Oral presentation

[1B01-02] Code Development 1 (Nuclear Data)

Wed. Mar 17, 2021 10:00 AM - 10:45 AM Room B (Zoom room 2)

Chair: Kunihiro Nakajima (Kindai Univ.)

10:00 AM - 10:15 AM

[1B01] Statistical error calculation method for probability table generation

*Kenichi Tada¹, Tomohiro Endo² (1. JAEA, 2. Nagoya Univ.)

10:15 AM - 10:30 AM

[1B02] Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations

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

*Michitaka Ono¹, Masayuki Tojo¹, Kenichi Tada², Akio Yamamoto³ (1. GNF-J, 2. JAEA, 3. Nagoya Univ.)

Time reserved for Chair （10:30 AM - 10:45 AM）

Oral presentation

[1B03-06] Code Development 2

Wed. Mar 17, 2021 10:45 AM - 12:00 PM Room B (Zoom room 2)

Chair: Rei Kimura (TOSHIBA ESS)

10:45 AM - 11:00 AM

[1B03] Development of Three-Dimentional Heterogenious Transient Calculation Code RYUHO

(1)Benchmark Calculation Results by Prototype Code and Future Development Works

*Tatsuya Fujita¹, Naofumi Tsukamto¹ (1. Nuclear Regulation Authority)

11:00 AM - 11:15 AM

[1B04] A Development of Multi-Physics Burnup Analysis System

(1)An Overall Plan and Implementation of Burnup Calculation Module

*Motomu Suzuki¹ (1. CRIEPI)

11:15 AM - 11:30 AM

[1B05] Development of Core Management Code System SHIKOKU2

(1)Improvement of Burnup Calculation Model

*Masami Hirano¹, Yosuke Kawamoto¹, Emi Yoshida¹, Kosuke Miyawaki¹, Kazuma Oohori², Yutaka Umakoshi² (1. Yonden Eng., 2. YONDEN)

11:30 AM - 11:45 AM

[1B06] Development of Core Management Code System SHIKOKU2

(2)Improvement of Neutron Transport Calculation Model

*Yosuke Kawamoto¹, Masami Hirano¹, Emi Yoshida¹, Kosuke Miyawaki¹, Kazuma Oohori², Yutaka Umakoshi² (1. Yonden Eng., 2. YONDEN)

Time reserved for Chair （11:45 AM - 12:00 PM）

Oral presentation

[1B07-11] Uncertainty Evaluation

Wed. Mar 17, 2021 2:45 PM - 4:15 PM Room B (Zoom room 2)

Chair: Kenichi Tada (JAEA)

2:45 PM - 3:00 PM

[1B07] Uncertainty Quantification of Criticality in the KUCA-C core with HEU Fuel

*Kota Morioka¹, Cheolho Pyeon¹ (1. Kyoto Univ.)

3:00 PM - 3:15 PM

[1B08] Reactor noise analysis using MVP code for subcritical systems in KUCA

*Kunihiro Nakajima¹, Yasunobu Nagaya², Atsushi Sakon¹, Tadafumi Sano¹, Kengo Hashimoto¹ (1. Kindai Univ., 2. JAEA)

3:15 PM - 3:30 PM

[1B09] Development of reactor noise measurement using BGO detectors in UTR-KINKI

*Masaki Goto¹, Takashi Kanda¹, Kunihiro Nakajima¹, Tadafumi Sano¹, Atsushi Sakon¹, Kengo Hashimoto¹ (1. KINDAI Univ.)

3:30 PM - 3:45 PM

[1B10] Numerical analysis and uncertainty quantification for pulsed neutron experiments with water tanks by PHITS

*Kenta Asakura¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya Univ.)

3:45 PM - 4:00 PM

[1B11] Nuclear Data-induced Uncertainty Quantification of Prompt Neutron Decay Constant for Water-only System

*Tomohiro Endo¹, Akihiro Noguchi¹, Akio Yamamoto¹ (1. Nagoya Univ.)

Time reserved for Chair （4:00 PM - 4:15 PM）

Oral presentation

[2B01-05] Criticality Safety (Fuel Debris)

Thu. Mar 18, 2021 9:30 AM - 11:00 AM Room B (Zoom room 2)

Chair: Tatsuya Fujita (NRA)

9:30 AM - 9:45 AM

[2B01] Application of Calculation Method of Estimated Criticality Lower-Limit Multiplication Factor using the Bootstrap Method to Fuel-Debris-Simulated Systems

*Takuto Hayashi¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya Univ.)

