Metallic Fuel Open Resources

Resources available in open literature.

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 10.2172/10199805 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
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
A. Oaks, K. Mo, D. Zhang, A.M. Yacout Fuels Irradiation and Physics Database (FIPD) Development and Data Qualification FY24 Updates Argonne National Laboratory 2024 ANL-ART-283 10.2172/2406947
K. Mo, A. Oaks Specification of FIPD Fission Gas Chemistry Data Argonne National Laboratory 2024 ANL/CFCT-23/16 10.2172/2339544
A.L. Swearingen, P.G. Medvedev, K. Paaren Status Report on Fast Flux Test Facility Mechanistic Fuel Failure Experiment Analysis with BISON for Post Irradiation Examination Support Idaho National Laboratory 2024 INL/RPT-24-77745-Rev000 10.2172/2352484 MFF-3, MFF-5
A. Probert, L. Capriotti, J. Schulthess Characterization of Mk-IV and EBR-II X441A Metallic Fuel Pins for the THOR-C-2 and THOR-M-TOP-1 Experiments Idaho National Laboratory 2023 INL/RPT-23-74361 10.2172/2371039 X441A
Y. Miao, S. Shu, A. Oaks, N. Fassino, A.M. Yacout, C. Matthews, S. Novascone Enhance BISON Metal Fuel Transient Models and Enable Assessment Based on Out-of-Pile Transient Experiments Argonne National Laboratory 2023 ANL/NEAMS-23/6 10.2172/2282877 X425
L.K. Aagesen, J.A. Hirschhorn, C. Jiang Mechanistic FCCI model for BISON Idaho National Laboratory 2023 INL/RPT-23-74500-Rev.001 10.2172/1999521 X447
A. Oaks, K. Mo, Z. Mei, D. Zhang, A.M. Yacout Fast Reactor Database Utilization for Qualification of Metallic Fuel Forms Argonne National Laboratory 2023 ANL-ART-270 10.2172/1997208
S.C. Marschman, P.K. Hogan, C.E. Baily, T.W. Zollinger, R.S. Fielding, D.S. Johnston, D.C. Crawrford, B.K. Grover, P.W. Fuhrman, C.M. Shannon, E.C. Nef, A.O. Capatina, P.W. Wilding, E.N. Moore Fabricating Fuel for the Versatile Test Reactor Idaho National Laboratory 2022 INL/RPT-22-63555-Rev002 10.2172/1894683
A. Yacout, M. Billone, K. Mo, A. Oaks, C. Tomchik Progress Report on SFR Metallic Fuel Data Qualification Argonne National Laboratory 2022 ANL/CFCT-22/30 10.2172/1891011
I. Greenquist J.J. Powers Sensitivity and Uncertainty of the IFR-1 BISON Benchmark Oak Ridge National Laboratory 2021 ORNL/TM-2021/2230 10.2172/1831619 IFR-1
K.M. Cunningham, R.A. Lefebvre, M. Tonks, J.A. Hirschhorn, I.T. Greenquist, J.J. Powers Streamlining the Coupling of BISON and Dakota Through the NEAMS Workbench Oak Ridge National Laboratory 2021 ORNL/TM-2021/1958 10.2172/1813199 IFR-1, X430
T. Carolyn Out-of-Pile Furnace Tests on Fast Reactor Metallic Fuels Conducted at the AGHCF Argonne National Laboratory 2021 ANL-ART-217 10.2172/1779724 X425, X429, X420, X421, X421A, X423C, X430A, X441, X441A, IFR-1, X425, X429B
J.A. Hirschhorn, J.J. Powers Assessment of the BISON Metallic Fuel Performance Models Oak Ridge National Laboratory 2021 ORNL/TM-2020/1824 10.2172/1763469 X430
I.T. Greenquist, J.J. Powers Metallic Fuel Benchmark Simulations Based on the X430 Experiments Oak Ridge National Laboratory 2020 ORNL/TM-2020/1565 10.2172/1649124 X430
A. Aitkaliyeva, M. Tonks, J. Hirschhorn, J. Powers, I. Greenquist, B. Beeler Research Needs for Uranium-Zirconium- Based Metallic Fuels Idaho National Laboratory 2020 INL/EXT-20-58719-Rev000 10.2172/1634988
