The program is now available here.

Program of ANFC2014 (as of September 1, 2014)
Sep. 18, 2014 (Thu.)
Sep. 19, 2014 (Fri.)
9:00
9:15
9:00
Session-6
FBR and Innovative-1
10:15
10:30
Coffee Break
Session-7
FBR and Innovative-2
12:00
12:15
Closing Oral Session
Lunch Time
13:30
Young Scientist Session
17:00
Closing Young Scientist Session
Opening
Session-1
Fukushima Related-1
10:30
10:45
Coffee Break
Session-2
Fukushima Related-2
12:00
Lunch Time
13:00
Session-3
Fundamentals
14:30
14:45
Group Photo & Short Break
Session-4
Zr Alloys-1
16:15
Session-5
Zr Alloys-2
17:30
17:40
Poster Session
18:30
Banquet
20:00
Closing Banquet
ANFC2014 Oral Session Program (as of September 1, 2014)
Sep. 18, 2014 (Thu.)
9:00
Opening
Session 1 Fukushima Related-1
Chair: Yuji Ohishi (Osaka Univ.)
Invited 1
9:15
Dong-Seong SOHN (UNIST)
S1-1
9:45
Akira Kirishima (Tohoku Univ.)
Gas release and rod internal pressure of BN added UO2
Fuel
Leaching of Actinide Elements from Simulated Fuel Debris
to Seawater
Thermodynamic calculation on possible chemical forms of
released fission products from failed fuel rod in the severe
S1-2
10:00
Akihiro Suzuki (Univ. of Tokyo)
accident conditions
The asset of advanced spectroscopy techniques to
S1-3
10:15
Claude Degueldre (PSI)
10:30-10:45
Coffee Break
complete post irradiation examination of nuclear fuels
Session 2 Fukushima related-2
Chair: Kwangheon Park (Kyunghee Univ.)
Invited 2
David Bottomley (ITU)
Investigations of the melting behaviour of the U-Zr-Fe-O
10:45
system
Development of SiC materials for light water reactor
S2-1
11:15
Moonhee Lee (Kyoto Univ.)
application
S2-2
11:30
Sosuke Kondo (Kyoto Univ.)
Irradiation stability of the SiC fibers at high dose
The influence of Pu and Zr on the melting temperatures of
S2-3
11:45
Kyoichi Morimoto (JAEA)
12:00-13:00
Lunch Time
Session 3 Fundamentals
the U-Pu-Zr-O system
Chair: Shiori Ishino (RACE, Univ. of Tokyo)
Practice and Prospect of Advanced Fuel Management and
Invited 3
13:00
Min Xiao (CNPRI/CGNPC)
S3-1
13:30
Ken Kurosaki (Osaka Univ.)
S3-2
13:45
Bon Young Kim (KAIST)
Fuel Technology Application in PWR in China
Effect of hafnium on the high-temperature stability of
zirconium hydrides
Spectroscopic properties of lanthanide elements in molten
LiCl-KCl eutectic
Chlorination of UO2 and (U, Zr)O2 solid solution using
S3-3
14:00
Takumi Sato (JAEA)
MoCl5
Self-radiation effects on the electronic ground state of
S3-4
14:15
Yo Tokunaga (JAEA)
14:30 - 14:45
Group Photo & Short Break
Session 4 Zr Alloys-1
AmO2 studied by 17O-NMR
Chair: Junji Matsunaga (NFD)
Fully Ceramic Microencapsulated and an Enhanced
Invited 4
14:45
Lance L. Snead (ORNL)
S4-1
15:15
Kan Sakamoto (NFD)
Accident Tolerant LWR Fuel
Change of chemical states of niobium in oxide layer of
zirconium-niobium alloys with oxide growth
Compression Deformation Behavior of Zr–1Sn–0.3Nb Alloy
S4-2
15:30
Qing Hui Zeng (Chongqing Univ.)
with Different Initial Orientations at 700℃
P.Chellapandi (Indira Gandhi
Invited 9
15:45
Center for Atomic Research)
TBD
ANFC2014 Oral Session Program (as of September 1, 2014)
Sep. 18, 2014 (Thu.)
Session 5 Zr Alloys-2
Chair: Isamu Sato (JAEA)
Development of Advanced Expansion Due to Compression
(AEDC) Test Method for Safety Evaluation of Degraded
Invited 5
16:15
Hiroaki Abe (Tohoku Univ.)
