Oral presentation

[1G07-10] Analysis Method Development 1 Burnup Calculation

Wed. Sep 7, 2022 2:45 PM - 3:50 PM Room G (E1 Bildg.3F No.32)

Chair:Satoshi TAKEDA

2:45 PM - 3:00 PM

[1G07] Improvement of the Predictor-Corrector method for burnup calculations in nuclear fuel containing burnable absorbers

*Fuga Miyazawa¹, Go Chiba¹, Kosuke Tsujita², Shuhei Miwa² (1. Hokkaido Univ., 2. NEL)

3:00 PM - 3:15 PM

[1G08] Study on fast computation of burnup calculations using MMPA on GPUs

*Yoshinari Harada¹, Hibiki Yamaguchi¹, Akio Yamamoto¹, Tomohiro Endo¹ (1. NAGOYA university)

3:15 PM - 3:30 PM

[1G09] Low-order model for time behavior of atomic number densities with radioactive decay

(3) Reduced order model for the difference to the asymptotic solutions

*Go Chiba¹, Yu Yoshifuji¹, Kosuke Tsujita², Shuhei Miwa² (1. Hokkaido Univ., 2. NEL)

3:30 PM - 3:45 PM

[1G10] Low-order model for time behavior of atomic number densities with radioactive decay

(4) Comparison between different modes

*Yu Yoshifuji¹, Go Chiba¹, Kosuke Tsujita², Shuhei Miwa² (1. Hokkaido Univ., 2. NEL)

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

Oral presentation

[1G11-13] Analysis Method Development 2 Transport Calculation

Wed. Sep 7, 2022 3:50 PM - 4:40 PM Room G (E1 Bildg.3F No.32)

Chair:Kenichi Tada(JAEA)

3:50 PM - 4:05 PM

[1G11] Treatment of scattering sources in numerical calculations of the radiative transfer equation with discrete ordinates methods

(3) Comprehensive comparison between DAR method and Legendre expansion method

*Ryosuke Shimizu¹, Go Chiba¹ (1. HokkaidoUniv.)

4:05 PM - 4:20 PM

[1G12] Application of neutron transport calculation method to accelerate photon transport analysis considering reflection and refraction

*Toranosuke Amano¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya University)

4:20 PM - 4:35 PM

[1G13] Study on the accuracy of POD basis expansion based on the Wilks’ method

*Shunya Teratani¹, Masato Ito¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya University)

Time reserved for Chair （4:35 PM - 4:40 PM）

Oral presentation

[1G14-16] Analysis Method Development 3 Monte-Carlo Calculation

Wed. Sep 7, 2022 4:40 PM - 5:30 PM Room G (E1 Bildg.3F No.32)

Chair:Willem F.G. van Rooijen(Univ. of Fukui)

4:40 PM - 4:55 PM

[1G14] Development of the Functional Expansion Tally Method Expanded by Numerical Basis Functions Extracted by Singular Value Decomposition

(1) Verification for One-Dimensional Geometry

*Ryoichi Kondo¹, Yasunobu Nagaya¹ (1. JAEA)

4:55 PM - 5:10 PM

[1G15] Utility value of generalized extreme value statistics in Monte Carlo criticality calculation

*UEKI TARO¹ (1. JAEA)

5:10 PM - 5:25 PM

[1G16] Consideration of nonuniformity effect on criticality safety evaluation using hybrid genetic algorithm

*SHIGEKI SHIBA¹ (1. Nuclear Regulation Authority)

Time reserved for Chair （5:25 PM - 5:30 PM）

Oral presentation

[2G01-04] Analysis Code Development, V&V 1

Thu. Sep 8, 2022 9:30 AM - 10:35 AM Room G (E1 Bildg.3F No.32)

Chair:Shouhei Araki(JAEA)

9:30 AM - 9:45 AM

[2G01] Development of Nuclear Data Processing Code FRENDY Version 2

(1) Overview of FRENDY Version 2

*Kenichi Tada¹, Akio Yamamoto², Tomohiro Endo², Go Chiba³, Michitaka Ono⁴, Masayuki Tojo⁴ (1. JAEA, 2. Nagoya Univ., 3. Hokkaido Univ., 4. GNF-J)

