Oral Program - elsevier.com · Armstrong, A.J. Wilkinson, University of Oxford, UK [O4.02]...
Transcript of Oral Program - elsevier.com · Armstrong, A.J. Wilkinson, University of Oxford, UK [O4.02]...
The 5th Nuclear Materials Conference 2018
Oral Program
Sunday 14th October 2018 17:00-18:00 Registration
Room: Emerald Foyer
Monday 15th October 2018 07:30-08:45 Registration
Room: Emerald Foyer
08:45-08:55 Welcome and Introductions | Room: Seattle 1-3
08:55-09:15 Welcome | Room: Seattle 1-3
09:15-09:30 Introduction | Room: Seattle 1-3
09:30-10:10
Robert Cahn Award Lecture |Room: Seattle 1-3
[L01]
Radioactive waste forms for the future
R.C. Ewing, Stanford University, USA
10:10-10:30 Coffee Break | Room: Emerald
10:30-11:10 Room: Seattle 1-3
[PS01]
New insights from advanced characterization of irradiated fuels
J. Bertsch*1, M. Martin1, M. Chollet1, D. Grolimund2, G. Kuri1, 1Nuclear Energy and Safety, Switzerland, 2Swiss Light Source, Switzerland
11:10-11:50 [PS02]
Behavior of accident tolerant fuel cladding materials during severe accidents
M.K. Grosse*, M. Steinbrück, J. Stuckert, C. Tang, Karlsruhe Institute of Technology, Germany
11:50-13:00 Lunch Break Room: Emerald
Room: Seattle 1 Room: Seattle 2 Room: Seattle 3 Room: Belltown Room: Pioneer Room: Capitol Hill
13:00-15:15 Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Session Chairs:
M.G. Burke, K. Field,
S. Kondo
Track 4- Modelling and
Simulation of Structural
Materials
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization
of Irradiated Materials and
Nuclear Fuels
Session Chairs: R.
Kennedy, J. Wharry
Track 3- Modelling and
Simulation of Nuclear
Fuels
Session Chair: G. Pastore
Track 5- Behavior of
Materials during Severe
Accidents and
Accident Tolerant Fuels
Session Chair: M. Kurata
Track 8- Materials for the
Nuclear Fuel Cycle
Session Chairs: C. Fazio,
S. Miro, K. Minato
13:00-13:25
[O2.01]
The transformational
challenge reactor
K.A. Terrani, Oak Ridge
National Laboratory,
USA
[O4.01]
Multi-scale simulation for
reduced activation
ferritic/martensitic steel
with dislocation based
constitutive model
W. Jeong1 ,3, Y.E. Na2, D.
Jang2, M.G. Lee*3, 1Korea
University, Republic of
Korea, 2KAIST, Republic of
Korea, 3Seoul National
University, Republic of
Korea
[O7.01]
Overview of the U.S.
Nuclear Science User
Facilities (NSUF)
J.R. Kennedy, Idaho
National Laboratory, USA
[O3.01]
UO2 fuel oxidation,
oxygen redistribution, and
fission gas release from
UO2+x
L-O. Jernkvist, A.R.
Massih*, Quantum
Technologies AB, Sweden
[O5.01]
Developing the test
conditions for the first
fuelled transients in the
TREAT reactor
D. Kamerman*, N.
Woolstenhulme, C. Jensen,
C. Davis, C. Folsom, D.
Wachs, Idaho National
Laboratory, USA
[O8.01]
Investigating hydrogen
segregation to secondary
phase particles in
Zircaloy-2 and Zircaloy-4
fuel cladding using
nanoscale secondary ion
mass spectroscopy
C. Jones*1, M. Preuss1, K.
Moore1 ,2, 1University of
Manchester, UK,
2University of Manchester,
UK, 3Wood plc, UK
The 5th Nuclear Materials Conference 2018
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Session Chairs: M.G.
Burke, K. Field, S.
Kondo
Track 4- Modelling and
Simulation of Structural
Materials
Session Chairs: B. Wirth, T.
Okita, M. Gilbert
Track 7- Characterization
of Irradiated Materials and
Nuclear Fuels
Session Chairs: R.
Kennedy, J. Wharry
Track 3- Modelling and
Simulation of Nuclear
Fuels
Session Chair: G. Pastore
Track 5- Behavior of
Materials during Severe
Accidents and
Accident Tolerant Fuels
Session Chair: M. Kurata
Track 8- Materials for the
Nuclear Fuel Cycle
Session Chairs: C. Fazio,
S. Miro, K. Minato
13:25-13:50 [O2.02]
Radiation resistant high
entropy alloys for fast
reactor cladding
applications
A. Kareer*, D.E.J.
Armstrong, A.J.
Wilkinson, University of
Oxford, UK
[O4.02]
Phosphorous effect on
vacancy-mediated
diffusion and ordering
kinetics in nickel alloys
J.H. Ke*, G. Young, J.
Tucker, Oregon State
University, USA
[O7.02]
The influence of post-
irradiation annealing on
the crack growth
resistance of Zr-2.5Nb
S. St Lawrence, Canadian
Nuclear Laboratories,
Canada
[O3.02]
Modeling volatile fission
products transport into the
germinal v2 fuel
performance code by
coupling to
thermochemical software
J-C. Dumas*1, M. Lainet1,
K. Samuelsson2, B.
Sundman3, 1CEA,
DEN/DEC/SESC, France,
2KTH, Sweden, 3INSTN,
France
[O5.02]
Fission products and
nuclear fuel behaviour
under severe accident
conditions: Speciation of
fission products in the
Verdon 3 and -4 samples
F. Audubert*, C. Le Gall, L.
Fayette, P. Bienvenu, I.
Zacharie-Aubrun, K. Hanifi,
Y. Pontillon, CEA, France
[O8.02]
Zirconium hydride
nucleation and growth
kinetics studied using
differential scanning
calorimetry and
synchrotron radiation
diffraction
E. Lacroix*, A.T.
Motta, Pennsylvania
State University, USA
13:50-14:15 [O2.03] Designing solute
stabilized nanocrystalline
tungsten alloys for fusion
applications
J.R. Trelewicz, Stony
Brook University, USA
[O4.03]
Simulation of irradiation-
induced grain boundary
phosphorus segregation
by first-principles-based
rate theory model
including trapping and
detrapping processes
K. Ebihara*, T. Suzudo, M.
Yamaguchi, Japan
Atomic Energy Agency,
Japan
[O7.03]
Microstructural
investigation of hydride
reorientation in zirconium
based spent nuclear fuel
cladding
T.S. Smith*1, S. Zinkle1, K.
Terrani2, 1The University of
Tennessee Knoxville, USA,
2Oak Ridge National
Laboratory, USA
[O3.03]
Modeling ATF with coated
cladding under accident
conditions using BISON
code
W. Liu*, A. Mai, J.
Rashid, Structural Integrity
Associates, Inc, USA
[O5.03]
Modelling of Cs
chemisorption behaviour
under LWR severe accident
S. Nishioka*1 ,2, K.
Nakajima1 ,2, E. Suzuki1, F.
Miradji1 ,2, M. Osaka1
,2, 1Japan Atomic Energy
Agency, Japan,
2International Research
Institute for Nuclear
Decommissioning, Japan
[O8.03]
Comparison of second
phase particles in
autoclave and neutron
irradiated Zr cladding
alloys
J. Hu*, S. Lozano-Perez, M.
Moody, C.
Grovenor, University of
Oxford, UK
14:15-14:40 [O2.04]
Pure vanadium
characterization for
fusion applications
B. Garcinuño*1 ,2, M.
Malo1, H. Liu3, I.
Fernández-Berceruelo1,
D. Rapisarda1, H. Zhou3,
G. Luo3, J.
Sanz2, 1CIEMAT, Spain,
2UNED, Spain, 3ASIPP,
China
[O4.04]
Ab initio study of point
defect interactions with
grain boundaries in fcc
nickel
E. Toijer*1, N. Sandberg1 ,2,
P. Olsson1, 1KTH Royal
Instiute of Technology,
Sweden, 2OECD-NEA
Boulogne Billancourt,
France
[O7.04]
The effect of transverse
and axial cold work on
irradiation creep of
Zircaloy-2 alloys at low
(330 K) temperature
X. Song*, W. Li, Canadian
Nuclear Laboratories,
Canada
[O3.04]
Validation of the pre-
transient metal fuel
performance models of
SAS4A A. Karahan, Argonne
National Laboratory, USA
[O5.04]
ATTILHA - A novel
experimental setup for
thermodynamic and
thermophysical properties
measurements on nuclear
materials
A. Quaini*, S. Gossé, C.
Guéneau, T. Alpettaz, E.
Lizon a Lugrin, C.
Bonnet, Université Paris-
Saclay, France
[O8.04]
Hydrogen migration in
duplex zirconium fuel
cladding quantified by
high-resolution neutron
imaging
W. Gong*1, P. Trtik1, L.
Duarte1, M. Mille1,2, J.
Bertsch1 1Paul Scherrer Institut,
Switzerland, 2EPF
Graduate School of
Engineering, France
The 5th Nuclear Materials Conference 2018
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors Session Chairs: M.G.
Burke, K. Field, S.
Kondo
Track 4- Modelling and
Simulation of Structural
Materials Session Chairs:
B. Wirth, T. Okita,
M. Gilbert
Track 7- Characterization
of Irradiated Materials and
Nuclear Fuels
Session Chairs:
R. Kennedy, J. Wharry
Track 3- Modelling and
Simulation of Nuclear
Fuels
Session Chair: G. Pastore
Track 5- Behavior of
Materials during Severe
Accidents and
Accident Tolerant Fuels
Session Chair: M. Kurata
Track 8- Materials for the
Nuclear Fuel Cycle
Session Chairs: C. Fazio,
S. Miro, K. Minato
14:40-15:15 [T2.INV01]
Structural materials
roadmap for the Fluoride-
Salt-Cooled High
Temperature Reactor
(FHR)
M. Hackett, Kairos
Power, LLC, USA
[T4.INV01]
Combined analysis of
first-principles
calculations and fracture
mechanics experiments
on intergranular
embrittlement of a Ni-Cr
steel
M. Yamaguchi, Japan
Atomic Energy Agency,
Japan
[T7.INV01]
Understanding
irradiation-induced
growth of Zr-based
fuel cladding through
advanced
characterisation
M. Preuss, University
of Manchester, UK
[T3.INV01]
Insight into the behaviour
of nuclear fuels through
investigations coupling
multi-scale modelling and
separate effects
experiments
G. Jomard*1, M-F. Barthe2,
R. Belin1, M. Bertolus1, E.
Bourasseau1, G. Carlot1, I.
