TABLE OF CONTENTS


MONDAY, OCTOBER 7, 2019, 10:20 A.M.

1Electronic Energy Deposition and Radiation Effects in Oxides, Carbides and Metallic Alloys

Yanwen Zhang, Ritesh Sachan, Neila Sellami, Mohammad Ullah, Aleksi Leino, Ke Jin, Eva Zarkadoula (ORNL), Haizhou Xue Univ of Tennessee, Knoxville), William J. Weber (Univ of Tennessee, Knoxville/ORNL), invited

2Understanding of the Chemical Effects on the Morphology of Neutron Irradiation-Induced Solute Clusters in Reactor Pressure Vessel Steels

Joven J. H. Lim (UK Atomic Energy Authority), M..Grace Burke (Univ of Manchester)

3Mechanisms of Stability and Defect Trapping in Doped Iron Grain Boundaries

J. R. Trelewicz, Y. Zhang (Stony Brook Univ), B. P. Uberuaga (LANL)

4Effect of Cr and C on Dislocation Loops in Heavy Ion Irradiated Ultra-High Purity FeCr Alloys

Yao Li, Yajie Zhao (Univ of Tennessee, Knoxville), Arunodaya Bhattacharya (ORNL), Jean Henry (CEA), Steven John Zinkle (Univ of Tennessee Knoxville/ORNL)

5Influence of Irradiation Conditions on Precipitation Behavior in Fe-Cr and Ni Alloys

E. Reese, L.-J. Yu (Univ of Michigan), N. Almirall (Univ of California, Santa Barbara), K. Hattar (SNL), T. Yamamoto, G. R. Odette (Univ of California, Santa Barbara), J. Tucker (Oregon State Univ), M. G. Burke (Univ of Manchester), E. A. Marquis (Univ of Michigan), invited

6In-Situ Ion Irradiation of Ni-Based Austenitic Model Alloys

K. MA (CEA), B. Decamps (CSNSM), F. Prima (Institut de Recherche de Chimie), M. Loyer-Prost (CEA)

7Dislocation Loop Evolution in an Ion Irradiated FeCrAl Alloy with Various Irradiation Parameters

P. Xiu, L. Jiang, C. Lu, L. Wang (Univ of Michigan)

8In-Situ Observation of Irradiation Effects on High Entropy Alloys, 316H Stainless Steels and Nickel at 500-700°C

Wei-Ying Chen, Marquis Kirk (ANL), Naoyuki Hashimoto (Hokkaido Univ), Jien-Wei Yeh (Natl Tsing Hua Univ)

9Heat Treatment Effects on Precipitation in Irradiated HT9 Steel

T. M. K. Green, Todd Allen (Univ of Michigan), Li He (Univ of Wisconsin, Madison)

10Positron Annihilation Spectroscopy to Better Understand Void Formation in Neutron Irradiated Fe-Cr Alloys

C. J. Romnes (Univ of Illinois), M. Liu (NCSU), J. F. Stubbins (Univ of Illinois)

11TEM Study of Irradiated Fast Reactor MOX Fuels

Oliver Dieste, Thierry Wiss, Dragos Staicu (EC-JRC), Nathalie Chauvin (CEA), Jean-Yves Colle, Ondrej Benes, Mara Marchetti, Rudy Konings (EC-JRC)

12Cluster Dynamics Simulation of Xe Diffusion in UO2 and Doped UO2 for Out-of-Pile and In-Pile Conditions

D. A. Andersson, C. Matthews, R. Perriot, M. W. D. Cooper (LANL), G. Pastore (INL), B. P. Uberuaga, C. R. Stanek (LANL)

13Preparation of Ultrafine Nanofibrous Uranium Oxides by Electrospinning

V. Kundrat, J. Pinkas (Masaryk Univ)

14Fabrication of UO2-Mo Composite Fuel Candidates with Enhanced Thermal Conductivity from Sol-Gel Feedstock

S. Finkeldei (ORNL/Univ of California, Irvine), R. D. Hunt, J. Kiggans, K. A. Terrani, A. T. Nelson (ORNL)

15Three-Dimensional Microstructural Characterization of the Peripheral Region in FBR MOX Fuel

Casey McKinney, Riley Parrish, Assel Aitkaliyeva (Univ of Florida)


MONDAY, OCTOBER 7, 2019, 2:00 P.M.

16Atomistic Model of Fission Gas Bubble Re-Solution Rate in UO2

W. Setyawan (PNNL), M. W. D. Cooper (LANL), K. J. Roche (PNNL), B. P. Uberuaga, D. A. Andersson (LANL), B. D. Wirth (Univ of Tennessee, Knoxville), R. J. Kurtz (PNNL), invited

17The Influence of Mo Content on the Microstructural Evolution of Irradiated U-Mo Fuels

Charlyne Alexandria-Marie Smith (Univ of Florida), Dennis D. Keiser, Brandon D. Miller (INL), Assel Aitkaliyeva (Univ of Florida)

18Irradiation Driven Diffusion in UMo Fuels

Benjamin W. Beeler (INL), Zhi-Gang Mei (ANL), Michael William Donald Cooper (LANL)

19In-Situ Atomic Force Microscopy of Halide Salts Under X-Ray Irradiation

S. J. Riechers, N. B. Petrik, C. J. Pearce, J. S. Loring, K. M. Rosso, G. A. Kimmel (PNNL)

20Measurement of Low-Dose Irradiation Effects in PTFE Using Differential Scanning Calorimetry

Rachel C. Connick, Charles A. Hirst, Kangpyo So, Michael P. Short, R. Scott Kemp (MIT)

21Neutron Irradiated Microstructure of FeCr Alloys Investigated by TEM

M. Hernández-Mayoral, E. Oñorbe (CIEMAT), B. Gómez-Ferrer (Normandie Univ), C. Heintze (HZDR), L. Malerba (CIEMAT), P-M. Gueye, C. Pareige (Normandie Univ), invited

22Dose Rate and Temperature Effect on Irradiation-Enhanced Alpha Prime Precipitation in Ultra-High Purity FeCr Alloys

Yajie Zhao (Univ of Tennessee, Knoxville), Arunodaya Bhattacharya, Philip D. Edmondson (ORNL), Caleb Massey (Univ of Tennessee, Knoxville), Jean Henry (CEA), Steven J. Zinkle (Univ of Tennessee, Knoxville/ORNL)

23Effect of Heavy Ion Irradiation on α’ Precipitate Stability in Fe-15Cr

K. Thomas, Z. Jiao, G. S. Was (Univ of Michigan)

24High Dose Neutron Irradiation-Induced Microstructure Evolution in PM2000 and MA957 ODS Steels

Arunodaya Bhattacharya (ORNL), Samara M. Levine (Univ of Michigan), David T. Hoelzer, Josina W. Geringer, Kevin G. Field, Yutai Katoh (ORNL)

25Effect of Neutron Irradiation on the Microstructure of the ODS 14YWT Ferritic Alloy

David T. Hoelzer (ORNL), Maria A Auger (Universidad Carlos III de Madrid), Michael P. Moody (Univ of Oxford), Philip D. Edmondson, Kevin G. Field (ORNL)

26Microstructural Evolution of High-Dose Neutron Irradiated E97 at the Nano-Scale

C. Pareige, B. Gòmez-Ferrer (Normandie Univ), C. Dethloff (KIT/CIEMAT), E. Gaganidze (KIT), P. Pareige (Normandie Univ), L. Malerba (SCK-CEN/CIEMAT)

27Uranium Diboride, Accident Tolerant Fuel Concepts

J. Turner, T. J. Abram (Univ of Manchester)

28Development of Microstructurally-Engineered Uranium Mononitride

Aditya P. Shivprasad, Joshua T. White, Christopher J. Grote, Tarik A. Saleh (LANL)

29Thermal Property Measurement of Micrometer-Sized Samples

Heng Ban (Univ of Pittsburgh)

30Modeling Reactor Fuel Performance for Nuclear Thermal Propulsion

Michael Tonks (Univ of Florida), Marina Sessim (Penn State), Marvin Barnes (NASA)

31High Temperature Nanoindentation of Advanced Accident Tolerant Fuels

D. Frazer (Univ of California, Berkeley), J. T. White, T. A. Saleh (LANL)


MONDAY, OCTOBER 7, 2019, 4:30 P.M.

