Oral presentation

[1K01-04] Accident Analysis

Mon. Mar 16, 2020 10:45 AM - 11:55 AM Room K (Lecture Bildg. S 2F S-21)

Chair:Chiaki Kino(IAE)

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10:45 AM - 11:00 AM

[1K01] Analysis of Pressure Suppression Chamber Behavior in BWR Accidents by GOTHIC Code

*Hideo Konishi¹, Hiroshi Eguchi¹, Masashi Sekine¹ (1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))

11:00 AM - 11:15 AM

[1K02] Modeling of safety equipments based on Fukushima accident in MAAP

*Takayoshi Kusunoki¹, Toshiya Takaki¹, Naoki ano¹ (1. INSS)

11:15 AM - 11:30 AM

[1K03] Analysis of Halden LOCA Test Using Coupled TRACE/FRAPTRAN Code

*Hiroshi Eguchi¹, Kazuharu Fujioka¹, Hiroshi Ono¹, Hiroaki Uehara² (1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R), 2. Japan Atomic Energy Agency)

11:30 AM - 11:45 AM

[1K04] 3D Particle-Based Simulation of Molten Pool-to-Duct Wall Heat Transfer in EAGLE ID1 In-Pile Test

*Kazuya Sakaguchi¹, Kanji Funakoshi¹, Masatsugu Kato¹, Xiaoxing Liu¹, Wei Liu¹, Koji Morita¹, Kenji Kamiyama² (1. Kyushu Univ., 2. JAEA)

Time reserved for Chair （11:45 AM - 11:55 AM）

Oral presentation

[1K05-06] Numerical analysis of Molten Corium Behavior

Mon. Mar 16, 2020 2:45 PM - 3:20 PM Room K (Lecture Bildg. S 2F S-21)

Chair:Kenji Kamiyama(JAEA)

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2:45 PM - 3:00 PM

[1K05] Validation and Verification for the multi-physics models in JUPITER code

*Penghui Chai¹, Susumu Yamashita¹ (1. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[1K06] Numerical Analysis of melt spreading behavior by MELTSPREAD code

*Kazuyuki Katsuragi¹, Hiroshi Goda¹, Taro Toda¹, Kenichiro Ueda¹ (1. MHI)

Time reserved for Chair （3:15 PM - 3:20 PM）

Oral presentation

[1K07-12] Mitigation of Molten Core Concrete Interaction

Mon. Mar 16, 2020 3:20 PM - 4:55 PM Room K (Lecture Bildg. S 2F S-21)

Chair:Yoshiro Nishioka(TOSHIBA)

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3:20 PM - 3:35 PM

[1K07] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(1)Overview

*Junichi Takeuchi¹, Satoru Kamohara¹, Hideaki Ikeda¹, Makoto Yamagishi¹ (1. Mitsubishi Heavy Industries, Ltd.)

3:35 PM - 3:50 PM

[1K08] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(2)Development of Sacrificial Material and Physical Properties Measurements

*Nobuyuki Ukai¹, Kiyoshi Tatsuhara¹, Yuki Asai¹, Taro Toda¹, Hiroshi Goda¹ (1. Mitsubishi Heavy Industries)

3:50 PM - 4:05 PM

[1K09] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(3)Physical Properties Measurements of Molten Corium Sacrificial Material Mixture by VITI and Cold Crucible

*Taro Toda¹, Kiyoshi Tatsuhara¹, Junichi Takeuchi¹, Satoru Kamohara¹ (1. MHI)

4:05 PM - 4:20 PM

[1K10] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(4)Viscosity measurement of molten corium-sacrificial material mixture by aerodynamic levitation technique

*Toshiki Kondo¹, Yuji Ohishi¹, Hiroaki Muta¹, Taro Toda² (1. Osaka university, 2. MHI)

4:20 PM - 4:35 PM

[1K11] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(5)Development of Physical Property Models of Molten Corium-Sacrificial Material Mixture

*Kiyoshi Tatsuhara¹, Nobuyuki Ukai¹, Yasuhiko Tsuru¹, Mineaki Matsumoto¹, Koji Imasaka¹, Takashi Nakano¹, Yuki Asai¹, Taro Toda¹ (1. Mitsubishi Heavy Industries, Ltd. )

4:35 PM - 4:50 PM

[1K12] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(6)Development of molten core spreading model

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

Time reserved for Chair （4:50 PM - 4:55 PM）

Oral presentation

[2K01-05] Fire-Hazards/PRA/FP Aerosol Behavior

Tue. Mar 17, 2020 10:00 AM - 11:20 AM Room K (Lecture Bildg. S 2F S-21)

Chair:Hitoshi Muta(Tokyo City Univ.)

