonne National Laboratory 1994 ANL-IFR-236 10.2172/10200258
Palm, R. G.;Stanford, G. S.;Kovaleski, S. D.;Regis, J. P.;Dickerman, C. E. M8 POWER CALIBRATION (M8CAL) HODOSCOPE REPORT Argonne National Laboratory 1994 ANL-IFR-240 10.2172/10200318
Sofu, T.;Kramer, J. M.;Cahalan, J. E. VALIDATION OF THE INTEGRATED SASSY S/S AS4A-FPIN2 MODEL FOR THE TRANSIENT ANALYSIS OF METALLIC FUEL ELEMENTS Argonne National Laboratory 1994 ANL-IFR-241 10.2172/10200347 X419 X419A
Chang, Y I;Walters, L C;Laidler, J J;Pedersen, D R;Wade, D C;Lineberry, M J INTEGRAL FAST REACTOR PROGRAM ANNUAL PROGRESS REPORT FY 1993 Argonne National Laboratory 1994 ANL-IFR-244 10.2172/10118502
Chang, Y I;Walters, L C;Laidler, J J;Pedersen, D R;Wade, D C;Lineberry, J J INTEGRAL FAST REACTOR PROGRAM ANNUAL PROGRESS REPORT FY 1994 Argonne National Laboratory 1994 ANL-IFR-246 10.2172/100272
Bezella, W. A.;Huntsman, T. S.;Cassulo, J. C.;Holtz, R. E.;Thompson, D. H. ELECTROMAGNETIC PUMP INSULATION POSTIRRADIATION TEST REPORT Argonne National Laboratory 1995 ANL-IFR-257 10.2172/10200806
IN-VESSEL RETENTION OF CORE DEBRIS IN INTEGRAL FAST REACTOR SEVERE ACCIDENT SEQUENCES Argonne National Laboratory 1995 ANL-IFR-258 10.2172/10200711
Bezella, W. A.;Poloncsik, J.;Thompson, D. H.;Holtz, R. E. A LOW TEMPERATURE IRRADIATION VEHICLE FOR EBR-II FEASIBILITY DESIGN STUDY Argonne National Laboratory 1995 ANL-IFR-259 10.2172/10200924
Farmer, M.;Spencer, B. AN ASSESSMENT OF THE POTENTIAL FOR IN-VESSEL FISSION PRODUCT SCRUBBING FOLLOWING A CORE DAMAGE EVENT IN IFR Argonne National Laboratory 1995 ANL-IFR-260 10.2172/10200672
I. Greenquist, K.M. Cunningham, J. Hu, J.J. Powers A Metallic Fuel Performance Benchmark Problem Based on the IFR-1 Experiment Oak Ridge National Laboratory 2020 ORNL/TM-2020/1534 10.2172/1649204 IFR-1
K.M. Cunningham, J.J. Powers, R.A. Lefebvre Modeling the IFR-1 Experiment: A BISON Metallic Fuel Benchmark Oak Ridge National Laboratory 2019 ORNL/TM-2019/1270 10.2172/1649544 IFR-1
H. Tsai, J.F. Koenig Special Handling and Preheating Requirements for IFR-1 Metal Fuel Experiment in FFTF Argonne National Laboratory 1986 ANL-IFR-39 10.2172/711878 IFR-1
H. Tsai, L.A. Neimark, M.C. Billone, R.M. Fryer, J.F. Koenig, W.K. Lehto, D.J. Malloy Test Design Description (TDD). Volume 1A. Design description and safety analysis for IFR-1 metal fuels irradiation test in FFTF Argonne National Laboratory 1986 ANL-IFR-33 10.2172/711873 IFR-1
N.E. Dodds Test design description. Volume 1B. IFR-1 metal fuel irradiation (AK-181) Argonne National Laboratory 1986 ANL-IFR-43 10.2172/712141 IFR-1
N.E. Dodds Test design description Volume 2, Part 1. IFR-1 metal fuel irradiation test (AK-181) element as-built data Argonne National Laboratory 1986 ANL-IFR-44 10.2172/712348 IFR-1
W.J. Carmack, D.L. Porter, D.G. Cummings, H.J.M. Chichester, S.L. Hayes, D.W. Wootan Examination of Legacy Metallic Fuel Pins (U-10Zr) Tested in FFTF Idaho National Laboratory 2013 INL/EXT-20-28987 10.2172/1617195 MFF-3, MFF-5
