Oral presentation

[3B01-03] PRA 3

Wed. Mar 28, 2018 9:45 AM - 10:35 AM Room B (C1-311 -C1 Building)

Chair: Katsumi Ebisawa (CRIEPI)

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9:45 AM - 10:00 AM

[3B01] Development of PRA Methodology Considering Integration of Seismic-Tsunami Event

Part 1: SSC Model for Loss of Function

*Yasuki Ohtori¹, Hitoshi Muta¹ (1. Tokyo City University)

10:00 AM - 10:15 AM

[3B02] Development of PRA Methodology Considering Integration of Seismic-Tsunami Event

Part 2: Core Damage Accident Sequence Analysis

*Hitoshi Muta¹, Yasuki Ohtori¹ (1. Tokyo City University)

10:15 AM - 10:30 AM

[3B03] Internal Fire PSA of ABWR

*Yuki Ishiwatari¹, Daichi Shiota¹, Yoshifumi Nozaki¹, Michinao Bunno¹ (1. Hitachi-GE Nuclear Energy, Ltd.)

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

Oral presentation

[3B04-08] PRA 4

Wed. Mar 28, 2018 10:35 AM - 11:55 AM Room B (C1-311 -C1 Building)

Chair: Hitoshi Muta (Tokyo City Univ.)

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10:35 AM - 10:50 AM

[3B04] The Progress of PRA for SHIKA NPS Unit 2

(3)Development of Plant Risk Monitoring Tool During Shutdown State

*Junya Masuko², Mutsuhiro Nakada¹, Toshihiro Aida¹, Daisuke Suimon¹, Shinichi Hamayani^2,1, Takayuki Negishi², Atsuo Ikeda² (1. Hokuriku Electric Power Company, 2. Nuclear Engineering and Services Company)

10:50 AM - 11:05 AM

[3B05] The Progress of PRA for SHIKA NPS Unit 2

(4)Evaluation Results of Spent Fuel Storage Pool PRA

*Shinichi Hamatani^2,1, Mutsuhiro Nakada¹, Toshihiro Aida¹, Daisuke Suimon¹, Takayuki Negishi², Atsuo Ikeda², Junya Masuko² (1. Hokuriku Electric Power Co., 2. Nuclear Engineering and Services Co.)

11:05 AM - 11:20 AM

[3B06] KK-6,7 project Internal Event Operating Level 1 PRA Model Sophistication Progress Report

(5)Classification of Accident Sequence of LOCA inside PCV

*Shunsuke Tanno¹, Shohei Yamagishi¹, Ryota Tomiyasu¹, Teruyoshi Sato¹, Toshiteru Saito¹, Masayuki Hiraide², Toshinobu Kita² (1. TEPCO SYSTEMS CORPORATION, 2. Tokyo Electric Power Company Holdings, Inc.)

11:20 AM - 11:35 AM

[3B07] KK-6,7 project Internal Event Operating Level 1 PRA Model Sophistication Progress Report

(6)Scope of LOCA outside PCV and internal flooding PRA

*Hiroaki Sonoyama¹, Shohei Yamagishi¹, Ryota Tomiyasu¹, Shunsuke Tanno¹, Teruyoshi Sato¹, Toshiteru Saito¹, Masayuki Hiraide², Toshinobu Kita² (1. TEPCO SYSTEMS CORPORATION, 2. Tokyo Electric Power Company Holdings, Inc.)

11:35 AM - 11:50 AM

[3B08] Dynamic Risk Analysis on Multi-hazards of Seismic and Seismic-induced Internal Flooding in Nuclear Installation

*SUNGHYON JANG¹, AKIRA YAMAGUCHI¹ (1. The University of Tokyo)

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

Oral presentation

[3B09-13] Light Water Reactor Safety Assessment

Wed. Mar 28, 2018 2:45 PM - 4:05 PM Room B (C1-311 -C1 Building)

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

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2:45 PM - 3:00 PM

[3B09] Development of Reduced Order Model of Severe Accident Analysis Code for Probabilistic Safety Margin Analysis

*Masaki Matsushita¹, Tomohiro Endo¹, Akio Yamamoto¹, Takumi Kitao² (1. Nagoya University, 2. Nuclear Engineering Ltd.)

