Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan

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2006 Fall Meeting

Displaying 151-200 of 852 articles from this issue

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Divergence of cold neutron beam with supermirror

Itaru Tamura, Kazuyoshi Yamamoto, Kiyoshi Nakamura, Kazuhiko Soyama, T ...

Session ID: F50
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.156.0

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Prelominary Test of Radiography using Monochromatic Cold Neutron Beam

Masayoshi TAMAKI, Takaharu ISHII, Noriaki MORI, Eberhard LEHMANN

Session ID: F51
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.157.0

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Development of a grooved type coupled methane moderator for an accelerator based small neutron source

Hidenori Iwashita, Hirokatsu Iwasa, Fujio Hiraga, Takashi Kamiyama, Yo ...

Session ID: F52
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.158.0

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Optimization and performance evaluation of a neutron ellipsoidal mirror

Kunihiko Kamada, Yoshiaki Kiyanagi, Takashi Kamiyama, Fujio Hiraga, Mi ...

Session ID: F53
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.159.0

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Core Characteristics Prediction Technique for High Enriched MOX Fueled Tight Lattice Core (4)

- 1. Experiment and Analysis on Moderator Void Reactivity Using FCA -

Masaki ANDOH, Masahiro FUKUSHIMA, Shigeaki OKAJIMA, Takamasa MORI

Session ID: O34
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.160.0

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Core Characteristics Prediction Technique for High Enriched MOX Fueled Tight Lattice Core (4)

- 2.Evaluation of Applicability of FCA Experiments to Void Reactivity of Light Water Breeding Reactor -

Teruhiko KUGO, Kensuke KOJIMA, Masaki ANDOH, Shigeaki OKAJIMA, Takamas ...

Session ID: O35
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.161.0

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Sensitivity Analysis of Doppler Reactivity in FCA

Toshikazu Takeda, Keita Naitou, Tadafumi Sano, Masaki Andoh

Session ID: O36
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.162.0

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Effect of Anisotropic Scattering in Neutronics Analysis of BWR Assembly

Toshikazu Takeda, Toshiki Okamoto, Akira Inoue, Shinya Kosaka, Hideaki ...

Session ID: O37
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.163.0

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Evaluation of Core Characteristics Using Americium-containing Fuel with Molybdenum Inert Matrix

Sho Takano, Yoshihiro Yamane, Akio Yamamoto, Masahiko Osaka, Tsuyoshi ...

Session ID: O38
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.164.0

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Accident Scenario and Kinetic Analysis for Criticality Accident Evaluation of MOX Powder System

YUICHI YAMANE, SATOSHI TAKAHASHI, TOSHIHIRO YAMAMOTO, YOSHINORI MIYOSH ...

Session ID: O39
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.165.0

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Development of real time subcriticality measurement by Rossi-alpha method

Shinobu Tsubota, Yoshihiro Yamane, Yasunori Kitamura

Session ID: O40
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.166.0

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Subcriticality measurement of Accelerator-Driven Subcritical Reactor by the pulsed Feynman-alpha method

Yoichi Goto, Yoshihiro Yamane, Akio Yamamoto, Yasunori Kitamura

Session ID: O41
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.167.0

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Calculation of critical and subcritical actinide concentrations in the infinite sea of silicon-dioxide or water

Hiroshi Okuno, Shohei Sato, Hiromitsu Kawasaki

Session ID: O42
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.168.0

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Dynamic measurements in a thermal ADSR core with pulsed neutrons method

Morgan Hervault, Takanori Kitada, Hironobu Unesaki, Cheol Ho Pyeon, Ts ...

Session ID: O43
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.169.0

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Pulsed neutron method and dynamic measurements analysis allow reactivity assessment in subcritical systems. However, in ADSR, detectors responses dependency on their positions is amplified by core heterogeneities like zoning and the presence of the beam neutron source itself. Neutron decay constant measurements by optical fiber have been conducted in KUCA to evaluate the variation on deduced reactivities, and compared with calculations.

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Measurement of neutron energy spectrum using activation foil method for ADSR at KUCA

Hiroshi Shiga, Morgan Hervault, Cheol Ho Pyeon, Tsuyoshi Misawa, Seiji ...