M.A. Okuniewski, V. Tomar, X. Bai, C. Deo, B. Beeler, Y. Zhang Microstructure, Thermal, and Mechanical Properties Relationships in U and UZr Alloys (Final Report) Department of Energy 2020 NEUP-16-10821 10.2172/1632268 MFF-3
J.J. Carmack, D.L. Porter, D.G. Cummings, H.M. Chichester, S.L. Hayes, D.W. Wootan Examination of Legacy Metallic Fuel Pins (U-10Zr) Tested in FFTF Idaho National Laboratory 2020 INL/EXT-20-28987-Rev.01 10.2172/1617195 MFF-3, MFF-5
A.X. Zabriskie, K.D. Weaver Select Transient Metallic Fuel Bison Benchmarks Idaho National Laboratory 2019 INL/EXT-19-55892-Rev.0 10.2172/1604753 X441, X512, X419A, X419, X425, MFF-3, MFF-5
K.R. Tolman, D.L. Porter X-ray Diffraction Characterization of U-10wt% EBR-II Driver Fuel and Fuel Used for AFC-4B and AFC-4D Testing in the Advanced Test Reactor Idaho National Laboratory 2018 INL/EXT-18-52276-Rev000 10.2172/1515017 MFF-8A (Unirradiated Sample)
J.M. Harp, L. Capriotti, F. Cappia Baseline Postirradiation Examination of the AFC-3C, AFC-3D, and AFC-4A Experiments Idaho National Laboratory 2018 INL/EXT-18-51447-Rev000 10.2172/1498255
J. Zhang, C. Taylor Studies of Lanthanide Transport in Metallic Fuel Ohio State University 2018 14-6482 10.2172/1432451 X447
F. Di Lemma, D.L. Porter Secondary Phase Objects in As-cast U-10 wt% Zr Idaho National Laboratory 2017 INL/EXT-17-41918-Rev002 10.2172/1482120
D.L. Porter Density of U-10wt%Zr Materials Idaho National Laboratory 2017 INL/EXT-17-41917-Rev002 10.2172/1482119
J.M. Harp, L. Capriotti, S.L. Hayes, P.G. Medvedev, D.L. Porter Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report Idaho National Laboratory 2017 INL/EXT-17-41677-Rev000 10.2172/1468425
D.W. Wootan, J.V. Nelson Irradiation Data for the MFF-3 and MFF-5 Tests in the FFTF Pacific Northwest National Laboratory 2011 PNNL-20249 10.2172/2217344 MFF-3, MFF-5
K. Mo, A. Oaks, Y. Miao, Z. Dandan, D. L. Porter, J. L. Schulthess Advances in Metallic Fuel Database Development and Data Qualification Idaho National Laboratory 2024 INL/CON-24-76957-Revision-0 10.2172/2352721
C. B. Jensen, D. L. Porter AFC Metallic Fuel Research and Development 5-Year Plan Idaho National Laboratory 2024 INL/RPT-23-74940-Revision-0 10.2172/2371528
L. Capriotti, K. Paaren, D. Salvato, F. Di Lemma, Y. Wang, X. Fei, Y. Tiankai, D. L. Porter Characterization of Legacy Fuels- Progress to Fuel Cladding Chemical Interaction Idaho National Laboratory 2024 INL/MIS-24-78202-Revision-0 10.2172/2427327 MFF-2 MFF-3
C. Adkins, T. Pavlov, R. Schley, S. Middlemas, C. Marshall, M. Cole Demonstrate Thermal Property Measurement on Irradiated Fuel in IMCL Idaho National Laboratory 2019 INL/EXT-19-55902 10.2172/1605593 MFF-3
S. Yoon, C. Rabiti, J. Sackett EBR-II Data Digitization Idaho National Laboratory 2014 INL/EXT-14-32937 10.2172/1196549
L. Capriotti, K. Wright, F. Di Lemma, T. Trowbridge, A. Aitkaliyeva, T. T. Rahn Engineering & Microstructure Scale PIE Report on EBR-II X441A Metallic Fuel Pins for the MORPH Experiment Idaho National Laboratory 2022 INL/-EXT-19-55851 10.2172/2283741 X441A
R. T. Sweet, S. Novascone Evaluation of Reduced Order Model for HT-9 Creep and Modifications to Current HT-9 Creep Model in BISON Idaho National Laboratory 2022 INL/RPT-22-70168 10.2172/1983617 X441
A. M. Yacout, A. Oaks, W. Mohamed, K. Mo FIPD EBR-II Fuels Irradiation & Physics Database Argonne National Laboratory 2017 ANL-ART-124 10.2172/1480520