3:00 PM - 3:15 PM

[3B10] Flood propagation analysis for internal flood PRA by using Apros code

(1)Development of flood propagation analysis models

*Tomomichi Itoh¹, Yoshikane Hamaguchi¹, Tamio Koriyama¹ (1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority(S/NRA/R))

3:15 PM - 3:30 PM

[3B11] Flood propagation analysis for internal flood PRA by using Apros code

(2)Results of flood propagation analysis for internal flood PRA

*Yoshikane Hamaguchi¹, Tomomichi Itoh¹, Tamio Koriyama¹ (1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority(S/NRA/R))

3:30 PM - 3:45 PM

[3B12] The characteristics of concrete after high temperature exposures simulating severe accident

*Nhut Vu Luu¹, Thi Mai Dung Do¹, Kenta Murakami¹, Masahide Suzuki¹, Tomonori Yamada², Shibata Takuya² (1. Nagaoka University of Technology, 2. Japan Atomic Energy Agency)

3:45 PM - 4:00 PM

[3B13] Evaluation of the effect of irradiation on the fracture boundary of fuel cladding under LOCA conditions

*Takafumi Narukawa^2,1, Akira Yamaguchi¹, Sunghyon Jang¹, Masaki Amaya² (1. UTokyo, 2. JAEA)

Time reserved for Chair （4:00 PM - 4:05 PM）

Oral presentation

[1K01-04] PRA 1

Mon. Mar 26, 2018 10:50 AM - 11:55 AM Room K (U3-311 -U3 Building)

Chair: Yuki Ishiwatari (HGNE)

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10:50 AM - 11:05 AM

[1K01] Level 1 PRA for Design Works of External Vessel Storage Tank in Advanced Loop-Type Sodium-Cooled Fast Reactor

*Hidemasa Yamano¹, Kenichi Naruto², Kenichi Kurisaka¹, Hiroyuki Nishino¹ (1. Japan Atomic Energy Agency, 2. NESI Inc.,)

11:05 AM - 11:20 AM

[1K02] Level 1 PRA for Design Works of Spent Fuel Pool in Advanced Loop-Type Sodium-Cooled Fast Reactor

*Kenichi Naruto¹, Hidemasa Yamano², Kenichi Kurisaka², Hiroyuki Nishino² (1. NESI Inc, 2. JAEA)

11:20 AM - 11:35 AM

[1K03] A study on application of multi-agent system to probabilistic risk assessment of nuclear power plant

*Kenichi Kanda¹, Hiromichi Miura¹, Tomoaki Yoshida¹ (1. Central Research Institute of Electric Power Industry)

11:35 AM - 11:50 AM

[1K04] Discussion of some problems of HCR/ORE method

*Yoshihiro Ide¹, Kai Shimomura¹, Akira Okamoto¹, Hiroshi Ujita¹, Hidetoshi Morita¹ (1. AdvanceSoft Corporation)

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

Oral presentation

[1K05-11] Fault Displacement PRA and Earthquake Resistant

Mon. Mar 26, 2018 2:45 PM - 4:35 PM Room K (U3-311 -U3 Building)

Chair: Tatsuya Itoi (Univ. of Tokyo)

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2:45 PM - 3:00 PM

[1K05] Improvement of Fault Displacement PRA Methodology and Concept of its Application to a Hypothetical NPP

(1)Outline

*Katsumi Ebisawa¹, Hideaki Tsutsumi¹, Yoshinori Mihara², Yuji Nikkaido², Futoshi Tanaka³, Daisuke Ochi³, Ryuusuke Haraguchi³, Tetsuhiro Go³, Kunihiko Sato³, Shinichi Yoshida⁴ (1. Central Research Institute of Electric Power Industry, 2. kajima, 3. MHI, 4. Obayashi)

3:00 PM - 3:15 PM

[1K06] Improvement of Fault Displacement PRA Methodology and Concept of its Application to a Hypothetical NPP