Session ID: O44
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.170.0

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Analysis of SRNM Response during Refueling in BWR (2)

Masato Watanabe, Hidetugu Okada, Yoshio Kimura

Session ID: O45
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.171.0

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Analysis of Post-Irradiation Experiments on "JOYO" MK-II Driver Fuel Composition (1)

Overview of Experiments and Analysis Methods

Tomoyuki Jin, Kenji Yokoyama, Shin-ichi Koyama, Yasushi Ohkawachi

Session ID: O46
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.172.0

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Analysis of Post-Irradiation Experiments on "JOYO" MK-II Driver Fuel Composition (2)

Analysis Results and Evaluation

Kenji Yokoyama, Tomoyuki Jin, Yasushi Ohkawachi, Shin-ichi Koyama

Session ID: O47
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.173.0

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Analyses of PIE data with Lattice Analysis Codes(5)

-Analysis of Isotopic Composition Data of 9x9 UO2 Fuel after 5 Cycle Irradiation-

Toru Yamamoto, Katsuyuki Kawashima, Katsuichiro Kamimura, Yuichiro Kan ...

Session ID: O48
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.174.0

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Core Physics Experiment and Analysis of the Irradiated Fuel (5)

Irradiated UO2 Core Critical Experiment and Analysis

Katsuyuki Kawashima, Toru Yamamoto, Katsuichiro Kamimura, Yamato Hayas ...

Session ID: O49
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.175.0

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A Method to Calculate keff within a Convergence Criterion of Source Iteration in Monte Calro Calculation

Yoshitaka NAITO, Masakazu NAMEKAWA

Session ID: O50
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.176.0

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A Method to Calculate keff within a Convergence Criterion of Source Iteration in Monte Calro Calculation

2:demonstration calculation

Masakazu NAMEKAWA, Yoshitaka NAITO, Kenichi SUZUKI, Takeshi MITSUHASHI

Session ID: O51
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.177.0

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Monte Carlo criticality analysis of solutoin fuel system with free surface

shohei sato, hiroshi okuno

Session ID: O52
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.178.0

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Preparation of Nuclear Constants based on Monte Carlo Calculation (3)

Yoshihira Ando, Kenichi Yoshioka, Mitsuaki Yamaoka, Masahiko Kuroki, M ...

Session ID: O53
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.179.0

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Critical Experiment Analyses for BWR Fuel Assembly System

Verification of LANCER-AETNA BWR Core Design Code System

Hiromi Maruyama, Munenari Yamamoto, Tatsuya Iwamoto

Session ID: O54
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.180.0

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Analysis of Critical Assembly Using AEGIS/SCOPE2

Masahiro Tatsumi, Yasunori Ohoka, Naoki Sugimura, Tadashi Ushio, Masaa ...

Session ID: O55
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.181.0

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Analysis on SPERT-III core using 3 Dimensional nodal kinetics code ANCK

shigeaki aoki, kazuya yamagi, daisuke sato, takayuki suemura, toshikaz ...

Session ID: O56
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.182.0

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Application of Nodal BWR Transient Code TRACG05 for RIA Analysis

Masatoshi Sigawara, Tatsuya Iwamoto, Masashi Tamitani, Yoshiro Kudo

Session ID: O57
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.183.0

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The burn-up calculation model of the AEGIS code

Naoki Sugimura, Tadashi Ushio, Masahiro Tatsumi, Akio Yamamoto

Session ID: O58
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.184.0

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Development of NEXUS/PARAGON/ANC Code System

(1)Overview

MAKOTO NAKANO, HIDEKI MATSUMOTO, DAISUKE SATO, KAZUYA YAMAJI, SHINJI A ...

Session ID: O59
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.185.0

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Development of NEXUS/PARAGON/ANC Code System

(2)Lattice Physics Code -PARAGON-

MAKOTO NAKANO, HIDEKI MATSUMOTO, DAISUKE SATO, KAZUYA YAMAJI, SHINJI A ...

Session ID: O60
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.186.0

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Development of NEXUS/PARAGON/ANC Code System

(3)Critical Experiment Analysis

MAKOTO NAKANO, HIDEKI MATSUMOTO, DAISUKE SATO, KAZUYA YAMAJI, SHINJI A ...

Session ID: O61
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.187.0

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Development of NEXUS/PARAGON/ANC Code System

(4)Core Simulator -ANC-

MAKOTO NAKANO, HIDEKI MATSUMOTO, DAISUKE SATO, KAZUYA YAMAJI, SHINJI A ...

