3rd Asia Pacific Symposium on Tritium Science
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3rd Asia Pacific Symposium
on Tritium Science (APSOT-3)
November 3-6th, 2020,
UNIVERSITY OF TOYAMA, JAPAN



Program

APSOT-3 Oral Presentation Program (Tentative)

 

November 3, Tuesday

 

13:00-13:15          Opening, Announcements

 

13:15-14:55    Fuel Cycle I

I-1

Progress of tritium plant for fusion reactor in China

S. Peng

(CAEP, China)

I-2

Basic concept of JA DEMO fuel cycle

Y. Iwai

(QST, Japan)

O-1

The recent progress of CFETR tritium cycle demonstration system

Y. Gong

(CAEP, China)

O-2

The helium coolant purification system of CFETR: Preliminary design

and the performance of the copper oxide bed

J. Li

(CAEP, China)

 

14:55-15:05          Break

 

15:05-17:15    Basic Properties and Applications

I-3

Scanning negative muon microscopy by muon-catalyzed fusion using

tritium

Y. Nagatani

(KEK, Japan)

I-4

Theoretical and computational evaluation of thermodynamic properties

of hydrogen isotope gases

T. Oda

(SNU, Korea)

I-5

Cryogenic hydrogen, deuterium and tritium at the Tritium Laboratory

Karlsruhe

R. Größle

(KIT, Germany)

O-3

Detection of recycling muon after muon-catalyzed fusion reaction in solid

hydrogen isotope target

K. Okutsu

(Tohoku U., Japan)

O-4

A new plan to construct a tritium treating place inside an accelerator

facility, J-PARC

H. Natori

(KEK, Japan)

 

17:15-17:35          Break

 

17:35-19:15    Plasma-Material Interactions I

I-6

Experimental study of hydrogen isotope retention and release from irradiated materials using a tritium capable plasma exposure system at the

new H3AT facility

A. Hollingsworth (UKAEA, UK)

I-7

Synergistic effects of bulk/surface helium and irradiation damage on

hydrogen isotope retention behavior in plasma facing materials

F. Sun

(Shizuoka U., Japan)

O-5

Temperature dependence on deuterium retention on damaged tungsten by

deuterium plasma exposure

S. Yamazaki

(Shizuoka U., Japan)

O-6

Tritium release from tungsten with irradiation defects

H. Hirose

(U. Toyama, Japan)



November 4, Wednesday

 

8:50-9:00 Announcements

9:00-11:00      Plasma-Material Interactions II

I-8

Investigation of tritium retention and surface properties on the first wall

of LHD

M. Yajima

(NIFS, Japan)

I-9

Neutral-induced hydrogen isotope permeation and retention in the wall

materials of fusion reactors

H. -S. Zhou

(ASIPP, China)

O-7

Tritium retention on tungsten and stainless steel modified by plasma wall

interactions

K. Tokunaga

(Kyushu U., Japan)

O-8

Evaluation of hydrogen retention behavior for damaged tungsten exposed

to hydrogen plasma at QUEST with high temperature wall

A. Koike

(Shizuoka U., Japan)

O-9

Deuterium plasma driven super permeation through vanadium, tantalum

and niobium

L. Wang

(ASIPP, China)

 

11:00-11:20          Break

 

11:20-12:40    Behaviors in Environment and Biological Effects

O-10

Distributions of tritium in the coastal waters off Aomori and Iwate

prefectures

Y. Shirotani

(MERI, Japan)

O-11

Effect of swellable clay mineral on tritium behavior in tritiated water

percolation into soil

K. Katayama

(Kyushu U.)

O-12

Optimization of internal monitoring programmes for tritium in urine

S. Kinase

(JAEA, Japan)

O-13

Protective behavior of tea catechins on DNA double strand breaks by

radiations with different LET

T. Wada

(Shizuoka U., Japan)

 

12:40-14:00          Lunch

14:00-16:00    Ceramic Breeders and Oxides

I-10

Progress of ceramic breeder materials in China

L. Zhao

(CAEP, China)

I-11

Comparison of tritium release behavior from promising tritium breeding

materials

Q. Qi

(ASIPP, China)

O-14

In-pile irradiation and tritium extraction tests of Li4SiO4 breeder

C. Xiao

(CAEP, China)

O-15

Hydrogen isotopes behavior in oxide materials at high temperatures

M. Khalid Hossain

(Kyushu U., Japan)

O-16

Features of the in-situ experiments on studying of tritium release from lithium materials of fusion reactor breeders using vacuum extraction

method

A. Shaimerdenov (KazNU,

Kazakhstan)

  

 

November 5, Thursday

 

 7:20-7:30              Announcements

 

 7:30-9:30        Material Interactions I

I-12

High-temperature interactions between hydrogen isotopes and graphite

and their relevance to tritium management in high-temperature nuclear reactors

L. Vergari

(UC Berkely, USA)

I-13

Tritium transport in LiAlO2, Zircaloy-4 and stainless steel during neutron irradiation

D. J. Senor

(PNNL, USA)

