Oral Presentation

[2I01-07] Pu burning high-temperature gas-cooled reactor

Thu. Sep 8, 2016 10:00 AM - 11:55 AM Room I (Kumume City Plaza - Meeting Room)

Chair: Koki Hibi (MFBR)

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10:00 AM - 10:15 AM

[2I01] Development of Security and Safety Fuel for Pu-burner HTGR

(7)Objectives and current status

*Koji OKAMOTO¹, Kazuhiko KUNITOMI², Kazutaka OHASHI³, Hideaki KISHITA⁴ (1.The University of Tokyo, 2.Japan Atomic Energy Agency, 3.Fuji Electric Co., Ltd., 4.Nuclear Fuel Industries, Ltd.)

10:15 AM - 10:30 AM

[2I02] Development of Security and Safety Fuel for Pu-burner HTGR

(8)Quantitative Evaluation of Security and Safety

*Kazuyuki Demachi¹, Jonathan Poli¹, Wataru Sagawa¹, Masahiro Kondo¹, Nedjet Erkan¹, Koji Okamoto¹ (1.The University of Tokyo)

10:30 AM - 10:45 AM

[2I03] Development of Security and Safety Fuel for Pu-burner HTGR

(9)Radiation heat transfer property evaluation with graphite experiment

*Masahiro Kondo¹, Wataru Sagawa¹, Penghui Chai¹, Yang Wu¹, Koji Okamoto¹ (1.Tokyo University)

10:45 AM - 11:00 AM

[2I04] Development of Security and Safety Fuel for Pu-burner HTGR

(10)Evaluation on internal pressure of fuel and nuclear characteristics of reactor core

*Minoru GOTO¹, Shohei UETA¹, Yoshitomo INABA¹, Jun AIHARA¹, Yuji FUKAYA¹, Yukio TACHIBANA¹, Kazuhiko KUNITOMI¹, Koji OKAMOTO² (1.Japan Atomic Energy Agency, 2.The University of Tokyo)

11:00 AM - 11:15 AM

[2I05] Development of Security and Safety Fuel for Pu-burner HTGR

(11)Reactor temperature analyses in depressurization accident

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

11:15 AM - 11:30 AM

[2I06] Development of Security and Safety Fuel for Pu-burner HTGR

(12)Staudy on 3S-TRISO fuel fabrication

*Masaki Honda¹, Yohei Saiki¹, Hideaki Kishita¹, Koji Okamoto² (1.Nuclear Fuel Industries, LTD., 2.The University of Tokyo)

11:30 AM - 11:45 AM

[2I07] Development of Security and Safety Fuel for Pu-burner HTGR

(13)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 （11:45 AM - 11:55 AM）

Oral Presentation

[2I08-12] Core design of next generation sodium-cooled reactor

Thu. Sep 8, 2016 2:45 PM - 4:05 PM Room I (Kumume City Plaza - Meeting Room)

Chair: Minoru Goto (JAEA)

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2:45 PM - 3:00 PM

[2I08] Shielding design in the reactor vessel for the next generation sodium-cooled fast reactor

(1)Application of the connection method with Sn and Monte Carlo calculations for a streaming geometry

*FUKUCHI IKUO¹, HIGURASHI KOICHI¹, SHIRAKI TAKAKO², SUGINO KAZUTERU³, OHKI SHIGEO³ (1.MFBR, 2.MHI, 3.JAEA)

3:00 PM - 3:15 PM

[2I09] Shielding design in the reactor vessel for the next generation sodium-cooled fast reactor

(2)Improvement of shielding design methods for optimizing radial neutron shieldings

*Koki Hibi¹, Ikuo Fukuchi¹, Daisuke Masuyama², Kazuteru Sugino³, Shigeo Ohki³ (1.Mitsubishi FBR Systems, 2.Mitsubishi Heavy Industries,, 3.Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[2I10] Core design for the next generation sodium-cooled fast reactor

(1)Core performance requirements and design conditions

*Shigeo Ohki¹, Yoshitaka Chikazawa¹, Shigenobu Kubo¹, Koki Hibi², Taro Kan³ (1.JAEA, 2.MFBR, 3.MHI)