A. Oaks, K. Mo, Y. Miao, A. M. Yacout FY20 Progress Report on FIPD Development and User Support Argonne National Laboratory 2020 ANL-ART-1215 10.2172/1821697
Y. Miao, A. Oaks, A. M. Yacout, C. Matthews, S. Novascone FY21 Progress Report on BISON Metallic Fuel Model Development and V&V Using EBR-II Legacy Data Argonne National Laboratory 2021 ANL/CFCT-21/19 10.2172/1828881 X423 X447(X447A)
J. K. Hartwell, R. T. Klann, M. E. Mcllwain Gamma-Ray Spectrometric Characterization of Overpacked CC104/107 RH-TRU Wastes - Surrogate Tests Idaho National Laboratory 2000 INEEL/EXT-2000-00567 10.2172/764185 X486
L. K. Aagesen, J. A. Hirschhorn C. Jiang, Y. Miao Improvement of mechanistic fuel-cladding chemical interaction modeling in BISON Idaho National Laboratory 2024 INL/RPT-24-81050 10.2172/2477151 X425 X447
M. Cappiello, R. Hobbins, K. Penny, L. Walters Independent Review of AFC 2A, 2B, and 2E ATR Irradiation Tests Idaho National Laboratory 2014 INL/EXT-14-31445 10.2172/1123850
L. Capriotti Legacy EBR-II / FFTF Metallic Fuel PIE Examinations Idaho National Laboratory 2024 INL/MIS-23-75870-Revision-0 10.2172/2438040 X429B X430 X441 X486 X496 X501 X510 X512 X521
M. Billone Magnification Determination for AGHCF Metallographic Images Argonne National Laboratory 2023 ANL/NSE-23/90 10.2172/2221819 X425 X429 X447(X447A)
J. A. Hirschhorn, R. T. Sweet, J. J. Powers Metallic Fuel Performance Code Requirements for the Versatile Test Reactor Project Oak Ridge National Laboratory 2021 ORNL/TM-2021/1957 10.2172/1798590
L. Capriotti Metallic fuel PIE at INL from harvesting legacy materials to ATR/TREAT experiments Idaho National Laboratory 2024 INL/MIS-24-77135-Revision-0 10.2172/2427315 X429B X430 X441 X486 X496 X501 X510 X512 X521
L. Squires, K. Tolman, F. Di Lemma, T. Hartman, D. Porter Modified Peak Ratio Method for Quantitative Texture Analysis of U10Zr Alloys Idaho National Laboratory 2017 INL/EXT-17-43392 10.2172/1482122
L. Capriotti Non-Destructive Postirradiation Examination of the AFC-4C Capsule/ Rodlet 5 Experiment Idaho National Laboratory 2020 INL/EXT-20-59497 10.2172/1984274
L. L. Briggs, L. K. Chang, D. J. Hill, J. Ahrens, M. Billone, D. C. Crawford, E. Filewicz, P. J. Finck, E. K. Fujita, K. Grimm, K. C. Gross, S. Kamal, J. Kramer, J. Ku, C. Lahm, M. Lee, Y. Liu, D. Meneghetti, R. Pahl, W. A. Ragland, R. W. Schaefer, D. L. Porter, H. C. Tsai, A. M. Yacout Safety Analysis and Technical Basis for Establishing an Interim Bunup Limit for Mark-V and Mark-VA Fueled Subassemblies in EBR-II Argonne National Laboratory 2018 ANL-NSE-1 10.2172/1542889 X101 X133 X319 X390 X399 X402 X411 X412 X415 X416 X419(X419B) X420(X420B) X421(X421A) X425(X425B) X427 X429(X429B) X441(X441A) X447(X447A) X482(X482B) X483
M. A. Smith, L. Ibarra, A. Oaks Software Quality Assurance for EBR-II Fuels Irradiation and Physics Database (FIPD) Argonne National Laboratory 2021 ANL-ART-238 10.2172/1823468
N. Condon, K. Mo, A. Oaks Specification of EBR-II Gamma Scan Data from the Precision Gamma Scanner Argonne National Laboratory 2021 ANL/CFCT-22/19 10.2172/1973263 X447A
K. Mo, A. Oaks Specification of EBR-II Laser Profilometry Data Argonne National Laboratory 2021 ANL/CFCT-21/21 10.2172/1973265 X419B X420(X420A/B) X421(X421A) X425 X429(X429B) X431 X435 X441(X441A) X447(X447A)
