Oral Presentation

[2H01-05] Uncertainty Evaluation

Thu. Sep 8, 2016 9:30 AM - 10:50 AM Room H (Kumume City Plaza - Studio 3)

Chair: Tadafumi Sano (Kyoto Univ.)

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9:30 AM - 9:45 AM

[2H01] Establishment of an uncertainty estimation system for BWR core characteristics due to nuclear data covariance

(1)Lattice calculation part

*Tadashi Ikehara¹, Teppei Yamana¹, Hirohisa Kaneko¹, Masayuki Tojo¹ (1.GNF-J)

9:45 AM - 10:00 AM

[2H02] Establishment of an uncertainty estimation system for BWR core characteristics due to nuclear data covariance

(2)Core simulator part

*Teppei Yamana¹, Tadashi Ikehara¹, Hirohisa Kaneko¹, Masayuki Tojo¹ (1.GNF-J)

10:00 AM - 10:15 AM

[2H03] Model V&V and UQ procedure for the neutronics design methodology for the next generation fast reactor

(1)Outline of model V&V and UQ procedure

*Kazuya Ohgama¹, Kazumi Ikeda², Makoto Ishikawa¹, Taro Kan³, Shigeo Ohki¹ (1.Japan Atomic Energy Agency, 2.Mitsubishi FBR Systems, 3.Mitsubishi Heavy Industries)

10:15 AM - 10:30 AM

[2H04] Model V&V and UQ procedure for the neutronics design methodology for the next generation fast reactor

(2)Verification

*KAZUMI IKEDA¹, Kan Taro², Shuhei Maruyama³, Kazuya Ohgama³ (1.MFBR, 2.MHI, 3.JAEA)

10:30 AM - 10:45 AM

[2H05] Model V&V and UQ procedure for the neutronics design methodology for the next generation fast reactor

(3)Validation

*Makoto Ishikawa¹, Kenji Yokoyama¹, Kazuteru Sugino¹ (1.JAEA)

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

Oral Presentation

[2H06-09] Monte Carlo Method

Thu. Sep 8, 2016 10:50 AM - 11:55 AM Room H (Kumume City Plaza - Studio 3)

Chair: Yasushi Nauchi (CRIEPI)

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10:50 AM - 11:05 AM

[2H06] Prediction of Void Information in LWR using Neutron Noise calculated with Time-Dependent Monte Carlo Method

*Naoki takayama¹, Toshihiro Yamamoto², Tadafumi Sano², Jun-ichi Hori², Ken Nakajima² (1.Department of Nuclear Engineering, Kyoto University, 2.Kyoto University Research Reactor Institute)

11:05 AM - 11:20 AM

[2H07] Statistical error estimation by orthonormally weighted standardized time series

Statistical error of tallies in Monte Carlo criticality calculation

*Taro Ueki¹ (1.Japan Atomic Energy Agency, Nuclear Safety Research Center, Criticality Safety Research Group)

11:20 AM - 11:35 AM

[2H08] Prediction of Underestimation of Statistical Uncertainty in Monte Carlo

(1)Development of Higher-order Mode Calculation Code

*Tomohiro Endo¹, Koji Hayashi¹, Akio Yamamoto¹ (1.Nagoya university)

11:35 AM - 11:50 AM

[2H09] Prediction of Underestimation of Statistical Uncertainty in Monte Carlo Eigenvalue Calculation for 2D Heterogeneous Geometry

(2)Applying to UO₂-MOX 2×2 Assemblies

*Koji Hayashi¹, Tomohiro Endo¹, Akio Yamamoto¹ (1.Nagoya university)

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

Oral Presentation

[2H10-13] Transient Analysis

Thu. Sep 8, 2016 2:45 PM - 3:50 PM Room H (Kumume City Plaza - Studio 3)

Chair: Akio Yamamoto (Nagoya Univ.)