N.E. Dodds Test Design Description: Volume 2, Part 1, MFF-1 and MFF-1A metal fuel irradiations (HF168 and HF169) element as-built data Argonne National Laboratory 1987 ANL-IFR-72 10.2172/713773 MFF-1, MFF-1A
W.J. Carmack Temperature and Burnup Correlated FCCI in U-10Zr Metallic Fuel Idaho National Laboratory 2012 INL/EXT-12-25550 10.2172/1055966 MFF-3, MFF-5

Journal Articles

Authors Title Journal Year Volume Page DOI EBR-II Experiments
A. Gopalakrishnan, J.L. Gillette EBRFLOW: A Computer Program for Predicting the Coolant Flow Distribution in the Experimental Breeder Reactor-II Nuclear Technology 1973 17 205-216 10.13182/NT73-A31264
G.L. Hofman Irradiation Behavior of Experimental Mark-Ii Experimental Breeder Reactor-Ii Driver Fuel Nuclear Technology 1980 47 22-Jul 10.13182/NT80-A32408
R.E. Einziger, B.R. Seidel Irradiation performance of metallic driver fuel in Experimental Breeder Reactor-11 to high burn-up Nuclear Technology 1980 50 25-39 10.13182/NT80-A17067
L.C. Walters, B.R. Seidel, J.H. Kittel Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder-Reactors Nuclear Technology 1984 65 179-231 10.13182/NT84-A33408
L.C. Walters, B.R. Seidel and J.H. Kittel Performance of metallic fuels and blankets in liquid-metal fast breeder reactors Nuclear Technology 1984 65 179-231 10.13182/NT84-A33408
Y.I. Chang The Integral Fast-Reactor Nuclear Technology 1989 88 129-138 10.13182/NT88-129
L.K. Chang, D. Mohr, H.P. Planchon, E.E. Feldman, N.C. Messick Demonstration of EBR-II Power Maneuvers without Control Rod Movement Nuclear Engineering and Design 1989 113 141-148 10.1016/0029-5493(89)90304-X
R.G. Pahl, D.L. Porter, C.E. Lahm, G.L. Hofman Experimental Studies of U-Pu-Zr Fast-Reactor Fuel-Pins in the Experimental Breeder Reactor-Ii Metallurgical and Materials Transactions A 1990 21 1863-1870 10.1007/BF02647233 X421 X425A
G.L. Hofman, R.G. Pahl, C.E. Lahm, D.L. Porter Swelling Behavior of U-Pu-Zr Fuel Metallurgical and Materials Transactions A 1990 21 517-528 10.1007/BF02671924
D.L. Porter, C.E. Lahm, R.G. Pahl Fuel Constituent Redistribution during the Early Stages of U-Pu-Zr Irradiation Metallurgical and Materials Transactions A 1990 21 1871-1876 10.1007/BF02647234
T.H. Bauer, A.E. Wright, W.R. Robinson and E.A. Rhodes Behavior of modern metallic fuel in TREAT transient overpower tests Nuclear Technology 1990 92 325-352 10.13182/NT92-325
R.G. Pahl, D.L. Porter, D.C. Crawford, L.C. Walters Irradiation Behavior of Metallic Fast-Reactor Fuels Journal of Nuclear Materials 1992 188 9-Mar 10.1016/0022-3115(92)90447-S X419 X420 X421 X425 X431 X432 X441 X447 X492
R.G. Pahl, C.E. Lahm, S.L. Hayes Performance of Ht9 Clad Metallic Fuel at High-Temperature Journal of Nuclear Materials 1993 204 141-147 10.1016/0022-3115(93)90210-P X447
J. Rest Kinetics of Fission-Gas-Bubble-Nucleated Void Swelling of the Alpha-Uranium Phase of Irradiated U-Zr and U-Pu-Zr Fuel Journal of Nuclear Materials 1993 207 192-204 10.1016/0022-3115(93)90261-V X423
J.H. Kittel, B.R.T. Frost, J.P. Mustelier, K.Q. Bagley. G.C. Crittenden and J. Van Dievoet History of fast reactor fuel development Journal of Nuclear Materials. 1993 204 13-Jan 10.1016/0022-3115(93)90193-3