32Dislocation Loop Structure in Individual Grains of Proton Irradiated Polycrystalline Zr Aggregates

M. Topping (Univ of Manchester/Queen’s Univ), Gy Zilahi (Eötvös Univ Budapest), S. Irukuvarghula (Univ of Manchester), G. Ribárik (Eötvös Univ Budapest), A. Garner, A. Smith, R. Thomas (Univ of Manchester), P. Kenesel (ANL), P. Frankel, M. Preuss (Univ of Manchester), Tamas Ungar (Univ of Manchester/Eötvös Univ Budapest)

33Microstructure Characterization of Proton Irradiated Zircaloy-4

Peng Wang (Univ of Michigan), Josh Bowman, Arthur Motta (Penn State), Gary S. Was (Univ of Michigan)

34Characterization of a Neutron-Irradiated Zr-Nb-O Alloy Using Analytical Scanning Transmission Electron Microscopy

Xiang Liu (INL), M. Nedim Cinbiz (ORNL), Lingfeng He (INL), Daniel Jadernas (Studsvik Nuclear AB)

35Investigating the Effects of Existing Damage on the Primary Damage Formation in Zirconium

Jesse J. Carter, Richard W. Smith (NNL)

36Hardness Evolution of Zr2.5Nb and Zirconium Hydride Due to Proton-Irradiation

Igor Cherubin, Mark Daymond (Queen’s Univ)

37Machine Learning for Rapid Defect Quantification in Static and Dynamic Electron Microscopy Experiment

K. G. Field (ORNL), Mingren Shen, Guanzhao Li, Dongxia Wu, Yudai Yaguchi (Univ of Wisconsin, Madison), Jack Haley (Univ of Oxford), Dane Morgan (Univ of Wisconsin, Madison), invited

38Effect of Irradiation Temperature and Alloy Composition on Microstructural Evolution of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation

Caleb P. Massey (ORNL), Dalong Zhang (PNNL), Samuel A. Briggs (Oregon State Univ), Philip D. Edmondson, Maxim N. Gussev, Kevin G. Field (ORNL)

39Study of B2 and Laves Phase Evolution in a Novel Ferritic Steel Under Ion Irradiation

Li He (Univ of Wisconsin, Madison), L. Tan, Y. Yang (ORNL), K. Sridharan (Univ of Wisconsin, Madison)

40Heavy Ion Irradiation of FCC and BCC High Entropy Alloys for Advanced Nuclear Reactor Applications

Calvin A. Parkin, Michael Moorehead, Mohamed Elbakhshwan, Kumar Sridharan (Univ of Wisconsin, Madison), Wei-Ying Chen (ANL), Chuan Zhang (Computherm LLC), Lin Shao, Adam Gabriel (Texas A&M), Lingfeng He, Mukesh Bachhav (INL), Jing Hu (ANL), Adrien Couet (Univ of Wisconsin, Madison)

41Beyond TRISO: Applications and Opportunities for Particle Fuels in New Reactor Systems

A. T. Nelson (ORNL), invited

42Annular Fuel Pebble Test Program for the FHR

R. N. Latta (Kairos Power)

43Non-Destructive Geometric Characterization of TRISO Particles by X-Ray Tomography

Grant W. Helmreich, Tyler Gerczak, Dylan Richardson (ORNL)

44Influence of Irradiation Temperature on Fission Product and Actinide Distribution in AGR-2 TRISO Fuel

T. J. Gerczak, B. D. Eckhart, J. D. Hunn, F. C. Montgomery, R. L. Seibert, D. J. Skitt (ORNL)


MONDAY, OCTOBER 7, 2019, 6:00 P.M.

45Swelling, Creep and Embrittlement of D9 Stainless Steel Cladding and Duct in Four FFTF Driver Fuel Assemblies after High Neutron Exposure

F. A. Garner (Radiation Effects Consulting), B. J. Makenas (Hanford Mission Support Alliance, retired), S. A. Maloy (LANL)

46Radiation Damage Studies for Fe-Based Alloys Under 30 MeV Proton Irradiation

P. Uslu, M. Vedat Akdeniz, Amdulla Mekhrabov, M. Bilge Demirköz (Middle East Technical Univ)

47Helium Bubble Super-Lattice Formation, Grain Boundary Agglomeration, and Surface Blistering of Tungsten Under Combined Helium Implantation and Self-Ion Irradiation

Tianyao Wang, Frank A. Garner, Lin Shao (Texas A&M)

48Radiation Response of Pure Chromium for Evaluation of an Accident-Tolerant Fuel Concept Using Chromium Outer Coating on Zircalloy Cladding

Ekaterina Ryabikovskaya, Hyosim Kim, Tianyao Wang, Aaron French, Adam Gabriel, Frank A. Garner, Lin Shao (Texas A&M)

49Microstructure Evolution in Dual Ion-Irradiated HT9 at 445 °C and 460 °C to 16.6 dpa

L. He (Univ of Wisconsin, Madison), T. M. K. Green (Univ of Michigan), T. Allen (Univ of Michigan/Univ of Wisconsin, Madison)

50Peak Swelling Temperature in Ion Irradiated High-Purity Fe and Fe-Cr Alloys

Yan-Ru Lin (Univ of Tennessee, Knoxville), Arunodaya Bhattacharya (ORNL), Jean Henry (CEA), Steven J. Zinkle (Univ of Tennessee Knoxville/ORNL)

51Microstructural Stability of a 9Cr Ferritic-Martensitic Steel Irradiated to 7.44 dpa at ~490°C

Weicheng Zhong (ORNL), Tianyi Chen (Oregon State Univ), Lizhen Tan (ORNL)

52Microstructural Evolution after Helium-Pre-Implantation and Self-Ion Irradiation on a Dual-Phase 12Cr Oxide Dispersion Strengthened Alloy

Hyosim Kim, Tianyao Wang, Jonathan G. Gigax, Frank A. Garner, Lin Shao (Texas A&M)

53Radiation Tolerance of Additively Manufactured HT-9 Ferritic/Martensitic Steel

K. G. Field (ORNL), S. Taller (Univ of Michigan), N. Sridharan (ORNL)

54Effects of the Microstructure and Thickness of Porous Carbon Buffer Layer on the Thermo-Mechanical Behavior of an FCM Fuel Pellet

Hongyang Wei, Xiaobin Jian, Shurong Ding (Fudan Univ)

55A Model for Mesoscale Tensile Strength of Irradiated U-10Mo Fuels Considering Irradiation Creep Damage