O-17

TMIST-3 open capsule summary results

W. G. Luscher

(PNNL, USA)

O-18

Molecular dynamics simulations of helium bubble formation in palladium

tritides

X. Zhou

(SNL/CA, USA)

O-19

Thermodynamic and kinetic analysis on thermal desorption of hydrogen

isotopes released from graphite

H. Atsumi

(Kindai U., Japan)

 

9:30-9:50              Break

 

9:50-11:10      Material Interactions II

O-20

Tritium behavior in isotropic graphite

N. Kawamura

(KEK, Japan)

O-21

Deuterium desorption from graphite atomized in deuterium gas

atmosphere

N. Aqiesha

(Kindai U., Japan)

O-22

A preliminary assessment of Ti-Zr-Hf-Mo-Nb high-entropy alloy for

tritium storage

H. H. Shen

(CAEP, China)

O-23

The major trap sites of deuterium in CuCrZr alloy

H. -D. Liu

(ASIPP, China)

 

11:10-12:30          Lunch

12:30-14:00    Fuel Cycle II

I-14

Progresses of D-T fuel cycling for CFETR

H. Wang

(CAEP, China)

O-24

Dynamic and control behavior of cryogenic distillation column for

hydrogen isotope separation in CFETR

X. Wang

(CAEP, China)

O-25

Superhydrophobic and superaerophilic hierarchical Pt@MIL-101/PVDF

composite for hydrogen water isotope exchange reactions

X. Fu

(CAEP, China)

O-26

Engineering study on lithium isotope separation by ion exchange chromatography

T. Suzuki

(Nagaoka U. Tech., Japan)

 

14:40-14:20          Break

14:20-15:40    Permeation

O-27

Hydrogen permeation from the first wall coolant into the vacuum vessel

and its impact on the design of isotope separation system for CFETR

G. Ran

(CAEP, China)

O-28

Tritium permeation behaviors through F82H into pure water at 353 K

T. Otsuka

(Kindai U., Japan)

O-29

Deuterium permeation through reduced activation ferritic steel F82H after

exposure to high pressure water

T. Chikada

(Shizuoka U., Japan)

O-30

The effect of corrosion by liquid lithium-lead on deuterium permeation

through ceramic multi-layer coating

E. Akahoshi

(Shizuoka U., Japan)


November 6, Friday

 

 

7:20-7:30 Announcements

7:30-9:30 Material Interactions III

O-31

MAX phase materials as hydrogen isotope permeation barriers

D. Hitchcock

(SRNL, USA)

O-32

Tritium embrittlement of austenitic stainless-steel tubing at low helium

contents

T. M. Krentz

(SRNL, USA)

O-33

Tritium embrittlement of nickel-based alloys – Initial results

T. M. Krentz

(SRNL, USA)

O-34

The effect of alloying elements on deuterium retention in binary W alloys

after irradiation with high energy Fe ions at elevated temperature

J. Wang

(U. Toyama, Japan)

O-35

Numerical analysis of deuterium migration behaviors in Tungsten

damaged by fast neutron by means of gas absorption method

M. Kobayashi

(NIFS, Japan)

O-36

Influence of He and/or irradiation defects on the plasma driven

permeation behavior in tungsten material

Y. Oya

(Shizuoka U., Japan)

 

9:30-10:00            Break

10:00-11:00 Closing

 

APSOT-3  Poster Presentations

P-1

Dynamic Model of the ITER Vacuum Vessel Pressure Suppression System (VVPSS) and His Hydrogen Mitigation System (HMS) Using

EcosimPro and His Connection with Multiflash

L. Basili

(U. Pisa, Italy)

P-2

SMART_TC®: a R&D Programme on Uses of Artificial Intelligence Techniques for Tritium Control in Hyper-Complex ITER-Like Tritium

Plant Systems

L. Sedano (FUS_ALIAN     Sci.,

Eng. & Consult., Spain)

P-3

Estimation of Tritium Inventory in Exhaust Detritiation System for

Fusion Test Device in the Initial Tritium Recovery Operation

M. Tanaka

(NIFS, Japan)

P-4

Development of Evaluation Method for Oxidation of Tritium in Molecular Hydrogen on Soil Surface

H. Kakiuchi

(Inst.    Environ.     Sci., Japan)

P-5

Development of a Metabolic Model to Estimate Doses from Ingested Organically Bound Tritium Using Metabolic Data of Carbon in Humans

T. Masuda

(Inst.    Environ.            Sci., Japan)

P-6

Isotope and Chemical Composition of Monthly Precipitation Collected

at Sapporo, Northern Part of Japan

N. Akata

(Hirosaki U., Japan)

P-7

Investigation of Atmospheric Tritiated Water Vapor Level in Fukushima

S. Hirao

(Fukushima U., Japan)

P-8

Rate of Double Strand Breaks of Genome-Sized DNA in Tritiated Water

–Dependence  on  Tritium    Concentration, Water Temperature and DNA Concentration–

H. Shimoyachi

(U. Toyama, Japan)

P-9

Integrated Dynamic Modeling of Storage Delivery and Fueling System in ITER

M.-K. Lee

(Pohang       U.                    Sci. Technol.)