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2:45 PM - 3:00 PM

[2H10] Existence and Uniqueness of a Global-in-Time Solution to Time-Dependent Neutron Diffusion Equation

*Hiroki Sakamoto¹, Toshihiro Yamamoto² (1.TRANSNUCLEAR, LTD., 2.Kyoto University Research Reactor Institute)

3:00 PM - 3:15 PM

[2H11] An Efficient Method of Numerical Calculation of Reactor Kinetics Equations

*Yoshihisa Tahara¹, Takanori Kameyama¹ (1.Tokai University)

3:15 PM - 3:30 PM

[2H12] Supercritical transient analysis in light water moderated coupled small fuel debris regions using integral kinetic model and point kinetic model

*Delgersaikhan Tuya¹, Jun Nishiyama², Toru Obara² (1.Department of Nuclear Engineering, Tokyo Institute of Technology, 2.Laboratory for Advanced Nuclear Energy, Tokyo Institute of Technology)

3:30 PM - 3:45 PM

[2H13] Average time profile of energy release fluctuated due to radiolytic gas void in criticality accident

*Yuichi Yamane¹ (1.JAEA)

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

Oral Presentation

[2H14-18] Criticality Management 1

Thu. Sep 8, 2016 3:50 PM - 5:10 PM Room H (Kumume City Plaza - Studio 3)

Chair: Jun Nishiyama (Tokyo Tech)

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3:50 PM - 4:05 PM

[2H14] Criticality control technique development for Fukushima Daiichi fuel debris

(19)policy of critilcality control

*Makoto Nakano^1,2, Yasuhiro Harada^1,2, Yamato Hayashi^1,3, Hiromi Maruyama^1,4 (1.International Research Institute for Nuclear Decommissioning, 2.Mitsubishi Heavy Industries, LTD., 3.Toshiba Corporation Energy Systems & Solutions Company, 4.Hitachi-GE Nuclear Energy,Ltd.)

4:05 PM - 4:20 PM

[2H15] Criticality control technique development for Fukushima Daiichi fuel debris

(20)Evaluation of OECD/NEA Burnup Credit Criticality Benchmark Phase III-C using Core design code

*Takashi Yoshii¹, Yousuke Miki¹, Yasuhiro Harada^2,3, Takuya Umano^2,4, Kazuya Ishii^2,5, Kenya Suyama^2,6 (1.TEPCO SYSTEMS CORPORATION, 2.International Research Institute for Nuclear Decommissioning, 3.Mitsubishi Heavy Industries, Ltd., 4.TOSHIBA CORPORATION, 5.Hitachi-GE Nuclear Energy, Ltd., 6.Japan Atomic Energy Agency)

4:20 PM - 4:35 PM

[2H16] Criticality control technique development for Fukushima Daiichi fuel debris

(21)Criticality accident analysis for the core water filling

*yamato hayashi^1,2, takuya umano^1,2, yutaka takeuchi^1,2, makoto nakano^1,3, satoshi takeo^1,4 (1.IRID, 2.TOSHIBA, 3.Mitsubishi Heavy Industries, 4.HITACHI-GE)

4:35 PM - 4:50 PM

[2H17] Criticality control technique development for Fukushima Daiichi fuel debris

(22)Detection of approach to criticality by reactor noize analysis and period measurement

*Shigeto Kikuchi^1,2, Satoshi Wada^1,2, Yamato Hayashi^1,2 (1.IRID, 2.Toshiba)

4:50 PM - 5:05 PM

[2H18] Criticality control technique development for Fukushima Daiichi fuel debris

(23)Criticality detection using virtual neutron capture method

*Takeshi Mitsuyasu^1,2, Tetsushi Hino^1,2, Hiromi Maruyama^1,2 (1.International Research Institute for Nuclear Decommissioning, 2.Hitachi-GE Nuclear Energy, Ltd.)

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

Oral Presentation

[2H19-23] Criticality Management 2

Thu. Sep 8, 2016 5:10 PM - 6:30 PM Room H (Kumume City Plaza - Studio 3)

Chair: Tomohiro Endo (Nagoya Univ.)

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5:10 PM - 5:25 PM

[2H19] Criticality control technique development for Fukushima Daiichi fuel debris

(24)Neutron multiplication factor estimation using measured data form PCV gas control system at Fukishima daiichi nuclear power plant unit 1

*Hiromi Maruyama¹, Satoshi Takeo¹, Yu Toriyabe¹, Hiroshi Fukushima¹, Hideaki Matsumoto² (1.IRID(Hitachi-GE), 2.TEPCO HD)

5:25 PM - 5:40 PM

[2H20] Criticality control technique development for Fukushima Daiichi fuel debris

(25)Evaluation of Gamma-ray Irradiation Resistance of Insoluble Neutron Absorber

*Ryo Ishibashi^1,2, Toshiyuki Fujita^1,3, Kazuya Ishii^1,2, Yasuhiro Harada^1,4 (1.IRID, 2.Hitachi-GE Nuclear Energy, 3.Toshiba, 4.Mitsubishi heavy Industries)