Session ID: O62
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.188.0

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Development of NEXUS/PARAGON/ANC Code System

(5)Core Analysis

MAKOTO NAKANO, HIDEKI MATSUMOTO, DAISUKE SATO, KAZUYA YAMAJI, SHINJI A ...

Session ID: O63
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.189.0

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Fuel loading pattern optimization based on case based reasoning

Masafumi Adachi, Akio Yamamoto, Yosihiro Yamane, Yasunori Kitamura

Session ID: O64
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.190.0

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Improvement of Control Rod Pattern Adjustment technique

FUMIO MATSUURA, ISAMU MATSUYAMA

Session ID: O65
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.191.0

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Improvement accuracy of the method of characteristics using the diamond difference scheme

Akio YAMAMOTO

Session ID: O66
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.192.0

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Reduction of Spatial Dependence Observed in Least Squares Inverse Kinetics Analysis

Hiroshi Taninaka, Kengo Hashimoto

Session ID: O67
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.193.0

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Study on the acceleration of the nuclear reactor physics calculation based on GPGPU

Yasunori Ohoka, Masahiro Tatsumi

Session ID: O68
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.194.0

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Subgroup parameter production using the Krylov subspace method

TOSHIHISA YAMAMOTO, TOSHIKAZU TAKEDA

Session ID: O69
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.195.0

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Conceptual design of VHTR

(1) Design requirement and system concept

Futoshi Okamoto, Katsuhiro Tozawa, Tetsuo Nishihara, Kazuhiko Kunitomi

Session ID: L49
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.196.0

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Conceptual Design of VHTR

Core design study

Masaaki NAKANO, Eiji TAKADA, Tomoaki MOURI, Kazuhiko KUNITOMI

Session ID: L50
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.197.0

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Conceptual design of VHTR

(3) Evaluation of metallic FP release from fuel particles

Yujiro TAZAWA, Futoshi OKAMOTO, Kazutaka OHASHI, Kazuhiko KUNITOMI

Session ID: L51
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.198.0

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Conceptual design of VHTR

(4) Evaluation of core bypass flow

Nobumasa Tsuji, Futoshi Okamoto, Tomoyuki Murakami, Kazuhiko Kunitomi

Session ID: L52
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.199.0

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Conceptual design of VHTR

(5) Analysis of air ingress and its prevention

Xing L. Yan, Kazuhiko Kunitomi, Nobumasa Tsuji, Futoshi Okamoto

Session ID: L53
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.200.0

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Investigations on lifetime extension and waste reduction methods for graphite components

Junya Sumita, Satoshi Hanawa, Taiju Shibata, Tatsuya Tada, Tatsuo Iyok ...

Session ID: L54
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.201.0

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STRENGTH ANALYSIS OF PLATE=FIN HEAT EXCHANGER USING HOMOGENIZATION METHOD

TOSHIHIDE IGARI, FUMIKO KAWASHIMA, YORIKATA MIZOKAMI, MASANORI TANIHIR ...

Session ID: L55
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.202.0

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Helium Chemistry Research and Development for High-Temperature Reactors

(1) R&D Plan of Active Chemistry Control for Lifetime Extention for Primary Materials

NARIAKI SAKABA, YOICHI TAKEDA, SHIMPEI HAMAMOTO, HIROFUMI OHASHI, DAIS ...

Session ID: L56
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.203.0

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Application effect of region temperature coefficients used for reactor kinetics of HTGR

Kuniyoshi Takamatsu, Tetsuaki Takeda, Shigeaki Nakagawa, Minoru Goto

Session ID: L57
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.204.0

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Once-Through Pebble Fuel Core with Burnable Poison

Nam Hoai Tran, Taichi Yoshimi, Yasuyoshi Kato

Session ID: L58
Published: 2006
Released on J-STAGE: November 06, 2006

DOIhttps://doi.org/10.11561/aesj.2006f.0.205.0

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A study of PBMR core has been carried out applying once-through refueling scheme. In this scheme only fresh fuel pebbles are inserted into the top of reactor core and will be removed to spent-fuel tank after 1-pass. All of pebbles will reach their target burnup before removed from reactor core. Therefore power plant could be impressively simpler due to the lack of fuel checking system. Lattice and full core calculations with continuous fuel discharged are performed by MVP code via PERL scripts. The large excess reactivity and high power peaking factor are controlled by adding burnable poison particles containing B4C and Gd2O3 into fuel pebble.

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