*Delgersaikhan Tuya¹, Toru Obara² (1. Department of Nuclear Engineering, Tokyo Institute of Technology, 2. Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology)

10:50 AM - 11:05 AM

[2G06] Nuclear reactor one-point kinetic calculations with explicit model of fission product nuclides

*Koji Katagiri¹, Go Chiba¹, Tadashi Narabayashi¹ (1. Hokkaido Univ.)

11:05 AM - 11:20 AM

[2G07] Analysis of ICPP criticality accident by Quasi-steady-state method taking into account change in uranium concentration during boiling

*Tomoaki Watanabe¹, Yuichi Yamane¹ (1. Japan Atomic Energy Agency)

11:20 AM - 11:35 AM

[2G08] Investigation of burnup calculations using Optimally-Weighted Predictor Corrector Method

*Shintaro Okumura¹, Go Chiba¹, Tadashi Narabayashi¹ (1. Hokkaido Univercity)

11:35 AM - 11:50 AM

[2G09] An Investigation of the Core Neutronics Analysis Conditions for Evaluation of Burnup Nuclear Characteristics of Next-Generation Fast Reactors

(2)The Core Neutronics Analysis Conditions for Evaluation of Fuel Assembly Power Distribution and Maximum Linear Power Density

*Kazuo Takino¹, Kazuteru Sugino¹, Shigeo Ohki¹ (1. JAEA)

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

Oral presentation

[2G10-13] Analysis Method Development 2

Thu. Sep 14, 2017 2:45 PM - 3:50 PM Room G (C213 - C Block)

Chair:Tomoaki Watanabe (JAEA)

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2:45 PM - 3:00 PM

[2G10] Development of collision probability method based on Mesh to Mesh computation (9)

Application of combination method with IC method to cylindrical system

*Tetsuo Matsumura¹ (1. CRIEPI)

3:00 PM - 3:15 PM

[2G11] Research on a neutron transport calculation method based on IGA

*Willem Van Rooijen¹, Riho Horita¹ (1. Research Institute of Nuclear Engineering)

3:15 PM - 3:30 PM

[2G12] Partial Current Discontinuity Factors via JFNK in HIRE-Theoretic Multigroup Transport Equations

*Nam Zin Cho¹, Seungsu Yuk¹, YuGwon Jo¹ (1. KAIST)

3:30 PM - 3:45 PM

[2G13] Convergence Criterion in Monte Carlo Criticality Calculation based on Stochastic Differential Equation

*Taro Ueki¹ (1. Japan Atomic Energy Agency)

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

Oral presentation

[2G14-18] Criticality Control Technique Development 1

Thu. Sep 14, 2017 3:50 PM - 5:10 PM Room G (C213 - C Block)

Chair:Kenya Suyama (JAEA)

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3:50 PM - 4:05 PM

[2G14] Study on container capacity limitations of remove fuel debris in defueling Fukushima Daiichi nuclear power station

(1)Effect of floor materials on the criticality of fuel debris leaked from a container during defueling work

*Kei Yoshioka¹, Naoyuki Takaki¹, Hiroki Takezawa¹, Toru Morikawa¹, Isamu Sato¹ (1. Tokyo City University)

4:05 PM - 4:20 PM

[2G15] Study on container capacity limitations of removed fuel debris in defueling Fukushima Daiichi nuclear power station

(2)Criticality effect of deposition angle of fuel debris leaked from a container during defueling work

*Toru Morikawa¹, Kei Yoshioka¹, Naoyuki Takaki¹, Hiroki Takezawa¹, Isamu Sato¹ (1. Tokyo City University)

4:20 PM - 4:35 PM

[2G16] Criticality control technique development for Fukushima Daiichi fuel debris

(29)Criticality control technique development for Fukushima Daiichi fuel debris

*Makoto Nakano^1,2, Yasuhiro Harada^2,1, Yamato Hayashi^2,3, Yuuichi Morimoto^2,4 (1. MHI, 2. IRID, 3. Toshiba, 4. Hitachi GE)

4:35 PM - 4:50 PM

[2G17] Criticality control technique development for Fukushima Daiichi fuel debris

(30)Proposal of a statistical evaluation method for the criticality of the Fukushima Daiichi Nuclear Power Plants

*Yuichi Morimoto^1,2, Masanori Akaike^1,2, Satoshi Takeo^1,2, Kazuya Ishii^1,2, Hiromi Maruyama^1,2,3 (1. IRID, 2. Hitachi GE, 3. NAIS)

