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

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2011 Fall Meeting

Displaying 151-200 of 835 articles from this issue

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Application of the Discrete Ordinate CIP Scheme and the Fictitious Source Method for Reactor Shielding Calculations

Kotaro Nakano, Tomohiro Endo, Akio Yamamoto

Session ID: N06
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.151.0

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Verification of Kinetic Calculation on Simulated System of Accelerator Driven Subcritical Reactor

Naoto KUBOTA, Tomohiro ENDO, Akio YAMAMOTO

Session ID: N07
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.152.0

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BWR whole core nuclear-thermal hydraulic coupled simulation system

Development of 3D pin-by-pin neutronics code DACHS

Munenari Yamamoto, Akiko Toishigawa, Tadashi Ikehara, Tatsuya Iwamoto, ...

Session ID: N08
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.153.0

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BWR whole core nuclear-thermal hydraulic coupled simulation system

Investigation of nuclear-thermal hydraulic coupling model

Akiko Toishigawa, Tadashi Ikehara, Munenari Yamamoto, Tatsuya Iwamoto, ...

Session ID: N09
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.154.0

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Application of new core monitoring system "GNF-ARGOS" to TOKAI-II POWER STATION

(5) GNF-ARGOS System

Tatsunori Sakamoto, Masato Uchita, Takayuki Negishi, Hisashi Shiraga, ...

Session ID: N10
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.155.0

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Application of new core monitoring system "GNF-ARGOS" to TOKAI-II POWER STATION

(6) Accuracy Evaluation of GNF-ARGOS for On Line Core Monitoring

Tatsunori Sakamoto, Masato Uchita, Takayuki Negishi, Tatsuya Iwamoto, ...

Session ID: N11
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.156.0

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Application of new core monitoring system "GNF-ARGOS" to TOKAI-II POWER STATION

(7) Accuracy Evaluation of GNF-ARGOS for Prediction of Core Performances

Tatsunori Sakamoto, Masato Uchita, Takayuki Negishi, Tatsuya Iwamoto, ...

Session ID: N12
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.157.0

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Application of Augmented Reality for Reactor Core Simulation

Kosuke Tsujita, Tomohiro Endo, Akio Yamamoto

Session ID: N13
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.158.0

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Development of Mitsubishi FBR Nuclear Design Code System GALAXY-H/ENSEMBLE-TRIZ

(1)Lattice Physics Calculation Code GALAXY-H

YOHEI KAMIYAMA, KAZUKI KIRIMURA, WATARU NAKAZATO, HIDEKI MATSUMOTO, AK ...

Session ID: N14
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.159.0

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Development of Mitsubishi PWR Nuclear Design Code System GALAXY/COSMO-S

(5)Integrated Reaction Rate Preservation Method of Heterogeneous System for Resonance Calculation based on Multi-Term Rational Equation

HIROKI KOIKE, KAZUKI KIRIMURA, HIDEKI MATSUMOTO, AKIO YAMAMOTO

Session ID: N15
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.160.0

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Development of Mitsubishi PWR Nuclear Design Code System GALAXY/COSMO-S

(6) Method of nuclear constants correction for the effect of adjacent fuel at COSMO-S

KAZUKI KIRIMURA, DAISUKE SATO, SHINJI ABE, HIDEKI MATSUMOTO

Session ID: N16
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.161.0

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Development of Mitsubishi PWR Nuclear Design Code System GALAXY/COSMO-S

(7)Three-dimesional Kinetics Calculation Code COSMO-K

KAZUYA YAMAJI, KAZUKI KIRIMUEA, JUNTO OGAWA, HIDEKI MATSUMOTO, AKIO YA ...

Session ID: N17
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.162.0

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TAGS measurement and the gross theory of beta decay for decay heat calculations and pandemonium problem.

Takayuki Arai

Session ID: N18
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.163.0

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Neutron capture effect in FP decay heat of a LWR

Hiroto Matsumoto, Tadashi Yoshida

Session ID: N19
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.164.0

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Evaluation of Doppler reactivity effect in MOX fueled LWR using FCA

[2] Analysis of experimental data of UO2 samples in a uranium fueled core

Motomu SUZUKI, Toru YAMAMOTO, Yoshihira ANDO, Tetsuo NAKAJIMA, Masaki ...

Session ID: N20
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.165.0

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Neutron spectrum measurement for ADS target with Liquid organic scintillator and ADS characterization

Yoshiyuki Takahashi, Tetsushi Azuma, Takahiro Yagi, Cheol Ho Pyeon, Ja ...

Session ID: N21
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.166.0

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Development of Reactivity Feedback Effect Measurement Techniques under Sub-critical Condition in Fast Reactor (II)

(1) Skeleton of Program

Shigeaki OKAJIMA, Hiroshi NISHI, Shigeru KANEMOTO, Yoshihiro YAMANE, M ...