Y. Miao, K. Mo, A. Oaks, C. Tomchik, Z. Mei Specifications of EBR-II Neutron Radiography Method Description and Digitization Approach Argonne National Laboratory 2022 ANL/CFCT-22/22 10.2172/1973262 X423(X423A/B/C)
L. Capriotti, J. Harp Status PIE Report on Legacy EBR-II and FFTF Metallic Fuel Experiments Idaho National Laboratory 2019 INL/EXT-19-55847 10.2172/1604754 X430 X486 X496 X501 X521
S. R. Novascone, A. Casagranda, P. G. Medvedev, C. Matthews, A. X. Zabriskie Summary and Assessment of Metallic Fuel Capabilities in Bison Idaho National Laboratory 2018 INL/EXT-18-51399 10.2172/1765545 X441 X447
W. Weaver, T. Pavey Test Plan Proposal for an International Joint Project for Transient Testing of Fast Reactor Fuels Idaho National Laboratory 2019 INL/EXT-19-54161 10.2172/1604903 X419 X420 X421 X425
M. K. Meyer, S. L. Hayes, W. J. Carmack, H. Tsai The EBR-II X501 Minor Actinide Burning Experiment Idaho National Laboratory 2008 INL/EXT-08-13835 10.1016/j.jnucmat.2009.03.041 X501
A. Karahan, T. Kim, T. Fanning, D. O'Grady Validation of MFUEL Metal Fuel Performance Models of SAS4A/SASSYS-1 Argonne National Laboratory 2023 ANL/NSE-23/11 10.2172/1985487 X419 X423 X425 X430 X441 X447

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-II 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
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, 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
D. C. Crawford, D. L. Porter Applying U.S. metal fuel experience to new fuel designs for fast reactors Progress in Nuclear Energy 2024 171 105135 10.1016/j.pnucene.2024.105135
P. Jiang, R. Qiu, J. Cao, X. Liao, Y. Chen, Z. Liu, X. He, W. Yang, H. Deng Development of U-Zr-Xe ternary interatomic potentials appropriate for simulation of defect and Xe behaviors in U-Zr system Journal of Nuclear Materials 2024 588 154824 10.1016/j.jnucmat.2023.154824
K. Mahbuba, B. Beeler, A. Jokisaari Grain boundary self-diffusion and point defect interactions in ?-U via molecular dynamics Journal of Nuclear Materials 2025 604 155521 10.1016/j.jnucmat.2024.155521
W. J. Williams, J. Lund, R. E. Garcia, M. A. Okuniewski A modern reappraisal of the U-Zr phase diagram Journal of Nuclear Materials 2025 603 155378 10.1016/j.jnucmat.2024.155378
A. Karahan, J. Buongiorno A new code for predicting the thermo-mechanical and irradiation behavior of metallic fuels in sodium fast reactors Journal of Nuclear Materials 2010 396 283-293 10.1016/j.jnucmat.2009.11.022 X430 X425 X447
J. Fay, F. Di Lemma, A. Gribok, K. Paaren, P. Medvedev, L. Capriotti, D. Porter, J. Lian An analysis of fluff formation in metallic fuel via data analyzes from EBR-II experiments and BISON fuel code modeling Journal of Nuclear Materials 2022 567 153813 10.1016/j.jnucmat.2022.153813 X447 X419 X420 X421 X423 X435
T. Prathibha, A. S. Suneesh, A. Rout, B. Robert Selvan, M. A. Suba, J. S. Brahmaji Rao, G. V. S. Ashok Kumar, D. Bola Sankar, S. Rajeswari, N. Ramanathan, A. Suresh, V. Jayaraman, N. Sivaraman Assay of zirconium and americium in the irradiated U-Zr metal alloy fuel slug Journal of Nuclear Materials 2024 600 155292 10.1016/j.jnucmat.2024.155292
D. M. Wachs, L. Capriotti, D. Porter Behavior of metallic fast reactor fuels during an overpower transient Journal of Nuclear Materials 2021 557 153304 10.1016/j.jnucmat.2021.153304 X441(X441A) X448 X483 X512
