Oral presentation

[1I01-04] Criticality Safety of Fuel Debris

Mon. Mar 16, 2020 10:45 AM - 11:55 AM Room I (Lecture Bildg. M 2F M-23)

Chair:Rei Kimura(TOSHIBA ESS)

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10:45 AM - 11:00 AM

[1I01] Criticality calculations of fuel debris in various conditions during falling down

*Anton Smirnov¹, Ekaterina Bogdanova¹, Georgy Tikhomirov¹, Hiroki Takezawa², Jun Nishimaya³, Toru Obara³ (1. MEPhI, 2. TCU, 3. Tokyo Tech)

11:00 AM - 11:15 AM

[1I02] Criticality safety evaluation of powder fuel debris using DEM and MPS method

*Takeshi Muramoto¹, Jun Nishiyama¹, Toru Obara¹ (1. Tokyo institute of Technology)

11:15 AM - 11:30 AM

[1I03] Consequence analysis of postulated criticality in SFP using the randomized model of fuel debris

*Irwan Liapto Simanullang¹, Yuichi Yamane¹, Takeo Kikuchi¹, Kotaro Tonoike¹ (1. JAEA)

11:30 AM - 11:45 AM

[1I04] Radiolysis gas reactivity feedback effect on prompt supercritical transient analysis of fuel debris

*Kodai Fukuda¹, Jun Nishiyama², Toru Obara² (1. Graduate major in Nuclear Engineering, Tokyo Institute of Technology, 2. Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology)

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

Oral presentation

[1I05-07] Subcriticality Evaluation Method

Mon. Mar 16, 2020 2:45 PM - 3:35 PM Room I (Lecture Bildg. M 2F M-23)

Chair:Tadafumi Sano(Kindai Univ.)

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2:45 PM - 3:00 PM

[1I05] Applicability of the Extended Kalman Filter Technique to Reactivity Monitoring at KUCA

(2)Introduction of Area Ratio to the Filter Technique

*Masao Yamanaka¹, Cheol Ho Pyeon¹ (1. KURNS)

3:00 PM - 3:15 PM

[1I06] Subcriticality Estimation using Unscented Kalman Filter

*Tomohiro Endo¹, Akio Yamamoto¹, Masao Yamanaka², Cheol Ho Pyeon² (1. Nagoya Univ., 2. KURNS)

3:15 PM - 3:30 PM

[1I07] Measurement of Subcriticality in Dollar Units using Time-Domain Decomposition Based Integral Method

Asahi Nonaka¹, *Tomohiro Endo¹, Sho Imai¹, Kenichi Watanabe¹, Akio Yamamoto¹, Masao Yamanaka², Cheol Ho Pyeon² (1. Nagoya University, 2. Institute for Integrated Radiation and Nuclear Science, Kyoto University)

Time reserved for Chair （3:30 PM - 3:35 PM）

Oral presentation

[1I08-12] Advanced Reactor Development

Mon. Mar 16, 2020 3:35 PM - 5:00 PM Room I (Lecture Bildg. M 2F M-23)

Chair:Tomohiro Endo(Nagoya Univ.)

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3:35 PM - 3:50 PM

[1I08] Critical Experiments of Thorium Loaded Cores at KUCA

(3)A Critical experiment with hard neutron spectrum core (B1/8"p41ETE)

*Tadafumi Sano¹, Hironobu Unesaki², Yoshiyuki Takahashi², Jun-ichi Hori², Hiroshi Yashima², Kunihiro Nakajima¹ (1. Atomic Energy Research Institute, Kindai University , 2. Kyoto University)

3:50 PM - 4:05 PM

[1I09] Critical Experiments of Thorium Loaded Cores at KUCA

(4)Verification of Criticality Evaluation Accuacy of Thorium Loaded Critical Experiments at KUCA

*Hironobu Unesaki¹, Yoshiyuki Takahashi¹, Jun-ichi Hori¹, Hiroshi Yashima¹, Tadafumi Sano² (1. Inst. Integrated Radiation and Nuclear Science, Kyoto Univ., 2. Kindai Univ.)

4:05 PM - 4:20 PM

[1I10] Development of Inherent Safety Fast Reactor by Using Blanket Bearing Minor Actinides

(9)Effect of Control Rod Position on Void Reactivity for Fast Reactor with Sodium Plenum

*Sho Fuchita¹, Koji Fujimura¹, Kazuhiro Fujimata¹, Satoshi Takeda², Toshikazu Takeda³ (1. HGNE, 2. Osaka Univ., 3. Univ. of Fukui)

4:20 PM - 4:35 PM

[1I11] Hydride moderated heat-pipe cooled very small modular reactor MoveluX

(3)Conceptual design of the passive reactivity control device

*Rei Kimura¹, Shohei Kanamura¹, Yuya Takahashi¹, Kazuhito Asano¹ (1. Toshiba ESS)

4:35 PM - 4:50 PM

[1I12] Evaluation of analysis accuracy in graphite-moderated critical assembly by Monte-Carlo code