(2)Concept of evaluation position of fault displacement hazard

*hideaki tsutsumi¹, yoshinori mihra², yuji nikaido², Katsumi ebisawa¹ (1. Cental Research Institute of Electric Power Industry, 2. Kajima Corporation)

3:15 PM - 3:30 PM

[1K07] Improvement of Fault Displacement PRA Methodology and Concept of its Application to a Hypothetical NPP

(3)The Concept of Validation Strategy about Fault Displacement Fragility Evaluation Methodology

*Nikaido Yuji¹, Yoshinori Mihara¹, Hideaki Tsutsumi², Ryusuke Haraguchi³, Katsumi Ebisawa² (1. Kajima, 2. CRIEPI, 3. MHI)

3:30 PM - 3:45 PM

[1K08] Improvement of Fault Displacement PRA Methodology and Concept of its Application to a Hypothetical NPP

(4)Analysis Condition and Concept of Accident Scenario and Sequence Evaluation

*Futoshi Tanaka¹, Daisuke Ochi¹, Manabu Miyata¹, Hideaki Tsutsumi², Katsumi Ebisawa² (1. Mitsubishi Heavy Industries, LTD., 2. Central Research Institute of Electric Power Industry)

3:45 PM - 4:00 PM

[1K09] Improvement of Fault Displacement PRA Methodology and Concept of its Application to a Hypothetical NPP

(5)Concept of Application of Fragility Evaluation Methodology to a Hypothetical NPP

*Ryusuke Haraguchi¹, Tetsuhiro Gou¹, Kunihiko Sato², Shinichi Yoshida³, Hideaki Tsutsumi⁴, Katsumi Ebisawa⁴ (1. MHI, 2. MHI NS Eng., 3. Obayashi Corp., 4. CRIEPI)

4:00 PM - 4:15 PM

[1K10] High Performance Computing for Estimation of Fault Displacements

(1)Numerical Method

*Masataka Sawada¹, Kazumoto Haba², Muneo Hori³ (1. CRIEPI, 2. Taisei, 3. UTokyo)

4:15 PM - 4:30 PM

[1K11] High Performance Computing for Estimation of Fault Displacements

(2)Application

*Kazumoto Haba¹, Masataka Sawada², Muneo Hori³ (1. Taisei, 2. CRIEPI, 3. UTokyo)

Time reserved for Chair （4:30 PM - 4:35 PM）

Oral presentation

[1K12-16] Fast Reactor

Mon. Mar 26, 2018 4:35 PM - 5:55 PM Room K (U3-311 -U3 Building)

Chair: Kei Ito (Kyoto Univ.)

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4:35 PM - 4:50 PM

[1K12] Study on Effectiveness Evaluations of Countermeasures against Severe Accidents in Fast Reactor

(6)Effectiveness Evaluations of Countermeasures against Anticipated Transient without Scram

*Yuya Imaizumi¹, Fumiaki Yamada¹, Masahiro Nishimura¹, Takero Mori¹, Yoshitaka Fukano¹ (1. JAEA)

4:50 PM - 5:05 PM

[1K13] Study on Effectiveness Evaluations of Countermeasures against Severe Accidents in Fast Reactor

(7)Selecting the Important Accident Sequences during Reactor Shutdown

*Hiroyuki Nishino¹, Kenichi Kurisaka¹, Kazuo Yoshimura¹, Masahiro Nishimura¹, Yoshitaka Fukano¹ (1. JAEA)

5:05 PM - 5:20 PM

[1K14] Study on Effectiveness Evaluations of Countermeasures against Severe Accidents in Fast Reactor

(8)Effectiveness Evaluations of Countermeasures against Severe Accidents during Reactor Shutdown

*Masahiro Nishimura¹, Kazuo Yoshimura¹, Hiroshi Taninaka¹, Fumiaki Yamada¹, Takero Mori¹, Hiroyuki Nishino¹, Yoshitaka Fukano¹ (1. Japan Atomic Energy Agency)

5:20 PM - 5:35 PM

[1K15] Study on Effectiveness Evaluations of Countermeasures against Severe Accidents in Fast Reactor

(9)Effectiveness Evaluations of Countermeasures against Severe Accidents for Spent Fuel