Cheik Njifon1, M. Freyss1,
M. Gérardin1, S.
Maillard1, 1CEA/DEN,
France, 2CNRS/CEMHTI,
France
[T5.INV01]
Outline of a project for
core/plant status
evaluation of Fukushima-
Daiichi units 1 to 3 I. Sato*1 ,6, S. Mizokami1 ,6,
M. Kurata1 ,6, K. Okamoto1
,6, T. Yamashita1 ,6, T.
Honda2 ,6, K. Ito2 ,6, K.
Nozaki2 ,6, M. Pellegrini3, M.
Naito3, 1JAEA, Japan,
2TEPCO, Japan, 3IAE,
Japan, 4Toshiba ESS,
Japan, 5Hitachi-GE, Japan,
6IRID, Japan
[T8.INV01]
Process development of
ferritic steels for high dose
fast reactor applications
S.A. Maloy*1, E. Aydogan1,
B. Eftink1, T.A. Saleh1, T.J.
Lienert1, M. Toloczko2, T.S.
Byun2, C. Lavender2, G.R.
Odette3, M.E. Alam3, 1Los
Alamos National
Laboratory, USA, 2Pacific
Northwest National
Laboratory, USA,
3University of California,
Santa Barbara, USA, 4Oak
Ridge National
Laboratory, USA, 5CEA
Saclay, France
15:15-15:45 Coffee Break Room: Emerald
15:45-17:25 Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors Room: Seattle 1
Session Chairs: S. Kondo,
A. Kimura
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth, T.
Okita, M. Gilbert
Track 7- Characterization
of Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: R.
Kennedy, J. Wharry
Track 3- Modelling and Simulation of Nuclear Fuels
Room: Belltown
Session Chair: A. Prudil
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Room: Pioneer
Session Chair: I. Sato
Track 8- Materials for the
Nuclear Fuel Cycle
Room: Capitol Hill
Session Chairs: C. Fazio,
S. Miro, K. Minato
15:45-16:10 [O2.05]
Understanding neutron
irradiation performance
of dense γ-LiAlO2
D.J. Senor*, D.E.
Burkes, Pacific
Northwest National
Laboratory, USA
[T4.INV04]
Free energy landscape of
point defects in body-
centered-cubic metals
C.M. Marinica, Commissariat à l'énergie
atomique et aux énergies
alternatives , France
[O7.05]
Investigation on
(U,Pu)O2 fuel
microstructure by
Raman microscopy
L. Medyk1, P. Simon2, A.
Canizares2, D. Manara4,
R.J.M. Konings4, J-Y.
Colle4, C. Valot1, G.
Montagnac3, P.M.
Martin*1, 1CEA, France,
2CNRS Orléans, France,
3CNRS, ENS Lyon,
France, 4JRC-Karlsruhe,
[O3.05]
Developments in
engineering-scale
modelling of pore
migration in oxide fuels at
high temperature
S.R. Novascone*1, T.
Ozawa2, P.G. Medvedev1,
S. Hirooka2, 1Idaho
National Laboratory, USA,
2Japan Atomic Energy
Agency, Japan
[O5.05]
Thermophysical
property measurements
of molten stainless steel
containing 10mas%-B4C
by electromagnetic
levitation technique
H. Fukuyama*1, H.
Higashi1, H.
Yamano2, 1Tohoku
University, Japan,
2Japan Atomic Energy
Agency, Japan
[O8.05]
Fabrication and thermal
properties of sol-gel
derived enhanced UO2
ceramic fuel candidates
S.C. Finkeldei*, J.O.
Kiggans, R.D. Hunt, K.A.
Terrani, A.T. Nelson, Oak
Ridge National
Laboratory, USA
The 5th Nuclear Materials Conference 2018
Germany
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors Session Chairs: M.G.
Burke, K. Field, S.
Kondo
Track 4- Modelling and
Simulation of Structural
Materials Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization
of Irradiated Materials and
Nuclear Fuels
Session Chairs: R.
Kennedy, J. Wharry
Track 3- Modelling and
Simulation of Nuclear
Fuels Session Chair: G. Pastore
Track 5- Behavior of
Materials during Severe
Accidents and
Accident Tolerant Fuels
Session Chair: M. Kurata
Track 8- Materials for the
Nuclear Fuel Cycle
Session Chairs: C. Fazio,
S. Miro, K. Minato
16:10-16:35 [O2.06]
Investigation of
alumina coating as
tritium permeation
barrier for molten salt
nuclear reactors
G. Zheng*, D.
Carpenter, Massachus
etts Institute of
Technology, USA
[O4.05]
Modelling the effect of iodine at stress corrosion crack tips in zirconium using hybrid quantum mechanics/molecular dynamics simulations
V. Podgurschi*1, J.R. Kermode2, M.R. Wenman1, 1Imperial College London, UK, 2University of Warwick, UK
[O7.06]
Evaluation of radiation
damage of uranium-
molybdenum alloys
using extended X-ray
absorption fine structure
and synchrotron X-ray
diffraction
G. Park1, K. Bemis1, R.
Seibert2, D. Velazquez2,
J. Terry2, J. Wright3, D.
Sprouster4, M.
Elbakhshwan4, L. Ecker4,
M.
Okuniewski*1, 1Purdue
University, USA, 2Illinois
Institute of Technology,
USA, 3Argonne National
Laboratory, USA,
4Brookhaven National
Laboratory, USA
[O3.06]
Neutronic assessment of a
small-scale fuel irradiation
experiment in the High
Flux Isotope Reactor (HFIR)
J.R. Burns*, C.M. Petrie, R.
Morris, K.A. Terrani, Oak
Ridge National Laboratory,
USA
[O5.06]
Thermal and mechanical
properties of Fe2Zr: Main
component of the metallic
phase of fuel debris
D. Okada*1, H. Ishii1, Y.
Takamatsu1, Y. Ohishi1, H.
Muta1, K. Kurosaki1
,2, 1Osaka University,
Japan, 2University of Fukui,
Japan, 3JST, Japan
[O8.06]
Development of a high
temperature ultrasonic
viscometer for molten salt
S. Mastromarino*1 ,2, M.
Rohde1, O. Benes2, J.L.
Kloosterman1, 1Delft
University of Technology,
The Netherlands,
2European Commission,
Germany
16:35-17:00 [O2.07]
Static and impact
fracture characteristics
of cast austenitic
stainless steels after
long-term thermal aging
T.S. Byun*, D.A. Collins,
T.G. Lach, K.
Kruska, Pacific
Northwest National
Laboratory, USA
[O4.06]
Microstructural modeling of
concrete in LWR with
MOSAIC
J.D. Arregui-Mena*1,
A.B. Giorla1, G.E.
Jellison1, E. Tajuelo-
Rodriguez1, C.E.
Torrence2, Y. Le Pape1,
T.M. Rosseel1, 1Oak
Ridge National
Laboratory, USA,
2Texas A&M University,
USA
[O7.07]
Measurements of acoustic
phonons in irradiated UO2
epitaxial films
S. Rennie*1, E. Lawrence
Bright1, J.E. Darnbrough2 ,1,
L. Paolasini3, A. Bosak3,
G.H. Lander4, R.
Springell1, 1University of
Bristol, UK, 2University of
Oxford, UK, 3ESRF, France,
4European Commission,
Joint Research Centre,
Germany
[O3.07]
Mechanical property
evolution with radiation
damage in (U,Pu)O2: A MD
simulation study
L. Van Brutzel*1, H. Balboa-
Lopez1, A. Chartier1, Y. Le
Bouar2, 1CEA, France,
2CNRS, France
[O5.07]
Modeling high-
temperature corrosion of
zirconium alloys fuel
cladding using XFEM with
BISON
L. Borrel1, W. Jiang2, B.W.
Spencer2, K. Shirvan3, A.
Couet*1, 1University of
Wisconsin-Madison, USA,
2Idaho National
Laboratory, USA,
3Massachusetts Institute of
Technology, USA
[O8.07]
Impact of lanthanide
elements on the
dissolution of uranium
dioxide
T. Cordara1, L.
Claparede1, S. Szenknect1,
A. Mesbah1, C. Lavalette2,
R. Podor1, N.
Dacheux*1, 1University
Montpellier, France,
2AREVA NC, France
17:00-17:25 [O2.08]
Co-dependent
microstructural
evolution pathways in
ferrite and at ferrite-
austenite phase
boundary in cast
[O7.08]
Synergetic effect of ballistic
damage and electronic
excitations in uranium
dioxide investigated by in-
situ Raman spectroscopy
G. Gutierrez*1, M. Bricout1, C.
17:15-
17:50 [T3.INV02]
Multiscale
modeling of fission
gas bubble
evolution in UO2
under nominal
operating
17:15-
17:50 [T5.INV02]
A modern
methodology for
fuel safety
research
D. Wachs*, C.
Jensen, N.
[O8.08]
Layered double
hydroxides synthesis and
application for radioactive
iodine removal
W. Um*, J. Kang, Pohang
University of Science and
The 5th Nuclear Materials Conference 2018
Tuesday 16th October 2018
08:30-09:10 Room: Seattle 1-3
[PS03]
Challenges in predicting irradiated nuclear fuel thermodynamics
C. Guéneau, Commissariat à l'énergie atomique et aux énergies alternatives, France
09:10-09:50 [PS04]
Improving atomic displacement calculations with physically realistic damage models: arc-dpa and rpa
K. Nordlund, University of Helsinki, Finland
09:50-10:20 Coffee Break Room: Emerald
Room: Seattle 1 Room: Seattle 2 Room: Seattle 3 Room: Belltown Room: Pioneer Room: Capitol Hill
10:20-12:25 Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Session Chairs: M.G.