Xiaobin Jian, Xiangzhe Kong, Shurong Ding (Fudan Univ)

56Measurement of Nanoscale Material Properties of Irradiated Lithium Aluminate

S. L. Riechers, B. R. Johnson, W. Jiang (PNNL)

57Investigation of Proton Radiation Damage Effects on the Tensile Strength of 3D Printed Acrylonitrile Butadiene Styrene

Arielle Miller, Grant Warner, Dharmaraj Raghavan (Howard Univ)

58Interfacial Radiation Damage Resistance in Oxide Thin Film Heterojunctions: An Atomic Perspective

M. Sassi, T. Kaspar, V. Shutthanandan, K. M. Rosso, S. R. Spurgeon (PNNL)

59Microstructural and Fracture Surface Analysis of TIG-Welded Zircaloy-4

J. R. Echols, K. Bawane, L. M. Garrison (ORNL)

60Bi-Axial Deformation of Zr-2.5 Nb Pressure Tube Material

H. Mazhar, C. Azih, M. A. Gharghouri, C. Bramburger (CNL)

61Flux and Fluence Dependence of Irradiation Creep in Austenitic Stainless Steels

Malcolm Griffiths (Queens Univ), Frank A. Garner (Radiation Effects Consulting)

62A Mesoscopic Investigation of the Mechanical Response of Iron with Irradiated Microstructure

Y. Pachaury, S. Mazumder, C. Nuela Enebechi, G. Warren (Purdue Univ), G. Po (Univ of Miami), J. P. Wharry, A. El-Azab (Purdue Univ)

63Deformation Behavior of SiC-SiC Channel Box in Boiling Water Reactor Environment

G. Singh, J. Gorton, D. Schappel, N. R. Brown, B. D. Wirth (Univ of Tennessee, Knoxville)

64Development and Evaluation of High Temperature Lead-Bismuth Corrosion Facilities for Fast Reactor Material Development

R. N. Wahlen, T. L. Grimm, M. Mamtimin, F. Y. Odeh, W. A. Peters (Niowave, Inc.), S. A. Maloy, K. A. Woloshun, E. Olivas, Natalia Rubio (LANL)

65Mesoscale Modeling of High Burn-up Structure (HBS) Formation and Evolution in UO2

M. Gomma Abdoelatef, F. Badry, Karim Ahmed (Texas A&M), Andrea Jokisaari, Daniel Schwen, Youngfeng Zhang (INL)

66Development of a Lead-Bismuth Cooled Subcritical Fast/Thermal Testbed for Material Radiation Damage Studies

M. Mamtimin, T. L. Grimm, R. N. Wahlen, F. Y. Odeh, W. A. Peters (Niowave, Inc.), S. A. Maloy, K. A. Woloshun (LANL), W. Yang, P. Deng (Univ of Michigan)

67Accelerated Atomistic Simulation of Radiation Events in Metal

Elton Y. Chen (Georgia Tech), Remi P. Dingreville (SNL), Chaitanya S. Deo (Georgia Tech)

68Investigation of Threshold Stress Level of Radially Reprecipitated Hydrides: A Phase-Field Approach

Wooseob Shin, Kunok Chang (Kyung Hee Univ)

69Local Chemical Environment Effects on the Energetics of Stacking Faults and Vacancy Platelets in α-Zirconium

J. F. March-Rico, G. Huang, B. D. Wirth (Univ of Tennessee, Knoxville)


TUESDAY, OCTOBER 8, 2019, 10:20 P.M.

70Neutron-Irradiated Microstructure of Light Water Reactor Materials

W. L. Karlsen (VTT), invited

71Re-Irradiation of Flux Thimble Tubes Using Heavy Ions

M. Song (Univ of Michigan), K. G. Field, J. T. Busby (ORNL), C. Topbasi (EPRI), G. S. Was (Univ of Michigan)

72Effect of High Dose Ion-Irradiation on Laser Weld Repairs of Previously Neutron Irradiated AISI 304 Stainless Steel

K. Mao (Purdue Univ), A. French, L. Shao (Texas A&M), Emmanuel Perez (INL), P. D. Freyer (Westinghouse), F. A. Garner (Texas A&M), Yaqiao Wu (Boise State Univ), J. P. Wharry (Purdue Univ)

73A New Void Swelling Phenomenon Revealed During Self-Ion Irradiation of Neutron-Preconditioned 304 Stainless Steel

Aaron J. French, Hyosim Kim, Laura Hawkins, Tianyao Wang, ChingHeng Shiau, Frank A. Garner, Lin Shao (Texas A&M)

74Re-Irradiation of Neutron Irradiated 304L Stainless Steel to High Damage Levels

Samara M. Levine, Zhijie Jiao, Gary S. Was (Univ of Michigan), Chad M. Parish (ORNL)

75Recent Applications of Transient Grating Spectroscopy for Inferring Radiation-Induced Evolution of Nuclear Materials

S. E. Ferry, K. B. Woller, C. A. Dennett, M. P. Short (MIT)

76Hardening and Strain Localisation in Irradiated Materials

Malcolm Griffiths (Queens Univ), Roman Voskoboynikov (Kurchatov Inst), invited

77Influence of Impurities in Microstructural Evolution of FeCr Alloys Under Ion Irradiation—Link with Hardening

C. Pareige, B. Gòmez-Ferrer (Normandie Univ), C. Heintze (HZDR), E. Oñorbe, M. Hernández-Mayoral (CIEMAT), P-M Gueye (Normandie Univ), L. Malerba (CIEMAT)

78Deformation-Based Recovery of Irradiation-Induced Ostwald Ripening in Nanocrystalline CuTa Alloy

Priyam V. Patki (Purdue Univ), Yaqiao Wu (Boise State Univ/Center for Advanced Energy Studies), Janelle P. Wharry (Purdue Univ)

79Effect of Temperature and Friction Stir Welding on Microstructure Evolution on Self-Ion Irradiated MA956 up to 200 dpa

J. McMahan, E. Getto, N. Nathan, B. Tobie (U.S. Naval Academy), S. Briggs (Oregon State Univ), K. Hattar (SNL), B. Baker (U.S. Naval Academy)

80Neutron Attenuation Effect on Cu-Rich Precipitate Formation and Evolution in a Pressure Vessel Weldment from the Zion NPP

Philip D. Edmondson, Thomas M. Rosseel, Mikhail A. Sokolov (ORNL)

81Effect of Friction Stir Welding on Microstructure Evolution on -Ion Irradiated MA956 up to 25 dpa

E. Getto, B. Tobie, N. Nathan (U.S. Naval Academy), S. Briggs (Oregon State Univ), K. Hattar (SNL), B. Baker (U.S. Naval Academy)

82Understanding the Driving Forces for Microstructural Evolution in Ceramics Subject to Ion Irradiation

Nathan Madden (Univ of Illinois), Khalid Hattar (SNL), Jessica A. Krogstad (Univ of Illinois), invited

83Effects of High Temperature Neutron Irradiation on the Structure of Graphite

Anne A. Campbell, Ercan Cakmak, Cristian I. Contescu, Nidia C. Gallego, Timothy D. Burchell (ORNL)

84Nanotube/Nanowire as Effective Defect Sinks in Metals: Atomistic Simulations and In Situ Ion Radiation Transmission Electron Microscopy

Kangpyo So, Penghui Cao, Yang Yang (MIT), Jong Gil Park (Sungkyunkwan Univ), Mingda Li, Yan Long (MIT), Yan Long (Shanghai Inst of Applied Physics), Jing Hu, Mark Kirk, Meimei Li (ANL), Young Hee Lee (Sungkyunkwan Univ), Michael P. Short, Ju Li (MIT)

85Cross-Sectional X-Ray Nanodiffraction Characterization of Radiation Damage, Stresses, and Microstructure in W Coatings

K. Hlushko (Montanuniversität Leoben), A. Mackova (Czech Academy of Sciences), J. Todt, J. Zalesak (Austrian Academy of Sciences), R. Daniel (Montanuniversität Loeben), J. Keckes (Montanuniversität Loeben/Austrian Academy of Sciences)

86Dependence of Microstructure Evolution in an Ion Irradiated Molybdenum Alloy on Irradiation Temperature and Ion Dose

P. Xiu, L. Jiang, C. Lu, L. Wang (Univ of Michigan)


TUESDAY, OCTOBER 8, 2019, 2:00 P.M.