3:30 PM - 3:45 PM

[2I11] Core design for the next generation sodium-cooled fast reactor

(2)Reference core design

*Toru Tsuboi¹, Hiroyuki Moriwaki², Masashi Ogura², Koki Hibi², Seiichiro Maeda³, Kazuya Ohgama³, Yoshitaka Chikazawa³, Shigeo Ohki³ (1.MHI, 2.MFBR, 3.JAEA)

3:45 PM - 4:00 PM

[2I12] Core design for the next generation sodium-cooled fast reactor

(3)Design optimization for the core arrangement

*Hiroyuki Moriwaki¹, Masashi Ogura¹, Taro Kan², Shigeo Ohki³ (1.MFBR, 2.MHI, 3.JAEA)

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

Oral Presentation

[2I13-17] System of sodium-cooled reactor

Thu. Sep 8, 2016 4:05 PM - 5:25 PM Room I (Kumume City Plaza - Meeting Room)

Chair: Masaaki Nakano (Fuji Electric)

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4:05 PM - 4:20 PM

[2I13] Dry cleaning process test for fuel assembly of fast reactor plant system

(1)Master-planning

*Atsushi Katoh¹, Masako Tanaka³, Yuuichi Ohtani³, Nobuki Oka³, Akihiro Ide², Keiichi Nagai¹ (1.JAEA, 2.MFBR, 3.MHI)

4:20 PM - 4:35 PM

[2I14] Dry cleaning process test for fuel assembly of fast reactor plant system

(2)Glove box test results

*NOBUKI OKA¹, ATSUSHI KATO², KEIICHI NAGAI², MASAKO TANAKA¹, YUICHI OHTANI¹, AKIHIRO IDE³ (1.MHI, 2.JAEA, 3.MFBR)

4:35 PM - 4:50 PM

[2I15] Design study for the structures for gas entrainment prevention and gas exclusion at the primary pump of the next generation sodium-cooled fast reactor

*Katsunori Amano¹, Yasuhiro Enuma¹, Yoshitaka Chikazawa¹, Osamu Watanabe², Satoshi Hayakawa², Tomoyuki Inoue² (1.Japan Atomic Energy Agency, 2.MITSUBISHI FBR SYSTEMS, INC.)

4:50 PM - 5:05 PM

[2I16] A study of measures against sodium-water reaction in next generation sodium-cooled fast reactor based on SDG

*Hironori Kanda¹, Yasuhiro Enuma¹, Satoshi Futagami¹, Yoshitaka Chikazawa¹, Yasushi Okano¹, Naoki Yoshioka², Hiroshi Ushiki² (1.JAEA, 2.MFBR)

5:05 PM - 5:20 PM

[2I17] Reinforcement of imergency power supply system for next generation SFR

*Nobuyuki Ishikawa¹, Yoshitaka Chikazawa¹, Daisuke Sato², Risako Ikari² (1.JAEA, 2.MFBR)

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

Oral Presentation

[2I18-21] Sodium with suspended nanoparticles

Thu. Sep 8, 2016 5:25 PM - 6:30 PM Room I (Kumume City Plaza - Meeting Room)

Chair: Kuniyoshi Takamatsu (JAEA)

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5:25 PM - 5:40 PM

[2I18] Study on safety enhancement of the fast reactor by using nanoparticle suspension sodium

(22)Progress of Project

*KUNIAKI ARA¹, AKIRA MIYAMOTO², MASAHIKO NAGAI³, KOICHI KURITA⁴ (1.JAEA, 2.Touhoku Univ., 3.MHI, 4.MFBR)

5:40 PM - 5:55 PM

[2I19] Study on safety enhancement of the fast reactor by using nanoparticle suspension sodium

(23)Reaction Suppression (6)

*JUN-ICHI SAITO¹, KEIICHI NAGAI¹, KUNIAKI ARA¹ (1.JAEA)

5:55 PM - 6:10 PM

[2I20] Study on safety enhancement of the fast reactor by using nanoparticle suspension sodium