Burke, M. Hackett
Track 4- Modelling and
Simulation of Structural
Materials
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization
of Irradiated Materials and
Nuclear Fuels
Session Chairs: F. Cappia,
T. Wiss,
Track 3- Modelling and
Simulation of Nuclear Fuels
Session Chair: A. Prudil
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Session Chair: A. Nelson
Track 8- Materials for the
Nuclear Fuel Cycle
Session Chairs:
C. Fazio, S. Miro, K.
Minato
10:20-10:45 [O2.09]
Thermogravimetric
oxidation analysis of
carbon tokamak
dust and flakes
U. Shahid1, B.W.N.
Fitzpatrick*1, J.W.
Davis2, M.H.A.
Piro1, 1University of
Ontario Institute of
Technology,
Canada, 2University
of Toronto, Canada
[O4.07]
A microstructure dependent
rate theory for predicting
defect evolution in
irradiated polycrystalline
LiAlO2
S.Y. Hu*, Y.L. Li, D.E. Burkes,
D.J. Senor, Pacific
Northwest National
Laboratory, USA
[O7.09]
Recent observations from
the microstructural
characterization of
irradiated U-Mo fuels
using advanced
techniques
D. Keiser*, B. Miller, J.
Gan, L. He, D. Jadernas,
M. Bachhav, A. Robinson,
J. Madden, Idaho
National Laboratory, USA
[O3.08]
Evaluation of explicit
fracture models on the
performance of FeCrAl and
Zircaloy cladding using the
BISON fuel performance
code
R.T. Sweet*1, Y.R. Rashid2,
B.D. Wirth1, 1University of
Tennessee, USA, 2Structural
Integrity Associates Inc.,
USA
[O5.08]
Accident tolerant FeCrAl-
ODS ferritic steels in Japan:
High temperature steam
oxidation and creep rupture
strength
S. Ukai*1, T. Sowa1, S.M.S.
Aghamiri1, N. Sugawara1, S.
Zhang1, N. Oono1, S.
Hayashi1, K. Sakamoto2, T.
Furukawa3, 1Hokkaido
University, Japan, 2Nippon
Nuclear fuel Development
[O8.09]
Effect of platinoid
elements on the
dissolution of uranium
dioxide
T. Cordara1, S.
Szenknect1, L.
Claparede1, A. Mesbah1,
C. Lavalette2, R. Podor1,
N. Dacheux*1, 1University
Montpellier, France,
2AREVA NC, France
austenitic stainless
steels during thermal
aging
T.G. Lach*, A. Devaraj,
T.S. Byun, Pacific
Northwest National
Laboratory, USA
Onofri1, F. Lepretre1, R. Belin1,
L. Thomé2, A. Debelle1 ,2, F.
Garrido2, 1CEA, France,
2Centre de Sciences
Nucléaires et de Sciences
de la Matière, France
conditions
B.D. Wirth*1 ,2, A.D.
Andersson3, S.
Blondel1, G.
Pastore4, R.J. Kurtz5,
W.
Setyawan5, 1Univer
sity of Tennessee,
USA, 2Oak Ridge
National
Laboratory, USA,
3Los Alamos
National
Laboratory, USA,
4Idaho National
Laboratory, USA,
5Pacific Northwest
National
Laboratory, USA
Woolstenhulme, I
daho National
Laboratory, USA
Technology (POSTECH),
Republic of Korea
17:25-19:10 Poster Session 1 & Drinks Reception
The 5th Nuclear Materials Conference 2018
Co. Ltd., Japan, 3Japan
Atomic Energy Agency,
Japan
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Session Chairs: M.G.
Burke, M. Hackett
Track 4- Modelling and
Simulation of Structural
Materials
Session Chairs: B. Wirth, T.
Okita, M. Gilbert
Track 7- Characterization
of Irradiated Materials and
Nuclear Fuels
Session Chairs: F. Cappia,
T. Wiss
Track 3- Modelling and
Simulation of Nuclear Fuels
Session Chair:
A. Prudil
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Session Chair: A. Nelson
Track 8- Materials for the
Nuclear Fuel Cycle
Session Chairs:
C. Fazio, S. Miro, K.
Minato
10:45-11:10 [O2.10]
Corrosion of
structural materials
in molten chloride
salts
S.S. Raiman*1, J.W.
McMurray1, R.T.
Mayes1, J.M. Kurley1,
J. Moon2 ,1, 1Oak
Ridge National
Laboratory, USA,
2University of
California, USA
[O4.08]
Effect of
trapping/detrapping SIA
clusters by impurities on
damage accumulation in
neutron irradiated tungsten:
Comparison of 14 MeV-
neutron and High-Flux
Isotope Reactor (HFIR) PKA
spectra
G. Nandipati*1, W.
Setyawan1, K.J. Roche1 ,3,
R.J. Kurtz1, B.D.
Wirth2, 1Pacific Northwest
National Laboratory, USA,
2University of Tennessee,
USA, 3University of
Washington, USA
[O7.10]
Examination of UO2
surface oxidation using
atomic-scale electron
energy loss spectroscopy
S.R. Spurgeon*1, M. Sassi1,
J. Stubbs2, E. Ilton1, E.
Buck1, 1Pacific Northwest
National Laboratory, USA,
2University of Chicago,
USA
[O3.09]
Modelling the effect of
fracture strength on pellet
fracture patterns in
peridynamics
L. Jones*, T.A. Haynes, M.R.
Wenman, Imperial College
London, UK
[O5.09]
Oxidation behaviour of
alumina-forming duplex
stainless steels in high
temperature steam
environments
H. Kim*, C. Kim, C.
Jang, Korea Advanced
Institute of Science and
Technology, Republic of
Korea
[O8.10]
Sequestration of
radionuclides in metal-
organic frameworks from
first principles
calculations
S. Pendey1, Z. Jia1, B.
Demaske1, N. Shustova2,
E. Dolgopolova2, W.
Setyawan3, C.H.
Henager3, S.R.
Phillpot*1, 1University of
Florida, USA, 2University of
South Carolina, USA,
3Pacific Northwest
National Laboratory, USA
11:10-11:35 [O2.11]
A combined
corrosion/irradiation in
situ material testing
facility for molten salt
reactor materials
W. Zhou*, M.P.
Short, Massachusetts
Institute of Technology,
USA
[O4.09]
Interactions between
transmutation Re and
irradiation defects in W bulk
by molecular dynamics
simulations based on new W-
Re potentials
Y.C. Chen*1, H.Q. Deng1, J.
Fu1, L.X. Liu1, W.Y. Hu1, F. Gao1
,2, 1Hunan University, China,
2University of Michigan, USA
[O7.11]
Preliminary
postirradiation
examination of several
EBR-II metallic fuel
pins
L.C. Capriotti*, J.H.
Harp, D.W. Wachs, S.H.
Hayes, Idaho National
Laboratory, USA
[O3.10]
Predicting the
behaviour of
complex grain
boundaries in
zirconia to
understand cladding
corrosion and PCI
M.J.D. Rushton*1,
W.E. Lee1 ,2, S.C.
Middleburgh1, 1Ban
gor University, UK,
2Imperial College
London, UK
[O5.10]
Tritium permeation through
oxide film of FeCrAl-ODS
ferritic steel
K. Sakamoto*1, Y. Urabe2, K.
Hashizume2, S.
Yamashita3, 1NFD, Japan,
2Kyushu University, Japan,
3JAEA, Japan
[O8.11]
Recent structural
investigations of zirconium-
plutonium molybdate
precipitation and its
inhibition during the
dissolution step of the spent
nuclear fuels treatment
S. Costenoble*1, M.
Nadolny2, N. Henry3, T.
Dumas1, C. Lavalette2, M.
Rivenet3, S.
Grandjean1, 1CEA, France,
2Orano Group, France,
3UCCS, France
11:35-12:00 [O2.12]
Corrosion of Hastelloy-n
in molten FLiNaK salt at
700°C
C. Falconer*1, W.H.
Doniger1, R. Scarlat1, L.
Shao2, K. Sridharan1, A.
Couet1, 1University of
[O4.10]
First-principle study of H in
Fe/W interface
J.M. Shi*, N.
Hashimoto, Hokkaido
University, Japan
[O7.12]
Postirradiation examination
of recently irradiated
metallic fuel concepts
J.M. Harp*, L. Capriotti, F.
Cappia, Idaho National
Laboratory, USA
[O3.11]
Simulation of historical
experiments related to
hydrogen migration and
redistribution in Bison
Z. Aly*1, G. Pastore2, N.
Brown1, A.
Casagranda2, 1Pennsylvania
[O5.11]
The solubility of hydrogen in
U3Si2 accident tolerant fuel
candidate - impact on fuel
manufacturing and
operation
S.C. Middleburgh*1 ,2, A.
Claisse2, D.A. Andersson3,
[O8.12]
Iron XANES analysis of
irradiated Zircaloy-4 oxide
layers formed at different
neutron flux levels and
corrosion temperatures
B. Ensor*1, J.R.
The 5th Nuclear Materials Conference 2018
Wisconsin-Madison, USA,
2Texas A&M University,
USA
State University, USA, 2Idaho
National Laboratory, USA
R.W. Grimes4, P. Olsson5, S.
Mašková6, 1Bangor
University, UK,
2Westinghouse Electric
Sweden AB, Sweden, 3Los
Alamos National
Laboratory, USA, 4Imperial
College London, UK, 5KTH,
Sweden, 6Charles University,
Czech Republic
Seidensticker1, A.T.
Motta2, 1Naval Nuclear
Laboratory, USA, 2The
Pennsylvania State
University, USA
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors Session Chairs: M.G.
Burke, M. Hackett
Track 4- Modelling and
Simulation of Structural
Materials
Session Chair: B. Wirth, T.
Okita, M. Gilbert
Track 7- Characterization
of Irradiated Materials and
Nuclear Fuels Session Chair: F. Cappia, T.
Wiss
Track 3- Modelling and
Simulation of Nuclear Fuels
Session Chair:
A. Prudil
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Session Chair: A. Nelson
Track 8- Materials for the
Nuclear Fuel Cycle
Session Chair: C. Fazio,
S. Miro, K. Minato
12:00-12:25 [O2.13]
Corrosion behavior of Ni-
based alloy in molten
FLiNaK salt as a
fundamental research
on molten salt reactors
K. Ogasawara*1, Y.
Sekiguchi1, T. Terai1, H.