*Naoki Nakagawa¹, Nozomu Fujimoto¹, Quan Hai Ho², Shimpei Hamamoto², Satoru Nagasumi², Etsuo Ishitsuka² (1. Kyushu Univ., 2. JAEA)

Time reserved for Chair （4:50 PM - 5:00 PM）

Oral presentation

[2I01-03] Analysis Method of Experiment

Tue. Mar 17, 2020 10:00 AM - 10:50 AM Room I (Lecture Bildg. M 2F M-23)

Chair:Satoshi Wada(TOSHIBA ESS)

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10:00 AM - 10:15 AM

[2I01] Application of SG method to reactivity estimation based on subcrtical quasi-state power profile equation

*Yuichi Yamane¹ (1. JAEA)

10:15 AM - 10:30 AM

[2I02] Development of Measurement Method of Prompt Neutron Decay Constant α using the Dynamic Mode Decomposition

*Fuga Nishioka¹, Tomohiro Endo¹, Akio Yamamoto¹, Masao Yamanaka², Cheol Ho Pyeon² (1. Nagoya Univ., 2. Institute for Integrated Radiation and Nuclear Science, Kyoto University)

10:30 AM - 10:45 AM

[2I03] A Study for Reactor Noise Measurement in Power Operation at Kyoto Univ. Reactor Part.3

*Sin-ya Hohara¹, Atsushi Sakon¹, Kunihiro Nakajima², Kazuki Takahashi², Tadafumi Sano¹, Jyunichi Hori³, kengo Hashimoto¹ (1. Kindai Univ. AERI, 2. Graduate School of Sci. and Eng., Kindai Univ., 3. Institute of Integrated Radiation and Nuclear Science, Kyoto Univ.)

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

Oral presentation

[2I04-07] Development of Nuclear Data Processing Code

Tue. Mar 17, 2020 10:50 AM - 12:00 PM Room I (Lecture Bildg. M 2F M-23)

Chair:Go Chiba(Hokkaido Univ.)

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10:50 AM - 11:05 AM

[2I04] Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations

(1)Overview of comparison of nuclear data processing

*Kenichi Tada¹, Tadashi Ikehara¹, Michitaka Ono², Masayuki Tojo² (1. JAEA, 2. GNF-J)

11:05 AM - 11:20 AM

[2I05] Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations

(2)Investigation of the impact of difference between nuclear data processes on nuclear calculations

*Michitaka Ono¹, Masayuki Tojo¹, Kenichi Tada², Tadashi Ikehara² (1. GNF-J, 2. JAEA)

11:20 AM - 11:35 AM

[2I06] Feasibility study of low power HTGR for long-term operation

*Hai Quan Ho¹, Nozomu Fujimoto², Shimpei Hamamoto¹, Satoru Nagasumi¹, Etsuo Ishitsuka¹ (1. JAEA, 2. Kyushu Univ.)

11:35 AM - 11:50 AM

[2I07] Multi-group Cross Section Generation Capability using ACE File

*Akio Yamamoto¹, Tomohiro Endo¹, Kenichi Tada² (1. Nagoya Univ., 2. JAEA)

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

Oral presentation

[2I08-11] Development of Analysis Method & Code 1

Tue. Mar 17, 2020 2:45 PM - 3:50 PM Room I (Lecture Bildg. M 2F M-23)

Chair:Go Chiba(Hokkaido Univ.)

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2:45 PM - 3:00 PM

[2I08] Development of a Monte Carlo Solver Solomon for Criticality Safety Analysis

(3)Implementation of Thermal Neutron Scattering Models

*Yasunobu Nagaya¹ (1. JAEA)

3:00 PM - 3:15 PM

[2I09] Adjoint-weighted kinetics parameter calculation using multigroup version of Solomon solver

*Delgersaikhan Tuya¹, Yasunobu Nagaya¹ (1. Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[2I10] A Resonance Calculation Method using Energy Expansion Bases based on Reduced Order Model

(3)Application to multi-cells

*Ryoichi Kondo¹, Tomohiro Endo¹, Akio Yamamoto¹, Satoshi Takeda², Hiroki Koike³, Kazuya Yamaji³, Daisuke Sato³ (1. Nagoya Univ., 2. Osaka Univ., 3. MHI)

3:30 PM - 3:45 PM

[2I11] Development of Mitsubishi Three-Dimensional Heterogeneous Transport Calculation Code GALAXY-Z

(4)Resonance Calculation using the RSE Method

*Kazuya Yamaji¹, Hiroki Koike¹, Koichi Ieyama¹, Daisuke Sato¹, Akio Yamamoto², Satoshi Takeda³ (1. MHI, 2. Nagoya Univ., 3. Osaka Univ.)