87Radiation-Induced Microstructural Changes Under Neutron and Ion Irradiations

Meimei Li, Mark Kirk, Weiying Chen (ANL), invited

88The Role of High Damage Rates on Cavity Nucleation with Co-Injected Helium in Dual Ion Irradiated T91 Steel

Stephen Taller, Zhijie Jiao, Gary Was (Univ of Michigan)

89Effect of Helium on Swelling and Bubble and Cavity Evolution in Dual Ion Irradiated HT9 Steel

David Woodley, Zhijie Jiao, Kai Sun, Gary S. Was (Univ of Michigan)

90Dual Ion Irradiation of Commercial and Advanced Structural Materials: High Dose Resistance for Extended LWR Operation

C. R. Lear, M..Song, M. Wang, G. S. Was (Univ of Michigan), L. Tan (ORNL), R. Pathania (EPRI), J. L. Nelson (JLN Consulting)

91The Effect of Helium Co-Injection on the Cavity Evolution in Ion irradiated 21Cr32Ni Model Alloy

Muhammet Ayanoglu, Arthur T. Motta (Penn State)

92Reassessment of Void Swelling Rates in Austenitic Pressure Vessel Internals and Structural Components of Other Lower Operating Temperature Devices

F. A. Garner (Radiation Effects Consulting), S. A. Maloy (LANL)

93Advanced Manufacturing Technologies for Nuclear Applications

Fanny Balbaud-Célérier, P. Aubry, A. Chniouel, O. Hercher, F. Lomello, H. Maskrot, A. Michau, M. Ougler, M. Schlegel, W. Pacquentin, F. Schuster (CEA), invited

94Fabrication of Massive Crack-Free Delta-Phase Zirconium Hydride for High-Performance Moderator Application

Xunxiang Hu, Kurt Terrani (ORNL)

95Mechanical Behavior of Alloy 709 for Advanced Fast Reactor Applications

Dominic Piedmont (Univ of Illinois), Donghee Park (Univ of Illinois/KAIST), Victoria Riso (Univ of Illinois/Exelon Generation), Xiang Liu (Univ of Illinois/INL), James F. Stubbins (Univ of Illinois)

96Radiation Response of Bulk Metallic Glasses and Nanostructured Metallic Glasses: Fundamentals and Applications

Lin Shao, Hyosim Kim, Tianyao Wang (Texas A&M)

97Potential Solid-State Welding Processes of Advanced Ferritic-Martensitic Steels in the Nuclear Industry

Mei He (TerraPower)

98Westinghouse Electric Company Accident Tolerant Fuels Development

Kallie Metzger (Westinghouse), invited

99Atomic Scale Simulations of Self-Diffusion and Xe Diffusion in U3Si2 for Reactor Conditions

Michael Cooper (LANL), Ben Beeler, Kyle Gamble, Giovanni Pastore (INL), Christopher Matthews, Xiang-Yang Liu (LANL), Simon Middleburgh (Bangor Univ), Antoine Claisse (Westinghouse), Chris Stanek, David Andersson (LANL)

100A Phase-Field Approach to Predict the Formation Conditions of the High Burn-Up Structure in U3Si2

A. Cheniour, M. R. Tonks (Univ of Florida), J. Lian (RPI), Y. Zhang (Univ of Wisconsin, Madison)

101High Density Uranium Silicide Fuels—Fabrication and Oxidation Resistance

Bowen Gong (RPI), Lu Cai (Westinghouse), Tiankai Yao (RPI), Edward J. Lahoda, Frank Boylan, Peng Xu (Westinghouse), Jason Harp (INL), Jie Lian (RPI)

102Thermophysical Properties of Crystalline and Amorphous Uranium Silicides from First-Principles

Zhi-Gang Mei, Yinbin Miao, Abdellatif M. Yacout (ANL)

103Steam Oxidation Dynamics of Alloyed U3Si2+X (X=Al, Cr, Nb, Y, and Zr)

Elizabeth Sooby Wood, Cole Moczygemba, Geronimo Robles, Sean Nesloney (Univ of Texas at San Antonio), Christopher Grote (LANL), Lu Cai, Edward Lahoda (Westinghouse)


TUESDAY, OCTOBER 8, 2019, 4:30 P.M.

107Novel Amorphous SiOC Dispersion-Strengthened Austenitic Steel

Xueliang Yan, Fei Wang (Univ of Nebraska-Lincoln), Khalid Hattar (SNL), Michael Nastasi, Bai Cui (Univ of Nebraska Lincoln)

108Capacitive Discharge Resistance Welding for ODS Steel Cladding: Weld Properties and Radiation Resistance

C. R. Lear, B. P. Eftink, S. A. Maloy (LANL), T. J. Lienert (T.J. Lienert Consulting, LLC.)

109Radiation Response of Nanostructured Austenitic Stainless Steels

Zhongxia Shang, C. Fan, Jin Li (Purdue Univ), T. D. Shen (Yanshan Univ), Y. M. Wang (LLNL), M. A. Kirk, M. Li (ANL), Xinghang Zhang (Purdue Univ)

110Novel Fabrication Route for Oxide Dispersion Strengthened (ODS) Steel Cladding Tubes Using Cold Spray Technology

H. Yeom, M. Lenling (Univ of Wisconsin, Madison), J. Graham, P. Hosemann (Univ of California, Berkeley), D. Hoelzer (ORNL), S. Maloy (LANL), P. Grant (Oxford Univ), K. Sridharan (Univ of Wisconsin, Madison)

111Elucidating Three-Dimensional Microstructural Evolution in Neutron Irradiated HT-UPS Steel

M. A. Okuniewski, S. T. Nori, J. Thomas, G. Park, A. Figueroa (Purdue Univ), H. Sharma, J.-S. Park, P. Kenesei, J. Almer (ANL)

112Modeling Fission Gas Behavior in Traditional and Advanced Fuels Applied to Engineering Simulations

G. Pastore, K. A. Gamble, Y. Zhang (INL), D. A. Andersson, M. W. D. Cooper (LANL), L. Luzzi (Politecnico di Milano), invited

113Determination of Phase Equilibria in Uranium Silicide Fuel

Tashiema L. Ulrich, Theodore M. Besmann (Univ of South Carolina), Joshua T. White, Sven C. Vogel (LANL)

114Challenges and Opportunities of High Density Nuclear Fuel Use in Light Water Reactors

J. T. White, A. P. Shivprasad, C. Grote, Nan Li, Artaches Migdissov, K. Hollis, N. Abdul-Jabbar, T. Saleh (LANL)

115Microstructure Design Insights for UO2 Composite Fuels from a Microstructure Dependent Thermal Resistor Model and Fission Gas Study

Floyd W. Hilty, Michael R. Tonks (Univ of Florida)


TUESDAY, OCTOBER 8, 2019, 6:00 P.M.