Kawamura2, K. Tsuchiya3,
T.Watanabe4, 1University of Tokyo,
Japan, 2Chiyoda
Technol Corp., Japan,
3Japan Atomic Energy
Agency, Japan, 4ational
Institute for Fusion
Science, Japan
[O4.11]
Modeling ductile-phase
toughened tungsten for
plasma-facing materials by
a multiscale microstructural
approach
B.N. Nguyen*, C.H. Henager,
Jr., R.J. Kurtz, Pacific
Northwest National
Laboratory, USA
[O7.13]
Microstructural evolution
and phase
transformations in U-10Mo
alloys with varying Zr
content after heat
treatments relevant to the
monolithic fuel plate
fabrication process
A. Mehta1, N. Eriksson1, R.
Newell1, L. Zhou1, E. Schulz1,
W. Sprowes1, F. Betancor1,
Y.J. Park1, D.D. Keiser, Jr.*2,
Y.H. Sohn1, 1University of
Central Florida, USA, 2Idaho
National Laboratory, USA
[O3.12]
Grand potential modeling
of nanoscale zirconium
hydride precipitates in a
zirconium matrix
P-C. Simon*1, A.T. Motta1,
M.R. Tonks2, 1The
Pennsylvania State
University, USA, 2University of
Florida, USA
[O5.12]
Thermophysical properties,
microstructure, and
oxidation behavior of UN-
UO2 composites
N.R. Wozniak*1, J.T. White1,
A.T. Nelson1 ,2, 1Los Alamos
National Laboratory, USA,
2Oak Ridge National
Laboratory, USA
12:00-
12:35
[T8.INV02]
In situ Raman
spectroscopy on
nuclear materials in
hot cell
S. Miro*1, S.
Peuget1, M. Tupin2,
L. Fayette3, A.
Nakayoshi4, C.
Jégou1, 1CEA, DEN,
DE2D, France,
2CEA, DEN, DMN,
France, 3CEA, DEN,
DEC, France,
4Atomic energy
Agency (JAEA),
France
12:25-13:25 Lunch Break | Room: Emerald
13:25-15:15 Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1 Session Chair: M. Sokolov
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: K. Field,
A. Leenaers
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chairs: M. Lang,
L. Walters, K. Arakawa
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Room: Pioneer
Session Chair: M. Steinbrück
Track 1- Thermodynamics
and Thermal Properties of
Nuclear Fuels Room: Capitol Hill
Session Chair:
T.M. Besmann
13:25-13:50 [O2.14]
Microstructure evolution
and radiation hardening
of proton-irradiated
reactor pressure vessel
steels
H-H. Jin*1, E. Ko1 ,2, S.
Lim1, M-C. Kim1, J.
Kwon1, G-G.
[O4.12]
The formation and structure
of Fe-Mn-Ni-Si solute
clusters and G-phase
precipitates in steels
D.J.M. King*1, P.A. Burr2, S.C.
Middleburgh3 ,5, T.M.
Whiting1, M.G. Burke4, M.R.
Wenman1, 1Imperial
[O7.14]
Determining enrichment
and distribution of
uranium isotopes in
metallic nuclear fuel with
atom probe tomography
E. Kautz*, A. Devaraj, V.
Joshi, D. Burkes, C.
Lavender, Pacific
[O6.01]
Atomic-scale observation
of antisite defects and the
formation of solid solutions
in Mn+1AXn phases
C. Wang*1 ,2, T. Yang2, C.L.
Tracy1, 1Stanford University,
USA, 2Peking University,
China, 3University of
[O5.13]
Analytical development
of oxidation models for new
perspective types of
accident tolerant fuel
claddings
A.D. Vasiliev, Nuclear
Safety Institute, Russia
[O1.01]
Low temperature thermal
conductivity of ThxU1-xO2
oxides
J-C. Griveau*, O. Valu, K.
Popa, European
Commission, Germany
The 5th Nuclear Materials Conference 2018
Lee1, 1Korea Atomic
Energy Research
Institute, Republic of
Korea, 2KEPCO,
Republic of Korea
College London, UK,
2University of New South
Wales, Australia,
3Westinghouse Electric
Sweden, Sweden, 4The
University of Manchester,
UK, 5Bangor University, UK
Northwest National
Laboratory, USA
Michigan, USA, 4Monash
University, Australia,
5Chinese Academy of
Sciences, China
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1 Session Chair: M. Sokolov
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chair: B. Wirth, T.
Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chair: K. Field, A.
Leenaers
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chair: M. Lang, L.
Walters, K. Arakawa
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Room: Pioneer
Session Chair: M. Steinbrück
Track 1- Thermodynamics
and Thermal Properties of
Nuclear Fuels Room: Capitol Hill
Session Chair: T.M. Besmann
13:50-14:15 [O2.15]
Investigation of
susceptibility of A533B
steel to temper
embrittlement
M.A. Sokolov*1, B.A.
Gurovich2, E.A.
Kuleshova2, Z.V. Bukina2,
A.S. Frolov2, D.A.
Maltsev2, S.V.
Fedotova1, 1Oak Ridge
National Laboratory,
USA, 2NRC “Kurchatov
Institute”, Russia
[O4.13]
Density functional theory
simulations of solute triplets
in reactor pressure vessel
steels
T.M. Whiting*1, D.J.M. King1,
P.A. Burr2, M.R.
Wenman1, 1Imperial
College London, UK,
2University of New South
Wales, Australia
[O7.15]
Investigation of grain
boundary segregation by a
correlative EBSD/TKD/APT
methodology for a 16MND5
weld metal
L. Zhang1, B. Radiguet1, C.
Domain2, Y. Shen3, P.
Todeschini2, P.
Pareige*1, 1Normandie
University, France, 2EDF Lab,
France, 3EDF DIPNN, France
[O6.02]
Effects of electronic energy
loss on the production and
evolution of radiation
damage in nuclear
ceramics
W.J. Weber*1 ,2, E.
Zarkadoula2, Y.
Zhang2, 1University of
Tennessee, USA, 2Oak Ridge
National Laboratory, USA
[O5.14]
Fabrication,
characterisation and testing
of Cr coated Zr alloy
cladding for enhanced
accident tolerance
D.T. Goddard1, A. Evans*2,
P. Kelly2, G. Obasi3, M.
Preuss3, A. Cole-Baker4, E.P.
Vernon1, 1National Nuclear
Laboratory, UK, 2Manchester
Metropolitan University, UK,
3University of Manchester,
UK, 4Wood plc, UK
[O1.02]
Effect of off-stoichiometry and
grain size on thermal
transport in uranium dioxide
K. Gofryk,
Idaho National Laboratory,
USA
14:15-14:40
[O2.16]
Correlation between
master curve testing and
Charpy impact test
results of long term
thermally aged VVER-
440 RPV surveillance
specimens
M. Kolluri*1, H. Nolles1,
F.J. Frith1, Z. Szaraz2, O.
Martin2, P. Hähner2, V.
Petrosyan3, A.
Petrosyan3, G.
Sevikyan4, 1Nuclear
Research & consultancy
Group (NRG), The
Netherlands, 2European
Commission, The
Netherlands,
3ARMATOM, Armenia,
4ANPP, Armenia
[O4.14]
Entropy contributions to
phase stability in binary
random solid solutions
A. Manzoor*1, S.
Pandey2, D.
Chakraborty1, S.
Phillpot2, D.
Aidhy1, 1University of
Wyoming, USA,
2University of Florida, USA
[O7.16]
Post-irradiation examination
of metallic components
from tritium producing
burnable absorber rods
using atomic-scale
scanning transmission
electron microscopy
E.C. Buck*, P.J. MacFarlan,
D.D. Reilly, G.J.
Sevigny, Pacific Northwest
National Laboratory, USA
[O6.03]
Radiation-induced volume
swelling and microcracking
in glass ceramic and
crystalline ceramic nuclear
waste forms
M. Tang
Los Alamos National
Laboratory, USA
[O5.15]
Experimental Behavior of
Chromium Based Coatings
for Nuclear Reactor Fuel
J. Krejci*1 ,2, M. Sevecek2, L.
Cvrcek3, P. Sutta4, P.
Bublikova5, J. Kabatova1, J.
Malek1 ,3, S. Krum3, P.
Halodova5, H.K.
Namburi5, 1UJP PRAHA a.s.,
Czech Republic, 2CTU in
Prague, Faculty of Nuclear
Sciences and Physical
Engineering, Czech
Republic, 3CTU in Prague,
Faculty of Mechanical
Engineering, Czech
Republic, 4University of West
Bohemia, New Technologies
– Research Centre, Czech
Republic, 5Research Centre
Řež, Czech Republic
[O1.03]
Experimental and
computational determination
of U-Si-N phase behavior for
application in advanced
fuels
D.A. Lopes*1, T.L. Wilson1, V.
Kocevski1, T.M. Besmann1, J.T.
White2, A. Claisse3, 1University
of South Carolina, USA, 2Los
Alamos National Laboratory,
USA, 3Westinghouse Electric
Co, Sweden
The 5th Nuclear Materials Conference 2018
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1 Session Chair: M. Sokolov
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: K. Field,
A. Leenaers
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chairs: M. Lang,
L. Walters, K. Arakawa
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Room: Pioneer
Session Chair: A. Evans
Track 1- Thermodynamics
and Thermal Properties of
Nuclear Fuels Room: Capitol Hill
Session Chair:
T.M. Besmann
14:40-15:15 [T2.INV02]
Insights into the
mechanisms of
irradiation assisted stress
corrosion cracking G.S. Was*1, D. Johnson1, M-R. He2, I. Robertson2, 1University of Michigan, USA, 2University of Wisconsin, USA
[T4.INV02] Prediction of nuclear materials behavior for reactors life-span extension: Towards a multi-scale approach dedicated to microstructure and mechanical properties of irradiated materials C. Gallé*, L. Dupuy, T. Jourdan, L. Gélébart, CEA, France
[T7.INV02]
Nanoscale
characterization of
novel fuel claddings
using complementary
SANS-APT-STEM
techniques
K.G. Field*1, D. Zhang1,
S.A. Briggs2, C.P.
Massey3, K.C.
Littrell1, 1Oak Ridge
National Laboratory,
USA, 2Sandia National
Laboratories, USA,
3University of Tennessee,
USA
[T6.INV01]
Radiation damage in
oxide systems for nuclear
materials: A short review
G.R. Lumpkin*, R.D.
Aughterson, M. de los
Reyes, M.J. Qin, S.C.
Middleburgh, Z.