*Takero Mori¹, Hiroshi Taninaka¹, Kenichi Kurisaka¹, Fumiaki Yamada¹, Masahiro Nishimura¹, Yoshitaka Fukano¹ (1. JAEA)

5:35 PM - 5:50 PM

[1K16] Investigation of energetic power excursion caused by sloshing motion of molten core pool

*Koji Morita¹, Masayuki Fukuda¹, Wei Liu¹, Isao Tatewaki¹ (1. Kyushu University)

Time reserved for Chair （5:50 PM - 5:55 PM）

Oral presentation

[2K01-05] Fuel Reprocessing Plants

Tue. Mar 27, 2018 9:30 AM - 10:50 AM Room K (U3-311 -U3 Building)

Chair: Hidetoshi Karasawa (IAE)

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9:30 AM - 9:45 AM

[2K01] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(16)Hydrogen explosion experiment and combustion analysis with various liquid level in simulated large scale annular vessels

*Wenbin Dai¹, Motohiro Sakaihara¹, Osamu Kanehira¹, Yoshikazu Tamauchi², Tatsuya Kudo², Masanao Nakano², Naoya Sakagami², Kohei Otake², Nobuyuki Arai² (1. Mitsubishi Materials Corporation, 2. Japan Nuclear Fuel Limited)

9:45 AM - 10:00 AM

[2K02] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(17)Hydrogen concentration dependence of hydrogen explosion behavior in simulated large scale annular vessels

*Yoshitaka Saito¹, Yoshikazu Tamauchi¹, Tatsuya Kudo¹, Masanao Nakano¹, Naoya Sakagami¹, Kohei Otake¹, Nobuyuki Arai¹, Wenbin Dai², Motohiro Sakaihara², Osamu Kanehira² (1. Japan Nuclear Fuel Limited, 2. Mitsubishi Materials Corporation)

10:00 AM - 10:15 AM

[2K03] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(18)Summary of this project

*Yoshikazu Tamauchi¹, Tatsuya Kudo¹, Masanao Nakano¹, Naoya Sakagami¹, Kohei Otake¹, Nobuyuki Arai¹, Wenbin Dai², Motohiro Sakaihara², Osamu Kanehira² (1. Japan Nuclear Fuel Limited, 2. Mitsubishi Materials Corporation)

10:15 AM - 10:30 AM

[2K04] Experiment on airborne release fraction in hydrogen explosion accident at Reprocessing plant

(8)Hydrogen explosion experiment in small vessel

*Takashi Kobayashi¹, Takahiro Chikazawa¹, Takahiro Ishio², Yoshikazu Tamauchi², Hiroshi Kinuhata², Takashi Kodama² (1. Mitsubishi Materials Corporation, 2. Japan Nuclear Fuel Limited)

10:30 AM - 10:45 AM

[2K05] Experiment on airborne release fraction in hydrogen explosion accident at Reprocessing plant

(9)Comparison results between hydrogen explosion experiment and pressurization experiment

*Takashi Kodama¹, Takahiro Ishio¹, Yoshikazu Tamauchi¹, Hiroshi Kinuhata¹, Takashi Kobayashi², Takahiro Chikazawa² (1. Japan Nuclear Fuel Limited, 2. Mitsubishi Materials Corporation)

Time reserved for Chair （10:45 AM - 10:50 AM）

Oral presentation

[2K06-09] PRA 2

Tue. Mar 27, 2018 10:50 AM - 11:55 AM Room K (U3-311 -U3 Building)

Chair: Koichi Nakamura (CRIEPI)

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10:50 AM - 11:05 AM

[2K06] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(10)Project overview and achievements

*Hiroyuki Sato¹, Akemi Nishida¹, Ken Muramatsu², Hitoshi Muta², Tatsuya Itoi³, Tsuyoshi Takada³, Masayuki Tanabe⁴, Tsuyoshi Yamamoto⁴ (1. Japan Atomic Energy Agency, 2. Tokyo City University, 3. The University of Tokyo, 4. JGC Corporation)

11:05 AM - 11:20 AM

[2K07] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(11)Development of Accident Sequence Analysis Methodology