(24)Reaction Suppression (7)

*KEIICHI NAGAI¹, JUN-ICHI SAITO¹, KUNIAKI ARA¹ (1.JAEA)

6:10 PM - 6:25 PM

[2I21] Study on safety enhancement of the fast reactor by using nanoparticle suspension sodium

(25)Theoretical study (8)

*Nozomu Hatakeyama¹, Ryuji Miura¹, Ai Suzuki¹, Akira Miyamoto¹, Junichi Saito², Kuniaki Ara² (1.Tohoku University, 2.JAEA)

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

Oral Presentation

[3I01-07] Knowledge preservation of Monju data and next generation sodium-cooled reactor

Fri. Sep 9, 2016 10:00 AM - 11:55 AM Room I (Kumume City Plaza - Meeting Room)

Chair: Kazuyuki Demachi (Univ. of Tokyo)

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10:00 AM - 10:15 AM

[3I01] The results obtained from the 20 years of “Monju” plant data

(1)Overview

*hiromasa sawazaki¹, naoyuki kisohara¹, yoshihide nakamura¹, takeshi sato¹ (1.JAEA)

10:15 AM - 10:30 AM

[3I02] The results obtained from the 20 years of “Monju” plant data

(2)Purity management of primary sodium system

*Yoshihide Nakamura¹, Hiromasa Sawazaki¹, Takeshi Sato¹, Naoyuki Kisohara¹ (1.JAEA)

10:30 AM - 10:45 AM

[3I03] The results obtained from the 20 years of “Monju” plant data

(3)Purification efficiency of secondary sodium purification system cold trap

*Takeshi Sato¹, Yasushi Ohkawachi¹, Yoshihide Nakamura¹, Hiromasa Sawazaki¹ (1.Japan Atomic Energy Agency)

10:45 AM - 11:00 AM

[3I04] Conceptual design of horizontal type under sodium viewer for next generation sodium-cooled fast reactor

*Kosuke Aizawa¹, Nobuchika Kawasaki¹, Yoshitaka Chikazawa¹, Eto Masao², Shoko Matsunaga² (1.JAEA, 2.MFBR)

11:00 AM - 11:15 AM

[3I05] Measures to prevent Loss of Heat Removal System in Next Generation Sodium-cooled Fast Reactor

*Yoshitaka Chikazawa¹, Shigenobu Kubo¹, Yoshio Shimakawa², Fumiaki Kaneko², takashi Shoji², shuhei Nakata² (1.JAEA, 2.MFBR)

11:15 AM - 11:30 AM

[3I06] Fuel and NFBC assemblies design for the next generation sodium-cooled fast reactor

(1)The conceptual design for the upper structure of fuel assembly

*Takayuki Ozawa¹, Seiichiro Maeda¹, Satoshi Hayakawa², Yukihide Mori² (1.Japan Atomic Energy Agency, 2.Mitsubushi FBR Systems, INC.)

11:30 AM - 11:45 AM

[3I07] Fuel and NFBC assemblies design for the next generation sodium-cooled fast reactor

(2)Optimization of a radial shielding structure

*HIROYUKI SAITO¹, Koichi Higurashi¹, Daisuke Masuyama², Shigeo Ohki³, Kazuya Ohgama³, Seiichiro Maeda³ (1.MFBR, 2.MHI, 3.JAEA)

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

Oral Presentation

[3I08-14] Space reactor, high-temperature gas-cooled reactor, and coated-particle-fueled light water reactor

Fri. Sep 9, 2016 2:45 PM - 4:40 PM Room I (Kumume City Plaza - Meeting Room)

Chair: Jun Nishiyama (Tokyo Tech)

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2:45 PM - 3:00 PM

[3I08] Small nuclear reactor for dispersed power systems

1)conceptual design of the reactor system for Luna and Mars surface missions

*Rei Kimura¹, Satoshi Wada¹, Taishi Yoshida¹, Yoshihiro Hyodo¹, Kunio Hoshino¹, Yoshiro Nishioka¹ (1.Toshiba)