R. L. Williamson, J. D. Hales, S. R. Novascone, G. Pastore, K. A. Gamble, B. W. Spencer, W. Jiang, S. A. Pitts, A. Casagranda, D. Schwen, A. X. Zabriskie, A. Toptan, R. Gardner, C. Matthews, W. Liu, H. Chen BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms Nuclear Technology 2021 207 954-980 10.1080/00295450.2020.1836940 X411
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)
L. Capriotti, J. M. Harp Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II Journal of Nuclear Materials 2020 539 152279 10.1016/j.jnucmat.2020.152279 X501
A. Pradhan, F. Xu, D. Salvato, I. Charit, C. Judge, L. Capriotti, T. Yao, Characterization of Fuel Cladding Chemical Interaction on a High Burnup U-10Zr Metallic Fuel via Electron Energy Loss Spectroscopy Enhanced by Machine Learning Materials Characterization 2024 218 114524 10.1016/j.matchar.2024.114524
K. Paaren, N. Lybeck, K. Mo, P. Medvedev, D. Porter Cladding Profilometry Analysis of Experimental Breeder Reactor-II Metallic Fuel Pins with HT9, D9, and SS316 Cladding Energies 2021 14 515 10.3390/en14020515 X421 X441(X441A) X421A X486
K. M. Paaren, S. Christian, L. Capriotti, A. Aitkaliyeva, D. Porter Comparison of Zirconium Redistribution in BISON EBR-II Models Using FIPD and IMIS Databases with Experimental Post Irradiation Examination Energies 2023 16 6817 10.3390/en16196817 X430 X441(X441A) X430A X430B
S. Middlemas, D. E. Janney, C. Adkins, K. Bawane, Determining the effects of U/Pu ratio on subsolidus phase transitions in U-Pu-Zr metallic fuel alloys Journal of Nuclear Materials 2024 591 154909 10.1016/j.jnucmat.2024.154909
C. Matthews, S. Novascone, A. Casagranda, L. Aagesen, C. Unal, D. Andersson Development and formulation of physics based metallic fuel models and comparison to integral irradiation data Journal of Nuclear Materials 2023 578 154343 10.1016/j.jnucmat.2023.154343 X441(X441A)
T. Ogata, T. Yokoo Development and Validation of ALFUS: An Irradiation Behavior Analysis Code for Metallic Fast Reactor Fuels Nuclear Technology 1999 128 113-123 10.13182/NT99-A3018
N. D. Jerred, R. Khanal, M. T. Benson, S. Choudhury, I. Charit Evaluation of Sb-Nd and Te-Nd phases within the U-Zr fuel matrix and their interactions with HT9 alloy Journal of Nuclear Materials 2024 592 154966 10.1016/j.jnucmat.2024.154966
K. E. Wright, L. Lecrivain, C. Pincock, M. Coleman, P. Wiscaver, B. Barker, L. G. Rodrigues Albuquerque, L. Capriotti, A. Aitkaliyeva Exploring constituent redistribution in irradiated U-19Pu-14Zr fuel via electron probe microanalysis Journal of Nuclear Materials 2025 603 155411 10.1016/j.jnucmat.2024.155411 X441
A. Karahan, N. C. Andrews Extended fuel swelling models and ultra high burn-up fuel behavior of U-Pu-Zr metallic fuel using FEAST-METAL Nuclear Engineering and Design 2013 258 26-34 10.1016/j.nucengdes.2013.02.004 X430 X425
G. Beausoleil, L. Capriotti, B. Curnutt, R. Fielding, S. Hayes, D. Wachs FAST irradiations and initial post irradiation examinations - Part I Nuclear Engineering and Technology 2022 54 4084-4094 10.1016/j.net.2022.07.008 X425 X419 X423 X486A
A. M. Yacout, K. Mo, A. Oaks, Y. Miao, T. Sofu, W. Mohamed FIPD: The SFR metallic fuels irradiation & physics database Nuclear Engineering and Design 2021 380 111225 10.1016/j.nucengdes.2021.111225
