Oral presentation

[1J01-04] Innovative Reactors and Technologies

Wed. Sep 13, 2017 10:50 AM - 12:00 PM Room J (C309 - C Block)

Chair:Tetsuo Matsumura (CRIEPI)

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10:50 AM - 11:05 AM

[1J01] Study on safety enhancement of the fast reactor by using nanoparticle suspension sodium

Reaction Suppression (11)

*Keiichi Nagai¹, Jun-ichi Saito¹, Kuniaki Ara¹ (1. Japan Atomic Energy Agency)

11:05 AM - 11:20 AM

[1J02] Study on safety enhancement of the fast reactor by using nanoparticle suspension sodium

Reaction Suppression (12)

*Jun-ichi SAITO¹, Keiichi NAGAI¹, Kuniaki ARA¹ (1. Japan Atomic Energy Agency)

11:20 AM - 11:35 AM

[1J03] Research on fundamental technology for SCWR based on RISA

3rd report, Electrochemical measurement of radioactivated stainless steel

*Ryota Taguchi¹, Tomonori Ihara¹, Tatsuya Hazuku¹, Tomoji Takamasa¹, Sho Kano², Hiroaki Abe² (1. Tokyo University of Marine Science and Technology , 2. The University of Tokyo)

11:35 AM - 11:50 AM

[1J04] Research on fundamental technology for SCWR based on RISA

4th report, RISA on metal surface wettability

*Toru Miyoshi¹, Tomonori Ihara², Tatsuya Hazuku², Tomoji Takamasa², Shinichi Morooka¹ (1. Waseda Univ., 2. Tokyo Univ. of Marine Science and Technology)

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

Oral presentation

[1J05-08] Pu-burning Gas-cooled Reactor

Wed. Sep 13, 2017 2:45 PM - 3:55 PM Room J (C309 - C Block)

Chair:Masatoshi Kuroda (Kumamoto Univ.)

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2:45 PM - 3:00 PM

[1J05] Development of Security and Safety Fuel for Pu-burner HTGR

(14)Objectives, current status and future

*Koji OKAMOTO¹, Kazutaka Ohashi², Koichi Ohira³, Kazuhiko Kunitomi⁴ (1. The University of TOkyo, 2. Fuji Electric Co., Ltd., 3. Nuclear Fuel Industries, Ltd., 4. Japan Atoic Energy Agency)

3:00 PM - 3:15 PM

[1J06] Development of Security and Safety Fuel for Pu-burner HTGR

(15)Vital Area Identification Analysis concerning Pu-burner HTGR

*Kazuyuki Demachi¹, Shi Chen¹, Koji Okamoto¹ (1. The University of Tokyo)

3:15 PM - 3:30 PM

[1J07] Development of Security and Safety Fuel for Pu-burner HTGR

(16)Experimental Study on the Transient Oxidation of Nuclear Graphite under Air Ingress Conditions

*Wataru SAGAWA¹, Yang Wu¹, Penghui Chai², Masahiro Kondo¹, Koji Okamoto¹ (1. The University of Tokyo, 2. The University of Tokyo(currently working at JAEA))

3:30 PM - 3:45 PM

[1J08] Development of Security and Safety Fuel for Pu-burner HTGR

(17)Numerical Study on the Transient Oxidation of Nuclear Graphite under Air Ingress Conditions

*Yang Wu¹, Wataru Sagawa¹, Penghui Chai², Masahiro Kondo¹, Koji Okamoto¹ (1. The University of Tokyo, 2. The University of Tokyo (Currently working at JAEA))

Time reserved for Chair （3:45 PM - 3:55 PM）

Oral presentation

[1J09-12] Gas-cooled Reactors

Wed. Sep 13, 2017 3:55 PM - 5:05 PM Room J (C309 - C Block)

Chair:Masaki Honda (NFI)

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3:55 PM - 4:10 PM

[1J09] Development of Security and Safety Fuel for Pu-burner HTGR

(18)Fuel design and core design

*Minoru Goto¹, Yoshitomo Inaba¹, Shohei Ueta¹, Jun Aihara¹, Yuji Fukaya¹, yukio Tachibana¹, Koji Okamoto² (1. Japan Atomic Energy Agency, 2. The University of Tokyo)