Session ID: N22
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.167.0

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Development of Reactivity Feedback Effect Measurement Techniques under Sub-critical Condition in Fast Reactor (II)

(2) A Study on Reactivity Measurement Method and Items to be measured under Sub-critical State

Hiroshi NISHI, Akihiro KITANO, Takayuki SUZUKI, Shigeaki OKAJIMA

Session ID: N23
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.168.0

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Development of Reactivity Feedback Effect Measurement Techniques under Sub-critical Condistion in Fast Reactor (II)

(3) FCA Experiment -Modified Source Multiplication Method-

Masahiro FUKUSHIMA, Yasunori KITAMURA, Masaki ANDOH, Shigeaki OKAJIMA, ...

Session ID: N24
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.169.0

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Development of Reactivity Feedback Effect Measurement Techniques under Sub-critical Condition in Fast Reactor (II)

(4) FCA Experiment - Reactor Noise Method -

Yasunori KITAMURA, Masahiro FUKUSHIMA, Masaki ANDOH, Shigeaki OKAJIMA, ...

Session ID: N25
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.170.0

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Development of Reactivity Feedback Effect Measurement Techniques under Sub-critical Condition in Fast Reactor (II)

(5) A Feasibility Study on Sub-critical Reactivity Measurement System Application to Power Reactors

Akihiro Kitano, Shigeru Kanemoto, Hiroshi Nishi, Takayuki Suzuki, Shig ...

Session ID: N26
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.171.0

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Research Reactor, Application of Neutron / Reactor Physics, Nuclear Data, Criticality Safety

Study on Criticality Safety Transient Analysis in Weakly Coupling System

(1) Preliminary Analysis for Uranium Fuel Solutions

Haruka Kikuchi, Toru Obara

Session ID: N27
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.172.0

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Application of Iterative Solution Technique for Numerical Analysis of Power Reactor Noise

Tomohiro Endo, Akio Yamamoto, Demazière Christophe, Pázs ...

Session ID: N28
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.173.0

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Ratingpractice and use state of KUR in 2010 fiscal year

Yasuyuki Fujihara, Jian Zhang, Yoshiyuki Takahashi, Tadafumi Sano, Tos ...

Session ID: N29
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.174.0

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DESIGN STUDY OF INNOVATIVE SIMPLIFIED SMALL PEBBLE BED REACTOR

(4) ANALYSIS OF THE THORIUM FUEL IN THE SIMPLIFIED PBR DESIGN WITH PEU A PEU FUEL LOADING SCHEME

DWI IRWANTO, TORU OBARA

Session ID: N30
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.175.0

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Optimization of the fuel use in a small simplified pebble bed reactor with a peu a peu fuel loading scheme have been performed for uranium fuel in the previous study. In the present study, thorium are introduced to the fuel compound and parametric surveys are performed to find the best fuel configuration in order to achieved better burnup characteristics of the reactor system.

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Study on SiC components to Improve the Neutron Economy in HTGR

Piyatida Trinuruk, Toru Obara

Session ID: N31
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.176.0

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SiC material has been proposed to use instead of graphite material in various parts of HTGR to shift the neutron spectrum which is expected to improve the neutron economy of HTGR. This concept can also reduce the excess reactivity in place of using a poison material.

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Reactor Physics, Nuclear Data, Criticality Safety

Sensitivity analysis of effective multiplication factor for KUR core by JENDL-4

Tadafumi Sano, Ken Nakajima, Hironobu Unesaki

Session ID: N32
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.177.0

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Analyses of critical experiments for LWR configurations with containing Gd rods by JENDL-4

Hiroshi MATSUMIYA, Takuya UMANO, Kenichi YOSHIOKA

Session ID: N33
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.178.0

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Analysis of BASALA experiments by using CASMO-4/SIMULATE-3

Toru Yamamoto, Tomohiro Sakai, Yoshihira Ando, Tetsuo Nakajima, Shin O ...

Session ID: N34
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.179.0

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Analysis of REBUS experiments by using CASMO-4/SIMULATE-3

Yoshihira ANDO, Toru YAMAMOTO, Tomohiro SAKAI, Tetsuo NAKAJIMA, Tomoyu ...

Session ID: N35
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.180.0

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Analysis of UAM benchmark problems

(5)Uncertainty analysis of assembly problems using stochastic sampling method

Tomohiro Sakai, Shigeki Shiba, Tomoyuki Takada

Session ID: N36
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.181.0

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Investigation on uncertainty correlations among core neutronic characteristic parameters in LWR

Yoshihiro Yasue, Tomohiro Endo, Akio Yamamoto, Yasuhiro Kodama, Yasuno ...