Zhang, Australian Nuclear
Science and Technology
Organisation, Australia
[T5.INV03]
Framatome's enhanced
accident tolerant fuel
developments: Focus on
chromium-coated claddings
N. Chaari*1, J. Bischoff1, P.
Barberis1, C. Delafoy1, F.
Bourlier1, K.
Nimishakavi2, 1Framatome,
France, 2Framatome Inc., USA
[T1.INV01]
Thermochemistry of the
uranium silicide system
A.T. Nelson*1, J.W. White2,
E.S. Wood3, 1Oak Ridge
National Laboratory, USA,
2Los Alamos National
Laboratory, USA, 3University
of Texas at San Antonio,
USA
15:15-15:45 Coffee Break | Room: Emerald
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1 Session Chair:
M. Sokolov
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: K. Field,
A. Leenaers
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chairs: M. Lang,
L. Walters, K. Arakawa
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Room: Pioneer
Session Chair: A. Evans
Track 1- Thermodynamics
and Thermal Properties of
Nuclear Fuels Room: Capitol Hill
Session Chair:
T.M. Besmann
15:45-16:10 [O2.17]
Microstructural
evolution in proton-
irradiated A508 Gr4N
forging steel
A. Carruthers1, M.G.
Burke*1, J. Hyde2, S.
Dumbill2, 1University of
Manchester, UK,
2National Nuclear
Laboratory, UK
[O4.15]
A new insight into void
swelling near grain
boundary from phase-
field simulations
Y.Y. Wang*1, J.H. Ding1,
J.J. Zhao1, Y.Z.
Wang2, 1Dalian University
of Technology, China,
2The Ohio State University,
USA
[O7.17]
Real-time property
monitoring during ion beam
irradiation using transient
grating spectroscopy
C.A. Dennett*1, K. Hattar2,
M.P. Short1, 1Massachusetts
Institute of Technology, USA,
2Sandia National
Laboratories, USA
[O6.04]
Simulations show how
lattice strain evolution in
irradiated materials is
driven by changes in
defect configuration
J-P. Crocombette*1,
A. Debelle2 ,1, A.
Boulle3, A.
Chartier1, 1Universit
é Paris-Saclay,
France, 2Université
Paris-Sud, France,
3SPCTS, France
[O5.16]
Chromium hardening and
Zr-Cr interface stability of
irradiated chromium-
coated Zircaloy-4 alloy
J. Ribis*1, A. Wu1, J.C.
Brachet1, E. Clouet1, B.
Arnal1, E. Rouesne1, S.
Urvoy1, F. Barcelo1, A.
Gentils2, C. Baumier2, 1CEA,
France, 2Université Paris Sud,
France, 3Framatome,
France, 4EDF, France
[O1.04]
Evidence of the negative
thermal expansion of the
UO2.00 fluorite local structure
P.M. Martin*1, D. Prieur2 ,3, E.
Epifano1, K. Dardenne4, J.
Rothe4, C. Hennig2 ,3, A.C.
Scheinost2 ,3, D.
Neuville5, 1CEA Marcoule,
France, 2Helmholtz-Zentrum
Dresden-Rossendorf,
Germany, 3European
Synchrotron Radiation
Facility, France, 4Karlsruhe
Institute of Technology,
Germany, 5Institut de
The 5th Nuclear Materials Conference 2018
Physique du Globe de Paris-
CNRS, France
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1
Session Chair: M. Sokolov
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: K. Field,
A. Leenaers
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chairs: M. Lang,
L. Walters, K. Arakawa
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Room: Pioneer
Session Chair: A. Evans
Track 1- Thermodynamics
and Thermal Properties of
Nuclear Fuels Room: Capitol Hill
Session Chair:
T.M. Besmann
16:10-16:35 [O2.18]
Positron annihilation spectroscopy studies on ferritic/martensitic steels exposed to different radiation environments
V. Krsjak*1, Y. Dai2, J.
Degmova1, V.
Slugen1, 1Slovak
University of Technology,
Slovakia, 2Paul Scherrer
Institut, Switzerland
[O4.16]
Modeling of hardening in spinodally-decomposed Fe-Cr binary alloys
T. Suzudo*1, H. Takamizawa1,
Y. Nishiyama1, A. Caro2, T.
Toyama3, Y. Nagai3, 1Japan
Atomic Energy Agency,
Japan, 2George Washington
University, USA, 3Tohoku
University, Japan
[O7.18]
Fracture properties
characterization of nuclear
fuel using micro-cantilever
bending
R. Henry*1, T. Blay2, I.
Zacharie-Aubrun2, J-M.
Gatt2, C. Langlois1, S.
Meille1, 1INSA-Lyon, France,
2CEA Cadarache, France
[O6.05]
Atomistic modeling of
defects and diffusion in
tritium-producing burnable
absorber rod pellets
W. Setyawan, G.
Nandipati, D.J. Senor, R.
Devanathan*, Pacific
Northwest National
Laboratory, USA
[O5.17]
Development of cold
spray coatings for
accident tolerant fuel
cladding
B.R. Maier*1, H. Yeom1,
G.O. Johnson1, T.
Dabney1, J. Walters2, H.
Shah2, J. Romero2, K.
Sridharan1, 1University of
Wisconsin-Madison, USA,
2Westinghouse Electric
Company, USA
[O1.05]
Modelling the Nuclear Fuel
- Cladding interaction and
Fission Products behaviour
during a simulated Severe
Accident (VERDON-1 test)
with the TAF-ID
E. Geiger*1, Y. Pontillon2, M.
Piro1, C. Guéneau3, E.
Corcoran4, 1University of
Ontario Institute of
Technology, Canada,
2Commissariat à l’Energie
Atomique et aux Energies
Alternatives, France,
3Université Paris-Saclay,
France, 4Royal Military
College of Canada,
Canada
16:35-17:00 [O2.19]
Microstructural and
micromechanical
characterization of
laser weld repairs on
neutron irradiated 304
stainless steel
K. Mao*1 ,2, L.A.
Giannuzzi3, P.D. Freyer4,
C. Sun1 ,2, J.P. Wharry1,
F.A. Garner5, 1Purdue
University, USA, 2Idaho
National Laboratory,
USA, 3L.A. Giannuzzi &
Associates LLC, USA,
4Westinghouse Electric
Company LLC, USA,
5Texas A&M University,
USA
[O4.17]
Phase-field model simulation
of spinodal decomposition in
Fe-Cr-X ternary alloys
G. Obulan Subramanian*, B.
Kong, C. Jang, Korea
Advanced Institute of
Science and Technology,
Republic of Korea
[O7.19]
Advanced EBSD-and STEM-
based methodologies for
studying nuclear materials
C.M. Parish*1, K. Wang1, A.
Bhattacharya1, P.D.
Edmondson1, R. Doerner2,
M. Baldwin2, Y.
Katoh1, 1Oak Ridge
National Laboratory, USA,
2University of California San
Diego, USA
16:35-
17:10 [T6.INV02]
Deformation
mechanisms in
zirconium alloys
under and after
irradiation
F. Onimus*1, M.
Gaumé1, F.
Mompiou2, L.
Dupuy1, W.
Kassem1, L.
Gélébart1, R.
Brenner3, 1Universi
té Paris-Saclay,
France, 2Centre
d'Elaboration de
Matériaux et
d'Etudes
Structurales,
[O5.18]
Fatigue behavior of cold
spray-coated accident
tolerant cladding
M. Sevecek*1 ,2, M. Shahin2,
J. Petrik2, R. Ballinger2, K.
Shirvan2, 1Czech Technical
University in Prague, Czech
Republic, 2Massachusetts
Institute of Technology, USA
[O1.06]
Validation of TAF-ID
thermodynamic database
based on post irradiation
examinations of high
burnup MOX fuel in fast
reactors
K. Samuelsson*1, J-C.
Dumas2, B. Sundman3, C.
Guéneau2, 1KTH Royal
Institute of Technology,
Sweden, 2CEA, France,
3INSTN, France
The 5th Nuclear Materials Conference 2018
France, 3Sorbonne
Université, France
17:00-18:45 Poster Session 2 (Refreshments will be available to purchase) | Room: Emerald
Wednesday 17th October 2018 08:30-09:10 [PS05] Room: Seattle 1-3
The role of compositional complexity on irradiation effects in concentrated solid solution alloys
Y. Zhang, Oak Ridge National Laboratory, USA
09:10-09:50 [PS06]
Materials challenges for future nuclear fuel cycles – R&D on nitride fuel cycle for MA transmutation
M. Takano, Japan Atomic Energy Agency, Japan
09:50-10:20 Coffee Break Room: Emerald
10:20-12:25 Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1
Session Chair: G. Was
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: M. Preuss,
T. Wiss
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chair: W. Weber
Track 3- Modelling and
Simulation of Nuclear Fuels
Room: Pioneer
Session Chair: C. Valot
Track 1 Continued
Room: Capitol Hill
Session Chair: E.C.
Corcoran
10:20-10:45 [O2.20]
Helium effects in
materials of the nuclear
importance
S. Agarwal*, J. Brechtl,
S.J. Zinkle, University of
Tennesseee, USA
[O4.18]
Quantum mechanical simulations of displacement cascades in metals
P. Olsson*, D. Karlsson, KTH Royal Institute of Technology, Sweden
[O7.20]
Effect of thermal and
irradiation-induced long
range ordering in Ni-Cr
model alloys
F. Teng*1, D. Sprouster2, H.T.
Vo3, L.J. Yu4, E. Marquis4, P.
Hosemann3, J.
Tucker1, 1Oregon State
University, USA, 2Brookhaven
National Laboratory, USA,
3University of California
Berkeley, USA, 4University of
Michigan, USA
[O6.06]
Nano-scale microstructure
damage by neutron
irradiations in a novel Boron-
11 enriched TiB2 ultra-high
temperature ceramic
A. Bhattacharya*1, T.
Koyanagi1, C. Parish1, C.
Ang3, D. King2, G. Hilmas2, W.
Fahrenholtz2, S. Zinkle1 ,3, Y.
Katoh1, 1Oak Ridge National
Laboratory, USA, 2Missouri
University of Science and
Technology, USA, 3University
of Tennessee, USA
[O3.13]
Stability of uranium
vacancies, oxygen
interstitial clusters and U4O9
phase in hyper-
stoichiometric UO2 with DFT-
empirical free energies
calculations and empirical
molecular dynamics
simulations
A. Soulié*1, F. Bruneval1, M-
C. Marinica1, S. Murphy2, F.
Garrido3, J-P.
