Oral presentation

[2K06-08] SA Analysis

Thu. Sep 17, 2020 2:45 PM - 3:40 PM Room K (Zoom room 11)

Chair:Tadashi Fujii(Hitachi-GE)

2:45 PM - 3:00 PM

[2K06] Study on improvement of MAAP heat exchanger model using API function

*MINGXI WEI¹, Daisuke Fujiwara¹, Seiichirou Nakatubo ¹ (1. TEPSYS)

3:00 PM - 3:15 PM

[2K07] Modeling of safety equipment based on Fukushima Daiichi accident in MAAP (Part 2)

*Takayoshi Kusunoki¹, Toshiya Takaki¹, Naoki Sano¹, Akira Nakamura¹ (1. INSS)

3:15 PM - 3:30 PM

[2K08] Study of downstream effect of the sump screen for post LOCA long term core cooling

(4)Fuel assemblies test of flow path feeding coolant at the core inlet

*Kei Higashi¹, Tomoaki Ogata¹, Ryo Fukuda¹, Hideyuki Sakata¹, Yugen Shiratsuchi³, Toshihiko Nakano² (1. MHI, 2. KEPCO, 3. NSE)

Time reserved for Chair （3:30 PM - 3:40 PM）

Oral presentation

[2K09-13] Molten Core Behavior, Mitigation of FCI/MCCI

Thu. Sep 17, 2020 3:40 PM - 5:05 PM Room K (Zoom room 11)

Chair:Kenji Kamiyama(JAEA)

3:40 PM - 3:55 PM

[2K09] Numerical Analysis of melt spreading behavior by MELTSPREAD code

(2)Sensitivity analyses

*Kazuyuki Katsuragi¹, Hiroshi Goda¹, Naoya Hayashi¹, Kenichiro Ueda¹ (1. MHI)

3:55 PM - 4:10 PM

[2K10] Study on mitigation measures for steam explosions

*Tadashi Fujii¹, Keisuke Kurihara¹, Kiyofumi Moriyama² (1. HGNE, 2. Masaki Tech LLC.)

4:10 PM - 4:25 PM

[2K11] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(7)Spreading experiment of molten core with sacrificial material

*Hiroshi Goda¹, Satoru Kamohara¹, Junichi Takeuchi¹, Taro Toda¹ (1. Mitsubishi Heavy Industries)

4:25 PM - 4:40 PM

[2K12] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(8)CFD Calculation of the molten core spreading experiment

*Nobuhide Hara¹, Takuo Oda¹, Keisuke Yoshida¹, Hironori Noguchi¹, Koichi Tanimoto¹, Hiroshi Goda¹, Junichi Takeuchi¹, Naoya Hayashi¹ (1. MHI)

4:40 PM - 4:55 PM

[2K13] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(9)Evaluation of effectiveness of the sacrificial material for application to the nuclear power plants

*Naoya Hayashi¹, Junichi Takeuchi¹, Hiroshi goda¹, Nobuhide Hara¹, Taro Toda¹ (1. MHI)

Time reserved for Chair （4:55 PM - 5:05 PM）

Oral presentation

[2K14-18] Risk Analysis, Metal Material Models

Thu. Sep 17, 2020 5:05 PM - 6:30 PM Room K (Zoom room 11)

Chair:Hidemasa Yamano Yamano(JAEA)

5:05 PM - 5:20 PM

[2K14] System Risk Analysis on Primary Containment Vessel Venting focusing on Interactions among Organizations

*Naoki HIROKAWA Hirokawa¹, Akira Yamaguchi¹, Takashi Takata¹, Sunghyon Jang¹ (1. Univ. of Tokyo)

5:20 PM - 5:35 PM

[2K15] Trial evaluation on the improved human reliability analysis for internal event PRA at Rokkasho Reprocessing Plant

*Masahiro Yamamoto¹, Kazumi Takebe¹, Hiroki Haga¹, Kazuya Kishimoto², Yoshinobu Mizuno³, Takashi Kodama¹, Satoru Hayami¹ (1. JNFL, 2. MHI, 3. MHI NSE)

