*Koji Tasaka¹, Koji Shirai¹, Junghoon Ji¹, Toshiko Udagawa², Shigeru Yamada³ (1. Central Research Institute of Electric Power Industry, 2. WDB Co., Ltd., 3. Fujita Corporation )

11:05 AM - 11:20 AM

[2P07] Application of a fire zone model for compartment fires under mechanically ventilated conditions

-(2) Prediction on fire behavior under multi-fire sources using BRI2002-

*Junghoon Ji¹, Koji Tasaka¹, Koji Shirai¹, Toshiko Udagawa², Shigeru Yamada³ (1. Central Research Institute of Electric Power Industry, 2. WDB Co., Ltd., 3. FUJITA CORPORATION)

11:20 AM - 11:35 AM

[2P08] Development of Methodology for Fire Propagation and Effect Analysis

(4) Fire Effect Analysis for Multi-room Compartments Using FDS

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

11:35 AM - 11:50 AM

[2P09] Internal Arc Tests with High Voltage Electrical Cabinets for Emergency Diesel Generator

*KOJI SHIRAI¹, TSUKASA MIYAGI¹, KOJI TASAKA¹, JUNGHOON JI¹, MIKIMASA IWATA¹ (1. Central Research Institute of Electric Power Industry)

Time reserved for Chair （11:50 AM - 12:00 PM）

Oral presentation

[2P10-17] Spent Fuel Pool

Thu. Sep 6, 2018 2:45 PM - 4:55 PM Room P (E21 -E Building)

Chair:Yamato Hayashi(TOSHIBA ESS)

+Add all to schedule

2:45 PM - 3:00 PM

[2P10] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(20) Overview

*Yoshiyuki Kaji¹, Yoshiyuki Nemoto¹, Taku Nagatake¹, Hiroyuki Yoshida¹, Masayuki Tojo², Daisuke Goto², Satoshi Nishimura³, Hiroaki Suzuki⁴, Masaaki Yamato⁵ (1. JAEA, 2. GNF-J, 3. CRIEPI, 4. IAE, 5. MHI)

3:00 PM - 3:15 PM

[2P11] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(21) Investigation of cladding oxidation model

*Yoshiyuki Nemoto¹, Takashi Onizawa¹, Yoshiyuki Kaji¹, Kazuo Nakashima², Toru Kanazawa², Masayuki Tojo² (1. Japan Atomic Energy Agency, 2. Global Nuclear Fuel - Japan)

3:15 PM - 3:30 PM

[2P12] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(22) Acquisition of Validation Data by 4x4 Simulated Fuel Bundle

*Taku Nagatake¹, Mitsuhiko Shibata¹, Hiroyuki Yoshida¹, Yoshiyuki Nemoto¹, Yoshiyuki Kaji¹ (1. Japan Atomic Energy Agency)

3:30 PM - 3:45 PM

[2P13] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(23) CFD analysis for the loss of coolant accident in SFP with Zircaroy cladding oxidation model

*Masayuki Tojo¹, Toru Kanazawa¹, Kazuo Nakashima¹, Kensuke Kobayashi¹, Daisuke Goto¹, Yoshiyuki Nemoto², Yoshiyuki Kaji² (1. GNF-J, 2. JAEA)

3:45 PM - 4:00 PM

[2P14] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(24) Create a data base of BWR fuel temperature in SFP based on the steady-state heat transfer analyses

*Daisuke Goto¹, Kensuke Kobayashi¹, Masayuki Tojo¹, Yoshiyuki Nemoto², Yoshiyuki Kaji² (1. GNF-J, 2. JAEA)

4:00 PM - 4:15 PM

[2P15] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(25) Experiment and analysis of the water level mismatch between in and out of CB of BWR fuel under Loss of Cooling System

*Kensuke Kobayashi¹, Daisuke Goto¹, Masayuki Tojo¹, Yoshiyuki Nemoto², Yoshiyuki Kaji² (1. GNF-J, 2. JAEA)

4:15 PM - 4:30 PM

[2P16] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(26) Characteristics Evaluation of Fuel Cladding Oxidation Model with MAAP Code

*Satoshi Nishimura¹, Masaaki Satake¹, Yoshihisa Nishi¹, Yoshiyuki Kaji², Yoshiyuki Nemoto² (1. CRIEPI, 2. JAEA)