Crocombette1, 1CEA DEN
Service de Recherche en
Métallurgie Physique,
France, 2Lancaster
University, UK, 3Université
Paris-Sud, France
[O1.07]
First-principles studies of
mechanical, vibrational,
thermodynamic and thermal
transport properties of UAlx
(x=2,3,4)
Z.G. Mei*1, A.M. Yacout1, J.
Yang2, 1Argonne National
Lab, USA, 2Shanghai
University, China
10:45-11:10 [O2.21]
Grain boundary
embrittlement of neutron
irradiated Inconel X-750
M. Griffiths*1, S.
Xu2, 1Queens University,
Canada, 2Kinectrics Inc,
Canada
[O4.19]
Understanding of nano size
<100> interstitial loop within
high displacement
cascades and their
migration in iron-based
alloys
F. Gao*1, Q. Peng1, N. Gao2,
R.J. Kurtz3, 1University of
Michigan, USA, 2Chinese
[O7.21]
Microstructural
characterization of
neutron-irradiated
polycrystalline TiC.
S. Agarwal*1, T.
Koyanagi2, Y. Katoh2 ,1, X.
Hu1, W.J. Weber1 ,2, S.J.
Zinkle1 ,2, 1University of
Tennesseee, USA, 2Oak
[O6.07]
The swelling equation: From
10-2 to 10-8 dpa/s
M.J. Fluss, U.C. Berkeley, USA
[O3.14]
A DFT study of burnup-
induced volume changes in
U3Si2
A. Claisse*1, S.
Middleburgh2, D.
Nanopoulos3, P.
Olsson3, 1Westinghouse
Electric Sweden, Sweden,
2Bangor University, UK, 3KTH
[O1.08]
Assessment of Sb and Te as
U-Zr fuel additive to mitigate
fuel-cladding chemical
interaction
J. Zhang*1, Y. Xie1, M.
Benson2, R.D. Mariani1 1Virginia Tech, USA, 2Idaho
National Laboratory, USA
The 5th Nuclear Materials Conference 2018
Academy of Sciences,
China, 3Pacific Northwest
National Laboratory, USA
Ridge National
Laboratory, USA
Royal Institute of
Technology, Sweden
Track 2 Continued
Room: Seattle 1
Session Chair: G. Was
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: M. Preuss,
T. Wiss
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chair: W. Weber
Track 3- Modelling and
Simulation of Nuclear Fuels
Room: Pioneer
Session Chair: C. Valot
Track 1 Continued
Room: Capitol Hill
Session Chair:
E.C. Corcoran
11:10-11:35 [O2.22]
Understanding the grain
boundary strength of X-
750 alloy by small scale
tensile testing and
advanced
characterization and
modeling
L. He*1, M. Bachhav1, D.
Murray1, X. Liu1, E. Perez1,
W. Jiang1, X. Bai2, C.
Sun1, S.
Teysseyre1, 1Idaho
National Laboratory,
USA, 2Virginia
Polytechnic Institute and
State University, USA
[O4.20]
The effects of applied strain
on defect formation process
under high energy of a
primary knock-on atoms in
face-centered cubic metals
K. Kawamitsu1, T. Okita*1, T.
Kawabata1, M. Itakura2, 1The
University of Tokyo, Japan,
2Japan Atomic Energy
Agency, Japan
[O7.22]
Radiation damage with a
twist - a study of helical
dislocations in irradiated
FeCr alloys
J.C. Haley*1, G.R. Odette2,
S. Lozano-Perez1, S.G.
Roberts1, 1University of
Oxford, UK, 2University of
California Santa Barbara,
USA
[O6.08]
Descriptions of energy
deposition rates of self-ions
and their impact on the
credibility of simulation of
neutron-induced swelling
F.A. Garner*1 ,2, L.
Shao1, 1Radiation Effects
Consulting, USA, 2Texas
A&M University, USA
[O3.15]
Fission gas behaviour in
U3Si2 from DFT calculations
and atomistic simulations
D.A. Andersson*, X-Y. Liu,
M.W.D. Cooper, Los Alamos
National Laboratory, USA
[O1.09]
Vapor pressure
measurement of cesium
and iodine dissolved in
molten LiF-NaF-KF Salt by
TG-DTA-MS
Y. Sekiguchi*1, T. Kato2, K.
Uozumi2, T. Terai1, 1The
University of Tokyo, Japan,
2Central Research Institute
of Electric Power Industry,
Japan
11:35-12:00 [O2.23]
Quantitative
determination of the
stress state required to
induce crack initiation in
irradiated austenitic
stainless steels
D.C. Johnson*, G.S.
Was, University of
Michigan, USA
[O4.21]
Threshold displacement
energy of bcc metals by
molecular dynamics
simulation using force-
matching potential
S. Park*, T. Oda, Seoul
National University, Republic
of Korea
[O7.23]
Study on degree of
recrystallization in
zirconium-niobium cladding
using image quality by EBSD
T.S. Jung*, H. Jang, Y.K. Mok,
J.I. Kim, J.S. Yoo, KEPCO NF,
Republic of Korea
[O6.09]
Use of pure iron to study
the impact of self-ion
energy, displacement per
atom value, displacement
rate and irradiation
temperature on charged
particle simulation of void
swelling: swelling in four
dimensions
A.J. French*, F.A. Garner, L.
Shao, Texas A&M
University, USA
[O3.16]
Monte-Carlo and
molecular dynamics study
of PuO2 and UO2 properties
by use of improved
charge-variable SMTBQ
interatomic potentials
R. Ducher*1, D. MBongo1, A.
Shahsavari1, R. Tétot2, R.
Dubourg1, 1Institut de
Radioprotection et de
Sûreté Nucléaire, France,
2Institut de Chimie
Moléculaire et des
Matériaux d'Orsay, France
[O1.10]
Noble metal fission products
behaviour in Molten Salt
Reactor
E. Capelli*1 ,2, F. Cappia3,
P.R. Hania2, R.J.M.
Konings1,4, 1Delft University
of Technology, The
Netherlands, 2NRG, The
Netherlands, 3Idaho
National Laboratory, USA,
4European Commission,
Germany
12:00-12:25 [O2.24]
Experiments and
simulations with In-situ
Depth markers for
Evaluating high-z
[O4.22]
The evolution processes of
self-interstitial atom clusters
under displacement
cascades in FCC metals
[O7.24]
Development of methods for
post-irradiation examination
of miniature fuel specimens
irradiated in the High Flux
[O6.10]
Defect-free zones in
irradiated materials
S.J. Zinkle1 ,2, 1University of
Tennessee, USA, 2Oak Ridge
[O3.17]
Modeling and assessment
of intra-granular bubble
evolution and coarsening
in uranium dioxide
[O1.11]
Thermodynamic modeling
and database development
for molten salt reactor fuel
performance simulation
The 5th Nuclear Materials Conference 2018
materials with AIMS
(iDEA)
L.A. Kesler*, K.B. Woller,
Z.S. Hartwig, D.G.
Whyte, Massachusetts
Institute of Technology,
USA
S. Hayakawa*1, T. Okita1, M.
Itakura2, H. Xu3, Y.N.
Osetsky4, 1The University of
Tokyo, Japan, 2Japan
Atomic Energy Agency,
Japan, 3The University of
Tennessee, USA, 4Oak Ridge
National Laboratory, USA
Isotope Reactor
A. Raftery*, C. Petrie, R.
Morris, K. Smith, S. Finkeldei,
K. Terrani, Oak Ridge
National Laboratory, USA
National Laboratory, USA T. Barani*1, A. Magni1, D.
Pizzocri1, L. Cognini1, P. Van
Uffelen2, L. Luzzi1, G.
Pastore3 ,4, 1Politecnico di
Milano, Italy, 2European
Commission, Joint Research
Centre, Directorate for
Nuclear Safety and
Security, Germany, 3Idaho
National Laboratory, USA,
4Massachusetts Institute of
Technology, USA
T.M. Besmann*1, J.C. Ard1,
J.W. McMurray2, D.
Shin2, 1University of South
Carolina, USA, 2Oak Ridge
National Laboratory, USA
12:25-13:25
13:25-16:10
Lunch Break | Room: Emerald
13:25-15:15 Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1
Session Chairs: K. Field,
T.S. Byun
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: C. Judge,
A. Leenaers
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chair: G. Lumpkin
Track 3- Modelling and
Simulation of Nuclear Fuels
Room: Pioneer
Session Chair: G. Pastore
Track 1 Continued
Room: Capitol Hill
Session Chairs: C.A Atkins,
E.C. Corcoran
13:25-13:50 [O2.25]
Phase stability of a 14Cr-
ODS ferritic steel
strengthened by Y-Ti-O
oxide particles under Fe
ions irradiation at room
temperature
P. Song*, A. Kimura, K.
Yabuuchi, Kyoto
University, Japan
[O4.23]
The effect of local chemical
environment on the
energetics of stacking faults
and vacancy platelets in
zirconium
J. March-Rico*, B.D. Wirth, G.
Huang, University of
Tennessee, USA
[O7.25]
The MARS beamline, a
unique multipurpose
instrument for the
examination of
radioactive samples with
advanced synchrotron
techniques
D. Menut*, M.O.J.Y.
Hunault, H. Hermange,
P.L. Solari, Synchrotron
SOLEIL, France
[O6.11]
Atomic scale instrumental
methodology to quantify
intergranular segregation:
Application to phosphorous
in ferritic thermally aged or
irradiated alloys
A. Akhatova1, F. Christien2,
V. Barnier2, E. Cadel1, F.
Cuvilly1, B. Radiguet1, P.
Pareige*1, 1Normandie
University, France, 2Ecole
des Mines Sait Etienne,
France
[O3.18]
Temperature dependence
of phonon spectra of UMo
alloys with 12.5 and 25 at.%
Mo
B. Dorado*1, D. Chaney2, J.
Bouchet1, G.H.
Lander3, 1CEA, France,
2University of Bristol, UK, 3JRC,
Germany
[O1.12]
Applicability of Machine
Learning to Modeling Thermal
Conductivity of Irradiated
Uranium-Molybdenum
Nuclear Fuels
E. Kautz*, J. Johns, A. Hagen,
D. Burkes, Pacific Northwest
National Laboratory, USA
13:50-14:15 [O2.26]
Fabrication and
characterization of thin-
walled ODS FeCrAlY tubes
for accident tolerant fuel
cladding applications
S. Dryepondt*1, C.P.
Massey2, M.N. Gussev1,
K.D. Linton1, K.A.