*Kosuke Matsuda¹, Ken Muramatsu¹, Hitoshi Muta¹, Yasuki Ohtori¹, Hiroyuki Sato² (1. TCU Univ., 2. JAEA)

11:20 AM - 11:35 AM

[2K08] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(12)Development and Application of Seismic Fragility Analysis Method

*Tatsuya Itoi¹, Akemi Nishida², Tsuyoshi Takada¹, Takenori Hida¹, Hiroyuki Sato² (1. The University of Tokyo, 2. Japan Atomic Energy Agency)

11:35 AM - 11:50 AM

[2K09] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(13)Development of source term evaluation method

*YUKI HONDA¹, Hiroyuki Sato¹, Hirofumi Ohashi¹ (1. JAEA)

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

Oral presentation

[2K10-13] Source Term

Tue. Mar 27, 2018 2:45 PM - 3:50 PM Room K (U3-311 -U3 Building)

Chair: Akihide Hidaka (JAEA)

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2:45 PM - 3:00 PM

[2K10] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(5)Applicability evaluation of the source term PRD to the dynamic PRA

*Koichi Nakamura¹, Yoko Yamane², Keigo Murata², Taizo Kanai¹, Hiroshi Endo¹ (1. Central Research Institute of Electric Power Industry, 2. AdvanceSoft Corporation)

3:00 PM - 3:15 PM

[2K11] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(6)Development of Source term PRD method by incorporating transported cesium mass into CV by core damage

*Yoko Yamane¹, Koichi Nakamura², Taizo Kanai², Keigo Murata¹, Hiroshi Endo² (1. Advancesoft Corporation, 2. Central Research Institute of Electric Power Industry)

3:15 PM - 3:30 PM

[2K12] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(7)Applicability confirmation of re-evaporation behavior model of cesium in the reactor cavity of the severe accident analysis code

*Keigo Murata¹, Koichi Nakamura², Yoko Yamane¹, Taizo Kanai², Hiroshi Endo² (1. AdVanceSoft Corporation, 2. Central Research Institute of Electric Power Industry)

3:30 PM - 3:45 PM

[2K13] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(8)Experimental study on aerosol behavior and its diameter

*Taizo Kanai¹, Koichi Nakamura¹, Hiroshi Endo¹, Satoshi Nishimura¹ (1. CRIEPI)

Time reserved for Chair （3:45 PM - 3:50 PM）

Oral presentation

[2K14-16] Light Water Reactor Behavior Under Accident Conditions

Tue. Mar 27, 2018 3:50 PM - 4:40 PM Room K (U3-311 -U3 Building)

Chair: Hidemasa Yamano (JAEA)

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3:50 PM - 4:05 PM

[2K14] ATWS analyses with reactor simulator based on RELAP/SCDAPSIM code.

*Ryo kikuchi¹, Masahiro Sakamoto¹, Takanori Kameyama¹ (1. TOKAI University)

4:05 PM - 4:20 PM

[2K15] Analysis on the ex-vessel core debris cooling and containment pressurization in 1000MWe PWR plant

*Kiyofumi Moriyama¹, Hyun Sun Park¹, Mooneon Lee¹, Jin Ho Park¹ (1. Pohang University of Science and Technology (POSTECH))

4:20 PM - 4:35 PM

[2K16] Analysis of MCCI phenomena by MELCOR and SAMPSON

(3)Study on Heat Banance of Fuel Debris in Wet Cavity

*Masashi Himi¹, Hidetoshi Morita¹, Koetsu Ito¹, Yoshihiro Ide¹, Koichi Nakamura² (1. Advancesoft co., 2. CRIEPI)

Time reserved for Chair （4:35 PM - 4:40 PM）

Oral presentation

[2K17-21] Severe Accident Management

Tue. Mar 27, 2018 4:40 PM - 6:00 PM Room K (U3-311 -U3 Building)

Chair: Kiyofumi Moriyama (Pohang Univ. of Sci. & Tech.)