9:45 AM - 10:00 AM

[2B02] Criticality safety analysis of fuel debris by Japan-Russia international joint study

*Toru Obara¹, Jun Nishiyama¹, Takeshi Muramoto¹, Taro Fumimoto¹, Hiroki Takezawa², Smirnov D. Anton³, Ekaterina V. Bogdanova³, Pavel A. Pugachev³, Ivan S. Saldikov³, Georgy V. Tikhomirov³ (1. Tokyo Tech, 2. TCU, 3. MEPhI)

10:00 AM - 10:15 AM

[2B03] Delta Tracking Monte Carlo Neutron Transport with Voxel Mesh Overlay

*TARO UEKI¹ (1. JAEA)

10:15 AM - 10:30 AM

[2B04] Criticality safety analysis in fuel debris falling down simulation using MPS in real scale geometry

*Taro Fumimoto¹, Takeshi Muramoto¹, Jun Nishiyama¹, Toru Obara¹ (1. Tokyo Tech)

10:30 AM - 10:45 AM

[2B05] Effect of Neutron Generation Time on Supercritical Transient Analysis in Fuel Debris during Falling Down in Water

*Kodai Fukuda¹, Takeshi Muramoto¹, Jun Nishiyama¹, Toru Obara¹ (1. Tokyo Tech)

Time reserved for Chair （10:45 AM - 11:00 AM）

Oral presentation

[2B06-08] HTTR Analysis

Thu. Mar 18, 2021 11:00 AM - 12:00 PM Room B (Zoom room 2)

Chair: Jun Nishiyama (Tokyo Tech)

11:00 AM - 11:15 AM

[2B06] Reanalysis of HTTR's start-up physics tests using detailed models

*Yudai Yamamoto¹, Hai Quan Ho², Etsuo Ishitsuka², Nozomu Fujimoto¹ (1. KYUSHU UNIVERSITY, 2. Japan Atomic Energy Agency)

11:15 AM - 11:30 AM

[2B07] Calculation of decay gamma spectrum of the HTTR after shutdown

*Hai Quan Ho¹, Shimpei Hamamoto¹, Nozomu Fujimoto², Satoru Nagasumi¹, Minoru Goto¹, Etsuo Ishitsuka¹ (1. JAEA, 2. Kyushu Univ.)

11:30 AM - 11:45 AM

[2B08] HTTR brunup calculation with MVP-BURN

Calculation with detailed axial mesh model

*Nozomu Fujimoto¹, Reiji Ikeda¹, Hai Quan Ho², Shinpei Hamamoto², Satoru Nagasumi², Etsuo Ishitsuka² (1. Kyushu Univ., 2. JAEA)

Time reserved for Chair （11:45 AM - 12:00 PM）

Oral presentation

[2B09-12] Analysis Method 1 (Burnup)

Thu. Mar 18, 2021 2:45 PM - 4:00 PM Room B (Zoom room 2)

Chair: Tomohiro Endo (Nagoya Univ.)

2:45 PM - 3:00 PM

[2B09] Development of pseudo FP generation algorithm for nuclear fuel burnup calculations

(1)Outline of the algorithm

*Kento Yanagihara¹, Go Chiba¹ (1. Hokkaido Univ.)

3:00 PM - 3:15 PM

[2B10] Development of Pseudo FP generation algorithm for nuclear fuel burnup calculations

(2)Numerical results

Kento Yanagihara¹, *Go Chiba¹ (1. Hokkaido University)

3:15 PM - 3:30 PM

[2B11] Depletion calculation of subcritical system with consideration of spontaneous fission reaction

*Eka Sapta Riyana¹, Keisuke Okumura¹, Masahiro Sakamoto¹, Taichi Matsumura¹, Kenichi Terashima¹ (1. JAEA)

3:30 PM - 3:45 PM

[2B12] Development of Accelerated Matrix Exponential Method for Burnup Calculation in Nuclear Material Balance code

*Tomohiro OKAMURA¹, Kenji NISHIHARA², Akito Oizumi², Masahiko NAKASE¹, Kenji TAKESHITA¹ (1. Tokyo Tech, 2. JAEA)

Time reserved for Chair （3:45 PM - 4:00 PM）

Oral presentation

[2B13-17] Analysis Method 2

Thu. Mar 18, 2021 4:00 PM - 5:30 PM Room B (Zoom room 2)

Chair: Kenichi Tada (JAEA)

4:00 PM - 4:15 PM

[2B13] Dimension-reduced cross-section adjustment method based on Bayesian Monte-Carlo method

*Yuhei Fukui¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya University)

4:15 PM - 4:30 PM

[2B14] Treatment of scattering sources in numerical calculations of the radiative transfer equation with discrete ordinates methods

*Ryosuke Shimizu¹, Go Chiba¹ (1. Hokkaido Univ.)

4:30 PM - 4:45 PM

[2B15] Impact of Flat Flux Approximation on Convergence Performance of ACMFD Acceleration

*Yoshiki Oshima¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya Univ.)