C.F. Lahm, J.F. Koenig, R.G. Pahl, D.L. Porter and D.C. Crawford Experience with advanced driver fuels in EBR-11 Journal of Nuclear Materials. 1993 204 119-223 10.1016/0022-3115(93)90207-F
D.C. Crawford, C.E. Lahm, H. Tsai and R.G. Pahl Performance of U-Pu-Zr fuel cast into zirconium molds Journal of Nuclear Materials. 1993 204 157-164 10.1016/0022-3115(93)90212-H X492A
Y.Y. Liu, H. Tsai, M.C. Billone, J.W. Holland and J.M. Kramer Behavior of EBR-11 Mk-V-type fuel elements in simulated loss of-flow tests Journal of Nuclear Materials. 1993 204 194-202 10.1016/0022-3115(93)90217-M
A.B. Cohen. H. Tsai and L.A. Neimark Fuel/cladding compatibility in U-19Pu-10Zr/HT9-clad fuel at elevated temperatures Journal of Nuclear Materials. 1993 204 244-251 10.1016/0022-3115(93)90223-L X441
T.H. Bauer, J.W. Holland In-Pile Measurement of the Thermal-Conductivity of Irradiated Metallic Fuel Nuclear Technology 1995 110 407-421 10.13182/NT95-A35110
A.M. Yacout, S. Salvatores, Y. Orechwa Degradation analysis estimates of the time-to-failure distribution of irradiated fuel elements Nuclear Technology 1996 113 177-189 10.13182/NT96-A35187 X425 X425A X425B X425C
C.E. Till, Y.I. Chang, W.H. Hannum The integral fast reactor-an overview Progress in Nuclear Engery 1997 31 11-Mar 10.1016/0149-1970(96)00001-7
G.L. Hofman, L.C. Walters, T.H. Bauer METALLIC FAST REACTOR FUELS Progress in Nuclear Energy 1997 31 83-110 10.1016/0149-1970(96)00005-4 X482(X482A/B)
C. Nam, W. Hwang, D.S. Sohn Statistical failure analysis of metallic U-10ZR/HT9 fast reactor fuel pin by considering the Weibull distribution and cumulative damage fraction Annals of Nuclear Engergy 1998 25 1441-1453 10.1016/S0306-4549(98)00043-7 X425 X447
G.L. Hofman, S.L. Hayes, M.C. Petri Temperature gradient driven constituent redistribution in U-Zr alloys Journal of Nuclear Materials 2004 227 277-286 10.1016/0022-3115(95)00129-8 X447
Y.S. Kim, G.L. Hofman, S.L. Hayes, Y.H. Sohn Constituent redistribution in U-Pu-Zr fuel during irradiation Journal of Nuclear Materials 2004 327 27-36 10.1016/j.jnucmat.2004.01.012 X419 X501
Y.S. Kim, S.L. Hayes, G.L. Hofman, A.M. Yacout Modeling of constituent redistribution in U-Pu-Zr metallic fuel Journal of Nuclear Materials 2006 359 17-28 10.1016/j.jnucmat.2006.07.013 X419
D.C. Crawford, D.L. Porter, S.L. Hayes Fuels for sodium-cooled fast reactors:US perspective Journal of Nuclear Materials 2007 371 202-231 10.1016/j.jnucmat.2007.05.010 X419 X420(X420A/B) X421 X423 X425(X425A/B/C) X429(X429A/B) X430(X430A/B) X431(X431A) X432(X432A) X435(X435A) X436 X437 X438 X441(X441A) X447(X447A) X448(X448A) X449 X450 X451(X451A) X452 X453 X454 X455 X481 X482(A/B) X483(X483A) X484 X485 X486 X489 X492(X492A/B) X496 X501
Y.I. Chang Technical rationale for metal fuel in fast reactors Nuclear Engineering and Technology 2007 39 161-107 10.5516/NET.2007.39.3.161 X397 X419 X420 X421 X423X425 X427 X429 X430 X431 X432 X435 X436 X437 X438 X441 X447 X448 X449 X450 X451 X452 X453 X454 X455 X481 X482 X483 X484 X485 X486 X489 X492 X496 X501 X510 X521