5:40 PM - 5:55 PM

[2H21] Criticality control technique development for Fukushima Daiichi fuel debris

(26)Fundamental test for study on application method of insoluble neutron absorber

*Yuta Shindo^1,2, Yutaka Ishiwata^1,2, Yamato hayashi^1,2, Ryo Ishibashi^1,3 (1.IRID, 2.Toshiba, 3.HitachiGE)

5:55 PM - 6:10 PM

[2H22] Criticality control technique development for Fukushima Daiichi fuel debris

(27)applicability of soluble neutron absorber

*Yasuhiro Harada^1,2, Makoto Nakano^1,2, Yousuke Kamikawa^1,2, Yuichi Shimizu^1,2 (1.International Research Institute for Nuclear Decommissioning, 2.Mitsubishi Heavy Industries, LTD.)

6:10 PM - 6:25 PM

[2H23] Criticality control technique development for Fukushima Daiichi fuel debris

(28)Fuel rod heatup analysis in uncovered core condition

*Yutaka Takeuchi^1,2, Taishi Yoshida^1,2, Yamato Hayashi^1,2 (1. International Research Institute for Nuclear Decommissioning, 2.Toshiba Corporation Energy System Solution Company)

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

Oral Presentation

[1L13-18] Burnup Analysis

Wed. Sep 7, 2016 4:05 PM - 5:40 PM Room L (Kumume City Plaza - Assembly Room 2)

Chair: Go Chiba (Hokkaido Univ.)

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4:05 PM - 4:20 PM

[1L13] Evaluation of the breeding performance of heavy water cooled thorium reactor

*Sota Muso¹, Naoyuki takaki¹ (1.Tokyo city university)

4:20 PM - 4:35 PM

[1L14] Effect of BP cell model for HTTR burnup characteristics

*fujimoto nozomu¹, Yuki honda², Kodai Fukuda³, Minoru Goto², Daisuke Tochio², Shoji Takada² (1.Kyushu university, 2.JAEA, 3.Tokyo Institute of Technology)

4:35 PM - 4:50 PM

[1L15] Measurement and burnup analysis of ¹⁰⁶Ru/¹⁴⁴Ce activity ratio for spent fuel cooled more than 10 years

*Shunsuke Sato¹, Yasushi Nauchi¹, Takehito Hayakawa², Yasuhiko Kimura³, Kenya Suyama³ (1.CRIEPI, 2.QST, 3.JAEA)

4:50 PM - 5:05 PM

[1L16] Analysis of measured isotopic compositions of fuels irradiated in light water reactors by CASMO5

(1)UO₂ fuel

*Toru Yamamoto¹, Tomohiro Sakai¹, Daiki Iwahashi¹ (1.S/NRA/R)

5:05 PM - 5:20 PM

[1L17] Analysis of measured isotopic compositions of fuels irradiated in light water reactors by CASMO5

(2)MOX fuel

*tomohiro sakai¹, Toru Yamamoto¹, Daiki Iwahashi¹ (1.S/NRA/R)

5:20 PM - 5:35 PM

[1L18] Core Follow Calculations of Operation Cycles after About 10 Years Outage in a U.S. BWR

Katsuyoshi Oyama¹, *Tsuyoshi Ama², Tadashi Maeda², Takashi Yoshii², Akihiro Fukao² (1.TEPCO Holdings, 2.TEPSYS)

Time reserved for Chair （5:35 PM - 5:40 PM）

Oral Presentation

[1L19-22] Experiment and Analysis

Wed. Sep 7, 2016 5:40 PM - 6:45 PM Room L (Kumume City Plaza - Assembly Room 2)

Chair: Hideki Matsumoto (MHI)

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5:40 PM - 5:55 PM

[1L19] Analysis of kinetic parameters and reactor period for CROCUS perturbed core

*Yasushi Nauchi¹, Andrea Zoia², Emeric Brun², Cedric Jouanne² (1.CRIEPI, 2.CEA)

5:55 PM - 6:10 PM

[1L20] Analysis of HTC critical experiments

(1)Phase 1,2

*SHIGEKI SHIBA¹, Tomohiro Sakai¹ (1.S/NRA/R)

6:10 PM - 6:25 PM

[1L21] Preliminary Experiments for Reactor Noise Analysis using Neutron Detector with Eu doped LiCaAlF₆

*Kensuke Maeno¹, Akio Yamamoto¹, Tomohiro Endo¹ (1.Nagoya University)