4:45 PM - 5:00 PM

[2B16] Sub-group method applied to Iso Geometric Analysis calculation code

*Matthias Hermann Nezondet¹, Willem F.G. van Rooijen¹ (1. Univ. of Fukui)

5:00 PM - 5:15 PM

[2B17] Implementation of SP₃ method calculation capability to FRBurner module of CBZ code system

(2)Component-wise sodium void reactivity results investigation and comparison

*Junshuang Fan¹, Go Chiba¹ (1. Hokkaido Univ.)

Time reserved for Chair （5:15 PM - 5:30 PM）

Oral presentation

[3B01-04] Burunup Analysis (BWR)

Fri. Mar 19, 2021 9:30 AM - 10:45 AM Room B (Zoom room 2)

Chair: Tomohiro Endo (Nagoya Univ.)

9:30 AM - 9:45 AM

[3B01] Whole Core Three-Dimensional Nuclide Inventory Calculation of the Fukushima Daiichi Nuclear Power Station

(1)Background and Purpose

*Keisuke Okumura¹, Masahiro Sakamoto¹, Kenichi Tada¹, Kenji Nishihara¹, Shinya Mizokami², Masato Mizokami², Miki Yousuke³, Seiji Kaneko³ (1. JAEA, 2. TEPCO HD, 3. TEPSYS)

9:45 AM - 10:00 AM

[3B02] Whole Core Three-Dimensional Nuclide Inventory Calculation of the Fukushima Daiichi Nuclear Power Station

(2)Calculation Method and Result for Unit-2

*Masahiro Sakamoto¹, Keisuke Okumura¹, Kenichi Tada¹, Kenji Nishihara¹, Shinya Mizokami², Masato Mizokami², Yousuke Miki³, Seiji Kaneko³ (1. JAEA, 2. TEPCO HD, 3. TEPSYS)

10:00 AM - 10:15 AM

[3B03] Evaluation of operating history effect on BWR fuel reactivity in storage rack

*Daiki Iwahashi¹, Tetsuo Nakajima¹ (1. NRA)

10:15 AM - 10:30 AM

[3B04] Improvement of high-efficiency random sampling method by using control variates method and sensitivity

(2)Application to burnup characteristics of BWR fuel assembly

*Takumi Kida¹, Go Tiba¹ (1. Hokkaido Univ.)

Time reserved for Chair （10:30 AM - 10:45 AM）

Oral presentation

[3B05-08] Advanced Reactor

Fri. Mar 19, 2021 10:45 AM - 12:00 PM Room B (Zoom room 2)

Chair: Takanori Sugawara (JAEA)

10:45 AM - 11:00 AM

[3B05] Core power distribution re-construction method based on the ex-core detector with power correlation between fuel regions

(1)Theoretical examination and its verification

*Rei Kimura¹, Yuki Nakai¹, Satoshi Wada¹ (1. TOSHIBA ESS)

11:00 AM - 11:15 AM

[3B06] Core power distribution re-construction method based on the ex-core detector with power correlation between fuel regions

(2)Effect of detector uncertainty

*Yuki Nakai¹, Rei Kimura¹, satoshi wada¹ (1. TOSHIBA ESS)

11:15 AM - 11:30 AM

[3B07] Measurement of Calcium Hydrate sample worth in UTR-KINKI

*Takashi Kanda¹, Kunihiro Nakajima¹, Atsushi Sakon¹, Tadafumi Sano¹, Rei Kimura², Satoshi Wada², Kengo Hashimoto¹ (1. Kindai Univ., 2. TOSHIBA ESS)

11:30 AM - 11:45 AM

[3B08] An inherent safety gas-cooled fast reactor concept of “Eco-KAMADO”

Reactivity change due to core inundation in accident

*Tetsuo Matsumura¹, Takanori Kameyama¹ (1. Tokai University)

Time reserved for Chair （11:45 AM - 12:00 PM）

Sessions

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

[1B01-02] Code Development 1 (Nuclear Data)

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

[1B03-06] Code Development 2

(1)Benchmark Calculation Results by Prototype Code and Future Development Works

(1)An Overall Plan and Implementation of Burnup Calculation Module

(1)Improvement of Burnup Calculation Model

(2)Improvement of Neutron Transport Calculation Model

[1B07-11] Uncertainty Evaluation

[2B01-05] Criticality Safety (Fuel Debris)

[2B06-08] HTTR Analysis

Calculation with detailed axial mesh model

[2B09-12] Analysis Method 1 (Burnup)

(1)Outline of the algorithm

(2)Numerical results

[2B13-17] Analysis Method 2

(2)Component-wise sodium void reactivity results investigation and comparison

[3B01-04] Burunup Analysis (BWR)

(1)Background and Purpose

(2)Calculation Method and Result for Unit-2

(2)Application to burnup characteristics of BWR fuel assembly

[3B05-08] Advanced Reactor

(1)Theoretical examination and its verification

(2)Effect of detector uncertainty

Reactivity change due to core inundation in accident

Authentication