Terrani1, 1Oak Ridge
National Laboratory,
United States Minor
Outlying Islands, 2University
of Tennessee, United
States Minor Outlying
Islands
[O4.24]
Fast efficient modelling of
hydrided microstructures of
zirconium at the millimetre
scale
P. Patel, D.S. Balint, A.P.
Sutton,
M.R. Wenman*, Imperial
College London, UK
[O7.26]
Advanced characterisation
of iodine-induced stress
corrosion cracks in
zirconium alloys
A. Garner*, C. Gillen, P.
Frankel, University of
Manchester, UK
[O6.12]
Atom-probe
tomography
characterization of
nano-sized hardening
features of high-dose
neutron irradiated
Eurofer97
B. Gómez-Ferrer*1, C.
Dethloff2, E. Gaganidze2,
L. Malerba3, P. Pareige1,
C. Pareige1, 1Universite
de Rouen - CNRS,
France, 2Karlsruhe
Institute of Technology,
Germany, 3SCK•CEN,
[O3.19]
Microstructure dependent
swelling model in monolithic
UMo nuclear fuels by
coupling the rate theory and
phase field approach
S.Y. Hu*, V.V. Joshi, C.A.
Lavender, D.E. Burkes, Pacific
Northwest National
Laboratory, USA
[O1.13]
Development of effective
thermal conductivity model
for FCM and pebble fuels with
randomly distributed TRISO
particles
M. Liu1, Y. Lee*1, D.V.
Rao2, 1University of New
Mexico, USA, 2Los Alamos
National Laboratory, USA
The 5th Nuclear Materials Conference 2018
Belgium
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1
Session Chairs: K. Field,
T.S. Byun
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: C. Judge,
A. Leenaers
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chair: G. Lumpkin
Track 3- Modelling and
Simulation of Nuclear Fuels
Room: Pioneer
Session Chair:
G. Pastore
Track 1 Continued
Room: Capitol Hill
Session Chairs: C.A Atkins,
E.C. Corcoran
14:15-14:40 [O2.27]
Evolution of materials
properties and
macropores in thermally
crept nuclear graphite
J.J. Kane*, T.S. Yoder,
W.E. Windes, Idaho
National Laboratory,
USA
[O4.25]
DFT studies on the nature
of Y-Ti-O nanoclusters in
bcc Fe
M. Vallinayagam*, M.
Posselt, J.
Faßbender, Institute of
Ion Beam Physics and
Materials Research,
Germany
[O7.27]
Digital image correlation
strain measurement and
geometrically necessary
dislocation determination at
a crack tip in zirconium
Z. Wang*, M.
Daymond, Queen's
University, Canada
[O6.13]
In situ Raman spectroscopy
for characterization of ion
induced defects in model
graphite
N. Galy1, N. Moncoffre*1, N.
Toulhoat1 ,2, N. Bérerd1 ,3, Y.
Pipon1 ,3, M.R. Ammar4, P.
Simon4, A. Canizarès4, N.
Raimboux4, P.
Sigot4, 1Université de lyon,
France, 2CEA Saclay,
France, 3UCBL IUT A, France,
4CNRS CEMHTI, France
[O3.20]
The role of dopant charge
state on defect chemistry
and grain growth of
doped UO2
M.W.D. Cooper*, C.R.
Stanek, D.A.
Andersson, Los Alamos
National Laboratory, USA
[O1.14]
Viscosities of stainless steel
and boron-carbide alloy
melts
T. Nishi*1, H. Ohta1, H.
Kokubo1, H.
Yamano2, 1Ibaraki University,
Japan, 2Japan Atomic
Energy Agency, Japan
14:40-15:15 [T2.INV03] Phase stability of oxide
particles under ion-irradiation in different sorts of ODS ferritic steels
A. Kimura*, P. Song, K. Yabuuchi, Kyoto University, Japan
[T4.INV03] Using computational modeling to understand radiation damage tolerance in complex oxides both from the bottom-up and the top -down B.P. Uberuaga, Los Alamos National Laboratory, USA
[T7.INV03] Image analysis and computer vision: A tool for investigating irradiated fuel microstructure F. Cappia*, G.L. Beausoleil, L. Capriotti, G.L. Povirk, J.M. Harp, Idaho National Laboratory, USA
[T6.INV03]
Radiation damage in
irradiated thermal and fast
nuclear reactor fuels
T. Wiss*1, O. Dieste1, R.
Konings1, V. Rondinella1, D.
Staicu1, O. Benes1, D.
Wegen1, N.
Chauvin2, 1European
Commission, Germany,
2Centre d’études
nucléaires de Cadarache,
France
[T3.INV03]
Combining CALPHAD,
phase-field, and
transport models for
quantitative prediction
of nuclear materials
behaviour
M.J. Welland*, A.A.
Prudil, E. Thomas, E.
Tenuta, Canadian
Nuclear Laboratories,
Canada
[T1.INV02]
Determination of
melting transitions in
fast reactor fuels
K. Ananthasivan*1 ,2, B.
Samanta1 ,2, S.
Balakrishnan1, K.
Joseph1, 1Indira
Gandhi Centre for
Atomic Research,
India, 2Homi Bhabha
National Institute, India
15:15-15:45 Coffee Break Room: Emerald
The 5th Nuclear Materials Conference 2018
15:45-16:10 [O2.28]
Preparing highly
structured B4C control-
rod via magnetic field-
assisted colloidal
processing
S. Azuma*1, T. Uchikoshi1,
K. Yoshida2, T.S.
Suzuki1, 1National
Institute for Materials
Science, Japan, 2Tokyo
Institute of Technology,
Japan
[O4.26]
The effect of nanoscale
precipitates on the
mechanical properties of
T91 steel during early aging
based on experimental and
computational analysis
L.J. Hu*, Q.F. Zhang, H.Y.
Dong, W.Y. Liang, B.Q. Lin,
M.Y. Yao, Y.P. Xie, Shanghai
University, China
[O7.28]
Characterizing swift heavy
ion induced effects in
nuclear materials with
neutron total scattering
M. Lang*1, E.C. O'Quinn1,
R.I. Palomares1, I. Gussev1,
J. Neuefeind2, C.
Trautmann3 ,4, R.C.
Ewing5, 1University of
Tennessee, USA, 2Oak
Ridge National Laboratory,
USA, 3GSI Helmholtzzentrum
für Schwerionenforschung,
Germany, 4Technische
Universität, Germany,
5Stanford University, USA
[O6.14]
Developing a method to
quantify radiation damage
using stored energy
C.A. Hirst*, R.C. Connick, K.
So, P. Cao, R.S. Kemp, M.P.
Short, Massachusetts
Institute of Technology,
USA
[O3.21]
Development of the MFPR/R
code for characterization of
the rim zone and high
burnup structure evolution in
UO2 fuel pellets
V.I. Tarasov1, V.E. Shestak1,
P.V. Polovnikov1, M.S.
Veshchunov*2, 1Russian
Academy of Sciences,
Russia, 2International Atomic
Energy Agency (IAEA),
Austria
[O1.15]
Phase identification and
thermophysical properties
of Pu-Zr and U-Pu-Zr fuel
alloys
C. Adkins*1, A. Aitkaliyeva2
,1, S. Middlemas1, 1Idaho
National Laboratory, USA,
2University of Florida, USA
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1
Session Chairs: K. Field,
T.S. Byun
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: C. Judge,
A. Leenaers
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chair: G. Lumpkin
Track 3- Modelling and
Simulation of Nuclear Fuels
Room: Pioneer
Session Chair: G. Pastore
Track 1 Continued
Room: Capitol Hill
Session Chairs: C.A Atkins,
E.C. Corcoran
16:10-16:35 [O2.29]
Irradiation induced
hydrothermal corrosion
of SiC and the
surface passivation for
ATF
S. Kondo, Tohoku
University, Japan
[O4.27]
Radiation damage tolerant
materials: Zr-Nb nanoscale
metallic multilayer composite
H.S. Sen*, T. Polcar, Czech
Technical University in
Prague, Czech Republic
[O7.29]
Neutron irradiation effects on
the microstructure of nuclear
graphite
J.D. Arregui-Mena*1, B.
Maerz2, C. Contescu1, H.
Wu2, A.A. Campbell1, R.N.
Worth3, P.D. Edmondson1,
J.W. Geringer1, Y.
Katoh1, 1Oak Ridge National
Laboratory, USA,
2Loughborough University,
UK, 3The University of
Manchester, UK
[O6.15]
Theoretical prediction of
void superlattice formation
under irradiation
Y. Zhang*1, Y. Gao1, C. Sun1,
D. Schwen1, C. Jiang1, L.
He1, J. Gan1, D. Sprouster2,
L. Ecker1, 1Idaho National
Laboratory, USA,
2Brookhaven National
Laboratory, USA
[O3.22]
Molecular dynamics
modeling of grain boundary
mobilities in UO2
J. French, X.M. Bai*, Virginia
Polytechnic Institute and
State University, USA
[O1.16]
Annealing effects on
thermal diffusivity and
electrical resistivity of a
surrogate for metallic fuel
N. Odaira*, Y.
Arita, University of Fukui,
Japan
16:35-17:00 [O2.30]
Analysis of irradiation
induced element
redistribution in TPBAR
components using atom
probe tomography
[O7.30]
Mechanisms of
embrittlement and fracture
for Inconel X-750 irradiated
to high dose and high
concentrations of helium
[O6.16]
Combined study of
microstructure evolution of
irradiated and deuterium
exposed Eurofer and
tungsten
[O3.23]
Development of a
molecular dynamics
methodology to examine
the dynamic structure of
vacancies in nuclear fuel
[O1.17]
Fuel fabrication and
characterization of
surrogate fuel blocks for the
low-enriched fuel
conversion effort at the
The 5th Nuclear Materials Conference 2018
A. Devaraj, B. Arey, E.J.
Kautz*, G. sevigny, J.
Hardy, D. Senor, Pacific
Northwest National
Laboratory, USA
and hydrogen
C.D. Judge*, V. Bhakhry, C.