5:35 PM - 5:50 PM

[2K16] Study on Quantitative Impact Analyses of Vector-valued Fragility Curves’ Variation on System Failure Probability

*Masato NAKAJIMA¹ (1. CRIEPI)

5:50 PM - 6:05 PM

[2K17] Material models for high strength wire mesh under biaxial stresses

*KOSUKE NAMBA¹, YUKI HYODO² (1. CRIEPI, 2. Terraservice)

6:05 PM - 6:20 PM

[2K18] Review of Method for Estimating Most Probable Power Distribution in BWRs by Least Squares Method Using In-core Measurements (1)

*hideo ezure¹ (1. NAIS)

Time reserved for Chair （6:20 PM - 6:30 PM）

Oral presentation

[3K01-02] FP/Aerosol Behavior

Fri. Sep 18, 2020 11:15 AM - 12:00 PM Room K (Zoom room 11)

Chair:Hidetoshi Karasawa(JAEA)

11:15 AM - 11:30 AM

[3K01] Analytical study on removal mechanisms of cesium aerosol from noble gas bubble in sodium pool

(2)Effects of particle size distribution and coagulation in aerosols

*Shinya Miyahara¹ (1. Research Institute of Nuclear Engineering, University of Fukui)

11:30 AM - 11:45 AM

[3K02] Effects of boron on cesium and iodine chemistry in a severe accident

*Shuhei Miwa¹, Eriko Suzuki¹, Hiroyuki Shiotsu¹, Tomoyuki Sugiyama¹, Masahiko Osaka¹ (1. JAEA)

Time reserved for Chair （11:45 AM - 12:00 PM）

Oral presentation

[3K03-08] Sodium-Cooled Fast Reactors 1

Fri. Sep 18, 2020 2:45 PM - 4:25 PM Room K (Zoom room 11)

Chair:SUNGHYON JANG(Univ. of Tokyo)

2:45 PM - 3:00 PM

[3K03] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(19)Project Overview and Progress until 2019

*Hidemasa Yamano Yamano¹, Toshihide Takai¹, Shin Kikuchi¹, Yuki Emura¹, Hideo Higashi², Hiroyuki Fukuyama², Tsuyoshi Nishi³, Hiromichi Ohta³, Koji Morita⁴, Kinya Nakamura⁵ (1. JAEA, 2. Tohoku Univ., 3. Ibaraki Univ., 4. Kyushu Univ., 5. CRIEPI)

3:00 PM - 3:15 PM

[3K04] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(20)Thermophysical Properties of 17ass%B₄C-SS Eutectic Materials in the Solid State

*Toshihide Takai¹, Tomohiro Furukawa¹, Hidemasa Yamano¹ (1. Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[3K05] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(21)Density and Surface Tension of 2.5mass%B₄C-SS Eutectic Molten Material

*Hiroyuki Fukuyama¹, Hideo Higashi¹, Hidemasa Yamano² (1. Tohoku University, 2. JAEA)

3:30 PM - 3:45 PM

[3K06] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(22)Normal Spectral Emissivity, Heat Capacity and Thermal Conductivity of 2.5mass%B₄C-SS Eutectic Molten Material

*Hideo Higashi¹, Hiroyuki Fukuyama¹, Hidemasa Yamano² (1. Tohoku Univ, 2. JAEA)

3:45 PM - 4:00 PM

[3K07] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(23)Viscosity Measurement of 2.5mass%B₄C-SS Eutectic Molten Material

*Tsuyoshi NISHI¹, Rika SATO¹, Yuriko TAKATSUKA¹, Hiromichi OHTA², Hidemasa YAMANO² (1. Ibaraki Univ., 2. JAEA)

4:00 PM - 4:15 PM

[3K08] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(24)Interdiffusion between Boron Carbide and Stainless Steel in the Early Stage of the Eutectic Reaction