Session ID: N37
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.182.0

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Preparation of Nuclear Constants based on Monte Carlo Calculation

Effect of Statitical Error on Nuclear Constants

Taku KITAMURA, Yutaka TAKEUCHI, Ken-ichi YOSHIOKA

Session ID: N38
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.183.0

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A method of evaluating parameter errors (uncertainties) of a design caluculation of a target sysytem with utilizing measurement data of critical experiments: An application to a caluclation of a BWR fuel assembly

Takuya UMANO, Mitsuaki YAMAOKA, Kenichi YOSHIOKA, Satoshi SUGAHARA

Session ID: N39
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.184.0

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Validation of MA Nuclear Data by Sample Irradiation Experiments with the Fast Reactor "Joyo" (4)

Evaluation by Cross-section Adjustment Technique

Kazuteru SUGINO, Shigeo OHKI, Yasushi OHKAWACHI, Shin-ichi KOYAMA, Shi ...

Session ID: N40
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.185.0

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Advanced Reactor, Nuclear Design, Transmutation

Progress in 4S Technology Development

(1) Validation of Nuclear Design Method by Measured Data obtained in the Physics Tests at a Small Fast Reactor

Yasushi Tsuboi, Akito Nagata, Yasuyuki Moriki, Masatoshi Kawashima

Session ID: O17
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.186.0

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Progress in 4S Technology Development

(2) Thrmal hydraulic transient test in upper plenum

ryoji katsuki, chikako iwaki, nobuhiko usui, jun ohno, atsuko matsuda, ...

Session ID: O18
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.187.0

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Progress in 4S Technology Development

(3) ARGO Code Verification in 4S Upper Plenum Part

Jun OHNO, Atsuko MATSUDA, Nobuhiko USHUI, Hisao WATANABE, Ryoji KATSUK ...

Session ID: O19
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.188.0

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Progress in 4S Technology Development

(4) Measures against severe accident and evaluation of long-term coolability

Kyoko Ishii, Hisato Matsumiya, Kazuhito Asano, Yasushi Tsuboi

Session ID: O20
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.189.0

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Progress in 4S Technology Development

(5) Development of Steam Generator of double wall tube with wire mesh layer

Takehisa Hino, Masaki Tamura, Yoshimi Tanaka, Satoshi Tadano, Katsuhik ...

Session ID: O21
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.190.0

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Progress in 4S Technology Development

(6)R&D of large diameter high temperature electromagnetic pump and passive flowcoast back-up power supply system

Yasushi Fujishima, Rie Aizawa, Kenji Katsuki, Jun Ito, Daigo Kittaka, ...

Session ID: O22
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.191.0

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Design study of steam turbine system for JSFR

Fumiaki Kaneko, Yoshitaka Chikazawa, Atsushi Kato, Shinichi Suzuki, To ...

Session ID: O23
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.192.0

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Development of Safety Protection System of JSFR

Nobuyuki Ishikawa, Kaoru Fujita, Yoshitaka Chikazawa, Takashi Hiramats ...

Session ID: O24
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.193.0

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Improvement of analytical model on heat transfer tube failure accident of steam generator in fast reactor

Examination of "mole conversion ratio of water to hydrogen gas" in sodium water reaction

FUMIE SEBE, HIDEKI HORIE, NOBUHISA TAKEZAWA, HISATO MATSUMIYA

Session ID: O25
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.194.0

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Conceptual Design toward the Commercial Reactor of JSFR

(12)Summary of Evaluation of Innovative Technologies

Hiroki Hayafune, Nariaki Uto, Tsutomu Okubo, Yushi Ohno, Shoji Kotake, ...

Session ID: O26
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.195.0

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Conceptual Design toward the Commercial Reactor of JSFR

- (13) Overview of the plant based on evaluation of innovative technologies -

Shigeki Kobayashi, Takaya Ito, Mikio Toda, Hiroki Hayafune, Yoshihiko ...

Session ID: O27
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.196.0

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Study of Steel plate reinforced Concrete Containment Vessel for JSFR

(1) Experimental research on SCCV bearing wall against lateral load

Atsushi Katoh, Kazuo Negishi, Hiroyuki Hara, Takahiro Somaki

Session ID: O28
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.197.0

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Study of Steel plate reinforced Concrete Containment Vessel for JSFR

(2) Experimental research on SCCV opening and penetration

MIKINORI IWASAKI, ATSUSHI KATOH, KAZUO NEGISHI, YOU AKIYAMA, KATSUHIKO ...

Session ID: O29
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.198.0

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Study of Steel plate reinforced Concrete Containment Vessel for JSFR

(3) Experimental research on SCCV out-of-plane bending property

Atsushi KATOH, Kazuo NEGISHI, Hiroyuki HARA, Shinji TAKAMI, Takahiro S ...

Session ID: O30
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.199.0

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Development of maintenance technology for advanced fast breeder reactor application

Outline: Development of evaluation method for maintenance in FBR

Ken-ichi Fukumoto, Toshikazu Takeda, Naoki Yamano, Katsuhisa Yamaguchi ...

Session ID: O31
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.200.0

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