4:30 PM - 4:45 PM

[2P17] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(27) Improvement of SAMPSON code and evaluation of cooling characteristics of SFP spray

*Hiroaki Suzuki¹, Yoshihiro Morita¹, Masanori Naitoh¹, Yoshiyuki Nemoto², Yoshiyuki Kaji² (1. IAE, 2. JAEA)

Time reserved for Chair （4:45 PM - 4:55 PM）

Oral presentation

[2P18-21] Source Term

Thu. Sep 6, 2018 4:55 PM - 6:00 PM Room P (E21 -E Building)

Chair:Hidetoshi Karasawa(IAE)

+Add all to schedule

4:55 PM - 5:10 PM

[2P18] Development of source term analysis methodology considering FP chemistry

*Jun Ishikawa¹, Xiaoyu Zheng¹, Hiroyuki Shiotsu¹, Tomoyuki Sugiyama¹ (1. JAEA)

5:10 PM - 5:25 PM

[2P19] Effects of Boron on the chemical behavior of Cesium and Iodine in the Reactor Coolant System condition during LWR severe accident

(1) Evaluation of chemical bahavior of cesium iodide under steam condition

*Naoya Miyahara¹, Shuhei Miwa¹, Melany Gouello², Masahiko Osaka¹ (1. JAEA, 2. VTT)

5:25 PM - 5:40 PM

[2P20] Effects of Boron on the chemical behavior of Cesium and Iodine in the Reactor Coolant System condition during LWR severe accident

(2) Effects of Boron vapor species on chemical behavior of deposited Cesium Iodide.

*Junpei Imoto¹, Shuhei Miwa¹, Melany Gouello², Naoya Miyahara¹, Masahiko Osaka¹ (1. JAEA, 2. VTT)

5:40 PM - 5:55 PM

[2P21] Effects of Boron on the gaseous chemical reaction of Cesium and Iodine in Reactor Coolant System conditions during a severe accident

*Shuhei Miwa¹, Hiroyuki Shiotsu¹, Masahiko Osaka¹, Tomoyuki Sugiyama¹, Yu Maruyama¹ (1. JAEA)

Time reserved for Chair （5:55 PM - 6:00 PM）

Oral presentation

[3P01-04] Fast Reactor

Fri. Sep 7, 2018 9:30 AM - 10:35 AM Room P (E21 -E Building)

Chair:Kei Ito(Kyoto Univ.)

+Add all to schedule

9:30 AM - 9:45 AM

[3P01] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(10) Development of Eutectic Reaction Model for Use in Reactor Safety Analysis Code

*Xiaoxing Liu¹, Koji Morita¹, Hidemasa Yamano² (1. Kyushu University, 2. Japan Atomic Energy Agency)

9:45 AM - 10:00 AM

[3P02] A visualization test for fragmentation behavior of molten stainless steel discharged into a sodium pool

*Yuki Emura¹, Mikio Isozaki¹, Ken-ichi Matsuba¹, Kenji Kamiyama¹ (1. JAEA)

10:00 AM - 10:15 AM

[3P03] Studies on Relocation Behavior of Molten Core Materials in the Core Disruptive Accident of Sodium-cooled Fast Reactors

(6) A Modelling of the Tip of a Heavy Metal Jet with MPS Method

*Mamoru Konomoura¹, Kenji Kamiyama² (1. Univ. of Fukui, 2. JAEA)

10:15 AM - 10:30 AM

[3P04] Study on the discharge behavior of molten core materials through the control rod guide tube in the core disruptive accident of SFR

*Shinya Kato¹, Kenichi Matsuba¹, Kenji Kamiyama¹, Vladimir Zuev², Dmitry Ganovichev², Viktor Baklanov² (1. JAEA, 2. NNC)

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

Oral presentation

[3P05-07] LWR Performance during Accident

Fri. Sep 7, 2018 10:35 AM - 11:25 AM Room P (E21 -E Building)

Chair:Kenji Kamiyama(JAEA)

+Add all to schedule

10:35 AM - 10:50 AM

[3P05] Evaluation of Molten Core Coolability in Containment Vessel using JASMINE code

*Yuzuru Iwasawa¹, Toshinori Matsumoto¹, Ryuhei Kawabe¹, Kohei Ajima¹, Tomoyuki Sugiyama¹, Yu Maruyama¹ (1. JAEA)

10:50 AM - 11:05 AM

[3P06] Study of downstream effect of the sump screen for post LOCA long term core cooling

(1)最適評価コードによる炉心流路閉塞時の熱流動解析

*Tetsuya Teramae¹, Ryo Fukuda¹, Tomokazu Aoyagi², Toshihiko Nakano³, Takeshi Nishikawa³ (1. Mitsubishi Heavy Industries, Ltd., 2. MHI Nuclear Systems And Solution Engineering Co., Ltd., 3. Kansai Electric Power Co.,Inc.)

