＊Yuki Honda¹, Hiroyuki Sato¹, Shigeaki Nakagawa¹, Paul Bayless², Gerhard Strydom², Robin Baker², Hans Gougar², Nariaki Sakaba¹ (1.Japan Atomic Energy Agency, 2.Idaho National Laboratory)

11:30 AM - 11:45 AM

[1O07] Temperature dependence of temperature coefficient and void coefficient of reactivity for dilute plutonium solutions

＊Tomoaki Watanabe¹, Takao Kashima¹, Yuichi Yamane¹ (1.JAEA)

11:45 AM - 12:00 PM

[1O08] Energy released in criticality accident by instantaneous reactivity insertion to the system with non-linear temperature feedback

＊Yuichi Yamane¹ (1.JAEA)

Oral Presentation

[1O09-12] calculation model advancement 2

Sat. Mar 26, 2016 2:45 PM - 3:50 PM Room O (Lecture Rooms C C201)

Chair: Go Chiba (Hokkaido Univ.)

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2:45 PM - 3:00 PM

[1O09] Development of collision probability method based on Mesh to Mesh computation (6)

Application for transport calculation of a uniform XY geometry

＊Tetsuo Matsumura¹ (1.CRIEPI)

3:00 PM - 3:15 PM

[1O10] Development of Whole-Core Monte Carlo Analysis Method with Neutron Current Connection Method

Speed-up of Current Iteration

＊Michitaka Ono¹, Motoo Aoyama¹, Takeshi Mitsuyasu¹, Tetsushi Hino¹ (1.Hitachi, Ltd.)

3:15 PM - 3:30 PM

[1O11] Development of a New Statistical Geometry Model using the Delta-Tracking Method

＊Takahiro Koide¹, Tomohiro Endo¹, Akio Yamamoto¹ (1.Nagoya University Graduate School of Engineering Department of Material, Physics and Energy Engineering)

3:30 PM - 3:45 PM

[1O12] Delayed neutron fraction repartition per precursor group wighted by Iterated Fission Probability

＊Yasushi Nauchi¹ (1.Central Research Institute of Electric Power Industry)

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

Oral Presentation

[1O13-16] uncertainty quantification 1

Sat. Mar 26, 2016 3:50 PM - 4:55 PM Room O (Lecture Rooms C C201)

Chair: Shungo Sakurai (Toshiba)

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3:50 PM - 4:05 PM

[1O13] Statistical Uncertainty in Kinetic Analysis using Integral Kinetic Model for Re-criticality Accident in Weakly-Coupled Fuel Debris

＊Delgersaikhan Tuya¹, Hiroki Takezawa¹, Toru Obara¹ (1.Tokyo Institute of Technology)

4:05 PM - 4:20 PM

[1O14] Uncertainty of Criticality Analysis of UO2-Concrete System under Randomization

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

4:20 PM - 4:35 PM

[1O15] Subcriticality Measurement using Third Order Neutron-correlation Technique with Bootstrap Method

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

4:35 PM - 4:50 PM

[1O16] Estimation of unknown neutron source distribution using inverse problem solutions

＊Shinji SUGAYA¹, Tomohiro ENDO², Akio YAMAMOTO² (1.Nagoya University, School of Engineering, 2.Nagoya University, Graduate School of Engineering)

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

Oral Presentation

[1O17-21] uncertainty quantification 2

Sat. Mar 26, 2016 4:55 PM - 6:15 PM Room O (Lecture Rooms C C201)

Chair: Kazuki Kirimura (MHI)

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4:55 PM - 5:10 PM

[1O17] Uncertainty quantification due to cross section data for subcriticality measurement using area ratio method

＊Toshiki KIMURA¹, Tomohiro ENDO², Akio YAMAMOTO² (1.Nagoya University School of Engineering, 2.Nagoya University Graduate School of Engineering)

5:10 PM - 5:25 PM

[1O18] Uncertainty Quantification of Neutron Flux Due to Cross Section Data in Neutron Shielding Calculation

