Oral presentation

[2L12-14] Development of Evaluation Methodology

Thu. Mar 21, 2019 4:10 PM - 5:00 PM Room L (Common Education Bildg. 2 3F No.36)

Chair:Kenta Murakami(Nagaoka Univ. of Tech.)

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4:10 PM - 4:25 PM

[2L12] Development of Methodology for Fire Propagation and Effect Analysis

(5) Investigation of Analysis Model for Cable Tray Fire Using FDS

*Takaki Kato¹, Fumio Kasahara¹, Hajime Kabashima¹ (1. The Secretariat of the Nuclear Regulation)

4:25 PM - 4:40 PM

[2L13] Examination of measurement method of the hardness by Laser Induced Breakdown Spectroscopy (LIBS)

*Koudai Okazaki¹, Tomohiko Kawakami¹, Yuta Abe², Masahiko Ohtaka² (1. Kaken, 2. JAEA)

4:40 PM - 4:55 PM

[2L14] Investigation of mechanical characterization method with miniature specimen

*Yoshiyuki Kawaharada¹, satoshi miyashiro², Yuji Kitsunai¹, masato koshiishi¹, shigeaki tanaka², ryoji obata³, tetsuya toyota³ (1. NIPPON NUCLEAR FUEL DEVELOPMENT CO., 2. Toshiba Energy Systems & Solutions Corporation, 3. Hitachi-GE Nuclear Energy, Ltd.)

Time reserved for Chair （4:55 PM - 5:00 PM）

Oral presentation

[3L01-04] Fast Reactor

Fri. Mar 22, 2019 9:30 AM - 10:35 AM Room L (Common Education Bildg. 2 3F No.36)

Chair:Kennichi Matsuba(JAEA)

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9:30 AM - 9:45 AM

[3L01] Study on validation of initiating phase analysis code for core disruptive accident in an SFR

*Shinya Ishida¹, Kenichi Kawada¹, Yoshitaka Fukano¹ (1. JAEA)

9:45 AM - 10:00 AM

[3L02] Solidification behavior of molten materials falling into coolant

*Kota Kawasaki¹, shimpei Saito¹, Akiko Kaneko¹, Yutaka Abe¹, Kazuya Koyama² (1. University of Tsukuba, 2. Mitsubishi FBR Systems)

10:00 AM - 10:15 AM

[3L03] Three-Dimensional Particle-Based Simulation of Heat Transfer Behavior from Molten Mixture Pool to Structural Wall

*Kanji Funakoshi¹, Masatsugu Kato¹, Xiaoxing Liu¹, Wei Liu¹, Koji Morita¹, Kenji Kamiyama² (1. Kyushu Univ., 2. JAEA)

10:15 AM - 10:30 AM

[3L04] Development of Fast Reactor Containment Safety Analysis Code, CONTAIN-LMR

Validation Study of Sodium-concrete Reaction Model

*Munemichi Kawaguchi¹, Ikuo Yamamoto¹, Hiroshi Seino¹ (1. JAEA)

Time reserved for Chair （10:30 AM - 10:35 AM）

Oral presentation

[3L05-07] Severe Accident

Fri. Mar 22, 2019 10:35 AM - 11:25 AM Room L (Common Education Bildg. 2 3F No.36)

Chair:Shunichiro Nishioka(IRID/JAEA)

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10:35 AM - 10:50 AM

[3L05] Fundamental Study on the solidification morphology and segregation of Gd and Fe in simulated molten corium

*Ayako Sudo¹, Igor Poznyak², Takumi Sato¹, Yuji Nagae¹, Masaki Kurata¹ (1. JAEA, 2. Research Centre Rez)

10:50 AM - 11:05 AM

[3L06] Chemical equilibrium analysis for the enhancement of gaseous Iodine generation under the Boron-containing steam

*Hiroyuki Shiotsu¹, Shuhei Miwa¹, Masahiko Ohsaka¹, Tomoyuki Sugiyama¹, Yu Maruyama¹ (1. JAEA)

11:05 AM - 11:20 AM

[3L07] Development of Ru chemistry database under severe accident conditions of nuclear facilities

*Naoya Miyahara¹, Shuhei Miwa¹, Faoulat Miradji¹, Jiazhan Liu¹, Naoki Horiguchi¹, Masahiko Osaka¹ (1. JAEA)

Time reserved for Chair （11:20 AM - 11:25 AM）

Oral presentation

[3L08-09] ATWS

Fri. Mar 22, 2019 11:25 AM - 12:00 PM Room L (Common Education Bildg. 2 3F No.36)

Chair:Satoshi Takeda(Osaka Univ.)

