Oral presentation

[1A09-14] Treatment Technology of Concrete and Metal

Tue. Mar 26, 2024 2:45 PM - 4:20 PM Room A (21Bildg.2F 21-203)

Chair:Yukihiro IGUCHI(Univ. of Fukui)

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2:45 PM - 3:00 PM

[1A09] Management of non-radioactive waste in concrete dismantlement

*Keisuke Toda¹, Koji Ando¹, Haruhiko Kadowaki¹, Masashi Tezuka¹, Takumi Hatakeyama¹, Takeshi Iekura¹, Akira Matsushima¹ (1. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[1A10] Volume reduction of concrete contaminated by ¹⁴CO₂

(3) The amount of vaporization for ¹⁴CO₂ during concrete debris is heated

*Norikazu Kinoshita¹, Hitoshi Nakashima¹, Akira Saito¹, Hayato Takeshita¹, Koki Sakita¹, Kazuyuki Torii¹, Yuki Sasaki¹, Mamoru Hanzawa¹, Aya Sakaguchi² (1. Shimizu, 2. Univ. of Tsukuba)

3:15 PM - 3:30 PM

[1A11] Volume reduction of concrete contaminated by ¹⁴CO₂

(4) Removal of deposit from surface aggregate after rubbing

*Hitoshi Nakashima¹, Norikazu Kinoshita¹, Akira Saito¹, Hayato Takeshita¹, Koki Sakita¹, Kazuyuki Torii¹, Yuki Sasaki¹, Mamoru Hanzawa¹ (1. SHIMIZU CORPORATION)

3:30 PM - 3:45 PM

[1A12] Processing of concrete surface removal by high power density and rapid CW laser irradiation

*Satoshi Ishihara¹, Haruo Nagamine¹, Ryosuke Sato² (1. TAISEI CORPORATION, 2. Toyo Union)

3:45 PM - 4:00 PM

[1A13] Development of high-power density, high-speed scanning laser decontamination technology

(1) Experimental evaluation of metal surface delamination

*Atsushi Kosuge¹ (1. JAEA)

4:00 PM - 4:15 PM

[1A14] Development of high-power density, high-speed scanning laser decontamination technology

(2) Analytical evaluation of metal surface delamination

*Naoyuki Kisohara¹, Yuji Aoyagi², Toshihiro Taguchi¹ (1. Japan Atomic Energy Agency, 2. NESI Inc.)

Time reserved for Chair （4:15 PM - 4:20 PM）

Oral presentation

[1A15-18] Decommissioning of the Accident Reactor

Tue. Mar 26, 2024 4:20 PM - 5:30 PM Room A (21Bildg.2F 21-203)

Chair:Norikazu Kinoshita(Shimizu)

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4:20 PM - 4:35 PM

[1A15] Development of Technology for Inspection inside the Reactor Pressure Vessels (RPVs) at Fukushima Daiichi NPS

*Shingo Maeda¹, Takashi Mitsui¹, Hitoshi Manabe¹, Takashi Itou¹, Masanori Hatori¹, Itaru Suzuki¹ (1. Tousou Mirai Technology Co. Ltd. )

4:35 PM - 4:50 PM

[1A16] Underwater fuel debris recovery method

窒化ホウ素のブラストを用いたウォタージェット回収装置

*Yasufumi Kitaura¹, Haruo Morishige² (1. Kitamura, 2. Fukushima Accident Countermeasures Review Group)

4:50 PM - 5:05 PM

[1A17] Assessment of dust dispersion data for future safety analysis of Fukushima Daiichi fuel debris retrieval

(15) Simulations to evaluate the effects of casing shape and cutting conditions on the dust dispersion behavior

*Kenta Kato¹, Kenta Inagaki¹, Tadafumi Koyama¹, Koichi Uozumi¹, Taizo Kanai¹, Kinya Nakamura¹, Shun Kanagawa¹, Takatoshi Hijikata¹, Tetsuya Kato¹, Daisuke Yamauchi² (1. CRIEPI, 2. TEPCO HD)

5:05 PM - 5:20 PM

[1A18] Study on the degradation scenario of reinforced concrete structures and their reflection on the long-term maintenance plan for a reactor building in an accident-damaged nuclear power plant (Follow-up Report)

*Koji Dozaki¹, Takayuki Aoki¹ (1. Tohoku University)

Time reserved for Chair （5:20 PM - 5:30 PM）

Oral presentation

[2A01-04] Decommissioning of the Reactor Facility

Wed. Mar 27, 2024 9:30 AM - 10:35 AM Room A (21Bildg.2F 21-203)

Chair:Chikara Konno(JAEA)

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9:30 AM - 9:45 AM

[2A01] Introduction of the Decommissioning Project in Nuclear Science Research Institute

*Yuichi Handa¹, Ryota Nakajima¹, Yuta Yokozuka¹, Tatsuya Sakai¹, Satoshi Yamada¹ (1. JAEA)

9:45 AM - 10:00 AM

[2A02] A Study for the optimization of the decommissioning project of nuclear facilities

(5) Assessment of dismantlement cost performance evaluation

*Yukihiro IGUCHI¹, Daisuke KAWASAKI¹, Satoshi YANAGIHRA¹, Yuya KOUDA² (1. University of Fukui, 2. JAEA)

10:00 AM - 10:15 AM

[2A03] Research and development of lead block cutting technique for decommissioning nuclear power plants Ⅳ

*Tomohisa Goto^1,3, Glenn Harvel², Takeyoshi Sunagawa¹ (1. FUT, 2. Ontario Tech Univ., 3. Taihei Dengyo Ltd.)