116Micro-Nano Hetero Structures a Game Changer in Nuclear Fuel Cycle

Liviu Popa-Simil (LAVM LLC)

117First X-Ray Diffraction Characterizations of a Spent Nuclear Fuel Sample with Zy-4 Cladding at MARS Beamline of the SOLEIL Synchrotron

Sandrine Schlutig, Vincent Klosek (CEA), Denis Menut (Synchrotron SOLEIL), Raphaëlle Guillou, Jean Luc Bechade, Jean Noirot (CEA)

118Novel Synthesis Method for Three-Dimensional sp-2 Carbon Structure for Nuclear Waste Management

A. Resnick (Kennesaw State Univ), B. Haile (Georgia Tech), J. Park (Kennesaw State Univ)

119AFM Measurement of Adhesion Forces Under PWR Conditions Identifies Crud Resistant Coatings

M. Carlson, M. Short (MIT)

120LIBS Investigation of Nickel-Chromium Alloys Exposed to Molten Salt

William Ponder (Univ of Tennessee, Knoxville/ORNL), Kristian Myhre (ORNL), Steven Zinkle (Univ of Tennessee Knoxville/ORNL), Stephen Raiman (ORNL)

121Ab Initio Molecular Dynamics Study of U-Mo Alloys: Structural, Mechanical Vibrational and Defect Properties

Zhi-Gang Mei, Abdellatif M. Yacout (ANL)

122Room Temperature Mechanical Properties and Microstructure Evolution of TIG/FCAW Welded AISI 347 and AISI 347 Clad A533B-1 Low Alloy Steel

Kaustubh Bawane (Virginia Tech/ORNL), Lauren M. Garrison (ORNL)

123Fabrication of High-Entropy Alloys by Spark Plasma Sintering for Nuclear Applications

Xiang Zhang, Xueliang Yan, Fei Wang, Michael Nastasi, Bai Cui (Univ of Nebraska-Lincoln)

124Experimentally Validated Mesoscale Modeling of Thermal Conductivity of a UO2-BeO Composite Nuclear Fuel

F. Badry, Ryan Brito, M. Gomaa Abdoelatef, Sean McDeavitt, Karim Ahmed (Texas A&M)

125Heterogeneity by Design in Engineered Micro-Nano Hetero Structures

Liviu Popa-Simil (LAVM LLC)

126Atom Probe Tomography of Single Crystal ThO2 and the Associated Challenges of Analyzing Oxide Materials with this Technique

Amrita Sen (Purdue Univ), Mukesh Bachhav (INL), Janelle P. Wharry (Purdue Univ)

127Recent Examinations of Microstructural Evolution of Metallic Fuels for Sodium-Cooled Fast Reactors After a Reactor Transient

F. G. Di Lemma, K. E. Wright, L. Capriotti, C. B. Jensen, D. M. Wachs (INL)

128Investigation of Restructuring Behavior in Commercial LWR Fuel

T. J. Gerczak, M. Gussev (ORNL), C. McKinney (ORNL/Univ of Florida), Z. Burns, K. Linton, K. A. Terrani (ORNL)

129Shielded Fuel Organic Moderated and Cooled Reactor

D. R. Talbot (U.S. Air Force Academy)

130Post-Irradiation Examination of Thoria and Thoria-Based Fuel Experiments DME-176 and DME-221 at Canadian Nuclear Laboratories

A. Barry (CNL)

131Evaluation of the Accuracy of Computed Uranium Thermodynamic Properties with Dispersion-Corrected Density Functional Theory

Matthew S. Christian, Theodore Besmann (Univ of South Carolina), Erin R. Johnson (Dalhousie Univ)

132Resolution Capabilities for Measurement of Fuel Swelling Using X-Ray Tomography

Michael Dylan Richardson, Grant William Helmreich, Alicia Marie Raftery, Andrew T. Nelson (ORNL)

133Quantitative Microchemical Analysis Using Electron Probe Microanalysis: A Study Featuring the Analysis of Irradiated FUTURIX-FTA U-Pu-Zr with Added Minor Actinides

K. E. Wright, J. M. Harp, L. Capriotti (INL)

134Fabrication of UN-Mo CERMET Nuclear Fuel Using Advanced Manufacturing Techniques

A. M. Raftery, A. T. Schumacher, M. P. Trammell, J. W. McMurray, A. T. Nelson, K. A. Terrani (ORNL)

135Advanced Characterization of Annular Fast Reactor MOX

F. Cappia, K. Wright, L. He, D. Murray, B. Miller, J. Harp (INL)

136Molten Salt Thermochemical Database (MSTDB) to Support Reactor Design and Simulation

Johnathon Ard, Jacob Yingling, Kaitlin Johnson, Denise Lopes, Theodore Besmann (Univ of South Carolina), Jake McMurray (ORNL), Markus Piro (Univ of Ontario Inst of Tech)

137Assessment of Constituent Molten Salt Fuel Systems and Demonstration of Relevant Molten Salt Thermochemical Calculations

Jacob Yingling, Johnathon Ard, Kaitlin Johnson, Denise Lopes, Theodore Besmann (Univ of South Carolina), Jake McMurray, Stephen Utlak (ORNL)

138Comparison of Urania and Thoria Fuels Under Light Water Reactor Conditions and Investigation of Fracture/Relocation Behavior Using the BISON Fuel Performance Code

R. T. Sweet (Univ of Tennessee, Knoxville), B. D. Wirth (Univ of Tennessee, Knoxville/ORNL)


WEDNESDAY, OCTOBER 9, 2019, 8:00 A.M.

139Neutron Irradiation of Structural Materials in Molten Chloride Salt

Stephen S. Raiman, N. Dianne Bull Ezell, Kurt Smith, Richard T. Mayes, Joel McDuffee (ORNL)

140Simultaneous Proton Irradiation Can Decelerate Corrosion of Ni-20Cr in Molten Fluoride Salt

Weiyue Zhou, Michael P. Short (MIT)

141Comparison of Post-Irradiation Annealing Effects in Proton-Irradiated and Neutron-Irradiated 304 Stainless Steels

Zhijie Jiao, Justin Hesterberg, Gary Was (Univ of Michigan)

142Fundamental Understanding of Coupled Irradiation and Corrosion Effects on ZrNb Fuel Cladding

Adrien Couet, Zefeng Yu (Univ of Wisconsin, Madison), Lingfeng He, Mukesh Bachhav (INL)

143Effect of Thermal Aging on Static and Impact Fracture Properties of Cast Duplex Stainless Steels

T. S. Byun (ORNL), D. A. Collins, T. G. Lach (PNNL)

144Interdependent and Nonuniform Microstructural Evolution Pathways of Thermal Aging Degradation of Cast Austenitic Stainless Steels

Timothy G. Lach, William E. Frazier, Arun Devaraj, David A. Collins, Emily Barkley, Thak Sang Byun (PNNL)