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10:00 AM - 10:15 AM

[2K01] Study on safety assessment of cable fire accidents in nuclear power plants using FDS

*Shintaro Tanaka¹, Akihiro Matsuda² (1. Graduate School of Systems and Information Engineering, University of Tsukuba, 2. Faculty of Engineering, Information and Systems, University of Tsukuba)

10:15 AM - 10:30 AM

[2K02] Numerical modeling of pressure drop of HEPA filter in nuclear power plants

*Kohei Yasui¹, Akihiro Matsuda² (1. Graduate School of Systems and Information Engineering, University of Tsukuba, 2. Faculty of Engineering, Information and Systems, University of Tsukuba)

10:30 AM - 10:45 AM

[2K03] Treatment of software common cause failure issue in digital reactor protection system

*Masafumi Utsumi¹ (1. MHI)

10:45 AM - 11:00 AM

[2K04] Examination of 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)

11:00 AM - 11:15 AM

[2K05] Experiment study on Cs containing aerosol behavior under severe accidents in sodium cooled fast reactors

(3)水蒸気雰囲気下におけるセシウムエアロゾル及びナトリウムエアロゾルの凝集試験

*Daisuke Hoshino¹, Isamu Sato¹, Shogo Uchida¹ (1. Tokyo City University)

Time reserved for Chair （11:15 AM - 11:20 AM）

Oral presentation

[2K06-07] Fukushima Daiichi Nuclear Power Plant Accident

Tue. Mar 17, 2020 11:20 AM - 11:55 AM Room K (Lecture Bildg. S 2F S-21)

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

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11:20 AM - 11:35 AM

[2K06] About the cause of the reactor building explosion caused by the Fukushima Daiichi power plant accident and the countermeasures

排気塔閉塞が主因と特定（その3）

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

11:35 AM - 11:50 AM

[2K07] Temperature change due to radiative cooling under the fuel rod exposure in Fuku-Ichi No.1 Reactor

Recursive calculation of temperature using a simplified 3-D model(1)

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

Time reserved for Chair （11:50 AM - 11:55 AM）

Sessions

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

[1K01-04] Accident Analysis

[1K01] Analysis of Pressure Suppression Chamber Behavior in BWR Accidents by GOTHIC Code

[1K02] Modeling of safety equipments based on Fukushima accident in MAAP

[1K03] Analysis of Halden LOCA Test Using Coupled TRACE/FRAPTRAN Code

[1K04] 3D Particle-Based Simulation of Molten Pool-to-Duct Wall Heat Transfer in EAGLE ID1 In-Pile Test

[1K05-06] Numerical analysis of Molten Corium Behavior

[1K05] Validation and Verification for the multi-physics models in JUPITER code

[1K06] Numerical Analysis of melt spreading behavior by MELTSPREAD code

[1K07-12] Mitigation of Molten Core Concrete Interaction

[1K07] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(1)Overview

[1K08] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(2)Development of Sacrificial Material and Physical Properties Measurements

[1K09] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(3)Physical Properties Measurements of Molten Corium Sacrificial Material Mixture by VITI and Cold Crucible

[1K10] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(4)Viscosity measurement of molten corium-sacrificial material mixture by aerodynamic levitation technique

[1K11] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(5)Development of Physical Property Models of Molten Corium-Sacrificial Material Mixture

[1K12] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(6)Development of molten core spreading model

[2K01-05] Fire-Hazards/PRA/FP Aerosol Behavior

[2K01] Study on safety assessment of cable fire accidents in nuclear power plants using FDS

[2K02] Numerical modeling of pressure drop of HEPA filter in nuclear power plants

[2K03] Treatment of software common cause failure issue in digital reactor protection system

[2K04] Examination of human reliability analysis for internal event PRA at Rokkasho Reprocessing Plant

[2K05] Experiment study on Cs containing aerosol behavior under severe accidents in sodium cooled fast reactors

(3)水蒸気雰囲気下におけるセシウムエアロゾル及びナトリウムエアロゾルの凝集試験

[2K06-07] Fukushima Daiichi Nuclear Power Plant Accident

[2K06] About the cause of the reactor building explosion caused by the Fukushima Daiichi power plant accident and the countermeasures

排気塔閉塞が主因と特定（その3）

[2K07] Temperature change due to radiative cooling under the fuel rod exposure in Fuku-Ichi No.1 Reactor

Recursive calculation of temperature using a simplified 3-D model(1)

Authentication