10:15 AM - 10:30 AM

[2A04] Dismantlement of receiving and storage process equipment for transportation of spent fuels

*Yu Saegusa¹, Saki Nishino¹, Koji Horie¹, Hitoshi Yatabe¹, Takashi Yamada¹, Daisuke Ohyama¹, Naoki Uchida¹ (1. JAEA)

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

Oral presentation

[2A05-09] Radioactivity Inventory

Wed. Mar 27, 2024 10:35 AM - 12:00 PM Room A (21Bildg.2F 21-203)

Chair:Koji Dozaki(Tohoku Univ.)

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10:35 AM - 10:50 AM

[2A05] ORIGEN decay and fission product yield libraries produced from JENDL-5

*Chikara Konno¹, Mami Kochiyama¹, Hirokazu Hayashi¹ (1. Japan Atomic Energy Agency)

10:50 AM - 11:05 AM

[2A06] Standard models of commercial nuclear reactor in Japan for using radioactivity calculations

(3) Test calculation of BWR model

*Kazuaki Kosako¹, Takuma Noto¹, Hayato Takeshita¹, Yuki Sasaki¹, Kazuyuki Torii¹ (1. Shimizu Corporation)

11:05 AM - 11:20 AM

[2A07] Assessment of contamination distribution of “Monju”

(1) Overview of assessment and activation of fuel handling system

*Shotaro Hanaki¹, Takuma Kinoshita², Yasufumi Kishimoto², Hirokazu Hayashi¹ (1. JAEA, 2. NESI)

11:20 AM - 11:35 AM

[2A08] Assessment of contamination distribution of “Monju”

(2) Assessment of activation of the under-floor transfer car

*Takuma Kinoshita¹, Yasuhumi Kishimoto¹, Syotaro Hanaki², Hirokazu Hayashi² (1. NESI, 2. JAEA)

11:35 AM - 11:50 AM

[2A09] Assessment of contamination distribution of “Monju”

(3) Assessment of activation of Ex-Vessel Strage Tank (EVST)

*Yasufumi Kishimoto¹, Takuma Kinoshita¹, Shotaro Hanaki², Hirokazu Hayashi² (1. NESI, 2. JAEA)

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

Sessions

V. Nuclear Fuel Cycle and Nuclear Materials » 505-3 Decommissioning Technology of Nuclear Facilities

[1A09-14] Treatment Technology of Concrete and Metal

[1A09] Management of non-radioactive waste in concrete dismantlement

[1A10] Volume reduction of concrete contaminated by ¹⁴CO₂

(3) The amount of vaporization for ¹⁴CO₂ during concrete debris is heated

[1A11] Volume reduction of concrete contaminated by ¹⁴CO₂

(4) Removal of deposit from surface aggregate after rubbing

[1A12] Processing of concrete surface removal by high power density and rapid CW laser irradiation

[1A13] Development of high-power density, high-speed scanning laser decontamination technology

(1) Experimental evaluation of metal surface delamination

[1A14] Development of high-power density, high-speed scanning laser decontamination technology

(2) Analytical evaluation of metal surface delamination

[1A15-18] Decommissioning of the Accident Reactor

[1A15] Development of Technology for Inspection inside the Reactor Pressure Vessels (RPVs) at Fukushima Daiichi NPS

[1A16] Underwater fuel debris recovery method

窒化ホウ素のブラストを用いたウォタージェット回収装置

[1A17] Assessment of dust dispersion data for future safety analysis of Fukushima Daiichi fuel debris retrieval

(15) Simulations to evaluate the effects of casing shape and cutting conditions on the dust dispersion behavior

[1A18] Study on the degradation scenario of reinforced concrete structures and their reflection on the long-term maintenance plan for a reactor building in an accident-damaged nuclear power plant (Follow-up Report)

[2A01-04] Decommissioning of the Reactor Facility

[2A01] Introduction of the Decommissioning Project in Nuclear Science Research Institute

[2A02] A Study for the optimization of the decommissioning project of nuclear facilities

(5) Assessment of dismantlement cost performance evaluation

[2A03] Research and development of lead block cutting technique for decommissioning nuclear power plants Ⅳ

[2A04] Dismantlement of receiving and storage process equipment for transportation of spent fuels

[2A05-09] Radioactivity Inventory

[2A05] ORIGEN decay and fission product yield libraries produced from JENDL-5

[2A06] Standard models of commercial nuclear reactor in Japan for using radioactivity calculations

(3) Test calculation of BWR model

[2A07] Assessment of contamination distribution of “Monju”

(1) Overview of assessment and activation of fuel handling system

[2A08] Assessment of contamination distribution of “Monju”

(2) Assessment of activation of the under-floor transfer car

[2A09] Assessment of contamination distribution of “Monju”

(3) Assessment of activation of Ex-Vessel Strage Tank (EVST)

Authentication

Sessions

V. Nuclear Fuel Cycle and Nuclear Materials » 505-3 Decommissioning Technology of Nuclear Facilities

[1A09-14] Treatment Technology of Concrete and Metal

(3) The amount of vaporization for 14CO2 during concrete debris is heated

(4) Removal of deposit from surface aggregate after rubbing

(1) Experimental evaluation of metal surface delamination

(2) Analytical evaluation of metal surface delamination

[1A15-18] Decommissioning of the Accident Reactor

窒化ホウ素のブラストを用いたウォタージェット回収装置

(15) Simulations to evaluate the effects of casing shape and cutting conditions on the dust dispersion behavior

[2A01-04] Decommissioning of the Reactor Facility

(5) Assessment of dismantlement cost performance evaluation

[2A05-09] Radioactivity Inventory

(3) Test calculation of BWR model

(1) Overview of assessment and activation of fuel handling system

(2) Assessment of activation of the under-floor transfer car

(3) Assessment of activation of Ex-Vessel Strage Tank (EVST)

Authentication

(3) The amount of vaporization for ¹⁴CO₂ during concrete debris is heated