6:25 PM - 6:40 PM

[1L22] Development of Innovative Nuclear Waste Burning System by Fast Reactor Cycle Using Pu Metallic Fuel with MA

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

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

Time reserved for Chair （6:40 PM - 6:45 PM）

Oral Presentation

[3L01-04] Verification and Validation of Analysis Code

Fri. Sep 9, 2016 9:30 AM - 10:35 AM Room L (Kumume City Plaza - Assembly Room 2)

Chair: Kenji Yokoyama (JAEA)

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9:30 AM - 9:45 AM

[3L01] Generation of an MVP library with a Nuclear Data Processing System FRENDY

*Yasunobu Nagaya¹, Kenichi Tada¹ (1.JAEA)

9:45 AM - 10:00 AM

[3L02] Development of Mitsubishi Heterogeneous Transient Code GALAXY-K

Yohei Kamiyama¹, *Hiroki Koike¹, Kazuya Yamaji¹, Kazuki Kirimura¹, Shinya Kosaka¹ (1.MHI)

10:00 AM - 10:15 AM

[3L03] Verification and validation of the TRACE/PARCS code

(1)Analysis of the Benchmark problem by PARCS code

*Daiki Iwahashi¹, Tomohiro Sakai¹ (1.Nuclear Regulation Authority)

10:15 AM - 10:30 AM

[3L04] Verification and validation of the TRACE/PARCS code

(2)Analysis of the SPERT-III Experiments by TRACE/PARCS code (Hot startup condition)

*Tatsuya Fujita¹, Tomohiro Sakai¹, Daiki Iwahashi¹ (1.Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority)

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

Oral Presentation

[3L05-09] Development of Analysis Method

Fri. Sep 9, 2016 10:35 AM - 11:55 AM Room L (Kumume City Plaza - Assembly Room 2)

Chair: Hiroki Koike (MHI)

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10:35 AM - 10:50 AM

[3L05] Development of three-dimensional heterogeneous transport code, GENESIS(2)

Anisotropic scattering treatment using the SPn approximation

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

10:50 AM - 11:05 AM

[3L06] R&D of the Object-Integrated Code System for Fast Reactors

(14)Extension of Burnup and Decay Heat Calculation Capability of MARBLE

*Kenji Yokoyama¹, Tomoyuki Jin¹ (1.JAEA)

11:05 AM - 11:20 AM

[3L07] An Investigation on Improvement of the Core Neutronics Design Calculation Method for Advanced Fast Reactors (5)

Investigation on the cross-section homogenization method in power distribution evaluation

*Kazuteru Sugino¹, Maruyama Shuhei¹, Ohki Shigeo¹ (1.Japan Atomic Energy Agency)

11:20 AM - 11:35 AM

[3L08] Comparison of Fuel Loading Pattern Optimization Results using Exhaustive Search for Fresh Fuels and Local Search for Burned Fuels

*Satomi Ishiguro¹, Tomohiro Endo¹, Akio Yamamoto¹ (1.Nagoya University Graduate School of Engineering)

11:35 AM - 11:50 AM

[3L09] Development of collision probability method based on Mesh to Mesh computation (7)

Application for transport calculation of XY geometry with IC method

*Tetsuo Matsumura¹ (1.CRIEPI)

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

Oral Presentation

[3L10-14] Sub-criticality Evaluation and Monitoring 1

Fri. Sep 9, 2016 2:45 PM - 4:05 PM Room L (Kumume City Plaza - Assembly Room 2)

Chair: Tomohiro Endo (Nagoya Univ.)

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2:45 PM - 3:00 PM

[3L10] Effect of higher harmonics in subcriticality measurements by the area-ratio method

*Toshihiro Yamamoto¹, Hiroki Sakamoto² (1.Kyoto University, 2.Transnuclear Tokyo)

3:00 PM - 3:15 PM

[3L11] Study on criticality evaluation of fuel debris during the removal process and its accuracy

*Yoshiteru Sato¹, Takaya Suzuki¹, Naoyiki Takaki¹, Hiroki Takezawa¹, PengHong Liem² (1.Tokyo City Universitiy, 2.NAIS, Co., Inc.)

3:15 PM - 3:30 PM

[3L12] Sub-criticality monitoring method by measuring FP gases(III)

(1)Point of view of this method

*Yoshitaka NAITO¹ (1.NAIS.Co.,Inc.)

3:30 PM - 3:45 PM

[3L13] Sub-criticality monitoring method by measuring FP gases(III)

(2)Estimation of keff by measuring dose rate of Kr-88 to Xe-135

*Kouki HIRAI¹, Yoshitaka NAITO¹, Hong Peng LIEM¹ (1.NAIS.Co.,Inc.)