S. Shousha, B. Beeler, L. K. Aagesen, G. L. Beausoleil, M. A. Okuniewski First-principles investigation of lanthanides diffusion in HCP zirconium via vacancy-mediated transport Journal of Nuclear Materials 2024 601 155310 10.1016/j.jnucmat.2024.155310
S. Patnaik, G. L. Beausoleil, L. Capriotti Fission accelerated steady-state post irradiation examinations - Part II Nuclear Engineering and Technology 2024 56 4158-4168 10.1016/j.net.2024.05.019 X425(X425A)
H. Jung, H. Song, Y. Kim, D. Jerng Fracture simulation of SFR metallic fuel pin using finite element damage analysis method Nuclear Engineering and Technology 2021 53 932-941 10.1016/j.net.2020.08.009 X425
K. M. Paaren, M. Gale, D. Wootan, P. Medvedev, D. Porter Fuel Performance Analysis of Fast Flux Test Facility MFF-3 and -5 Fuel Pins Using BISON with Post Irradiation Examination Data Energies 2023 16 7600 10.3390/en16227600 MFF-3 MFF-5
J. K. Hartwell, M. E. McIlwain Gamma-ray spectrometry combined with acceptable knowledge (GSAK): A technique for characterization of certain remote-handled transuranic (RH-TRU) wastes Journal of Radioanalytical and Nuclear Chemistry 2005 264 205-211 10.1007/s10967-005-0695-8 X486
S. Shu, Y. Miao, A. Oaks, K. Mo, C. Tomchik, A. M. Yacout Improved correlations of the fuel/cladding liquid penetration rate with the out-of-pile transient database Nuclear Engineering and Design 2024 417 112819 10.1016/j.nucengdes.2023.112819 IFR-1
K. M. Paaren, M. Gale, M. J. Kerr, P. Medvedev, D. Porter Initial demonstration of automated fuel performance modeling with 1977 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 X430 X441 X486
G. L. Beausoleil, C. Petrie, W. Williams, A. Jokisaari, L. Capriotti, S. Novascone, C. Adkins, M. Kerr Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm Nuclear Technology 2021 207 1491-1510 10.1080/00295450.2020.1826272 X441 X496
T. Rahn, L. Capriotti, F. Di Lemma, T. L. Trowbridge, J. M. Harp, A. Aitkaliyeva Investigation of constituent redistribution in U-Pu-Zr fuels and its dependence on varying Zr content Journal of Nuclear Materials 2021 557 153301 10.1016/j.jnucmat.2021.153301 X441
F. G. Di Lemma, K. E. Wright, L. Capriotti, A. X. Zabriskie, A. J. Winston, C. B. Jensen, D. M. Wachs Investigation of fuel microstructure at the top of a metallic fuel pin after a reactor overpower transient Journal of Nuclear Materials 2021 544 152711 10.1016/j.jnucmat.2020.152711 X441 X512
D. Zhao, T. Yao, M. T. Benson, K. Yang, A. Broussard, J. Shen, F. G. Di Lemma, J. Lian Manufacturing porous U-10Zr metallic fuels with controllable microstructure by volume control spark plasma sintering Journal of Nuclear Materials 2024 593 154978 10.1016/j.jnucmat.2024.154978
J. A. Hirschhorn, J. J. Powers, I. Greenquist, R. T. Sweet, J. Hu, D. L. Porter, D. C. Crawford Metallic Fuel Performance Benchmarks for Versatile Test Reactor Applications Nuclear Science and Engineering 2022 196 123-147 10.1080/00295639.2022.2043539 X430 X425 X447 X419 X420 X421 X423 X435 X441 X448 X483 X501 X486 X496 X427 X429 X431 X432 X436 X438 X449 X450 X451 X452 X453 X454 X455 X481 X482 X484 X485 X489 X510 X521 IFR-1 MFF-1A MFF-1 MFF-2 MFF-3 MFF-4 MFF-5 MFF-6
R. D. Mariani, D. L. Porter, S. L. Hayes, J. Rory Kennedy Metallic Fuels: The EBR-II Legacy and Recent Advances Procedia Chemistry 2012 7 513-520 10.1016/j.proche.2012.10.078