145Degradation Resistance of FeCrAl Alloys in the Entire Nuclear Fuel Cycle

Raul B. Rebak (GE Global Research), invited

146Interface Reactions, Irradiation Response, and Mechanical Properties of FeCrAl-Coated Zircaloy-4

Miltiadis Kennas, Hyosim Kim (Texas A&M), Jonathan G. Gigax (Texas A&M/LANL), Benjamin R. Maier, Hwasung Yeom, Greg O. Johnson, Kumar Sridharan (Univ of Wisconsin, Madison), Lin Shao (Texas A&M)

147Creep Rupture Tests of FeCrAl Alloy for Accident Tolerant Fuel Cladding

P. Joshi (NCSU), M. N. Cinbiz, Boopathy Kombaiah (ORNL), K. L. Murty (NCSU)

148Simulation of the Homogenized Stress-Strain Relation for FeCrAl Alloys by Improved Crystal Plasticity Finite Element Method

Jingyu Zhang, Shurong Ding (Fudan Univ)

149Development of Advanced Low N 12Cr Ferritic/Martensitic Steel for Reactor Applications

C. J. Rietema, A. J. Clarke (CSM), T. A. Saleh (LANL), O. Anderoglu (Univ of New Mexico), B. Eftink (LANL), M. M. Hassan (Univ of New Mexico), K. D. Clarke (CSM)

150Development and Evaluation of Cold Spray Chromium Coatings for Accident-Tolerant Zirconium-Alloy Cladding

K. Sridharan, H. Yeom, B. Maier, G. Johnson, T. Dabney (Univ of Wisconsin, Madison), J. Walters, J. Romero, H. Shah, P. Xu (Westinghouse)

151Application of the Bison Fuel Performance Code to EBR-II Data

C. Matthews (LANL), S. Novascone, A. Casagranda (INL), C. Unal (LANL), invited

152Initial Efforts to Benchmark Bison for VTR Driver Fuel Analysis

J. J. Powers, J. Hu (ORNL), K. M. Cunningham (ORNL/Oak Ridge Inst for Science and Education), I. Greenquist (ORNL), S. L. Morrison (ORNL/Oak Ridge Inst for Science and Education), S. R. Novascone , A. Casagranda, D. C. Crawford (INL)

153Mesoscale Modeling and Experiments for Predicting the Thermal Conductivity of UZr Fuels

F. Badry, M. Gomaa Abdoelatef, Moiz Butt, Sean McDeavitt (Texas A&M), Mitch Meyer (INL), Karim Ahmed (Texas A&M)

154Recent Results of Microstructural Characterization of Neutron-Irradiated U-Mo Fuels Using Advanced Techniques

Dennis D. Keiser, Jr., Brandon Miller, Jian Gan, Fidelma Giulia Di Lemma, Mukesh Bachhav, Adam Robinson, James Madden (INL)

155Advanced Characterization Capabilities at INL

Jian Gan (INL)

156Hydrogen Corrosion of α-Uranium Observed by Transmission Electron Microscopy

Matthew T. Janish, Matthew M. Schneider, Edward F. Holby, Andrew W. Richards, Roland K. Schulze, Terry G. Holesinger (LANL)


WEDNESDAY, OCTOBER 9, 2019, 10:30 A.M.

157Development of Ultra High Temperature Ceramics for Extreme Environments and Their Potential for Nuclear Applications

Jeremy Watts (Missouri Univ Sci Tech), invited

158Microstructural Characterization of TRISO Particles in off-Normal Conditions

Katherine Montoya, Brian A. Brigham (Univ of Texas at San Antonio), Tyler J. Gerczak (ORNL), Elizabeth Sooby Wood (Univ of Texas at San Antonio)

159Results of a Machine Learning Model to Predict the Behavior of TRISO Particles Under High-Temperature Gas-Cooled Reactor Accident Conditions

M. D. Gaspar, K. I. Montoya, B. A. Brigham, A. S. Fernandez, E. S. Wood (Univ of Texas at San Antonio)

160Analysis of Matrix Burnoff in Off-Normal HTGR Conditions and the Impact on TRISO Particle Oxidation

Brian A. Brigham, Katherine I. Montoya (Univ of Texas at San Antonio), Tyler J. Gerczak (ORNL), Marielle D. Gaspar, Zachary Acosta, Elizabeth Sooby Wood (Univ of Texas at San Antonio)

161Microstructural Characterization of Metallic Fuel Alloys

Assel Aitkaliyeva, Jacob Hirschhorn, Michael Tonks (Univ of Florida), Cynthia Adkins (INL), invited

162Development and Sensitivity Analysis of a Quantitative Phase-Field Model for Non-Equilibrium U-Zr

Jacob Hirschhorn, Michael Tonks (Univ of Florida), Assel Aitkaliyeva, Cynthia Adkins (Univ of Florida/INL)

163Fuel Additives to Mitigate FCCI in Metallic Fuels

Michael T. Benson, Yi Xie, James A. King, Jason M. Harp, Lingfeng He (INL), Indrajit Charit, Samrat Choudhury (Univ of Idaho), Jinsuo Zhang (Virginia Tech)

164Fuel Cladding Chemical Interaction with Irradiated U-Zr-Ce Fuel with Fe Based Cladding Materials at High Temperatures

J.-S. Kim, J.-H. Kim, B.-O. Oon Lee, J.-S. Cheon (KAERI)


WEDNESDAY, OCTOBER 9, 2019, 1:30 P.M.

165The Size, Shape and Distribution of Intragranular Fission Product Bubbles in Spent Nuclear Fuel

M. J. D. Rushton (Bangor Univ), C. O. Galvin (Univ of New South Wales), M. W. D. Cooper (LANL), P. A. Burr (Univ of New South Wales), S. C. Middleburgh (Bangor Univ), R. W. Grimes (Imperial College), W. E. Lee (Bangor Univ/Imperial College), invited

166Identification of Chlorine-Containing Gases Generated by Hydrated PuO2/Salt Mixtures

Daniel Rios, Andrew J. Gaunt, Joshua E. Narlesky, John M. Berg, D. Kirk Veirs, Laura A. Worl (LANL), invited

167Ceramic Waste Form Design and Degradation: Mechanistic Understandings

Jie Lian (RPI)

168A Study for Zeolite Mixing Ratio and Strength Property of Cement Solidified Product Mixed with Zeolite

Atsushi Imabuchi, Kazuhito Niwase (Hachinohe College), Takeshi Yamamoto (CRIEPI)

169Evaluation of Microscopic Structure of Cement Solidification Mixed with Zeolite

Taisei Sakai, Kazuhito Niwase (Hachinohe College), Michio Kikuchi (CRIEPI)

170Cladding Development for Current and Advanced Reactor Applications: A Comparison of Thin-Walled Tubes for Three Variants of Oxide Dispersion Strengthened Alloys

Caleb P. Massey, David T. Hoelzer, Sebastien Dryepondt, Philip D. Edmondson (ORNL), Stuart A. Maloy (LANL), Maxim N. Gussev (ORNL), Anoop Kini, Baptiste Gault (Max-Planck-Institut für Eisenforschung GmbH), Kurt A. Terrani (ORNL), Steven J. Zinkle (ORNL/Univ of Tennessee, Knoxville)

171High Temperature Oxidation Behavior of CrAl Alloy Layer Coated Zr Fuel Cladding Using Arc Ion Plating