4:50 PM - 5:05 PM

[2G18] Criticality control technique development for Fukushima Daiichi fuel debris

(31)Debris uncertainty on sub-criticality estimation with Feynman-alpha method

*Satoshi Wada^1,2, Kenichi Yoshioka^1,2, Shigeto Kikuchi^1,2 (1. IRID, 2. TOSHIBA)

Time reserved for Chair （5:05 PM - 5:10 PM）

Oral presentation

[2G19-23] Criticality Control Technique Development 2

Thu. Sep 14, 2017 5:10 PM - 6:30 PM Room G (C213 - C Block)

Chair:Kenya Suyama (JAEA)

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5:10 PM - 5:25 PM

[2G19] Criticality control technique development for Fukushima Daiichi fuel debris

(32)Operation verification of Sub-criticality monitoring system using neutron source

*Shinya Kano^1,2, Mitsuru Oikawa^1,2, Hiroyuki Yazawa^1,2 (1. IRID, 2. Toshiba)

5:25 PM - 5:40 PM

[2G20] Criticality control technique development for Fukushima Daiichi fuel debris

(33)Study on Application of Y_inf Correlation Equation of Feynman-alpha Method to Sub-criticality

*Mikio TOKASHIKI¹, Shinya KANO^2,3, Satoshi WADA^2,3, Shigeto KIKUCHI^2,3 (1. Nuclear Fuel Industries, Ltd., 2. International Research Institute for Nuclear Decommissioning, 3. TOSHIBA CORPORATION)

5:40 PM - 5:55 PM

[2G21] Criticality control technique development for Fukushima Daiichi fuel debris

(34)Criticality detection by virtual neutron capture method

*Takeshi Mitsuyasu^1,2, Aoyama Motoo^1,2, Yuichi Morimoto^1,2 (1. IRID, 2. Hitachi-GE Nuclear Energy, Ltd.)

5:55 PM - 6:10 PM

[2G22] Criticality control technique development for Fukushima Daiichi fuel debris

(35)Applicable confirmation examination of neutron detectors to radiation environment derived from the fuel assembly for subcritical multiplication factor monitor

*Koichi Okada^1,2, Hiroyuki Yazawa^1,3, Yuichi Morimoto^1,2, Takahiro Tadokoro^1,2, Yuichiro Ueno^1,2 (1. IRID, 2. Hitachi-GE, 3. TOSHIBA)

6:10 PM - 6:25 PM

[2G23] Criticality control technique development for Fukushima Daiichi fuel debris

(36)Neutron Multiplication Factor Estimation using Measured Data from PCV Gas Control System at Fukushima Daiichi Nuclear Power Plant Unit 1 (II)

*Masanori Akaike^1,2, Yuichi Morimoto^1,2, Satoshi Takeo^1,2, Hiromi Maruyama^1,2,3, Yu Toriyabe^1,2, Hideaki Matsumoto⁴ (1. IRID, 2. Hitachi GE, 3. Present affiliation is NAIS, 4. TEPCO)

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

Oral presentation

[3G01-05] Criticality Control Technique Development 3

Fri. Sep 15, 2017 9:30 AM - 10:50 AM Room G (C213 - C Block)

Chair:Kenichi Tada (JAEA)

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9:30 AM - 9:45 AM

[3G01] Criticality control technique development for Fukushima Daiichi fuel debris

(37)Methodology for applying insoluble neutron absorbers

Ryo Ishibashi^1,2, Yuta Shindo^1,3, *Kazuya Ishii^1,2, Yuichi Morimoto^1,2, Yasuhiro Harada^1,4 (1. IRID, 2. Hitachi-GE Nuclear Energy, 3. Toshiba, 4. Mitsubishi Heavy Industries)

9:45 AM - 10:00 AM

[3G02] Criticality control technique development for Fukushima Daiichi fuel debris

(38)Viscosity and conveyance process performance of insoluble neutron absorber

*Shohei Kawano^1,2, Yuta Shindo^1,2, Satoshi Miyashiro^1,2 (1. IRID, 2. Toshiba)

10:00 AM - 10:15 AM

[3G03] Criticality control technique development for Fukushima Daiichi fuel debris

(39)Adhesion property of insoluble absorber

*Yuta Shindo^1,2, Shohei Kawano^1,2, Satoshi Miyashiro^1,2 (1. IRID, 2. TOSHIBA)

10:15 AM - 10:30 AM

[3G04] Criticality control technique development for Fukushima Daiichi fuel debris