P-10

Helium Recovery and Blanketing Effect with Hydriding Reaction of

ZrCo

P.-K. Jung

(ITER Korea, Korea)

P-11

Investigation of Isotopic Exchange Mechanism of Water-Hydrogen System on Hydrophobic Catalysts

V. Moseeva

(D. Mendeleev U. Chem. Technol. Russia, Russia)

P-12

The Effect of Flow Hydrodynamics in LPCE Columns on the Efficiency of Mass Transfer in a Water-Hydrogen System

A. Bukin

(D. Mendeleev U. Chem. Technol. Russia, Russia)

P-13

Optimization of Heat Pump Assisted Water Distillation Column in H2O- HTO Separation

C. Chen

(CAEP, China)

P-14

Performance of a Two-Stage Membrane Reactor for Processing of

Tritiated Water

L. Yue

(CAEP, China)

P-15

Dynamic Simulation Tools for Isotopic Separation System Modelling and Design

E. Iraola

(Inprocess Technol. & Consulting Gr., Spain)

P-16

Effect of Counter Cation on Chromatographic Fractionation of Lithium Isotope in Aqueous Solution

Y. Tachibana

(Nagaoka U. Technol., Japan)

P-17

Development of Precious Metal Catalyst for Tokamak Exhaust

Processing

Y. Edao

(QST, Japan)

P-18

Isotope Effect in Proton Conductivity of Gadolinium Oxide

M. Khalid Hossain

(Kyushu U., Japan)

P-19

Tritium Release Property of Li2TiO3-Li4SiO4 Biphasic Ceramics

M. Yang

(CAEP, China)

P-20

Determination of the Parameters of Tritium Release Processes from Lithium Ceramics during Experiments at the WWR-K Reactor

I. Kenzhina

(Inst.             Nucl.   Phys., Kazakhstan)

P-21

Modeling of Hydrogen Isotopes Release during In-Situ Experiments

Using Vacuum Extraction Method

T. Kulsartov

(KazNU, Kazakhstan)

P-22

Influence of Chemical Form of Bred Tritium in the Blanket on Tritium

Dynamics in Fuel Cycle System of Fusion Reactors

R. Oyama

(Kyushu U., Japan)

P-23

Effects of Irradiation Temperature on Tritium Retention in SS316L

M. Matsuyama

(U. Toyama, Japan)

P-24

Feasibility Study on Tritium Recoil Barrier for Neutron Reflectors of

Research and Test Reactors

E. Ishitsuka

(JAEA, Japan)

P-25

Modeling of Hydrogen Permeation Behavior through Tungsten Deposition Layer Growing on Nickel Substrate by Hydrogen Plasma

Sputtering

Y. Hara

(Kyushu U., Japan)

P-26

Retention Characteristics of Hydrogen in Pure Aluminum and

Aluminum Alloys with Cold-Working

M. Inoue

(Kindai U., Japan)

P-27

Investigation of Depth Profiles of Remaining Tritium Using a Sputtering

Treatment in Plasma Facing Components in LHD

S. Masuzaki

(NIFS, Japan)

P-28

Withdrawn

 

P-29

Time Evolution Calculation of Muon-Catalyzed Fusion in Deuterium-

Tritium Mixture

T. Yamashita

(Tohoku U., Japan)

P-30

On-Line Micro GC Testing of Protium in D-T from TCAP Products

W. Wang

(CAEP, China)

P-31

Multiple   Pass    Enhanced   Raman  Spectroscopy   for   Long‐Term

Monitoring of Hydrogen Isotopologues

C. Wen

(CAEP, China)

P-32

Monte Carlo Simulation of Beta-Ray Induced X-ray Spectra Caused by

Tritium in Various Depths in Solids

M. Hara

(U. Toyama, Japan)

P-33

Availability of Simple Sampler Using a Brass Bar for Gaseous Tritiated

Water Measurements

M. Nakayama

(U. Toyama, Japan)

P-34

Tritium Depth Profiling by Marker Layers

Marco Röllig

(Karlsruhe Inst. Techol., Germany)

P-35

Development of a Real-Time Process Gas Analysis System Using a

Semiconductor Laser

S. O’hira

(QST, Japan)

P-36

Working Environment of Tritium Analysis for Photo-Luminescence Control

T. Yasumatsu

(Tokyo Power Technol., Japan)

 


Technical Tour

A. L. M. T. Corp, Toyama Factory
This company is one of the biggest manufacturers of refractory metals including tungsten and providing divertor monoblocks to ITER. The tour will be held in the afternoon, November 6, 2020, Friday.
The number of participants is limited to be 30 or less. Please apply via e-mail to apsot20@ctg.u- toyama.ac.jp. The message title should be started with "APSOT-3 technical tour". Participants will be selected on the first-come-first-served basis. We cannot accept an employee of a competing company.