Nuclear Fuel Cladding Materials
The investigation on new zirconium alloys with good
S5-1
16:45
Zen Qifeng (SNDREI)
S5-2
17:00
Hui Long Yang (Tohoku Univ.)
corrosion properties
Effect of Mo on microstructural evolution and mechanical
properties in Zr-Nb alloys as nuclear fuel cladding material
Towards understanding beneficial effects of slow power
S5-3
17:15
Ioan Arimescu (AREVA)
17:40
Poster Session
18:30 - 20:00
Banquet
ramps
Sep. 19, 2014 (Fri.)
Session 6 FBR and Inovative-1
Chair: Tsuyoshi Nishi (JAEA)
CEA R&D related to the fuel behavior under severe
Invited 6
9:00
Patrick Dumaz (CEA)
accidents
Effect of impurity on sintering and dissolution behavior of
S6-1
9:30
Yoko Akutsu (JAEA)
simulated molybdenum cermet fuels
Aberration-corrected TEM&STEM Characterization of
Nanoprecipitates in Al-alloyed high-Cr ODS steels for
S6-2
9:45
Peng Dou (Chongqing Univ.)
Generation IV Nuclear Fission Reactors
Mechanistic Modeling of UO2 Oxidation in the Dry Storage
Invited 7
10:00
Kwangheon Park (Kyunghee Univ.) Condition
10:15-10:30
Coffee Break
Session 7 FBR and Inovative-2
Chair: Peng Dou (Chongqing Univ.)
Pyrochemical Study of Uranium and Zirconium Oxides for
Invited 8
10:30
Nobuaki Sato (Tohoku Univ.)
Fuel Debris Treatment
Thermophysical properties of americium-containing barium
S7-1
11:00
Kosuke Tanaka (JAEA)
plutonate
S7-2
11:15
Junji Matsunaga (NFD)
An investigation of formation behavior of sodium-uranate
Study on the formation of Me-UO2-CO3 complexes (Me =
S7-3
S7-4
Jun-Yeop Lee (KAIST)
Ca2+ and Mg2+)
Hwang Dongki (Tokyo Institute of
Studies on Solubility of Lanthanoid(III) Complexes with
11:45
Technology)
Fluorinated β-diketones in Supercritical Carbon Dioxide
12:00
Closing Oral Session
12:15-13:30
Lunch Time
13:30 - 17:00
Young Scientist Session
- Technical Session
- Recreation
11:30
Invited Presentation : 30min. including 5 min. discussion
Oral Presentation : 15min. including 5min. discussion
ANFC2014 Poster Session Program (as of September 1, 2014)
18 September, 2014, 17:40-20:00
ID
Name
Affiliation
Title
P01
Hiroaki Muta
Osaka University
Indentation study on zirconium hydride
P02
Yunmock Jung
Kyunghee
University
Kinetics of Zr-alloy Cladding Oxidation of the Partial Pressure of
Nitrogen at 1200°C
P03
Jeongmin Choi
Kyunghee
University
The study of effects on Zinc Injection in CRUD Formation
P04
Donghee Lee
Kyunghee
University
Basic Study on the Development of a Metal Cladding with Protective
SiC composite
P05
Siori Kishita
Tohoku University
FEM analysis of Advanced Expansion Due to Compression Test
Method
P06
Risheng Qiu
Chongqing
University
Effect of alloying elements Cr and Cu on secondary intermetallic phase
of Zr alloys
P07
Taku
Matsumoto
Kyushu University
Oxygen potential measurement of (Pu0.928Am0.072)O2-x at high
temperatures
P08
Yuhei Fukuda
Tohoku University
Mechanochemical Treatment of UO2-ZrO2 Mixture for Fuel Debris
Management
P09
Yoshinobu
Matsumoto
Nagaoka University Hydrogen generation by water radiolysis of suspension with oxidation
of Technology
products of Zircaroy-4.
P10
Ayako Sudo
Japan Atomic
Energy Agency
Fundamental experiments on phase stabilities of Fe-B-C ternary
systems
P11
Haruaki
Matsuura
Tokyo Institute of
Technology
Pyrochemical treatment of fuel debris using selective fluorination and
molten salt electrolysis - Fluorination behavior of zirconium oxide and its
mixtures
P12
Hitoshi Mimura Tohoku University
Selective adsorption properties of Cs and Sr for novel granular mixed
zeolites
P13
Md. Shakilur
Rahman
Tohoku University
Selective removal of Cs and Sr in seawater by novel zeolite honeycomb
modeling
P14
Hiroki Shibata
Japan Atomic
Energy Agency
Chemical interaction between B4C and stainless steel materials used in
BWR of Japan
P15
Takahiro Usui
The University of
Tokyo
SiC coating as hydrogen permeation reduction and oxidation resistance
for nuclear fuel cladding
P16
Yukihiro
Murakami
University of Fukui.