(40)Applicability of soluble neutron absorber

*Yasuhiro Harada^1,2, Makoto Nakano^1,2, Minefumi Matsui^1,2 (1. MHI, 2. IRID)

10:30 AM - 10:45 AM

[3G05] Development of the insoluble neutron absorbers using self-assembled surfactant aggregates

*Noriaki Ushio¹, Kouji Koyanagi¹, Hiroyuki Terazaki¹ (1. Kao Corporation)

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

Oral presentation

[3G06-09] Criticality Safety

Fri. Sep 15, 2017 10:50 AM - 11:55 AM Room G (C213 - C Block)

Chair:Masahiro Fukushima (JAEA)

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10:50 AM - 11:05 AM

[3G06] Study on Criticality Safety of Directly Disposed Spent PWR Fuel

(1)Estimation of a Subcriticality Criterion and Neutron Poison Amount Evaluation to Ensure Subcriticality

*Hiroshi Akie¹, Masaharu Kataoka^1,2, Kenya Suyama¹ (1. Japan Atomic Energy Agency, 2. Current Affiliation: NAIS Co. Inc.)

11:05 AM - 11:20 AM

[3G07] Study on Criticality Safety of Directly Disposed Spent PWR Fuel

(2)International Benchmark on Reflector Effect of SiO₂

*Kenya Suyama¹, Hiroshi Akie¹, Masaharu Kataoka^1,2, Kento Yamamoto^1,3 (1. Japan Atomic Energy Agency, 2. NAIS Co. Inc., 3. Nuclear Fuel Industries, Ltd.)

11:20 AM - 11:35 AM

[3G08] Confirmation of critical limit on low enriched UO₂ fuel using MVP / JENDL4

(1)The validation using the critical experiments benchmark calculation

*shigeaki aoki¹, takeshi nakamura¹ (1. MNF)

11:35 AM - 11:50 AM

[3G09] Confirmation of critical limit on low enriched UO₂ fuel using MVP / JENDL4

(2)Confirmation of critical limit

*TAKESHI NAKAMURA¹, SHIGEAKI AOKI¹ (1. Mitsubishi Nuclear Fuel)

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

Oral presentation

[3G10-13] Subcriticality Experiment and Evaluation 1

Fri. Sep 15, 2017 2:45 PM - 3:50 PM Room G (C213 - C Block)

Chair:Atsushi Sakon (Kindai Univ.)

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2:45 PM - 3:00 PM

[3G10] Student experiments using subcritical core with natural uranium

*Tsuyoshi Misawa¹ (1. Kyoto University Research Reactor Institute)

3:00 PM - 3:15 PM

[3G11] Study on Data Assimilation Techniques using Subcritical Experiment

*Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya University)

3:15 PM - 3:30 PM

[3G12] A research for the estimation of a prompt neutron decay constant using linear combination method.

*Ryota Katano¹, Kazufumi Tsujimoto¹ (1. JAEA)

3:30 PM - 3:45 PM

[3G13] Application of bias factor method for effective delayed neutron fraction using subcritical experiment data

*Toshiki Kimura¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya University)

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

Oral presentation

[3G14-17] Subcriticality Experiment and Evaluation 2

Fri. Sep 15, 2017 3:50 PM - 4:55 PM Room G (C213 - C Block)

Chair:Shunsuke Sato (CRIEPI)

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3:50 PM - 4:05 PM

[3G14] Development of Innovative Nuclear Waste Burning System by Fast Reactor Cycle Using Pu Metallic Fuel with MA

(14)Measurement of Doppler Effect for Metallic Fuel Alloy Material with Pulsed Neutron Source II

*Hironobu Unesaki¹, Tadafumi Sano¹, Jun-ichi Hori¹, Yoshiyuki Takahashi¹, Ken Nakajima¹, Akihiro Hara², Yasushi Tsuboi², Kazuo Arie² (1. Kyoto University Research Reactor Institute, 2. TOSHIBA CORPORATION)

4:05 PM - 4:20 PM

[3G15] Reactivity estimation based on asymptotic behavior of power in subcritical state

*Yuichi Yamane¹ (1. Japan Atomic Energy Agency)

4:20 PM - 4:35 PM

[3G16] Development of subcriticality monitoring method during shutdown and refueling modes of nuclear power plant

(6)Study on the aggregation method of the subcriticality results from multiple signals

*Shoichi Tashiro^1,2, Masayuki Tojo¹, Yoichiro Shimazu^2,3 (1. GNF-J, 2. Univ. of Fukui, 3. Khalifa Univ.)