D.E. Burkes, R.S. Fielding, D.L. Porter, D.C. Crawford, M.K. Meyer A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design Journal of Nuclear Materials 2009 389 458-469 10.1016/j.jnucmat.2009.02.035
Y.S. Kim, G.L. Hofman, A.M. Yacout Migration of minor actinides and lanthanides in fast reactor metallic fuel Journal of Nuclear Materials 2009 392 164-170 10.1016/j.jnucmat.2009.03.043 X447 X501
W.J. Carmack, D.L. Porter, Y.I. Chang, S.L. Hayes, M.K. Meyer, D.E. Burkes, C.B. Lee, T. Mizuno, F. Delage and J. Somers Metallic fuels for advanced reactors Journal of Nuclear Materials 2009 392 139-150 10.1016/j.jnucmat.2009.03.007 X425 X435 X501
R.L. Williamson, J.D. Hales, S.R. Novascone, M.R. Tonks, D.R. Gaston, C.J. Permann, D. Andrs, R.C. Martineau Multidimensional multiphysics simulation of nuclear fuel behavior Journal of Nuclear Materials 2012 423 149-163 10.1016/j.jnucmat.2012.01.012
Y.S. Kim, T.W. Cho and D.S. Sohn Thermal conductivities of actinides (U, Pu, Np, Cm, Am) and uranium alloys (U-Zr, U-Pu-Zr and U-Pu-TRU-Zr) Journal of Nuclear Materials 2014 445 272-280 10.1016/j.jnucmat.2013.11.018 X501
T. Sofu A Review of Inherent Safety Characteristics of Metal Alloy Sodium-Cooled Fast Reactor Fuel against Postulated Accidents Nuclear Engineering and Technology 2015 47 227-239 10.1016/j.net.2015.03.004
J. Galloway, C. Unal, N. Carlson, D. Porter, S. Hayes Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code BISON Nuclear Engineering and Design 2015 286 17-Jan 10.1016/j.nucengdes.2015.01.014
C. Matthews, C. Unal, J. Galloway, D.D. Keiser, S.L. Hayes Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review Nuclear Technology 2017 198 231-259 10.1080/00295450.2017.1323535
H.P. Sun, Y.P. Zhang, W.X. Tian, S.Z. Qiu, G.H. Su Development and validation of thermo-mechanical analysis code of metallic fuel under steady-state conditions in LMFR Annals of Nuclear Engergy 2020 138 107221 10.1016/j.anucene.2019.107221 X425 X441 X447
I. Greenquist, J.J. Powers 25-Pin metallic fuel performance benchmark case based on the EBR-II X430 experiments series Journal of Nuclear Materials 2021 556 153211 10.1016/j.jnucmat.2021.153211 X430
A.V. Gribok, D.L. Porter, K.M. Paaren, M.D. Gale, S.C. Middlemas, N.J. Lybeck Automatic information extraction from neutron radiography imaging to estimate axial fuel expansion in EBR-II Journal of Nuclear Materials 2021 557 153250 10.1016/j.jnucmat.2021.153250 X425 X425A X425B X430
K.M. Paaren, A. Black, N. Lybeck, K. Mo, B. W. Spencer, P. Medvedev. D. Porter BISON fuel performance modeling optimization for experiment X447 and X447A using axial swelling and cladding strain measurements Nuclear Engineering and Design 2022 394 111812 10.1016/j.nucengdes.2022.111812 X447 X447A
K.M. Paaren, N. Lybeck, K. Mo, P.G. Medvedev, D.L. Porter Cladding Profilometry Analysis of EBR-II metallic fuel pins with HT9, D9, and SS316 cladding Energies 2021 14 515 10.3390/en14020515 X421 X421A X441 X441A X486