＊KIMIHIRO YOKOI¹, TOMOHIRO ENDO², AKIO YAMAMOTO², YOSHIO KIMURA³, RYOJI MIZUNO³ (1.Nagoya University Division of Quantum Science and Energy Engineering, 2.Nagoya University Department of Materials,Physics and Energy Enginering, 3.Chuden CTI Analyzing and Engineering Solutions Department, IT Solutions Division)

5:25 PM - 5:40 PM

[1O19] Uncertainty analysis of neutronics characteristics in thorium loaded reactor core

＊Tadafumi Sano¹, Jun-ich Hori¹, Yoshiyuki Takahashi¹, Hironobu Unesaki¹ (1.KURRI)

5:40 PM - 5:55 PM

[1O20] Study for uncertainty reduction of FP decay heat of FBR fuel

＊Kazuya Ohgama¹, Futoshi Minato¹, Shigeo Ohki ¹, Jun-ichi Katakura² (1.Japan Atomic Energy Agency, 2.Nagaoka University of Technology)

5:55 PM - 6:10 PM

[1O21] An Investigation on Improvement of the Core Neutronics Design Calculation Method for Advanced Fast Reactors (4)

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

＊Kazuteru Sugino¹, Shuhei Maruyama¹, Shigeo Ohki¹ (1.Japan Atomic Energy Agency)

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

Oral Presentation

[2O01-04] code-system development

Sun. Mar 27, 2016 9:45 AM - 10:45 AM Room O (Lecture Rooms C C201)

Chair: Takanori Kitada (Osaka Univ.)

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9:45 AM - 10:00 AM

[2O01] Development of Nuclear Data Processing System FRENDY

(3)Construction of the probability table in the unresolved resonance region

＊Kenichi Tada¹, Yasunobu Nagaya¹ (1.JAEA)

10:00 AM - 10:15 AM

[2O02] Development of Three-dimensional Heterogeneous Transport Code GENESIS based on the LEAF method

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

10:15 AM - 10:30 AM

[2O03] Development of Core Calculation System for BWR composed of Open Computer Code

(12)Validation by the analysis of LWR core model

＊Naoto Aizawa¹, Masahiro Yoshimura¹, Kenji Owada¹, Keiji Shikoda², Takashi Nakui², Fumito Kubo² (1.Tohoku University, 2.TOiNX)

10:30 AM - 10:45 AM

[2O04] Development of Mitsubishi PWR Nuclear Design Code System GalaxyCosmo-S

(13)Application of sensitivity analysis to GALAXY

＊Kazuya Yamaji¹, Yohei Kamiyama¹, Hiroki Koike², Kazuki Kirimura¹, Shinya Kosaka¹ (1.Mitsubishi Heavy Industries,Ltd., 2.MHI Nuclear Systems and Solution Engineering Co., Ltd.)

Oral Presentation

[2O05-09] code-system verification 1

Sun. Mar 27, 2016 10:45 AM - 12:00 PM Room O (Lecture Rooms C C201)

Chair: Kazuya Yamaji (MHI)

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10:45 AM - 11:00 AM

[2O05] Verifications of design codes using ABWR MOX benchmark problems

(1)Overall plan

＊Kazuhito Yoshi¹, Michihiro Nakai¹, Masaru Sasagawa², Teppei Yamana², Masayuki Tojo², Tatsuya Iwamoto², Tadashi Ikehara² (1.J-POWER, 2.GNF-J)

11:00 AM - 11:15 AM

[2O06] Verifications of design codes using ABWR MOX benchmark problems

(2)Verification results of design codes

Kazuhito Yoshi¹, Michihiro Nakai¹, ＊Masaru Sasagawa², Teppei Yamana², Masayuki Tojo², Tatsuya Iwamoto², Tadashi Ikehara² (1.J-POWER, 2.GNF-J)

11:15 AM - 11:30 AM

[2O07] Verifications of design codes using ABWR MOX benchmark problems

(3)Analysis of verification results -1-

＊Teppei Yamana¹, Masayuki Tojo¹, Masaru Sasagawa¹, Tatsuya Iwamoto¹, Tadashi Ikehara¹, Kazuhito Yoshi², Michihiro Nakai² (1.GNF-J, 2.J-POWER)