4:35 PM - 4:50 PM

[3G17] Experimental Investigation on Probability Distribution of Neutron Counts in a Nuclear Reactor

*Kunihiro Nakajima¹, Sin-ya Hohara², Atsushi Sakon², Kengo Hashimoto² (1. Interdisciplinary Graduate School of Science and Technology, Kindai University, 2. Atomic Energy Research Institute, Kindai University)

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

Oral presentation

[1L01-04] Uncertainty Evaluation 1

Wed. Sep 13, 2017 2:45 PM - 3:50 PM Room L (N302 - N Block)

Chair:Tatsuya Fujita (NRA)

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2:45 PM - 3:00 PM

[1L01] Uncertainty analysis for neutronics parameters of PWR core

(5)Uncertainty evaluation of core characteristics

*Yuki Takemoto¹, Kazuki Kirimura¹, Shinya Kosaka¹, Hideki Matsumoto¹, Toshikazu Takeda² (1. Mitsubishi Heavy Industries, Ltd., 2. University of Fukui)

3:00 PM - 3:15 PM

[1L02] Uncertainty Analysis of Reactivity Measurement in Solid-Moderated and -Reflected Core at Kyoto University Critical Assembly (2)

*Masao YAMANAKA¹, Song Hyun KIM¹, Cheol Ho PYEON¹ (1. Kyoto University Research Reactor Institute)

3:15 PM - 3:30 PM

[1L03] Uncertainly evaluation of isotopic composition of spent fuel by random sampling method.

*Shunsuke Nihira¹, Go Chiba¹, Shintaro Okumura¹, Tadashi Narabayashi¹ (1. Hokkaido Univ )

3:30 PM - 3:45 PM

[1L04] Impact of truncated coated fuel particles on neutronic characteristic in statistical geometry model of MVP code

*Hai Quan Ho¹, Yuki Honda¹, Nozomu Fujimoto², Minoru Goto¹, Etsuo Ishitsuka¹ (1. Japan Atomic Energy Agency, 2. Kyushu University)

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

Oral presentation

[1L05-09] Uncertainty Evaluation 2

Wed. Sep 13, 2017 3:50 PM - 5:10 PM Room L (N302 - N Block)

Chair:Tomohiro Endo (Nagoya Univ.)

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3:50 PM - 4:05 PM

[1L05] Study on the impact of thermal scattering law data improvements on nuclear calculation for light water reactor

*Satoshi Takeda¹, Mikiihko Muta¹, Hikaru Yamaguchi¹, Takanori Kitada¹, Yasunori Ohoka², Matsuoka Shogo², Nagano Hiroaki² (1. Osaka University, 2. NUCLEAR FUEL INDUSTRIES, LTD.)

4:05 PM - 4:20 PM

[1L06] Investigation of the impact of the difference of probability table calculation method

*Kenichi Tada¹ (1. JAEA)

4:20 PM - 4:35 PM

[1L07] Study on the effect of temperature and uranium enrichment on burnup characteristics in HTGRs

*Keisuke Morita¹, Nozomu Fujimoto¹, Yuji Fukaya², Yuki Honda² (1. Kyushu university, 2. JAEA)

4:35 PM - 4:50 PM

[1L08] Reactivity effect of Pu heterogeneity in MOX fuel on critical analysis of light water reactor MOX core physics experiments

(1)Study on analysis models

*Tomohiro Sakai¹, Toru Yamamoto¹, Daiki iwahashi¹ (1. S/NRA/R)

4:50 PM - 5:05 PM

[1L09] Reactivity effect of Pu heterogeneity in MOX fuel on critical analysis of light water reactor MOX core physics experiments

(2)Analysis on MOX core physics experiments performed at EOLE critical facility

*Toru Yamamoto¹, Tomohiro Sakai¹, Daiki Iwahashi¹ (1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))

Time reserved for Chair （5:05 PM - 5:10 PM）

Oral presentation

[1L10-13] Code Development and Varidation 1

Wed. Sep 13, 2017 5:10 PM - 6:15 PM Room L (N302 - N Block)

Chair:Satoshi Wada (TOSHIBA)

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5:10 PM - 5:25 PM

[1L10] Development of Mitsubishi FBR nuclear design code system GALAXY-H/ENSEMBLE-TRIZ

(5)Development of fuel pin power reconstruction model

*Yohei Kamiyama¹, Hiroki Koike¹, Kazuki Kirimura¹, Yuki Takemoto¹, Shinya Kosaka¹ (1. Mitsubishi Heavy Industries, Ltd.)