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

Oral presentation

[2I12-15] Development of Analysis Method & Code 2

Tue. Mar 17, 2020 3:50 PM - 4:55 PM Room I (Lecture Bildg. M 2F M-23)

Chair:Hiroki Koike(MHI)

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3:50 PM - 4:05 PM

[2I12] BWR whole core nuclear-thermal hydraulic coupled simulation system

(6)Investigation of Assembly Discontinuity Factor correction method

*Masayuki Tojo¹, Michitaka Ono¹, Munenari Yamamoto (1. GNF-J)

4:05 PM - 4:20 PM

[2I13] An Investigation on Improvement of the Core Neutronics Design Calculation Method for Advanced Fast Reactors (6)

Investigation on the improvement in power distribution evaluation

*Kazuteru Sugino¹, Shigeo Ohki¹ (1. JAEA)

4:20 PM - 4:35 PM

[2I14] Improvement of Optimally-Weighted Predictor-Corrector Method for Nuclear Fuel Burnup Calculation (2)

*JUMPEI SASUGA¹, Go Chiba¹, Yasunori Ohoka², Kento Yamamoto², Hiroaki Nagano² (1. Hokkaido University, 2. NFI)

4:35 PM - 4:50 PM

[2I15] Extension of the hierarchical-domain decomposition boundary element method to the general multi-group diffusion equation

*Tian Qin¹, Go Chiba¹ (1. Hokkaido Univ)

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

Oral presentation

[3I01-05] Uncertainty Evaluation

Wed. Mar 18, 2020 10:30 AM - 11:55 AM Room I (Lecture Bildg. M 2F M-23)

Chair:Tomohiro Endo(Nagoya Univ.)

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10:30 AM - 10:45 AM

[3I01] Study on Probability Distribution of Input Nuclear Data using Random Sampling Method for Uncertainty Quantification of Reactor Physics Parameters

*Ryotaro Kimura¹, Go Chiba¹ (1. Hokkaido University)

10:45 AM - 11:00 AM

[3I02] Uncertainty Analysis on Depletion Calculation Using CASMO5

(2)Calculation Results in Fuel Assembly Geometry

*Tatsuya Fujita¹, Tomohiro Sakai¹ (1. Secretariat of Nuclear Regulation Authority)

11:00 AM - 11:15 AM

[3I03] Development of Nuclear Uncertainty Reduction Methodology for Spent Fuel Pit using Critical Experimental Data

(1)Objective and Outline of Methodology

*Hiroki Koike¹, Daisuke Sato¹, Toshikazu Takeda², Satoshi Takeda³, Takanori Kitada³ (1. MHI, 2. Univ. of Fukui, 3. Osaka Univ.)

11:15 AM - 11:30 AM

[3I04] Development of Nuclear Uncertainty Reduction Methodology for Spent Fuel Pit using Critical Experimental Data

(2)Uncertainty Evaluation by Cross Section Adjustment and Applicable Covariance Data

*Toshikazu Takeda¹, Satoshi Takeda², Takanori Kitada², Hiroki Koike³, Daisuke Sato³ (1. University of Fukui, 2. Osaka University, 3. Mitsubishi Heavy Industries)

11:30 AM - 11:45 AM

[3I05] Development of Nuclear Uncertainty Reduction Methodology for Spent Fuel Pit using Critical Experimental Data

(3)Uncertainty Evaluation for Sub-Criticality of Spent Fuel Pit

*Takanori Kitada¹, Satoshi Takeda¹, Hiroki Koike², Daisuke Sato², Toshikazu Takeda³ (1. Osaka University, 2. MHI, 3. Fukui University)

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

Sessions

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

[1I01-04] Criticality Safety of Fuel Debris

[1I05-07] Subcriticality Evaluation Method

(2)Introduction of Area Ratio to the Filter Technique

[1I08-12] Advanced Reactor Development

(3)A Critical experiment with hard neutron spectrum core (B1/8"p41ETE)

(4)Verification of Criticality Evaluation Accuacy of Thorium Loaded Critical Experiments at KUCA

(9)Effect of Control Rod Position on Void Reactivity for Fast Reactor with Sodium Plenum

(3)Conceptual design of the passive reactivity control device

[2I01-03] Analysis Method of Experiment

[2I04-07] Development of Nuclear Data Processing Code

(1)Overview of comparison of nuclear data processing

(2)Investigation of the impact of difference between nuclear data processes on nuclear calculations

[2I08-11] Development of Analysis Method & Code 1

(3)Implementation of Thermal Neutron Scattering Models

(3)Application to multi-cells

(4)Resonance Calculation using the RSE Method

[2I12-15] Development of Analysis Method & Code 2

(6)Investigation of Assembly Discontinuity Factor correction method

Investigation on the improvement in power distribution evaluation

[3I01-05] Uncertainty Evaluation

(2)Calculation Results in Fuel Assembly Geometry

(1)Objective and Outline of Methodology

(2)Uncertainty Evaluation by Cross Section Adjustment and Applicable Covariance Data

(3)Uncertainty Evaluation for Sub-Criticality of Spent Fuel Pit

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