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Authors	Title	Publisher	Year	Report Number	DOI	EBR-II/FFTF Experiments
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
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
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
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
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
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
M. Billone	Magnification Determination for AGHCF Metallographic Images	Argonne National Laboratory	2023	ANL/NSE-23/90	10.2172/2221819	X425 X429 X447(X447A)
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
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
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
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)
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
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. 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
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)
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
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. 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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
D.E. Janney, C.A. Papesch	FCRD Transmutation Fuels Handbook 2015	Idaho National Laboratory	2015	INL/EXT-15-36520	10.2172/1239879
S. Yoon, C. Rabiti, J. Sackett	EBR-II Data Digitization	Idaho National Laboratory	2014	INL/EXT-14-32937	10.2172/1196549
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
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.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
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
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
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
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
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
	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
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
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
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
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
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
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
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
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
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
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
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
Orechwa, Y;Khalil, H	PERFORMANCE CHARACTERISTICS OF A PRELIMINARY 330 MWe METAL CORE DESIGN	Argonne National Laboratory	1984	ANL-IFR-4	10.2172/707412
B.J. Toppel	User's guide for the REBUS-3 fuel cycle analysis capability	Argonne National Laboratory	1983	ANL-83-2	10.2172/6068571
C.P. Cabell	Summary description of the Fast Flux Test Facility	Hanford Engineering Development Laboratory	1980	HEDL-400	10.2172/6032523
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
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

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Authors	Title	Journal	Year	Volume	Page	DOI	EBR-II Experiments
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
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
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
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
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
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
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
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)
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
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
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
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
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
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
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
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)
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
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
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
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)
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
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
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
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
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
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)
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
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
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
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
A. Aitkaliyeva	Recent trends in metallic fast reactor fuels research	Journal of Nuclear Materials	2022	558	153377	10.1016/j.jnucmat.2021.153377	X501
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
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
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. 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
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
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, 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
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
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
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
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
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
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
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. 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
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
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
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
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
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
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.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
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
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
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
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
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
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
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
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.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
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
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
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
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
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
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
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
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)
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
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
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
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
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, 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
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
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
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
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

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Authors	Title	Chapter	Year	Volume	Page	DOI	EBR-II Experiments
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
C.E. Stevenson	The EBR-II Fuel Cycle Story		1987

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