Dong Jun Park, Yang Il Jung, Jung Hwan Park, Byoung Kwon Choi, Young Ho Lee, Hyun Gil Kim (KAERI)

172Study of the Effect of the Zirconium Grain Structure on Hydride Precipitation Using Phase Field Modeling

P.-C. A. Simon, A. T. Motta (Penn State), M. R. Tonks (Univ of Florida)

173Radiation Effects on the Aqueous Compatibility of Coated and Uncoated SiC for Accident-Tolerant Fuel Cladding in Light Water Reactors

Peter Doyle (Univ of Tennessee, Knoxville/ORNL), Takaaki Koyanagi (ORNL), Caen K. Ang (Univ of Tennessee, Knoxville), Yutai Katoh (ORNL), Steven Zinkle (ORNL/Univ of Tennessee, Knoxville), David Carpenter (MIT), Stephen Raiman (ORNL)

174Coating Development for SiC/SiC Fuel Cladding to Prevent Fission Gas Release

Peter Mouche, Takaaki Koyanagi, Yutai Katoh (ORNL)

175Multi-Scale Modeling of Irradiated Grain Boundaries: Radiation-Induced Segregation and Corrosion

Izabela Szlufarska (Univ of Wisconsin, Madison), Xing Wang (ORNL), Hongliang Zhang, Cheng Liu, Jianqi Xi, (Univ of Wisconsin, Madison), invited

176Ab Initio Modeling of Radiation Effects in NiFeMnCr High Entropy Alloy

Congyi Li (Univ of Tennessee, Knoxville), Khorgolkhuu Odbadrakh (ORNL), Sai Mu (Univ of California, Santa Barbara), Phil Sterne (LLNL), Brian Wirth (Univ of Tennessee, Knoxville)

177Modeling Activation and Radionuclide Decay in Proton Irradiated Zirconium Alloys

Jesse J. Carter, Richard W. Smith (NNL)

178Helium and Damage Rate Dependence of Swelling in Simulated Ferritic Alloys Using a Hybrid Cluster Dynamics Model

Gerrit VanCoevering (Univ of Michigan), Brian D. Wirth (Univ of Tennessee, Knoxville), Gary S. Was (Univ of Michigan)

179Developing a Method to Quantify Radiation Damage Using Stored Energy: Simulations and Experiments

C. A. Hirst (MIT), P. Cao (Univ of California, Irvine), R. S. Kemp, M. P. Short (MIT)

180Ab Initio Thermodynamic and Kinetic Model of Hydrogen Segregation in Zirconium Grain Boundaries

W. Setyawan, C. H. Henager, Jr., D. J. Senor (PNNL)


THURSDAY, OCTOBER 10, 2019, 8:00 A.M.

181Fracture and Fatigue Behaviors of Pressure Vessel Steels and Austenitic Steels in Light Water Reactor Environments

Philippe Spätig, Hans-Peter Seifert, Zaiqing Que, Wen Chen (PSI), invited

182Characterization of RPV Materials Harvested from the Decommissioned Zion Unit 1 Nuclear Power Plant

M. A. Sokolov, T. M. Rosseel, P. D. Edmondson, X. Chen (ORNL), R. K. Nanstad (R&S Consultants, LLC)

183Irradiation Assisted Stress Corrosion Cracking in SA508-304 Weldment Under BWR/NWC Simulated Environment

Zhen Li (Univ of Illinois), Weicheng Zhong (ORNL), Gary S. Was (Univ of Michigan), Brent J. Heuser (Univ of Illinois)

184Experimental Study on Irradiation Embrittlement of 2 1/4 Cr-1 Mo Steel for Reactor Pressure Vessels

L. Sun, P. Joly, F. Roch (Framatome), C. Ritter, B. Tanguy, P. Wident, B. Marini (CEA), P. Todeschini, L. Pineau (EdF)

185Mechanical Properties of Thermally Aged and Ion Irradiated FeCr Alloys

Shradha Agarwal, Pengcheng Zhu, Yajie Zhao (Univ of Tennessee, Knoxville), Jean Henry (CEA), Steven J. Zinkle (Univ of Tennessee, Knoxville/ORNL)

186Comparison of Shear Punch and Tensile Testing of Neutron Irradiated FeCrAl

B. P. Eftink, T. J. Romero, M. E. Quintana, T. A. Saleh, S. A. Maloy (LANL)

187Qualification of Additive Manufactured Components—Integration of Modeling, Measurement and Manufacturing Processes

Sudarsanam Sureshy Babu (Univ of Tennessee. Knoxville/ORNL), invited

188Transforming Nuclear Core Manufacturing: Application of Advanced Manufacturing and Process Monitoring

Kurt Terrani, Ryan Dehoff, Kevin Field, Vincent Paquit, Andrew Nelson, William Peter (ORNL)

189A Road Map to Process Ferritic Martensitic Steels Using Additive Manufacturing

Niyanth Sridharan, Maxim Gussev, Xiang Chen, Kevin G. Field (ORNL)

190Recent Progress in Testing and Qualification of PM-HIP Nuclear Structural Alloys

Janelle P. Wharry, George Warren (Purdue Univ), Donna P. Guillen (INL), Lucille A. Giannuzzi (L. A. Giannuzzi & Associates), Elizabeth Getto (U.S. Naval Academy), Darren C. Pagan (Cornell High Energy Synchrotron Source), Yaqiao Wu (Boise State Univ/Center for Advanced Energy Studies), Paula D. Freyer (Westinghouse), David W. Gandy (EPRI)

191Wear Behavior of Additive Manufactured Stainless Steels 304L for Nuclear Applications

Junhyun Kwon, Jung-Min Kim, Hyung-Ha Jin (KAERI)

192Surface near Helium Damage in Materials Studied with a High Throughput Implantation Method

Peter Hosemann, M. Balooch, A. Scott, S. Stevenson, Y. Yang, F. Allen (Univ of California, Berkeley/LBNL)

193Atomistic Modeling of the Effect of He on Vacancy Clustering Energetics in Ni

E. K. Stirrup, B. D. Wirth (Univ of Tennessee, Knoxville)

194Density Functional Theory Studies of Effects of Oxygen on Grain Boundary Fracture in Nickel

Ziqi Xiao, Xian-Ming Bai (Virginia Tech)

195Rapid, Non-Destructive Detection of Microstructural Degradation in Light Water Reactor Structural Materials Using Transient Grating Spectroscopy

Saleem A. Aldajani, Benjamin R. Dacus, Cody A. Dennett (MIT), M. Grace Burke (Univ of Manchester), James J. Wall (EPRI), Michael P. Short (MIT)

196Elemental Nuclear Data Application Libraries for Materials Sciences

Jean-Christophe C. Sublet (IAEA), Mark R. Gilbert (United Kingdom Atomic Energy Authority)

197Material Informatics Approach for Composition Reconstruction in Irradiated Fe-Cr-Al Alloys

Y. Pachaury, C. Nuela Enebechi, G. Warren, Janelle P. Wharry, Anter El-Azab (Purdue Univ)


THURSDAY, OCTOBER 10, 2019, 10:30 A.M.