9:45 AM - 10:00 AM

[2G02] Development of Nuclear Data Processing Code FRENDY Version 2

(2) Implementation of resonance up-scattering treatment for multi-group cross sections

*Akio Yamamoto¹, Tomohiro Endo¹, Go Chiba², Kenichi Tada³ (1. Nagoya University, 2. Hokkaido University, 3. JAEA)

10:00 AM - 10:15 AM

[2G03] Development of Nuclear Data Processing Code FRENDY Version 2

(3) Application of multi-group cross section generation function to BWR design code

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

10:15 AM - 10:30 AM

[2G04] Investigations on self-shielding calculation for 3-D spatial domains using Iso-Geometric Analysis

*Matthias Nezondet¹, Willem F. G. van Rooijen¹ (1. UNIVERSITY OF FUKUI)

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

Oral presentation

[2G05-09] Experiment Analysis, Validation

Thu. Sep 8, 2022 10:35 AM - 11:55 AM Room G (E1 Bildg.3F No.32)

Chair:Willem F.G. van Rooijen(Univ. of Fukui)

10:35 AM - 10:50 AM

[2G05] Development and validation of CASMO5 library based on JENDL-5

*Tomoaki Watanabe¹, Kenya Suyama¹, Kenichi Tada¹, Rodolfo Ferrer², Joshua Hykes² (1. JAEA, 2. Studsvik)

10:50 AM - 11:05 AM

[2G06] Integral validation for JENDL-5 with UTR-KINKI

*Takashi Kanda¹, Masaki Goto¹, Shoichi Ikeda¹, Hiroyuki Fukuda¹, Yasunori Matsuo¹, Atsushi Sakon¹, Tadafumi Tadafumi¹, Kengo Hashimoto¹ (1. Kindai Univ.)

11:05 AM - 11:20 AM

[2G07] Core analysis for accelerator-driven system using JENDL-5

*Takanori Sugawara¹, Satoshi Kunieda¹ (1. JAEA)

11:20 AM - 11:35 AM

[2G08] Measurement of U233-HEU Substitution Reactivity Worth in KUCA

*Tadafumi Sano¹, Jun-ichi Hori², Yoshiyuki Takahashi², Takashi Kanda¹, Kazuzhi Terada², Hiroshi Yashima², Hironobu Unesaki² (1. Kindai Univ., 2. Kyoto Univ.)

11:35 AM - 11:50 AM

[2G09] Neutronics Benchmark of CEFR Start-Up Tests

*Hiroshi Taninaka¹ (1. JAEA)

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

Oral presentation

[2G10-14] Fuel Debris

Thu. Sep 8, 2022 2:45 PM - 4:05 PM Room G (E1 Bildg.3F No.32)

Chair:Akio Yamamoto(Nagoya Univ.)

2:45 PM - 3:00 PM

[2G10] Modification of STACY for study of criticality characteristics of fuel debris

(6) Progress on manufacture and construction of the modified STACY

*Tomoyuki Maekawa¹, Masakazu Seki¹, Masato Sumiya¹, Shouhei Araki¹, Takahiko Murakami¹, Kenta Hasegawa¹, Takashi Mori², Junichi Ishii¹, Fuyumi Kobayashi¹, Kazuhiko Izawa¹ (1. JAEA, 2. TNS)

3:00 PM - 3:15 PM

[2G11] Modification of STACY for study of criticality characteristics of fuel debris

(7) Evaluations of reactivity effects of equipment in a core tank

*Satoshi GUNJI¹, Shouhei ARAKI¹, Masakazu SEKI¹, Kazuhiko IZAWA¹, Kenya SUYAMA¹ (1. JAEA)

3:15 PM - 3:30 PM

[2G12] Modification of STACY for study of criticality characteristics of fuel debris

(8) Design of a two-region core with 400 fuel rods

*Shouhei Araki¹, Satoshi Gunji¹, Kazuhiko Izawa¹, Kenya Suyama¹ (1. Japan Atomic Energy Agency)

3:30 PM - 3:45 PM

[2G13] Study on the land transportation for fuel debris samples to be retrieved on trial from Unit-2 of the Fukushima Daiichi NPS