*Kinya Nakamura¹, Shin Kikuchi², Hidemasa Yamano² (1. CRIEPI, 2. JAEA)

Time reserved for Chair （4:15 PM - 4:25 PM）

Oral presentation

[3K09-11] Sodium-Cooled Fast Reactors 2

Fri. Sep 18, 2020 4:25 PM - 5:15 PM Room K (Zoom room 11)

Chair:Koji Fujimura(Hitachi-GE)

4:25 PM - 4:40 PM

[3K09] Improvement of integrative severe accident analysis code, SPECTRA

Development of evaluating module for core disruptive behavior, (1) Model concept and plan

*Ken-ichi Kawada¹, Tkashi Takata¹, Tohru Suzuki² (1. JAEA, 2. Tokyo City University)

4:40 PM - 4:55 PM

[3K10] Studies on Relocation Behavior of Molten Core Materials in the Core Disruptive Accident of Sodium-cooled Fast Reactors

(8)A series of out-of-pile experiments on fragmentation and cooling behavior of molten core material discharged into the inlet coolant plenum

*Kenichi Matsuba¹, Shinya Kato¹, Kenji Kamiyama¹, Dmitry Ganovichev², Assan Akayev², Viktor Baklanov² (1. JAEA, 2. NNC RK)

4:55 PM - 5:10 PM

[3K11] Studies on Relocation Behavior of Molten Core Materials in the Core Disruptive Accident of Sodium-cooled Fast Reactors

(9)Validation of Analysis Models for the Fragmentation and Cooling Behavior of Melt Impinging onto a Horizontal Structure in Sodium

*Kai Igarashi¹, Takaaki Sakai¹, Shinya Kato², Ken-ichi Matsuba², Kenji Kamiyama² (1. Tokai Univ., 2. Japan Atomic Energy Agency)

Time reserved for Chair （5:10 PM - 5:15 PM）

Sessions

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

[2K06-08] SA Analysis

(4)Fuel assemblies test of flow path feeding coolant at the core inlet

[2K09-13] Molten Core Behavior, Mitigation of FCI/MCCI

(2)Sensitivity analyses

(7)Spreading experiment of molten core with sacrificial material

(8)CFD Calculation of the molten core spreading experiment

(9)Evaluation of effectiveness of the sacrificial material for application to the nuclear power plants

[2K14-18] Risk Analysis, Metal Material Models

[3K01-02] FP/Aerosol Behavior

(2)Effects of particle size distribution and coagulation in aerosols

[3K03-08] Sodium-Cooled Fast Reactors 1

(19)Project Overview and Progress until 2019

(20)Thermophysical Properties of 17ass%B4C-SS Eutectic Materials in the Solid State

(21)Density and Surface Tension of 2.5mass%B4C-SS Eutectic Molten Material

(22)Normal Spectral Emissivity, Heat Capacity and Thermal Conductivity of 2.5mass%B4C-SS Eutectic Molten Material

(23)Viscosity Measurement of 2.5mass%B4C-SS Eutectic Molten Material

(24)Interdiffusion between Boron Carbide and Stainless Steel in the Early Stage of the Eutectic Reaction

[3K09-11] Sodium-Cooled Fast Reactors 2

Development of evaluating module for core disruptive behavior, (1) Model concept and plan

(8)A series of out-of-pile experiments on fragmentation and cooling behavior of molten core material discharged into the inlet coolant plenum

(9)Validation of Analysis Models for the Fragmentation and Cooling Behavior of Melt Impinging onto a Horizontal Structure in Sodium

Authentication

(20)Thermophysical Properties of 17ass%B₄C-SS Eutectic Materials in the Solid State

(21)Density and Surface Tension of 2.5mass%B₄C-SS Eutectic Molten Material

(22)Normal Spectral Emissivity, Heat Capacity and Thermal Conductivity of 2.5mass%B₄C-SS Eutectic Molten Material

(23)Viscosity Measurement of 2.5mass%B₄C-SS Eutectic Molten Material