4:10 PM - 4:25 PM

[1J10] Development of Security and Safety Fuel for Pu-burner HTGR

(19)Preliminary reactivity transient analyses

*Masaaki Nakano¹, Kazutaka Ohashi¹, Koji Okamoto² (1. Fuji Electric, 2. The University of Tokyo)

4:25 PM - 4:40 PM

[1J11] Development of Security and Safety Fuel for Pu-burner HTGR

(20)Study on 3S-TRISO fuel fabrication

*Yohei Saiki¹, Masaki Honda¹, Masashi Takahashi¹, Koichi Ohira¹, Takashi Okamoto² (1. Nuclear Fuel Industries, Ltd., 2. The University of Tokyo)

4:40 PM - 4:55 PM

[1J12] Development of Security and Safety fuel for Pu-burner HTGR

(21)Test and Characterization for ZrC Coating

*Shohei Ueta¹, Jun Aihara¹, Yukio Tachibana¹, Kazuhiko Kunitomi¹, Koji Okamoto² (1. JAEA, 2. Univ. Tokyo)

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

Oral presentation

[1J13-16] Gas-cooled Reactor Fuel

Wed. Sep 13, 2017 5:05 PM - 6:15 PM Room J (C309 - C Block)

Chair:Masaaki Nakano (Fuji Electric)

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5:05 PM - 5:20 PM

[1J13] Research on Advanced Fuel Element for Upgrading Safety of High Temperature Gas-Cooled Reactors

(1)Outlines

*Yukio Tachibana¹, Koichi Ohira², Masatoshi Kuroda³ (1. JAEA, 2. NFI, 3. Kumamoto University)

5:20 PM - 5:35 PM

[1J14] Research on Advanced Fuel Element for Upgrading Safety of High Temperature Gas-Cooled Reactors

(2)Development of fabrication technology of oxidation resistant fuel element

*Jun Aihara¹, Shohei Ueta¹, Masaki Honda², Hiroaki Ogawa¹, Taiju Shibata¹, Naoki Mizuta¹, Yoshitomo Inaba¹, Yukio Tachibana¹ (1. JAEA, 2. NFI)

5:35 PM - 5:50 PM

[1J15] Research on Advanced Fuel Element for Upgrading Safety of High Temperature Gas-Cooled Reactors

(3)Development on Inspection of Oxidation Resistant Fuel Element

*Masaki Honda¹, Atushi Yasuda¹, Koichi Ohira¹, Yukio Tachibana² (1. Nuclear Fuel Industries, LTD., 2. Japan Atomic Energy Agency)

5:50 PM - 6:05 PM

[1J16] Research on Advanced Fuel Element for Upgrading Safety of High Temperature Gas-Cooled Reactors

(4)Modeling for Casting Oxidation Resistant Fuel Element

*Masatoshi Kuroda¹, Takuya Tojo¹, Takenori Yamamoto¹, Jun Aihara², Yukio Tachibana² (1. Kumamoto University, 2. JAEA)

Time reserved for Chair （6:05 PM - 6:15 PM）

Oral presentation

[2J01-09] Breakage Prevention of Containment Vessel

Thu. Sep 14, 2017 9:30 AM - 11:55 AM Room J (C309 - C Block)

Chair:Matsubara Shinichiro (MHI)

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9:30 AM - 9:45 AM

[2J01] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(17)Outline

*Masayoshi UNO¹, MItsuhiro AOYAGI², Tadashi WATANABE¹, Munemichi KAWAGUCHI², Ikuo YAMAMOTO¹, Daisuke DOI², Kei Itho², Hiroki YADA², Masanori ANDO² (1. Research Institute of Nuclear Engineering, University of Fukui, 2. Japan Atomic Energy Agency)

9:45 AM - 10:00 AM

[2J02] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(18)Summary of Development of Detailed Numerical Simulation Methods for Sodium Fire

*Mitsuhiro Aoyagi¹, Takashi Takata¹, Shuji Ohno¹, Erina Hamase¹, Masayoshi Uno² (1. JAEA, 2. University of Fukui)