*Masahiro Sakamoto¹, Keisuke Okumura¹, Masato Mizokami², Shinya Mizokami² (1. JAEA, 2. TEPCO HD)

3:45 PM - 4:00 PM

[2G14] Correlation between the canister’s criticality and activity ratio of short-half-life noble-gas fission products under various fuel debris material compositions

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

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

Oral presentation

[2G15-17] Kinetics Analysis

Thu. Sep 8, 2022 4:05 PM - 4:55 PM Room G (E1 Bildg.3F No.32)

Chair:Ryoichi Kondo(JAEA)

4:05 PM - 4:20 PM

[2G15] The reactivity condition for linear temperature feedback in estimating the number of fissions in power peak

*Yuichi Yamane¹ (1. JAEA)

4:20 PM - 4:35 PM

[2G16] Study on inverse kinetic method without explicitly using neutron generation time

*Tomohiro Endo¹, Kenichi Watanabe², Manobu Tanaka³ (1. Nagoya Univ., 2. Kyushu Univ., 3. KEK)

4:35 PM - 4:50 PM

[2G17] Development of Digital Triplet for Reactor Physics Education using Experiments

(2)Reactivity Estimation based on Inverse Kinetics Method

*Yoshiki Yamashita¹, Kaito Ito¹, Akio Yamamoto¹, Tomohiro Endo¹ (1. Nagoya Univ.)

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

Oral presentation

[2G18-21] Analysis Code Development, V&V 2

Thu. Sep 8, 2022 4:55 PM - 6:00 PM Room G (E1 Bildg.3F No.32)

Chair:Rei Kimura(Toshiba ESS)

4:55 PM - 5:10 PM

[2G18] Study of the introduction of SCALE/ORIGEN into the MCNP-BURN2 code

*Shunichiro Omika¹, Satoshi Wada¹, Kenichi Yoshioka¹ (1. TOSHIBA ESS)

5:10 PM - 5:25 PM

[2G19] Verification and Validation of BWR Core Analysis Code CASMO5/SIMULATE5

(1) Requirements and Assessment for Verification and Validation of BWR core Analysis code used in Reload Core Safety Evaluation

*Yoshiro Kudo¹, Keisuke Yamauchi¹, Daichi Yamada¹, Takashi Yoshii², Tsuyoshi Ama², Yusuke Kuroda² (1. Tokyo Electric Power Company Holdings, Inc, 2. TEPCO SYSTEMS CORP.)

5:25 PM - 5:40 PM

[2G20] Verification and Validation of BWR Core Analysis Code CASMO5/SIMULATE5

(2) Verification and Validation of CASMO5

*Yusuke Kuroda¹, Tsuyoshi Ama¹, Takashi Yoshii¹, Keisuke Yamauchi², Yoshiro Kudo², Daichi Yamada² (1. TEPSYS, 2. TEPCO HD)

5:40 PM - 5:55 PM

[2G21] Verification and Validation of BWR Core Analysis Code CASMO5/SIMULATE5

(3) Verification and Validation of SIMULATE5

*Tsuyoshi Ama¹, Yusuke Kuroda¹, Takashi Yoshii¹, Keisuke Yamauchi², Yoshiro Kudo², Daichi Yamada² (1. TEPSYS, 2. TEPCO HD)

Time reserved for Chair （5:55 PM - 6:00 PM）

Oral presentation

[3G01-03] Analysis Method Development 4 Sensitivity Analysis

Fri. Sep 9, 2022 9:30 AM - 10:20 AM Room G (E1 Bildg.3F No.32)

Chair:Satoshi Wada(Toshiba ESS)

9:30 AM - 9:45 AM

[3G01] Calculation of sensitivity coefficients for nuclear model parameters

*Willem F.G. van Rooijen¹ (1. Univ. of Fukui)

9:45 AM - 10:00 AM

[3G02] Correlation evaluation of critical and burnup properties

*Hiroki Harada¹, Go Chiba¹ (1. Hokkaido Univ.)