3:00 PM - 3:15 PM

[3I09] Small nuclear reactor for dispersed power systems

2)nuclear design of the core for Luna and Mars surface missions

*Satoshi Wada¹, Rei Kimura¹, Taishi Yoshida¹, Yoshiro Nishioka¹, Yoshihiro Hyodo¹, Kunio Hoshino¹ (1.TOSHIBA)

3:15 PM - 3:30 PM

[3I10] Small nuclear reactor for dispersed power systems

3)nuclear-thermal analysis of the core for Luna and Mars surface missions

*Taishi Yoshida¹, Rei Kimura¹, Kunio Hoshino¹, Satoshi Wada¹, Yoshihiro Hyodo¹, Yoshiro Nishioka¹ (1.Toshiba)

3:30 PM - 3:45 PM

[3I11] Batch wise burnup analysis and fuel pin temperature evaluation of coated particle fuel LWR

*TAKAYA SUZUKI¹, NAOYUKI TAKAKI¹ (1.Tokyo City University)

3:45 PM - 4:00 PM

[3I12] Consideration of the hot pressing conditions of the high-strength fuel compact for high-temperature gas-cooled reactor

*Takenori Yamamoto¹, Takuya Tojo¹, Masatoshi Kuroda¹, Junya Sumita², Jun Aihara², Yukio Tachibana² (1.Kumamoto University, 2.JAEA)

4:00 PM - 4:15 PM

[3I13] New Reactor Cavity Cooling System (RCCS) having passive safety features

(1)Experimental Conditions of a Scale-down Heat Removal Test Facility for Comparison with a Real RCCS

*Kuniyoshi Takamatsu¹, Tatsuya Matsumoto², Koji Morita² (1.Japan Atomic Energy Agency, 2.Kyushu University)

4:15 PM - 4:30 PM

[3I14] New Reactor Cavity Cooling System (RCCS) Having Passive Safety Features

(2)Experimental Study on Heat Transfer Characteristics Using a Scale Model

*Noriyasu Sato¹, Shuhei Yamaguchi¹, Tatsuya Matsumoto¹, Koji Morita¹, Kuniyoshi Takamatsu² (1.Kyushu Univ., 2.JAEA)

Time reserved for Chair （4:30 PM - 4:40 PM）

Sessions

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

[2I01-07] Pu burning high-temperature gas-cooled reactor

(7)Objectives and current status

(8)Quantitative Evaluation of Security and Safety

(9)Radiation heat transfer property evaluation with graphite experiment

(10)Evaluation on internal pressure of fuel and nuclear characteristics of reactor core

(11)Reactor temperature analyses in depressurization accident

(12)Staudy on 3S-TRISO fuel fabrication

(13)Test and characterization for ZrC coating

[2I08-12] Core design of next generation sodium-cooled reactor

(1)Application of the connection method with Sn and Monte Carlo calculations for a streaming geometry

(2)Improvement of shielding design methods for optimizing radial neutron shieldings

(1)Core performance requirements and design conditions

(2)Reference core design

(3)Design optimization for the core arrangement

[2I13-17] System of sodium-cooled reactor

(1)Master-planning

(2)Glove box test results

[2I18-21] Sodium with suspended nanoparticles

(22)Progress of Project

(23)Reaction Suppression (6)

(24)Reaction Suppression (7)

(25)Theoretical study (8)

[3I01-07] Knowledge preservation of Monju data and next generation sodium-cooled reactor

(1)Overview

(2)Purity management of primary sodium system

(3)Purification efficiency of secondary sodium purification system cold trap

(1)The conceptual design for the upper structure of fuel assembly

(2)Optimization of a radial shielding structure

[3I08-14] Space reactor, high-temperature gas-cooled reactor, and coated-particle-fueled light water reactor

1)conceptual design of the reactor system for Luna and Mars surface missions

2)nuclear design of the core for Luna and Mars surface missions

3)nuclear-thermal analysis of the core for Luna and Mars surface missions

(1)Experimental Conditions of a Scale-down Heat Removal Test Facility for Comparison with a Real RCCS

(2)Experimental Study on Heat Transfer Characteristics Using a Scale Model

Authentication