Program of Vietnam/Japan Research/HRD Forum on Nuclear Technology-I
Place of Forum:702 Meeting room, Ta Quang Buu Library, Hanoi University of Science and TechnologyTimeTitle

Name

MC/Responsible

Opening Remark

Masaki Saito

V: Tran Ngoc Toan (Vinatom)

Opening Remark

Tran Chi Thanh

J:Murata(Hitachi)

Opening Remark

Le Dinh Tien

Photograph-December 23(Monday), 2013

～8:30
8:30～9:00
8:30～8:40
8:40～8:50
8:50～8:55
8:55～9:00
9:00～11:20
9:00～9:35
9:35～10:10
8:00

Registration
Opening Ceremony

First session（Review paper）

Nuclear Safety Research in Japan

History and perspectives -Research on Severe Accidents at Nuclear Power Safety Division (NPS), RoyalJun Sugimoto

V: Le Van Hong (Vinatom)

Tran Chi Thanh

J:Kikura(Tokyo-Tech)Institute of Technology (KTH), Sweden

Thermal Hydraulic Research and Design in BWR～
10:45～11:20 Thermal Hydraulics Safety Research for NPPs in Vietnam
11:20～12:30 Working Lunch hosted by VINATOM
12:30～14:00 Second session (Poster session)
10:10 10:45

Development of focusing sensors for Air-coupled Utrasonic Flowmeter

Kumiaki Moriya
Le Dai DienKeisuke TSUKADA ,J:Saito,Ogawa,Moriya
V: Tran Chi Thanh, Ha ManhThu, Tran Kim Tuan

Numerical and Experimental Investigation of Chaotic Flow in a Cubic Joule-heatedThanh Tung DUONG

Glass Melter

J:Saito,Ogawa,Akimoto
V:Tran Chi Thanh, Ha ManhThu, Nguyen Minh Tuan

High-temperature chemical degradation of Basalt aggregates

Kentaro Ishizu

J*Sugimoto,Kikura,Yoshimoto
V:Nguyen Phu Khanh, Le Dai1

Program of Vietnam/Japan Research/HRD Forum on Nuclear Technology-I
Place of Forum:702 Meeting room, Ta Quang Buu Library, Hanoi University of Science and TechnologyDien, Nguyen Minh Tuan
Experimental Study of Stress Intensity Factor of the Intergranular Stress Corrosion

Masataka Hiruta

Cracking of Sensitized SUS304 Utilizing Fretting Corrosion

J:Sugimoto,Kikura,Tatsumi
V: Le Van Hong, Nguyen Phu
Khanh, Le Dai Dien

Natural hazard assessment of Ninh Thuan nuclear power plant based on the IAEA
safety standards

Vu Manh Kha

J:Akimoto,Moriya,Arai
V: Le Van Hong, Hoang Minh
Giang, Nguyen Viet Hung

Study of annular two-phase flow on nuclear fuel-rod bundle by using high-speed

Son Hong Phamcamera technique

J:Akimoto,Moriya,Kikura
V:HoangNguyen

MinhPhuGiang,Khanh,HaManh Thu
INVESTIGATION OF TEMPERETURE STRATIFICATION IN COLD LEG AND

Trần Văn Trung

DOWNCOMER IN LSTF/ROSA EXPERIMENT

J:Arai,Tatsui,Sugimoto
J: Tran Chi Thanh, Hoang
Minh Giang, Tran Kim Tuan

Calculating amount of hydrogen gas will be generated in a boiling water reactor when

Doan Manh Longthe SBO (Station Black Out) accident happens by using MELCOR.

～Third session（CFD）
Yuuichiro Yoshimoto
14:00～14:35 CFD Application in BWR Reactor System Design
14:35～15:10 Analysis of void behavior in Transient Boiling Experiments simulating BWR RIA Nguyen Minh Tuan

J:Arai,Tatsumi, Saito,
V: Le Dai Dien, Nguyen VietHung, Nguyen Minh Tuan

14:00 17:45

conditions by using the code TRAC-BF1

Two-Phase flow analysis code development for light water reactor
Hajime Akimoto～
15:45～16:00 Tea Break
16:00～16:35 SAFETY ANALYSIS FOR WORKING CORE OF THE DALAT NUCLEAR Nguyen Kien Cuong

V:Hoang

MinhGiang

Phu

Khanh(Vinatom)
J:Arai(Toshiba)

15:10 15:45

RESEARCH REACTOR USING LOW ENRICHED URANIUM FUEL

V:Nguyen(HUST)

2Program of Vietnam/Japan Research/HRD Forum on Nuclear Technology-I
Place of Forum:702 Meeting room, Ta Quang Buu Library, Hanoi University of Science and Technology～

16:35 17:10

Computational Fluid Dynamics Models for Boiling Flows in Nuclear Reactor Fuel

Nguyen Van Thai

J:Sugimoto(Kyoto)

Assemblies

STUDY ON PWR SUBCHANNEL VOID DISTRIBUTION BENCHMARK S1-PSBT～
18:00～20:00 Reception hosted by VINATOM
17:10 17:45

Hoang Minh Giang

December 24(Tuesday), 2013

～9:05
9:05～9:40
8:30

9:40

～10：15～
10:35～15:40
10:35～11:10
10:15 10:35

11:10～11:45～12:20
12:20～13:20
13:20～13:55
13:55～14:30
14:30～15:05
11:45

Forth session (Severe accident)
Melting attack of solid plates by a high-temperature liquid jet

Masaki Saito

V: Nguyen Viet Hung (HUST)The Effective Convectivity Model (ECM) and its Application to Analysis of Severe

Tran Chi Thanh

J:Ogawa(Nagaoka-Tech)Accidents
Simulation of FOREVER experiment with the ANSYS software for nuclear safety inLe Anh Tuansevere accident scenario
Tea Break
Fifth session (Experiment, Education, etc)
Contributions to severe accident chemistry :Education program on fundamental

Toru Ogawa

research

V: Tran Chi Thanh (Vinatom)
J:Akimoto(JAEA)LWR Thermal-Hydraulic Research in Japanese Nuclear Industry -Kenji

AraiFocusing on Experimental Research Advanced Flow Measurements for Thermal-Hydraulic Studies on LWRs

Hiroshige Kikura

Lunch Break hosted by Japan
Establishment of Evaluation Method for Heterogeneous External Boron Dilution

Eisaku Tatsumi

V: Le Dai Dien (Vinatom)

Design and construction of a PWR testing facility (Part I.)

Trinh Huu Toan

J:Moriya(Hitachi)

Development of Standardized and Consolidated Reference Experimental Database

Nguyen Hoang Anh(SCRED) for Code Assessment and Uncertainty Evaluation And application in LOFT

～15:05 16:30

facilityClosingsession

3

Program of Vietnam/Japan Research/HRD Forum on Nuclear Technology-I
Place of Forum:702 Meeting room, Ta Quang Buu Library, Hanoi University of Science and Technology～
15:30～15:55
15:55～16:15
16:15～16:20
17:00～19:00
15:05 15:30

Summarized by Vietnam

Tran Chi Thanh

V: Tran Ngoc Toan (Vinatom)

Summarized by Japan

Masaki Saito

J:Yamamoto(Toshiba)Awards

Saito/Thanh

Conclusive remark

TBD

Reception hosted by JapanV: Hoang Sy Than (Vinatom)
J:Saito(MHI)

4