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4:40 PM - 4:55 PM

[2K17] On the consideration of the explosion of the reactor building of the Fukushima Daiichi Power Plant accident and its countermeasures

Closure of the silencer in the exhaust tower is mainly attributed

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

4:55 PM - 5:10 PM

[2K18] A study of Emergency Radioactive Nuclides Release Estimation Method Based on Measured Parameters

*Hidetaka Imai¹, Satoshi Kawaguchi¹, Daisuke Fujiwara² (1. TEPCO Holdings, Inc., 2. TEPSYS)

5:10 PM - 5:25 PM

[2K19] Development of a Gamma Camera

(1)Development

*Takashi Takeuchi¹, Hidetaka Imai¹, Hideaki Tezuka¹ (1. TEPCO)

5:25 PM - 5:40 PM

[2K20] Development of a Gamma Camera

(2)Numerical Analysis

*Hideaki Tezuka¹, Takashi Takeuchi¹, Hidetaka Imai¹ (1. TEPCO)

5:40 PM - 5:55 PM

[2K21] Physicochemical stability and long-term storability of silver zeolite (AgX / AgR)

*Toshiki Kobayashi¹, Jifeng Wang¹, Yoshihiro Ishikawa¹, Yuichiro Uzuyama¹, Koji Endo¹ (1. Rasa Industries, Ltd)

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

Sessions

III. Fission Energy Engineering » 306-1 Nuclear Safety Engineering, Nuclear Installation Safety, PSA

[3B01-03] PRA 3

Part 1: SSC Model for Loss of Function

Part 2: Core Damage Accident Sequence Analysis

[3B04-08] PRA 4

(3)Development of Plant Risk Monitoring Tool During Shutdown State

(4)Evaluation Results of Spent Fuel Storage Pool PRA

(5)Classification of Accident Sequence of LOCA inside PCV

(6)Scope of LOCA outside PCV and internal flooding PRA

[3B09-13] Light Water Reactor Safety Assessment

(1)Development of flood propagation analysis models

(2)Results of flood propagation analysis for internal flood PRA

[1K01-04] PRA 1

[1K05-11] Fault Displacement PRA and Earthquake Resistant

(1)Outline

(2)Concept of evaluation position of fault displacement hazard

(3)The Concept of Validation Strategy about Fault Displacement Fragility Evaluation Methodology

(4)Analysis Condition and Concept of Accident Scenario and Sequence Evaluation

(5)Concept of Application of Fragility Evaluation Methodology to a Hypothetical NPP

(1)Numerical Method

(2)Application

[1K12-16] Fast Reactor

(6)Effectiveness Evaluations of Countermeasures against Anticipated Transient without Scram

(7)Selecting the Important Accident Sequences during Reactor Shutdown

(8)Effectiveness Evaluations of Countermeasures against Severe Accidents during Reactor Shutdown

(9)Effectiveness Evaluations of Countermeasures against Severe Accidents for Spent Fuel

[2K01-05] Fuel Reprocessing Plants

(16)Hydrogen explosion experiment and combustion analysis with various liquid level in simulated large scale annular vessels

(17)Hydrogen concentration dependence of hydrogen explosion behavior in simulated large scale annular vessels

(18)Summary of this project

(8)Hydrogen explosion experiment in small vessel

(9)Comparison results between hydrogen explosion experiment and pressurization experiment

[2K06-09] PRA 2

(10)Project overview and achievements

(11)Development of Accident Sequence Analysis Methodology

(12)Development and Application of Seismic Fragility Analysis Method

(13)Development of source term evaluation method

[2K10-13] Source Term

(5)Applicability evaluation of the source term PRD to the dynamic PRA

(6)Development of Source term PRD method by incorporating transported cesium mass into CV by core damage

(7)Applicability confirmation of re-evaporation behavior model of cesium in the reactor cavity of the severe accident analysis code

(8)Experimental study on aerosol behavior and its diameter

[2K14-16] Light Water Reactor Behavior Under Accident Conditions

(3)Study on Heat Banance of Fuel Debris in Wet Cavity

[2K17-21] Severe Accident Management

Closure of the silencer in the exhaust tower is mainly attributed

(1)Development

(2)Numerical Analysis

Authentication