5:25 PM - 5:40 PM

[1L11] Development of Mitsubishi FBR nuclear design code system GALAXY-H/ENSEMBLE-TRIZ

(6)Development of shielding analysis model

*Kazuki Kirimura¹, Hiroki Koike¹, Shinya Kosaka¹, Akio Yamamoto² (1. Mitsubishi Heavy Industries, Ltd., 2. Nagoya University)

5:40 PM - 5:55 PM

[1L12] Development of uncertainty evaluation methodology for core characteristics with Mitsubishi new nuclear design code system GalaxyCosmo-S

(1)Summary of uncertainty evaluation methodology and system

*Hiroki Koike¹, Kazuki Kirimura¹, Daisuke Sato¹, Shinya Kosaka¹, Hiroyuki Fujime² (1. MHI, 2. MHI NSE)

5:55 PM - 6:10 PM

[1L13] Development of uncertainty evaluation methodology for core characteristics with Mitsubishi new nuclear design code system GalaxyCosmo-S

(2)Test analysis of uncertainties for core characteristics

*Hiroyuki Fujime¹, Hiroki Koike², Kazuki Kirimura², Daisuke Sato², Shinya Kosaka² (1. MHI NSE, 2. MHI)

Time reserved for Chair （6:10 PM - 6:15 PM）

Sessions

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[2G01-04] Code Development and Varidation 2

5)reactivity control method of the solid-moderator core with burnable poisons

Analysis of the SPERT-III Experiments by TRACE/PARCS code (Cold-statrup, hot-standby, and operating power conditions)

(3)Analysis of Kobayashi 3D Benchmark Problem

[2G05-09] Analysis Method Development 1

(2)The Core Neutronics Analysis Conditions for Evaluation of Fuel Assembly Power Distribution and Maximum Linear Power Density

[2G10-13] Analysis Method Development 2

Application of combination method with IC method to cylindrical system

[2G14-18] Criticality Control Technique Development 1

(1)Effect of floor materials on the criticality of fuel debris leaked from a container during defueling work

(2)Criticality effect of deposition angle of fuel debris leaked from a container during defueling work

(29)Criticality control technique development for Fukushima Daiichi fuel debris

(30)Proposal of a statistical evaluation method for the criticality of the Fukushima Daiichi Nuclear Power Plants

(31)Debris uncertainty on sub-criticality estimation with Feynman-alpha method

[2G19-23] Criticality Control Technique Development 2

(32)Operation verification of Sub-criticality monitoring system using neutron source

(33)Study on Application of Yinf Correlation Equation of Feynman-alpha Method to Sub-criticality

(34)Criticality detection by virtual neutron capture method

(35)Applicable confirmation examination of neutron detectors to radiation environment derived from the fuel assembly for subcritical multiplication factor monitor

(36)Neutron Multiplication Factor Estimation using Measured Data from PCV Gas Control System at Fukushima Daiichi Nuclear Power Plant Unit 1 (II)

[3G01-05] Criticality Control Technique Development 3

(37)Methodology for applying insoluble neutron absorbers

(38)Viscosity and conveyance process performance of insoluble neutron absorber

(39)Adhesion property of insoluble absorber

(40)Applicability of soluble neutron absorber

[3G06-09] Criticality Safety

(1)Estimation of a Subcriticality Criterion and Neutron Poison Amount Evaluation to Ensure Subcriticality

(2)International Benchmark on Reflector Effect of SiO2

(1)The validation using the critical experiments benchmark calculation

(2)Confirmation of critical limit

[3G10-13] Subcriticality Experiment and Evaluation 1

[3G14-17] Subcriticality Experiment and Evaluation 2

(14)Measurement of Doppler Effect for Metallic Fuel Alloy Material with Pulsed Neutron Source II

(6)Study on the aggregation method of the subcriticality results from multiple signals

[1L01-04] Uncertainty Evaluation 1

(5)Uncertainty evaluation of core characteristics

[1L05-09] Uncertainty Evaluation 2

(1)Study on analysis models

(2)Analysis on MOX core physics experiments performed at EOLE critical facility

[1L10-13] Code Development and Varidation 1

(5)Development of fuel pin power reconstruction model

(6)Development of shielding analysis model

(1)Summary of uncertainty evaluation methodology and system

(2)Test analysis of uncertainties for core characteristics

Authentication

(33)Study on Application of Y_inf Correlation Equation of Feynman-alpha Method to Sub-criticality

(2)International Benchmark on Reflector Effect of SiO₂