11:05 AM - 11:20 AM

[3P07] Study of downstream effect of the sump screen for post LOCA long term core cooling

(2)炉心への冷却材供給流路に関する要素試験

*Tomoaki Ogata¹, Takei Rei¹, Nishida Keigo¹, Sakata Hideyuki¹, Kurimura Chikara¹, Fukuda Ryo¹ (1. Mitubishi Heavy Industries)

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

Oral presentation

[3P08-09] Prevention of Nuclear Disaster

Fri. Sep 7, 2018 11:25 AM - 12:00 PM Room P (E21 -E Building)

Chair:Tomohiko Ikegawa(Hitachi)

+Add all to schedule

11:25 AM - 11:40 AM

[3P08] A System Development for Enhancing Nuclear Emergency Response and Preparedness

*Shinnosuke Masuda¹, Kazuma Abe¹, Kazumasa Inomata¹, Yoshihiro Matsuto¹, Daisuke Sato¹ (1. Tohoku Electric Power Co., Inc.)

11:40 AM - 11:55 AM

[3P09] Effectiveness of the association between the containment vessel failure time and the evacuation time in nuclear disaster emergency preparedness

*KAZUFUMI NAGASHIMA¹, Nakahiro Yasuda¹ (1. Research Institute of Nuclear Engineeing, Fukui University)

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

Oral presentation

[3P10-11] Fukushima Daiichi NPP Accident

Fri. Sep 7, 2018 2:45 PM - 3:15 PM Room P (E21 -E Building)

Chair:Masao Chaki(IAE)

+Add all to schedule

2:45 PM - 3:00 PM

[3P10] Analysis of core temperature increase behavior in Fukushima Daiichi NPP Unit 2 by RELAP/SCDAPSIM

*Shinji Yoshikawa¹, Ikken Sato¹ (1. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[3P11] ^{Cause study of Fukushima accident - The closed exhaust towers resolve 14 unexplained phenomena}

The exhaust towers turns into a huge snow machine

*Haruo Morishige¹, Yosuke Yamashiki¹, Makito Watakabe¹, Yasufumi Kitamura¹ (1. Fukushima Nuclear Accident Countermeasures Review Group)

Sessions

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

[2P01-05] Safety Evaluation of LWR 1

[2P06-09] Safety Evaluation of LWR 2

-(1) Prediction on Fire Behavior using BRI2002 with Fan Curve Model-

-(2) Prediction on fire behavior under multi-fire sources using BRI2002-

(4) Fire Effect Analysis for Multi-room Compartments Using FDS

[2P10-17] Spent Fuel Pool

(20) Overview

(21) Investigation of cladding oxidation model

(22) Acquisition of Validation Data by 4x4 Simulated Fuel Bundle

(23) CFD analysis for the loss of coolant accident in SFP with Zircaroy cladding oxidation model

(24) Create a data base of BWR fuel temperature in SFP based on the steady-state heat transfer analyses

(25) Experiment and analysis of the water level mismatch between in and out of CB of BWR fuel under Loss of Cooling System

(26) Characteristics Evaluation of Fuel Cladding Oxidation Model with MAAP Code

(27) Improvement of SAMPSON code and evaluation of cooling characteristics of SFP spray

[2P18-21] Source Term

(1) Evaluation of chemical bahavior of cesium iodide under steam condition

(2) Effects of Boron vapor species on chemical behavior of deposited Cesium Iodide.

[3P01-04] Fast Reactor

(10) Development of Eutectic Reaction Model for Use in Reactor Safety Analysis Code

(6) A Modelling of the Tip of a Heavy Metal Jet with MPS Method

[3P05-07] LWR Performance during Accident

(1)最適評価コードによる炉心流路閉塞時の熱流動解析

(2)炉心への冷却材供給流路に関する要素試験

[3P08-09] Prevention of Nuclear Disaster

[3P10-11] Fukushima Daiichi NPP Accident

The exhaust towers turns into a huge snow machine

Authentication