D. S. Gelles, P. M. Rice, S. J. Zinkle, H. M. Chung Microstructural examination of irradiated V+-(4+-5%)Cr+-(4+-5%)Ti Journal of Nuclear Materials 1998 258-263 1380-1385 10.1016/S0022-3115(98)00206-2 X530
J. Gazda, M. Meshii, H. M. Chung Microstructure of V+-4Cr+-4Ti alloy after low-temperature irradiation by ions and neutrons Journal of Nuclear Materials 1998 258-263 1437-1441 10.1016/S0022-3115(98)00159-7 X530
A. Karahan, M. S. Kazimi On the significance of modeling nuclear fuel behavior with the right representation of physical phenomena Nuclear Engineering and Design 2011 241 484-491 10.1016/j.nucengdes.2010.10.028 X425
D. L. Porter, H. J. M. Chichester, P. G. Medvedev, S. L. Hayes, M. C. Teague Performance of low smeared density sodium-cooled fast reactor metal fuel Journal of Nuclear Materials 2015 465 464-470 10.1016/j.jnucmat.2015.06.014 X496
Y. La, C. Wen, L. Feng, Y. Luo, D. Yun, W. Liu Phase-Field Simulation of Spinodal Decomposition in U-50Zr Metallic Nuclear Fuel Nanomaterials 2024 14 1548 10.3390/nano14191548
J. M. Harp, H. J. M. Chichester, L. Capriotti Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations Journal of Nuclear Materials 2018 509 377-391 10.1016/j.jnucmat.2018.07.003
X. L. Pan, H. X. Song, H. Wang, F. C. Wu, Y. C. Gan, X. R. Chen, Y. Chen, H. Y. Geng Prediction of novel ordered phases in U-X (X= Zr, Sc, Ti, V, Cr, Y, Nb, Mo, Hf, Ta, W) binary alloys under high pressure Acta Materialia 2024 263 119489 10.1016/j.actamat.2023.119489
A. V. Gribok, F. G. Di Lemma, J. Fay, D. L. Porter, K. M. Paaren, L. Capriotti Qualification and Quantification of Porosity at the Top of the Fuel Pins in Metallic Fuels Using Image Processing Energies 2024 17 1990 10.3390/en17091990 X425B
A. M. Yacout, K. Mo, A. Oaks, M. Billone, Y. Miao, J. Alicz Qualification of Metallic Fuel Data for Advanced SFR Applications Nuclear Technology 2023 209 S109-S122 10.1080/00295450.2022.2105779
U. K. Maity, N. Janardhanan, M. Periasamy Quantification of Zr in simulated dissolver solution of U-Zr fuel by laser-induced breakdown spectroscopy Radiochimica Acta 2024 112 481-486 10.1515/ract-2023-0208
S. U. Mun, G. Oh, J. H. Kim, S. Gyu Park, B. M. Weon Solidification-induced nonuniformity in U-Zr-RE metallic nuclear fuel rods Scientific Reports 2024 14 19402 10.1038/s41598-024-69935-x
T. Vazhappilly, A. K. Pathak Structural, Electronic, and Mechanical Properties of alpha(U) and alpha(U-Zr) Alloy Fuels Nuclear Science and Engineering 2024 45301 10.1080/00295639.2024.2407699
H. M. Chung, D. L. Smith Tensile and impact properties of vanadium-base alloys irradiated at <430 C Journal of Nuclear Materials 1998 258-263 1442-1450 10.1016/S0022-3115(98)00325-0 X530
M. K. Meyer, S. L. Hayes, W. J. Carmack, H. Tsai The EBR-II X501 minor actinide burning experiment Journal of Nuclear Materials 2009 392 176-183 10.1016/j.jnucmat.2009.03.041 X501
D. Salvato, K. M. Paaren, J. A. Hirschhorn, L. K. Aagesen, F. Xu, F. G. Di Lemma, L. Capriotti, T. Yao The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study Journal of Nuclear Materials 2024 591 154928 10.1016/j.jnucmat.2024.154928 X447 MFF-3 MFF-5
J. Fay, F. Di Lemma, L. Capriotti, D. Zhao, M. T. Benson, P. Medvedev, J. Lian Uniaxial compressive creep tests by spark plasma sintering of 70% theoretical density alpha-uranium and U-10Zr Journal of Applied Physics 2024 135 235002 10.1063/5.0204227