10:00 AM - 10:15 AM

[3G03] Development of a robust nuclear data adjustment method to outliers

*Yuhei Fukui¹, Tomohiro Endo¹, Akio Yamamoto¹, Shuhei Maruyama² (1. Nagoya University, 2. JAEA)

Time reserved for Chair （10:15 AM - 10:20 AM）

Oral presentation

[3G04-05] Uncertainty Evaluation

Fri. Sep 9, 2022 10:20 AM - 10:55 AM Room G (E1 Bildg.3F No.32)

Chair:Tadafumi Sano(Kindai Univ.)

10:20 AM - 10:35 AM

[3G04] Uncertainty quantification of calculated nuclear material inventory caused by manufacturing tolerance of nuclear fuel

*Shunsuke Sato¹, Motomu Suzuki¹, Yasushi Nauchi¹ (1. CRIEPI)

10:35 AM - 10:50 AM

[3G05] Discrepancy of Calculation Results Due to Treatment of Manufacturing Uncertainties in Fuel Assembly Geometry

*Tatsuya Fujita¹ (1. NRA)

Time reserved for Chair （10:50 AM - 10:55 AM）

Oral presentation

[3G06-09] Advanced Reactor Property

Fri. Sep 9, 2022 10:55 AM - 12:00 PM Room G (E1 Bildg.3F No.32)

Chair:Tomoaki Watanabe(JAEA)

10:55 AM - 11:10 AM

[3G06] Reduced Enrichment Project for KUCA Fuel(2)

Core with U-Mo Fuel

*Tsuyoshi Misawa¹, Hironobu Unesaki¹, Yasunori Kitamura¹, Yoshiyuki Takahashi¹ (1. Kyoto University)

11:10 AM - 11:25 AM

[3G07] Effect of Activation Reaction Rate on Epithermal to Intermediate neutron in Reactor Experiment

(2) Numerical Analysis in Virtual Source-driven Subcritical Experiment

*Naoto Aizawa¹, Kosuke Kawabata¹ (1. Tohoku Univ.)

11:25 AM - 11:40 AM

[3G08] An inherent safety gas-cooled fast reactor concept of KAMADO-FR2

Design of Ultra-long life core

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

11:40 AM - 11:55 AM

[3G09] Consideration of reactivity decrease by assembling fuel assemblies in a heavy water-cooled reduced-moderation reactor

*Tomoatsu Shinohara¹, Yuki Sakurai¹, Hiroki Ishida^1,2, Naoyuki Takaki¹ (1. Tokyo City University, 2. Toshiba Plant Systems & Services Corporation)

Time reserved for Chair （11:55 AM - 12:00 PM）

Sessions

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

[1G07-10] Analysis Method Development 1 Burnup Calculation

(3) Reduced order model for the difference to the asymptotic solutions

(4) Comparison between different modes

[1G11-13] Analysis Method Development 2 Transport Calculation

(3) Comprehensive comparison between DAR method and Legendre expansion method

[1G14-16] Analysis Method Development 3 Monte-Carlo Calculation

(1) Verification for One-Dimensional Geometry

[2G01-04] Analysis Code Development, V&V 1

(1) Overview of FRENDY Version 2

(2) Implementation of resonance up-scattering treatment for multi-group cross sections

(3) Application of multi-group cross section generation function to BWR design code

[2G05-09] Experiment Analysis, Validation

[2G10-14] Fuel Debris

(6) Progress on manufacture and construction of the modified STACY

(7) Evaluations of reactivity effects of equipment in a core tank

(8) Design of a two-region core with 400 fuel rods

[2G15-17] Kinetics Analysis

(2)Reactivity Estimation based on Inverse Kinetics Method

[2G18-21] Analysis Code Development, V&V 2

(1) Requirements and Assessment for Verification and Validation of BWR core Analysis code used in Reload Core Safety Evaluation

(2) Verification and Validation of CASMO5

(3) Verification and Validation of SIMULATE5

[3G01-03] Analysis Method Development 4 Sensitivity Analysis

[3G04-05] Uncertainty Evaluation

[3G06-09] Advanced Reactor Property

Core with U-Mo Fuel

(2) Numerical Analysis in Virtual Source-driven Subcritical Experiment

Design of Ultra-long life core

Authentication