Howard, C. Mayhew, C.
Dixon, H. Rajakumar, G.A.
Bickel, Canadian Nuclear
Laboratories, Canada
A. Hollingsworth*1, A. Baron-
Wiechec1, A. Davies1, M.F.
Barthe3, 1Culham Science
Centre, UK, 2University Paris-
Saclay, France, 3Université
d'Orléans, France
C.A. Manring*, A.I.
Hawari, North Carolina
State University, USA
Transient Reactor Test
Facility
E. Luther*1, B. Coryell2, S.
Kwon2, J. Jiang2, D. Scates2,
J. Aguiar2, D. Cummins1, T.
Baker1, H. Hartman2, 1Los
Alamos National
Laboratory, USA, 2Idaho
National Laboratory, USA
17:00-18:45 Poster Session 3 (Refreshments will be available to purchase) | Room: Emerald
Thursday 18th October 2018 08:30-10:10 Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1
Session Chair: S.S. Raiman
Track 4- Modelling and
Simulation of Structural
Materials
Room: Seattle 2
Session Chairs: B. Wirth,
T. Okita, M. Gilbert
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: T. Lach,
J. Wharry
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chairs: M. Lang,
L. Walters, K. Arakawa
Track 5- Behavior of
Materials during Severe
Accidents and Accident
Tolerant Fuels
Room: Pioneer
Session Chair: M.K. Grosse
Track 3- Modelling and
Simulation of Nuclear Fuels Room: Capitol Hill
Session Chair: C. Valot
08:30-08:55 [O2.31]
Property evolutions of
neutron-irradiated Ti-Si-
C and Ti-Al-C MAX-
phase materials
Y. Katoh*1, C. Ang1, P.
Edmondson1, C. Shih1, C.
Parish1, M. Tunes2, 1Oak
Ridge National
Laboratory, USA,
2University of
Huddersfield, UK
[O4.28]
Numerical and analytical
modelling in support of
miniaturized mechanical
testing and micromechanical
property evaluation
P. Hähner*1, A. Ruiz Moreno1,
C. Soyarslan2, B. Gülçimen
Çakan3, S. Bargmann2, 1Joint
Research Centre, The
Netherlands, 2University of
Wuppertal, Germany,
3Uludag University, Turkey
[O7.31]
Direct observation of fission
product noble metal phase
particles in the UO2 nuclear
fuel - Zr cladding interaction
region in high burn-up spent
nuclear fuel
T.G. Lach*, E.G. Buck, B.K.
McNamara, M.A. Conroy,
J.M. Schwantes, R.
Clark, Pacific Northwest
National Laboratory, USA
[O6.17]
Comparison of
microstructural
development between Fe-
12Cr and Fe-12Cr-5Al under
irradiation
N. Hashimoto*1, K. Toyota1,
Y. Tang1, K. Sakamoto2, S.
Yamashita3, 1Hokkaido
University, Japan, 2Nippon
Nuclear Fuel Development,
Japan, 3Japan Atomic
Energy Agency, Japan
[O5.19]
Advanced
mechanical testing of
accident-tolerant fuel
cladding tubes
M.N. Cinbiz*, M. Gussev, K.
Linton, K. Terrani, M. Howell,
R. Lowden, Oak Ridge
National Laboratory, USA
[O3.24]
Development of a layered
two-dimensional approach
for modelling fuel rod
behaviour
K.A. Gamble*,
G. Pastore, Idaho National
Laboratory, USA
08:55-09:20 [O2.32]
Understanding the role of
niobium on the hydrogen
uptake mechanism of
zirconium alloys in
primary water
B. Queylat*1, M. Jublot1, F.
Martin2, N. Bendib1, F.
Miserque2, P. Bossis2, M.
Tupin1, 1CEA-DEN, France,
2Université Paris-Saclay,
France
[O4.29] Effects of uniaxial stress on 1D migrating self-interstitial clusters in production bias method
S.I. Choi*1, M.J.
Banisalman2, J.H.
Kim1, 1Ulsan National
Institute of Science and
Technology, Republic of
Korea, 2Seoul National
University, Republic of
Korea
[O7.32]
Effect of Mo presence on
the Cs migration in UOx
C. Panetier*1, Y. Pipon1 ,2, C.
Gaillard1, N. Moncoffre1, L.
Sarrasin1, D. Mangin3, P.
Sainsot4, R. Ducher5, R.
Dubourg5, 1UCBL,
CNRS/IN2P3, IPNL, France,
2UCBL, IUT Lyon 1, France,
3IJL Université de Lorraine,
France, 4INSA Lyon, France,
5IRSN, France
[O6.18]
Influence of the
microstructure on the void
swelling of a 6061 aluminum
alloy under irradiation
V. Garric*1, P. Donnadieu2,
G. Renou2, B.
Kapusta1, 1DEN-Service
d’Etudes des Matériaux
Irradiés, CEA Université Paris-
Saclay, France, 2University
Grenoble Alpes, France
[O5.20]
Advances in performance
and manufacturing of SiC-
SiC composite accident
tolerant fuel cladding
H.E. Khalifa*1, C.P. Deck1,
G.M. Jacobsen1, J.
Sheeder1, S. Oswald1, K.
Shapovalov1, E. Song1, S.
Gonderman1, R.
Haefelfinger1, J.
Gazza1, 1General Atomics,
USA, 2Westinghouse Electric
Company LLC, USA
[O3.25]
Effects of Cr dopants on
generalized stacking fault
energies in UO2 by means
of molecular dynamics
simulations
R.A. Ngayam-Happy*, M.
Kosa, M. Krack, Paul
Scherrer Institut, Switzerland
09:20-09:45 [O2.33]
A tomographic TEM
[O4.30]
Dislocation bias and sink
[O7.33]
Anisotropic mechanical [O6.19] Effect of helium on
[O5.21]
Micromechanical [O3.26]
Combining cluster
The 5th Nuclear Materials Conference 2018
study of dislocation slip
structures in pure
zirconium
Q. Wang*1, F. Long1, J.
Kacher2, Z. Yao1, M.R.
Daymond1, 1Queen's
University, Canada,
2Georgia Institute of
Technology, USA
strength in bcc Fe based on
mesoscale defect dynamics
H. Xu, The University of
Tennessee, USA
response of depleted
uranium single crystal
micro-pillar
P. Zhou*1, R.W. Li2, D.W.
Xiao2, C. Lu2, Y. Hu1, L.F.
He2, 1Science and
Technology on Surface
Physics and Chemistry
Laboratory, China,
2Insititute of Materials,
China Academy of
Engineering Physics
(CAEP), China
dislocation and cavity
evolution in neutron
irradiated TMS and ODS
ferritic alloys
H.J. Jung1, D.J.
Edwards*2, K.
Kruska2, R. Kurtz2, T.
Yamamoto3, Y. Wu3,
G.R.
Odette3, 1Northwes
tion University, USA,
2Pacific Northwest
National
Laboratory, USA,
3University of
California-Santa
Barbara, USA
characterization of the
radiation and temperature
effects on SiC-SiC fiber
composites for accident-
tolerant fuel applications
Y. Zayachuk*1, A. Hussey1,
D.E.J. Armstrong1, C. Deck2,
P. Hosemann3, 1University of
Oxford, UK, 2General
Atomic, USA, 3University of
California, USA
expansion and first-
principles calculations to
study the USi-USi2 pseudo-
binary phase space
V. Kocevski*, T.M.
Besmann, University of
South Carolina, USA
Track 2- Structural and
Functional Materials for
Fission and Fusion
reactors
Room: Seattle 1 Session Chair: S.S. Raiman
Track 7- Characterization of
Irradiated Materials and
Nuclear Fuels
Room: Seattle 3
Session Chairs: T. Lach,
J. Wharry
Track 6- Radiation Damage
Processes in Materials and
Complex Microstructures
Room: Belltown
Session Chairs: M. Lang,
L. Walters, K. Arakawa
Track 5 Continued
Room: Pioneer
Session Chair: M.K. Grosse
Track 3 Continued
Room: Capitol Hill
Session Chair: C. Valot
09:45-10:10 [O2.34]
Crystal orientation
dependence of
irradiation-induced
hardening in Zr-Nb alloys
H.L. Yang*1, S. Kano1, J.
McGrady1, Y.
Matsukawa2, D.Y. Chen1,
K. Murakami3, H.
Abe1, 1The University of
Tokyo, Japan, 2Tohoku
University, Japan,
3Nagaoka University of
Technology, Japan
[O7.34]
Non-destructive
characterization of hydrided
Zr and Zircaloy-4 cladding
by neutron radiography and
tomography B. Beers*1, H. Bilheux2, Y.
Yan2, B. Heuser2, 1University
of Tennessee - Knoxville,
USA, 2Oak Ridge National
Laboratory, USA
[O6.20]
Irradiation effects in high
entropy alloys
W-Y. Chen*1, Y. Chen1, X.
Liu2, J-W. Yeh3, K-K. Tseng3,
K. Natesan1, 1Argonne
National Laboratory, USA,
2University of Illinois, USA,
3National Tsing Hua
University, Taiwan
[O5.22]
Hermeticity evaluation of
SiC/SiC composite tubes
relevant to LWR cladding
application
X. Hu*, T. Koyanagi, G.P.
Singh, C.M. Petrie, Y.
Katoh, Oak Ridge National
Laboratory, USA
[O3.27]
Development of a thermal
resistor model and
microstructure design tool for
UO2 composite fuels
F.W. Hilty*, M.R.
Tonks, University of Florida,
USA
10:10-10:40 Coffee Break Room: Emerald
Room: Seattle 1-3
10:40-11:20 [L02] - Best Paper Award Presentation
Microstructure characterization and strengthening mechanisms of oxide dispersion strengthened (ODS) Fe-9%Cr and Fe-14%Cr extruded bars
A. Chauhan, Karlsruhe Institute of Technology, Germany
11:20-12:00 [PS7]
Structural material options for Gen IV and fusion energy systems
P. Yvon, Commissariat à l'énergie atomique et aux énergies alternatives, France
12:00-12:40 [PS8]
Recent advancements in multi-scale fuel modelling techniques
C. Stanek, Los Alamos National Laboratory, USA
12:40-13:10 NuMart Awards/Best Poster Awards/Young Researcher Awards/Closing Ceremony
The 5th Nuclear Materials Conference 2018
End of Conference