10:00 AM - 10:15 AM

[2J03] Development of Estimation Technology for Availability of Measure for Failure of Containment Vessel in Sodium Cooled Fast Reactor

(19)Numerical analysis of sodium droplet combustion by VOF method

*Tadashi Watanabe¹ (1. Univ. Fukui)

10:15 AM - 10:30 AM

[2J04] Development of Estimation Technology for Availability of Measure for Failure of Containment Vessel in Sodium Cooled Fast Reactor

(20)Summary of sodium-concrete reaction experiments

*Kawaguchi Munemichi¹, Miyahara Shinya¹, Uno Masayoshi² (1. JAEA, 2. Univ. of Fukui)

10:30 AM - 10:45 AM

[2J05] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(21)Examination of chemical reaction behavior of core debris-sodium-concrete interactions by thermodynamic calculation

*Ikuo YAMAMOTO¹, Masayoshi Uno¹, Shinya Miyahara¹ (1. University of Fukui)

10:45 AM - 11:00 AM

[2J06] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(22)Chemical reaction analysis of the hydrogen combustion by sodium vapor/mist ignition

*Daisuke DOI^1,2, Kei Ito¹, Hiroshi Seino¹, Shinya Miyahara², Masayoshi Uno² (1. JAEA, 2. Univ. of Fukui)

11:00 AM - 11:15 AM

[2J07] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(23)Numerical simulation of hydrogen combustion in containment vessel of fast reactor

*Kei Ito¹, Daisuke Doi¹, Takashi Takata¹, Masayoshi Uno² (1. JAEA, 2. Fukui Univ.)

11:15 AM - 11:30 AM

[2J08] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(24)Study on behaviors of boundary components until mechanical loss of function based on experiments and analyses

*Hiroki Yada¹, Masanori Ando¹, Kazuyuki Tsukimori^1,2, Masakazu Ichimiya², Yoshinari Anoda², Masayoshi Uno² (1. JAEA, 2. University of Fukui)

11:30 AM - 11:45 AM

[2J09] Development of Estimation Technology for Availability of Measure for Failure of Containment Vessel in Sodium Cooled Fast Reactor

(25)Proposal of evaluation method of the limits of mechanical loss of function in the boundary components

*Masanori Ando¹, Hiroki Yada¹, Kazuyuki Tsukimori^1,2, Masakazu Ichimiya², Yoshinari Anoda², Masayoshi Uno² (1. JAEA, 2. University of Fukui)

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

Oral presentation

[2J10-14] Decommissioning of Monju

Thu. Sep 14, 2017 2:45 PM - 4:05 PM Room J (C309 - C Block)

Chair:Yoshitaka Chikazawa (JAEA)

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2:45 PM - 3:00 PM

[2J10] Safety evaluations for MONJU during decommissioning phase

(1)Approach to safety evaluations during decommissioning phase

*Yoshitaka Fukano¹, Satoshi Futagami¹, Yasuhiro Enuma¹, Takayuki Suzuki¹, Ryodai Nakai¹, Makinori Ikeda¹ (1. JAEA)

3:00 PM - 3:15 PM

[2J11] Safety evaluations for MONJU during decommissioning phase

(2)Conservative thermal evaluations on fuel integrity

*Takero Mori¹, Masutake Sotsu¹, Yuya Imaizumi¹, Kazuo Yoshimura¹, Yoshitaka Fukano¹ (1. JAEA)

3:15 PM - 3:30 PM

[2J12] Safety evaluations for MONJU during decommissioning phase

(3)Evaluation of accidents during decommissioning phase

*Tetsuya Mouri¹, Rika Mitsumoto¹, Satoshi Futagami¹, Iwao Suse¹, Yasuhiro Enuma¹ (1. JAEA)

3:30 PM - 3:45 PM

[2J13] Safety evaluations for MONJU during decommissioning phase

(4)Resistance to hazards during decommissioning phase

*Kazuaki Matsui¹, Kosuke Aizawa¹, Rika Mitsumto¹, Satoshi Futagami¹, Iwao Suse¹, Yasuhiro Enuma¹ (1. JAEA)