Advance in estimation technology of thermal conductivity
of annular pellet
P17
Yuji Ohishi
Osaka University
Effect of oxygen on crystal structure and thermophysical properties of
zirconium-oxygen interstitial solid solutions
P18
Yuuma
Sekiguchi
The University of
Tokyo
Evaluation of vapor pressure of volatile FP elements from molten salt
reactor system
P19
Seung Park
KAIST
Redox Behaviors of Neodymium Chloride in High Temperature LiCl-KCl
Eutectic by UV-Vis Absorption Spectroscopy in Combination of
Electrolysis
P20
Shengchu Liu
Kyoto University
Electrochemical co-deposition of Pd and Rh in molten LiCl-2CsCl
eutectic
Yuji Shibahara
Kyoto University
Research Reactor
Institute
Fundamental study of analysis of isotopic composition for source
analysis of radioactive nuclides by thermal ionization mass spectrometry
P21
ANFC2014 Poster Session Program (as of September 1, 2014)
18 September, 2014, 18:00-20:00
ID
Name
Title
P24
Yu Takeno
Kyoto University
P25
Toshihide Takai
Japan Atomic
Energy Agency
Computational modeling for realization of rationalized replacement of
defective fuels in light water reactors
Studies on Extraction and Recovery of U(VI) in HNO3 aq-[BMI][NfO]
Ionic Liquid Biphasic System for Decontamination of Uranium Wastes
Leaching behavior of fission products and U from neutron-irradiated
UO2/ZrO2 solid solutions in non-filtered surface seawater
Development of Measurement Technique on the Equilibrium Vapor
Pressure of Simulated Fission Products
P26
Emmanuelle
Coulon-Picard
CEA
Thermal behavior of thorium fuel rod
P27
Ryota Fujimura Fukui University
P28
Ryosuke Ito
Tokyo Institute of
Technology
P29
Masahiko
Osaka
Japan Atomic
Energy Agency
P30
Tsuyoshi Tai
Nagaoka University
Adsorption behavior of iodine in seawater on inorganic ion exchanger
of Technology
P31
Yoshihiro Iwata
Japan Atomic
Energy Agency
P32
Kozo
Katsuyama
Japan Atomic
Energy Agency
P33
Vladimir
Likhanskii
SRC RF "TRINITI"
P34
Motoyasu
Kinoshita
RACE, University of
Introduction of safe liquid fuel in present nuclear industry
Tokyo
P35
Masatoshi
Akashi
Japan Atomic
Energy Agency
The influence of Gd content on the properties of simulated fuel debris
P36
Ji-Hyeon Kim
UNIST
Nb coating effect on interaction between U-Mo powder and Al matrix
P37
Byoung Jin Cho UNIST
Thermal Conductivity of U-10Mo/Al Dispersion Fuel
P38
Lars Hallstadius Westinghouse
Evolution of LWR cladding – a Westinghouse perspective
P39
Chikara Ito
Japan Atomic
Energy Agency
Development of remote sensing technique using radiation-resistant
optical fibers to survey in-vessel for fuel debris
P40
Cheol Min Lee
UNIST
Development of a creep correlation for HT9
P42
Tae-Won Cho
UNIST
U-Mo Thermal Conductivity Analysis through Abaqus Simulation
P43
Je-Kyun Baek
UNIST
Axial temperature distribution of a high temperature corrosion test
specimen
P44
Sun-Ki Kim
KAERI
High Temperature Air Oxidation Behavior and Its Kinetics of Zircaloy-4
During Loss of Coolant Accident in a Spent Fuel Pool
P22
P23
Toshiki
Nakasuji
Kouhei
Arakawa
Affiliation
Kyoto University
Tokyo Institute of
Technology
Fundamental study of FP corrosion behavior of Hastelloy-N in molten
salt fluoride FLiNaK
Synthesis of Crown Ether Derivative with Fluorinated Arms for
Decontamination of Radioactive Wastes Using Supercritical Carbon
Dioxide as Medium
Oxidation and reduction behaviors of a prototypic MgO-PuO2-x inert
matrix fuel
A study on resonance ionization mass spectrometry of fission products
released from molten fuel
Evaluation of Accompanying Behavior of Cerium with Nuclear Materials
for the Establishment of Nuclear Material Accountancy Method Using
Passive Gamma-ray Spectrometry
Evolution of metal/oxide interface structure during oxidation of Zr-alloys
Location Map of Katahira Campus
Katahira Campus
Katahira Campus Map
Sakura Hall
Only the
bank card
can be used
for this ATM
These maps were referred from
http://www.tohoku.ac.jp/english/profile/campus/01/katahira/

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