11:30 AM - 11:45 AM

[2O08] Verifications of design codes using ABWR MOX benchmark problems

(4)Analysis of verification results -2-

＊Masayuki Tojo¹, Teppei Yamana¹, Masaru Sasagawa¹, Tatsuya Iwamoto¹, Tadashi Ikehara¹, Kazuhito Yoshi², Michihiro Nakai² (1.GNF-J, 2.J-POWER)

11:45 AM - 12:00 PM

[2O09] Verifications of design codes using ABWR MOX benchmark problems

(5)Conclusions of verification results

＊Tadashi Ikehara¹, Teppei Yamana¹, Masayuki Tojo¹, Tatsuya Iwamoto¹, Masaru Sasagawa¹, Kazuhito Yoshi², Michihiro Nakai² (1.GNF-J, 2.J-POWER)

Oral Presentation

[2O10-12] nuclear data development

Sun. Mar 27, 2016 2:45 PM - 3:35 PM Room O (Lecture Rooms C C201)

Chair: Kenichi Tada (JAEA)

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2:45 PM - 3:00 PM

[2O10] Generation of multi-group cross sections and covariance data based on JENDL-4 for the SCALE code system

＊Willem van Rooijen¹ (1.Research Institute of Nuclear Engineering, University of Fukui)

3:00 PM - 3:15 PM

[2O11] Implementation of JENDL-4.0 for Burnup Analysis Code FLEX-BURN

＊Motomu Suzuki¹ (1.CRIEPI)

3:15 PM - 3:30 PM

[2O12] Preliminary study on burnup characteristics in HTGRs

＊Nozomu Fujimoto¹, keisuke Morita¹, yuji Fukaya² (1.Kyushu University, 2.JAEA)

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

Oral Presentation

[2O13-15] code-system validation 2

Sun. Mar 27, 2016 3:35 PM - 4:25 PM Room O (Lecture Rooms C C201)

Chair: Tadafumi Sano (Kyoto Univ.)

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3:35 PM - 3:50 PM

[2O13] Analysis of measured decay heat of fuel assemblies by ORIGEN2.2 and CASMO5

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

3:50 PM - 4:05 PM

[2O14] Analysis of PIE data of BWR Fuel using SWAT4

＊Takeo Kikuchi¹, Kenichi Tada¹, Kenya Suyama¹ (1.JAEA)

4:05 PM - 4:20 PM

[2O15] Basic Research on the Element Transmutation of All Fission Products Using Nuclear Reactors

(3)Validation of MVP-BURN Code by Neutron Activation Analysis in UCI-TRIGA^® Reactor

＊Atsunori Terashima¹, Leila Safavi-Tehrani², Mikael Nilsson², Masaki Ozawa¹ (1.Tokyo Institute of Technology, 2.University of California, Irvine)

Time reserved for Chair （4:20 PM - 4:25 PM）

Sessions

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

[1O01-03] optimization technique

[1O04-08] calculation model advancement 1

Derivation based on the concept of a fission chain reaction and Verification Calculations

[1O09-12] calculation model advancement 2

Application for transport calculation of a uniform XY geometry

Speed-up of Current Iteration

[1O13-16] uncertainty quantification 1

[1O17-21] uncertainty quantification 2

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

[2O01-04] code-system development

(3)Construction of the probability table in the unresolved resonance region

(12)Validation by the analysis of LWR core model

(13)Application of sensitivity analysis to GALAXY

[2O05-09] code-system verification 1

(1)Overall plan

(2)Verification results of design codes

(3)Analysis of verification results -1-

(4)Analysis of verification results -2-

(5)Conclusions of verification results

[2O10-12] nuclear data development

[2O13-15] code-system validation 2

(3)Validation of MVP-BURN Code by Neutron Activation Analysis in UCI-TRIGA® Reactor

Authentication

(3)Validation of MVP-BURN Code by Neutron Activation Analysis in UCI-TRIGA^® Reactor