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11:25 AM - 11:40 AM

[3L08] ATWS analyses with reactor simulator based on RELAP/SCDAPSIM code.

Application to precise nuclear properties computed with MVP-BURN code

*Ryo Kikuchi¹, Takanori Kameyama¹ (1. tokai Univ.)

11:40 AM - 11:55 AM

[3L09] Analysis and Evaluation for ATWS Event by RELAP5-3D

*Chihiro Yanagi¹ (1. INSS)

Time reserved for Chair （11:55 AM - 12:00 PM）

Oral presentation

[3L10-14] Safety Analysis

Fri. Mar 22, 2019 2:45 PM - 4:10 PM Room L (Common Education Bildg. 2 3F No.36)

Chair:Akifumi Yamaji(Waseda Univ.)

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2:45 PM - 3:00 PM

[3L10] Reduced Order Model of Severe Accident Analysis Code for SBO aiming Probabilistic Safety Margin Analysis

Development of an efficient data sampling method for ROM construction

*Masaki Matsushita¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya University)

3:00 PM - 3:15 PM

[3L11] Development of Next Generation Transient Analysis System for Nuclear Power Plant

Development of Procedure to Couple among Codes

*Sho Yoshizaki¹, Mitsunobu Hayashi¹, Akinori Kamito¹, Kenya Takiwaki¹ (1. Toshiba Energy Systems & Solutions Coporation)

3:15 PM - 3:30 PM

[3L12] Development of estimation measure for BWR LOCA break condition using machine learning technology

*Daisuke Fujiwara¹, Hiroshi Shirai¹, Ryunosuke Yamaguchi¹ (1. TEPSYS)

3:30 PM - 3:45 PM

[3L13] Analysis of BWR Containment Behavior under Severe Accidents Using GOTHIC

(4)Analysis of Primary Containment Vessel Spray

*Hiroshi Kawai¹, Tatsuya Hayasaki¹, Daisuke Fujiwara¹ (1. TEPCO SYSTEMS CORPORATION)

3:45 PM - 4:00 PM

[3L14] IC was no operation between earthquake and tunami in F1 No.1 Reactor

Observation of the Simulation of F1- No.1 Reactor by TEPCO

*Kiyoshi Yoneyama¹, Kazuo Watanabe² (1. H.O.Yoneyama, 2. WNR-Cx Watanabe Lab.)

Time reserved for Chair （4:00 PM - 4:10 PM）

Sessions

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[2L12-14] Development of Evaluation Methodology

[2L12] Development of Methodology for Fire Propagation and Effect Analysis

(5) Investigation of Analysis Model for Cable Tray Fire Using FDS

[2L13] Examination of measurement method of the hardness by Laser Induced Breakdown Spectroscopy (LIBS)

[2L14] Investigation of mechanical characterization method with miniature specimen

[3L01-04] Fast Reactor

[3L01] Study on validation of initiating phase analysis code for core disruptive accident in an SFR

[3L02] Solidification behavior of molten materials falling into coolant

[3L03] Three-Dimensional Particle-Based Simulation of Heat Transfer Behavior from Molten Mixture Pool to Structural Wall

[3L04] Development of Fast Reactor Containment Safety Analysis Code, CONTAIN-LMR

Validation Study of Sodium-concrete Reaction Model

[3L05-07] Severe Accident

[3L05] Fundamental Study on the solidification morphology and segregation of Gd and Fe in simulated molten corium

[3L06] Chemical equilibrium analysis for the enhancement of gaseous Iodine generation under the Boron-containing steam

[3L07] Development of Ru chemistry database under severe accident conditions of nuclear facilities

[3L08-09] ATWS

[3L08] ATWS analyses with reactor simulator based on RELAP/SCDAPSIM code.

Application to precise nuclear properties computed with MVP-BURN code

[3L09] Analysis and Evaluation for ATWS Event by RELAP5-3D

[3L10-14] Safety Analysis

[3L10] Reduced Order Model of Severe Accident Analysis Code for SBO aiming Probabilistic Safety Margin Analysis

Development of an efficient data sampling method for ROM construction

[3L11] Development of Next Generation Transient Analysis System for Nuclear Power Plant

Development of Procedure to Couple among Codes

[3L12] Development of estimation measure for BWR LOCA break condition using machine learning technology

[3L13] Analysis of BWR Containment Behavior under Severe Accidents Using GOTHIC

(4)Analysis of Primary Containment Vessel Spray

[3L14] IC was no operation between earthquake and tunami in F1 No.1 Reactor

Observation of the Simulation of F1- No.1 Reactor by TEPCO

Authentication