N. Rodriguez Pirez, J. Thomas, D. Murray, M. A. Okuniewski 3-D reconstruction and microstructural characterization of neutron-irradiated U-10Zr fuel using FIB-SEM serial sectioning MRS Advances 2023 1 14-20 10.1557/s43580-022-00464-3
H. Wang, F. Xu, L. Cai, D. Salvato, F. G. Di Lemma, L. Capriotti, T. Yao, M. Xian A fine pore-preserved deep neural network for porosity analytics of a high burnup U-10Zr metallic fuel Scientific Reports 2023 13 22274 10.1038/s41598-023-48800-3
K. M. Paaren, C. Boutros, R. J. Armstrong, P. G. Medvedev, N. E. Woolstenhulme, C. Jensen BISON automation to predict transient power history based off prescribed cladding temperature Nuclear Engineering and Design 2022 389 111665 10.1016/j.nucengdes.2022.111665
Y. Miao, A. Oaks, K. Mo, S. Shu, N. Fassino, C. Matthews, S. Novascone, A. M. Yacout BISON-FIPD integration enhanced low-burnup SFR metallic fuel swelling model evaluation framework Nuclear Engineering and Design 2023 414 112611 10.1016/j.nucengdes.2023.112611 X423(X421A/B/C)
K. Paaren, J. Yeh, P. G. Medvedev, S. C. Marschman Evaluation fuel slug eccentricity effects on fuel performance Annals of Nuclear Energy 2021 162 108498 10.1016/j.anucene.2021.108498
D. L. Porter, D. C. Crawford Fuel Performance Design Basis for the Versatile Test Reactor Nuclear Science and Engineering 2022 196 110-122 10.1080/00295639.2021.2009983 MFF-3 MFF-5
W. Chen, X. Bai Mesoscale modeling of microstructure-dependent thermal conductivity in U-Zr fuels Journal of Nuclear Materials 2022 562 153593 10.1016/j.jnucmat.2022.153593
Y. Miao, A. Oaks, K. Mo, M. Billone, C. Matthews, A. X. Zabriskie, S. Novascone, A. M. Yacout Metallic fuel cladding degradation model development and evaluation for BISON Nuclear Engineering and Design 2021 385 111531 10.1016/j.nucengdes.2021.111531
M. T. Benson, T. Yao, F. Teng, Y. Wang, J. A. King, J. Zhang Microstructural characterization of U-20Pu-10Zr-4Sb and U-20Pu-10Zr-4Sb-4Ln Journal of Nuclear Materials 2023 587 154729 10.1016/j.jnucmat.2023.154729
Y. Xie, M. T. Benson Microstructure and diffusion behavior of uranium fuel with minor additives Journal of Nuclear Materials 2020 535 152200 10.1016/j.jnucmat.2020.152200
J. Thomas, F. Teng, D. Murray, M. A. Okuniewski Nano-mechanical property assessment of a neutron-irradiated HT-9 steel cladding and a fuel-cladding chemical interaction region of a uranium-10 wt% zirconium nuclear fuel MRS Advances 2021 6 1048-1053 10.1557/s43580-021-00179-x
J. M. Harp, L. Capriotti, H. J. M. Chichester, P. G. Medvedev, D. L. Porter, S. L. Hayes Postirradiation examination on metallic fuel in the AFC-2 irradiation test series Journal of Nuclear Materials 2018 509 454-464 10.1016/j.jnucmat.2018.07.019
A. Aitkaliyeva Recent trends in metallic fast reactor fuels research Journal of Nuclear Materials 2022 558 153377 10.1016/j.jnucmat.2021.153377 X501
J. Thomas, X. Liu, L. He, D. Murray, F. Teng, B. Kombaiah, A. Winston, M. A. Okuniewski Transmission electron microscopy investigation of phase transformation and fuel constituent redistribution in neutron irradiated U-10wt.%Zr fuel Journal of Nuclear Materials 2023 581 154443 10.1016/j.jnucmat.2023.154443 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