3:45 PM - 4:00 PM

[3L14] Sub-criticality monitoring method by measuring FP gases (III)

(3)Estimated reactivity by this method and its error evaluation

*Masaya SEKI¹, Yoshitaka NAITO¹, Shigekazu USUDA¹, Yoshihumi MITSUMOTO¹ (1.NAIS.Co.,Inc.)

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

Oral Presentation

[3L15-17] Sub-criticality Evaluation and Monitoring 2

Fri. Sep 9, 2016 4:05 PM - 4:55 PM Room L (Kumume City Plaza - Assembly Room 2)

Chair: Yoshio Kimura (Chuden CTI)

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4:05 PM - 4:20 PM

[3L15] Development of subcriticality monitoring method during shutdown and refueling modes of nuclear power plant

(1)Development purposes and specifications of subcriticality monitoring method

*Shoichi Tashiro¹, Masayuki Tojo¹, Takao Kageyama¹, Yoichiro Shimazu² (1.GNF-J, 2.Univ. of Fukui)

4:20 PM - 4:35 PM

[3L16] Development of subcriticality monitoring method during shutdown and refueling modes of nuclear power plant

(2)Evaluation of source term of reactivity meters by determinestic code

*Masayuki Tojo¹, Shoichi Tashiro¹, Tatsuya Iwamoto¹, Kensuke Kobayashi¹, Yoichiro Shimazu² (1.GNF-J, 2.Univ. of Fukui)

4:35 PM - 4:50 PM

[3L17] Development of subcriticality minitoring method during shutdown and refueling modes of nuclear power plant

Evaluation of performance of reactivity meters for subcriticality monitoring

*Yoichiro Shimazu¹, Shoichi Tashiro², Masayuki Tojo² (1.Univ. of Fukui, 2.GNF-J)

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

Sessions

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

[2H01-05] Uncertainty Evaluation

(1)Lattice calculation part

(2)Core simulator part

(1)Outline of model V&V and UQ procedure

(2)Verification

(3)Validation

[2H06-09] Monte Carlo Method

Statistical error of tallies in Monte Carlo criticality calculation

(1)Development of Higher-order Mode Calculation Code

(2)Applying to UO2-MOX 2×2 Assemblies

[2H10-13] Transient Analysis

[2H14-18] Criticality Management 1

(19)policy of critilcality control

(20)Evaluation of OECD/NEA Burnup Credit Criticality Benchmark Phase III-C using Core design code

(21)Criticality accident analysis for the core water filling

(22)Detection of approach to criticality by reactor noize analysis and period measurement

(23)Criticality detection using virtual neutron capture method

[2H19-23] Criticality Management 2

(24)Neutron multiplication factor estimation using measured data form PCV gas control system at Fukishima daiichi nuclear power plant unit 1

(25)Evaluation of Gamma-ray Irradiation Resistance of Insoluble Neutron Absorber

(26)Fundamental test for study on application method of insoluble neutron absorber

(27)applicability of soluble neutron absorber

(28)Fuel rod heatup analysis in uncovered core condition

[1L13-18] Burnup Analysis

(1)UO2 fuel

(2)MOX fuel

[1L19-22] Experiment and Analysis

(1)Phase 1,2

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

[3L01-04] Verification and Validation of Analysis Code

(1)Analysis of the Benchmark problem by PARCS code

(2)Analysis of the SPERT-III Experiments by TRACE/PARCS code (Hot startup condition)

[3L05-09] Development of Analysis Method

Anisotropic scattering treatment using the SPn approximation

(14)Extension of Burnup and Decay Heat Calculation Capability of MARBLE

Investigation on the cross-section homogenization method in power distribution evaluation

Application for transport calculation of XY geometry with IC method

[3L10-14] Sub-criticality Evaluation and Monitoring 1

(1)Point of view of this method

(2)Estimation of keff by measuring dose rate of Kr-88 to Xe-135

(3)Estimated reactivity by this method and its error evaluation

[3L15-17] Sub-criticality Evaluation and Monitoring 2

(1)Development purposes and specifications of subcriticality monitoring method

(2)Evaluation of source term of reactivity meters by determinestic code

Evaluation of performance of reactivity meters for subcriticality monitoring

Authentication

(2)Applying to UO₂-MOX 2×2 Assemblies

(1)UO₂ fuel