3:45 PM - 4:00 PM

[2J14] Evaluation thermal resistance of electric instrumentation and installation for MONJU during decommissioning phase

*Sho Kawanago¹, Rika Mitsumoto¹, Satoshi Futagami¹, Iwao Suse¹, Yasuhiro Enuma¹ (1. JAEA)

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

Oral presentation

[2J15-19] Pump and Reactor Vessel of Na-cooled Reactor

Thu. Sep 14, 2017 4:05 PM - 5:25 PM Room J (C309 - C Block)

Chair:Yuichi Ohtani (MHI)

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4:05 PM - 4:20 PM

[2J15] The results obtained from the 20 years of "Monju" plant data

(10)Effect of natural convection prevention plate in primary sodium pump(2)

*Tatsuya Morioka¹, hashidate ryuta¹, Sawazaki Hiromasa¹, Shiotani Hiroki¹, Kunogi Kosuke¹ (1. JAEA)

4:20 PM - 4:35 PM

[2J16] The results obtained from the 20 years of "Monju" plant data

(11)the shaft sealing mechanism of primary sodium pump

*Ryuta Hashidate¹, Tatsuya Morioka¹, Hiromasa Sawazaki¹, Hiroki Shiotani¹, Ikuhito Obata¹, Takanori Kobayashi¹, Ryouichi Uekura¹, (1. Japan Atomic Energy Agency )

4:35 PM - 4:50 PM

[2J17] Preliminary Studies for Applicability related to the Large Reactor Vessel of Pool-type SFR

(1)Seismic Evaluation

*Masato Uchita¹, Koji Dozaki¹, Tetsuji Suzuno², Tsuyoshi Fukasawa², Hiroki Hayafune³, Atsushi Katoh³ (1. Japan Atomic Power Company , 2. Mitsubishi FBR Systems Inc., 3. Japan Atomic Energy Agency)

4:50 PM - 5:05 PM

[2J18] Preliminary Studies for Applicability related to the Large Reactor Vessel of Pool-type SFR

(2)Thermal Hydraulic Analysis

*Hiroyuki Hagiwara¹, Osamu Watanabe¹, Kazuhiro Oyama¹, Masato Ando¹, Hiroyuki Ohshima², Hidemasa Yamano³ (1. MFBR, 2. JAPC, 3. JAEA)

5:05 PM - 5:20 PM

[2J19] Preliminary Studies for Applicability related to the Large Reactor Vessel of Pool-type SFR

(3)Thermal Transient Evaluation

*Yoshitaka Chikazawa¹, Shigenobu Kubo¹, Takayuki Miyagawa², Masao eto³ (1. JAEA, 2. JAPC, 3. MFBR)

Time reserved for Chair （5:20 PM - 5:25 PM）

Oral presentation

[2J20-23] Decay Heat Removal and Na-cleaning

Thu. Sep 14, 2017 5:25 PM - 6:30 PM Room J (C309 - C Block)

Chair:Masato Uchita (JAPC)

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5:25 PM - 5:40 PM

[2J20] Study on In-Vessel Coolability by Decay Heat Removal Systems in Sodium-cooled Fast Reactors

Preliminary Investigation of Experimental Requirements for A Sodium Test Apparatus with Different In-Vessel Direct Heat Exchangers

*Masaaki Tanaka¹, Katsunori Amano¹, Nobuyuki Ishikawa¹, Kunihiko Nabeshima¹, Hiroyuki Ohshima¹, Kazuhiro Oyama², Hironori Nakamura², Takashi Ichihara² (1. JAEA, 2. MFBR)

5:40 PM - 5:55 PM

[2J21] PLANDTL-2 Experiment for Evaluation of Decay Heat Removal in Sodium-cooled Fast Reactors

Preliminary Confirmation Tests of Fundamental Performance at Steady and Transient Conditions

*Jun Kobayashi¹, Toshiki Ezure¹, Takamitsu Onojima¹, Ayako Ono¹, Akikazu Kurihara¹, Masaaki Tanaka¹, Hiroyuki Ohshima¹ (1. JAEA)