K.M. Paaren, M. Gale, M.J. Kerr, P.G. Medvedev, D.L. Porter Initial demonstration of Automated fuel performance modeling with 1,977 EBR-II metallic fuel pins using BISON code with FIPD and IMIS databases Nuclear Engineering and Design 2021 382 111393 10.1016/j.nucengdes.2021.111393 X419 X430 X430A X430B X441 X486
I. Greenquist, K.M. Cunningham, J. Hu, J.J. Powers, D.C. Crawford Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment Journal of Nuclear Materials 2021 553 152997 10.1016/j.jnucmat.2021.152997 IFR-1
D.L. Porter, H. Tsai Full-length U-xPu-10Zr (x = 0, 8, 19 wt.%) fast reactor fuel test in FFTF Journal of Nuclear Materials 2012 427 46-57 10.1016/j.jnucmat.2012.03.047 IFR-1
I. Greenquist, J.J. Powers Sensitivity and uncertainty of the IFR-1 BISON benchmark Progress in Nuclear Energy 2022 152 104361 10.1016/j.pnucene.2022.104361 IFR-1
A.L. Pitner, R.B. Baker Metal fuel test program in the FFTF Journal of Nuclear Materials 1993 204 124-130 10.1016/0022-3115(93)90208-G IFR-1, MFF-3, MFF-5
W.J. Carmack, H.M. Chichester, D.L. Porter, D.W. Wootan Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins Journal of Nuclear Materials 2016 473 167-177 10.1016/j.jnucmat.2016.02.019 MFF-3, MFF-5
M.T. Benson, J.M. Harp, Y. Xie, T. Yao, K.R. Tolman, K.E. Wright, J.A. King, A.I. Hawari, Q. Cai Out-of-pile and postirradiated examination of lanthanide and lanthanide-palladium interactions for metallic fuel Journal of Nuclear Materials 2021 544 152727 10.1016/j.jnucmat.2020.152727 MFF-3
J.M. Harp, D.L. Porter, B.D. Miller, T.L. Trowbridge, W.J. Carmack Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9 Journal of Nuclear Materials 2017 494 227-239 10.1016/j.jnucmat.2017.07.040 MFF-3
J. Thomas, A.F. Bengoa, S.T. Nori, R. Ren, P. Kenesei, J. Almer, J. Hunter, J. Harp, M.A. Okuniewski The application of synchrotron micro-computed tomography to characterize the three-dimensional microstructure in irradiated nuclear fuel Journal of Nuclear Materials 2020 537 152161 10.1016/j.jnucmat.2020.152161 MFF-3
Y. Wang, B.D. Miller, J.M. Harp, D. Salvato, L. Capriotti, T. Yao Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel Journal of Nuclear Materials 2022 572 153990 10.1016/j.jnucmat.2022.153990 MFF-3
D. Salvato, X. Liu, D.J. Murray, K.M. Paaren, F. Xu, T. Pavlov, M.T. Benson, L. Capriotti, T. Yao Transmission electron microscopy study of a high burnup U-10Zr metallic fuel Journal of Nuclear Materials 2022 570 153963 10.1016/j.jnucmat.2022.153963 MFF-3

Books

Authors Title Chapter Year Volume Page DOI EBR-II Experiments
C.E. Stevenson The EBR-II Fuel Cycle Story 1987
T. Ogata Comprehensive Nuclear Materials Metal Fuel 2012 5 1-40 10.1016/B978-0-12-803581-8.11678-9 X419 X420 X421 X423 X425 X430 X441 X447 X501
Takanari Ogata, Yeon Soo Kim, Abdellatif Yacout Comprehensive Nuclear Materials Metal Fuel Performance Modeling and Simulation 2012 5 713-753 10.1016/B978-0-12-803581-8.11676-5 X419 X420 X421 X425 X431 X432 X441 X447 X501
D.D. Keiser Jr. Comprehensive Nuclear Materials Metal Fuel-Cladding Interaction 2012 5 423 10.1016/B978-0-12-803581-8.00708-6