198Bridging the Length Scales on Mechanical Properties of Irradiated Materials

Peter Hosemann, H. Vo (Univ of California, Berkeley), A. Dong (LBNL), S. A. Maloy, L. Capolungo (LANL), A. Aitkaliyeva (Univ of Florida) invited

199Micro-Tensile Testing for Grain Boundary Fracture in Neutron-Irradiated Stainless Steels

T. Miura, K. Fujii, K. Fukuya (Inst of Nuclear Safety System, Inc.), Y. Kitsunai (Nippon Nuclear Fuel Development Co., Ltd)

200Mechanical Properties and Dislocation Dynamics in Irradiated FeCrAl Using In Situ TEM Tensile Tests

George Warren, Patrick Warren, Y. Pachaury, C. Nuela Enebechi (Purdue Univ), Jatuporn Burns, Megha Dubey, Yaqiao Wu (Boise State Univ/Center for Advanced Energy Studies), Kevin G. Field (ORNL), Anter El-Azab, Janelle P. Wharry (Purdue Univ)

201In-Situ X-Ray Diffraction and 4D X-Ray Microscopy Study of Tensile Deformation of Neutron-Irradiated Fe-9Cr Alloy

Xuan Zhang, Meimei Li, Jun-Sang Park, Peter Kenesei, Jonathan Almer (ANL), James F. Stubbins (Univ of Illinois)

202Development of Cladded and Alloy Systems for Short and Long Term Deployment of Molten Salt Reactors

Adrien Couet, Evan Buxton, William Doniger, Cody Falconer, Kumar Sridharan (Univ of Wisconsin, Madison), invited

203Comparison of Advanced and Conventional Austenitic Structural Alloys for Use in Molten Salts

George A. Young, Micah J. Hackett, Michael Hanson, Steven Huang, Pierre-Alexandre Juan, Henry Kim, Henry Korellis, Alan Kruizenga, Robert McReynolds, Augustus Merwin (Kairos Power), T.-L. Sham (ANL)

204Coating Down Selection for Fluoride-Cooled High-Temperature Reactor

Steven Huang, Micah Hackett, George Young, Henry Kim (Kairos Power LLC)

205Measurements and Modeling of Tritium Retention Mechanisms in Nuclear Graphite Irradiated in Molten Fluoride Salt

K. Dolan, G. Zheng, D. Carpenter (MIT), S. Huang (Kairos Power, LLC), L. W. Hu (MIT)

206Overview of Multiscale Fuels and Materials Modeling Within the U.S. DOE-NE NEAMS Program

C. R. Stanek (LANL), invited

207Modeling and Simulations of Irradiation-Induced Void Superlattices

Yipeng Gao, Yongfeng Zhang, Jian Gan (INL)

208Cluster Dynamics and Phase Field Model of Gas Bubble Evolution and Volumetric Swelling in Polycrystalline UMo Fuels

Shenyang Hu (PNNL), Benjamin W. Beeler (INL), Douglas E. Burkes (PNNL)

209Mesoscale Modeling of High Burn-Up Structure (HBS) Formation and Evolution in U-Mo Alloy

M. Gomma Abdoelatef, F. Badry, Karim Ahmed (Texas A&M), Andrea Jokisaari, Daniel Schwen, Yongfeng Zhang (INL)


THURSDAY, OCTOBER 10, 2019, 1:30 P.M.

210Radiation Effects on Mechanical Behavior of Zirconium Alloys: From Dislocations to Polycrystals

F. Onimus, L. Dupuy, Matthew Bono (CEA), F. Mompiou (CNRS), P. Pilvin (Univ. Bretagne Sud), invited

211A Molecular Dynamics Study of Irradiation Creep Deformation Mechanisms in α-Zirconium

Nargisse Khiara, Fabien Onimus, Laurent Dupuy, Jean-Paul Crocombette (CEA), Thomas Pardoen, Jean-Pierre Raskin (Université Catholique de Louvain), Yves Brechet (INPG) 

212Quantifying Radiation Embrittlement in Structural Materials

Steven J. Zinkle (Univ of Tennessee, Knoxville/ORNL)

213Quantification of Local Stress Fields in Crack Initiation in Irradiated Austenitic Stainless Steels

D. C. Johnson (Univ of Michigan), M. R. He, I. M. Robertson (Univ of Wisconsin, Madison), D. Farkas (Virginia Tech), G. S. Was (Univ of Michigan)

214Method for Extracting True Strain and Stress from TEM in Situ Compression Testing

H. Qu, K. H. Yano, P. Patki, J. P. Wharry (Purdue Univ)

215A New Method for TEM in Situ Tensile Testing of Ion Irradiated Alloys

Patrick Warren, George Warren, C. Nuela Enebechi (Purdue Univ), Jatuporn Burns, Megha Dubey (Boise State Univ/Center for Advanced Energy Studies), Janelle P. Wharry (Purdue Univ)

216Fabrication and Phase Analysis of U,3Si2 Alloyed with Cr, Nb, and Zr

G. Robles, C. Moczygemba (Univ of Texas at San Antonio), J. T. White (LANL), L. Cai, E. Lahoda (Westinghouse), E. Sooby-Wood (Univ of Texas at San Antonio)

217Development and Testing of Ultrafine-Grained and Nanocrystalline Steels for Enhanced Irradiation Tolerance

Haiming Wen, Andrew K. Hoffman (Missouri Univ Sci Tech), Rinat K. Islamgaliev (Ufa State Aviation Technical Univ)

218Corrosion of Refractory Metals and Advanced Steels in 700°C Stagnant and 250°C Flowing Lead-Bismuth Eutectic

S. A. Maloy, N. Rubio, K. A. Woloshun, E. Olivas (LANL), R. N. Wahlen, T. L. Grimm, M. Mamtimin,, F. Y. Odeh (Niowave, Inc.)

219An Advanced Metallic Composite for Use in Lead Fast Reactors

S. W. McAlpine, S. E. Ferry, M. P. Short (MIT)

220Qualifying Irradiated Structural Austenitic Stainless Steels for Kairos Power’s Fluoride-Salt-Cooled, High-Temperature Reactor

G. Meric de Bellefon, H. Kim, P.-A. Juan, G. Young, M. Hackett (Kairos Power LLC)

221Atomistic Modeling of Mixed Oxide Fuel Properties and Radiation Effects

Michel Freyss, Marjorie Bertolus, Emeric Bourasseau, Gérald Jomard, Martin Stéphane Talla Noutack, Ibrahim Cheik Njifon, Didier Bathellier (CEA)

222Investigating Defects in Actinides Oxides by Coupling Eectronic Structure Calculations and Positron Annihilation Lifetime Spectroscopy

Mamy Rivo Dianzinga, M. Bertolus, Gérald Jomard (CEA), M.-F. Barthe, (CNRS, CEMHTI), invited

223A Multi-Scale Microstructure Simulation Framework for Fission Gas Bubble Growth: Phase-Field and Cluster Dynamics Modeling

Dong-Uk Kim (Univ of Florida), Sophie Blondel, Brian Wirth (Univ of Tennessee, Knoxville), Michael Tonks (Univ of Florida)

2243D Comprehensive Effective Heat Conductivity Model of UO2

Bohyun Yoon, Heebaek Chang, Kunok Chang (Khung Hee Univ)

225Modeling Thermal-Mechanical Behavior of SiC-SiC Cladding in BWR Fuel Assemblies Using BISON

D. Schappel, G. Sing (Univ of Tennessee, Knoxville), Y. Katoh (ORNL), B. D. Wirth (Univ of Tennessee, Knoxville/ORNL)

226Simulating the Solid Chemical Composition of PWR Fuel CRUD

Jason Rizk, Brian Wirth (Univ of Tennessee, Knoxville)