5:55 PM - 6:10 PM

[2J22] Dry Cleaning Process Test for Fuel Assembly of Fast Reactor Plant System

(1)Sodium Test Loop Operation

*Yuichi Ohtani¹, Hideyuki Kudoh¹, Seiho Utsumi¹, Masako Tanaka¹, Atsushi Katoh², Yoshitaka Chikazawa², Keiichi Nagai², Kuniaki Ara², Masahiko Ohtaka², Akihiro Ide³ (1. MHI, 2. JAEA, 3. MFBR)

6:10 PM - 6:25 PM

[2J23] Dry Cleaning Process Test for Fuel Assembly of Fast Reactor Plant System

(2)Test Results and Prediction Evaluation of a Fuel Assembly

*Hideyuki Kudoh¹, Ohtani Yuichi¹, Seiho Utsumi¹, Masahide Hara¹, Atsushi Katoh², Yoshitaka Chikazawa², Keiichi Nagai², Kuniaki Ara², Masahiko Ohtaka², Akihiro Ide³ (1. MHI, 2. JAEA, 3. MFBR)

Time reserved for Chair （6:25 PM - 6:30 PM）

Sessions

III. Fission Energy Engineering » 302-1 Advanced Reactor System

[1J01-04] Innovative Reactors and Technologies

Reaction Suppression (11)

Reaction Suppression (12)

3rd report, Electrochemical measurement of radioactivated stainless steel

4th report, RISA on metal surface wettability

[1J05-08] Pu-burning Gas-cooled Reactor

(14)Objectives, current status and future

(15)Vital Area Identification Analysis concerning Pu-burner HTGR

(16)Experimental Study on the Transient Oxidation of Nuclear Graphite under Air Ingress Conditions

(17)Numerical Study on the Transient Oxidation of Nuclear Graphite under Air Ingress Conditions

[1J09-12] Gas-cooled Reactors

(18)Fuel design and core design

(19)Preliminary reactivity transient analyses

(20)Study on 3S-TRISO fuel fabrication

(21)Test and Characterization for ZrC Coating

[1J13-16] Gas-cooled Reactor Fuel

(1)Outlines

(2)Development of fabrication technology of oxidation resistant fuel element

(3)Development on Inspection of Oxidation Resistant Fuel Element

(4)Modeling for Casting Oxidation Resistant Fuel Element

[2J01-09] Breakage Prevention of Containment Vessel

(17)Outline

(18)Summary of Development of Detailed Numerical Simulation Methods for Sodium Fire

(19)Numerical analysis of sodium droplet combustion by VOF method

(20)Summary of sodium-concrete reaction experiments

(21)Examination of chemical reaction behavior of core debris-sodium-concrete interactions by thermodynamic calculation

(22)Chemical reaction analysis of the hydrogen combustion by sodium vapor/mist ignition

(23)Numerical simulation of hydrogen combustion in containment vessel of fast reactor

(24)Study on behaviors of boundary components until mechanical loss of function based on experiments and analyses

(25)Proposal of evaluation method of the limits of mechanical loss of function in the boundary components

[2J10-14] Decommissioning of Monju

(1)Approach to safety evaluations during decommissioning phase

(2)Conservative thermal evaluations on fuel integrity

(3)Evaluation of accidents during decommissioning phase

(4)Resistance to hazards during decommissioning phase

[2J15-19] Pump and Reactor Vessel of Na-cooled Reactor

(10)Effect of natural convection prevention plate in primary sodium pump(2)

(11)the shaft sealing mechanism of primary sodium pump

(1)Seismic Evaluation

(2)Thermal Hydraulic Analysis

(3)Thermal Transient Evaluation

[2J20-23] Decay Heat Removal and Na-cleaning

Preliminary Investigation of Experimental Requirements for A Sodium Test Apparatus with Different In-Vessel Direct Heat Exchangers

Preliminary Confirmation Tests of Fundamental Performance at Steady and Transient Conditions

(1)Sodium Test Loop Operation

(2)Test Results and Prediction Evaluation of a Fuel Assembly

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