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

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2011 Fall Meeting

Displaying 351-400 of 835 articles from this issue

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Analysis of Core Melt Accidents in Fukushima No.1 Nuclear Power Station

Fumiya Tanabe

Session ID: L13
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.351.0

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Prevention of severe accident caused by station blackout in PWR

Masaya Kondo, Yoshinari Anode

Session ID: L14
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.352.0

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Proposals for Increasing Defense in Depth for Severe Accident

Air cooling RHR system and filtered vent system

Tadashi Narabayashi, Kenichiro Sugiyama

Session ID: L15
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.353.0

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Investigation on Surveillance Specimen Exclusion for Heat Affected Zone Materials of Reactor Pressure Vessel Steels

Part 5: Evaluation of the Susceptibility to Neutron Irradiation Embrittlement

Tohru Tobita, Masaharu Fuse, Takuyo Ohtsu, Jinya Katsuyama, Kunio Oniz ...

Session ID: L16
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.354.0

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Investigation on Surveillance Specimen Exclusion for Heat Affected Zone (HAZ) Materials of Reactor Pressure Vessel (RPV) Steels

Part 6: Structural Integrity Assessment Based on Inhomogeneity and Irradiation Embrittlement

Jinya Katsuyama, Koichi Masaki, Kunio Onizawa

Session ID: L17
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.355.0

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Failure Probability Analysis for PWSCC in Reactor Vessel Head Penetrations

Makoto UDAGAWA, Jinya KATSUYAMA, Kunio ONIZAWA

Session ID: L18
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.356.0

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The Consideration of Seismically Induced Various Events in PSA

Kenji Kawaguchi, Tomoaki Uchiyama

Session ID: L19
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.357.0

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Seismic Margin vs. Risk level

Part5: Seismic Risk Map Based on Equivalent Gradient KH

Masato NAKAJIMA, Yasuki OHTORI, Kazuta HIRATA

Session ID: L20
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.358.0

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A study on response uncertainty of fragility evaluation for nuclear power plant with seismic isolation system

Takuya Toriyama, Akira Yamaguchi, Takashi Takata

Session ID: L21
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.359.0

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MPS Analysis ofMolten Core Solidification Bihavior

Takumi KAWAHARA

Session ID: L22
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.360.0

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Numerical Simulation on Penetration and Freezing Behavior of Solid-liquid Mixed Melt in a Pin-bundle

Shinya Nakayama, Md. Abdul Malek Soner, Yu Hasegawa, Tatsuya Matsumoto ...

Session ID: L23
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.361.0

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Numerical Simulation of Melt-structure Heat Transfer with Solidification Using a Hybrid Particle-grid Method

Tomoya Takeda, Takahito Suzuki, Kouji Morita, Rida Siti Nuraini Mahmud ...

Session ID: L24
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.362.0

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Application of the statistical technique to the non-operation phenomenon of high pressure infusion (HPI) in small break LOCA (1)Phenomena identification and ranking table (PIRT) making and sensitivity analysis

Ikuo Kawasaki, Minoru Yamada

Session ID: L25
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.363.0

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Development of Level-1 PSA Method for Sodium-cooled Fast Reactors

(1) Development plan and Reactor Shutdown Failure Event Evaluation

Kenichi KURISAKA, Takaaki SAKAI, Hidemasa YAMANO, Satoshi FUJITA, Keis ...

Session ID: N41
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.364.0

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Development of probabilistic safety assessment (Level-1PSA)

(2) Assessment methodology of failure probability for passive safety function

Hidemasa Yamano, Takaaki Sakai, Kenichi Kurisaka

Session ID: N42
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.365.0

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Development of Level-1 PSA Method for Sodium-cooled Fast Reactors

(3) Development of response analysis method considering seismic isolation characteristics

Keisuke Minagawa, Satoshi Fujita, Akira Yamaguchi, Takashi Takata, Kur ...

Session ID: N43
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.366.0

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Development of Level-1 PSA Method for Sodium-cooled Fast Reactors

(4) Development fragility evaluation method considering seismic isolation characteristics

Takashi Takata, Akira Yamaguchi, Satoshi Fujita, Keisuke Minagawa, Ken ...

Session ID: N44
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.367.0

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Experimental study on fragmentation behavior of molten core material during core disruptive accident for sodium-cooled fast reactors

Results of fragmentation test for molten oxide penetrating into a sodium pool

Ken-ichi Matsuba, Kenji Kamiyama, Kensuke Konishi, Jun-ichi Toyooka, I ...

Session ID: N45
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.368.0

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Experimental studies on upward discharge of molten core materials during core disruptive accident for sodium-cooled fast reactors

Kenji Kamiyama, Kensuke Konishi, Ikken Sato, Jun-ich Toyooka, Ken-ichi ...

Session ID: N46
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.369.0

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Uncertainty Evaluation Methods for ULOF Transient

Marco Pellegrini, Hisashi Ninokata, Hiroshi Endo, Yasushi Tsuboi

Session ID: N47
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.370.0

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The application of uncertainty methodologies is increasing in the nuclear field. Often, even though the methodology is validated and correct, a wrong estimation of the assumptions (e.g. input parameters' uncertainty) might lead to not completely correct results and plant expectations during the postulated accident. The paper addresses a rational and rigorous evaluation of the uncertainty parameters for fuel disruption during a FBR ULOF transient.

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Study on Upper Limit Energetics during ULOF transition phase of Fast Breeder Reactor(2)

Tomoko Ishizu, Hiroshi Endo

Session ID: N48
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.371.0

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Development of containment-response analysis code for level-2 PSA of FBR (8)

Study on Re-criticality in the core region after core damage

Osamu Kawabata, Hiroshi Endo, Kazuo Haga, Masaaki Inoue

Session ID: N49
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.372.0

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Development of the Integrated Core Disruptive Accident Analysis Code ASTERIA-FBR

Fuel behavior analysis module for the FBR core FEMAXI-FBR (part 3)

ISAO TATEWAKI, HIROSHI ENDO, TOMOKO ISHIZU

Session ID: N50
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.373.0

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Investigation of basic models for sevelopment pd analysis tool for over-heating rupture in FBR steam generator

TOMOMICHI ITOH, KAZUO HAGA, HIROSHI ENDO, YOSHIHISA SHIDO, YASUTOMO SA ...

Session ID: N51
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.374.0

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Investigation of basic models for development of analysis tool using CFD code to over-heating rupture in FBR steam generator

Kazuo Haga, Tomomichi Ito, Hiroshi Endo, Yoshihisa Shindo, Yasutomo Sa ...

Session ID: N52
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.375.0

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Development of Apparatus for Cesium Migration to Liquid Sodium

Kazuki Mizutani, Ken-ichiro Sugiyama, Masaaki Inoue, Yutaka Endo

Session ID: N53
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.376.0

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Examination of reqirements on the safety review of future FBR (III)

Hiroshi Endo, Osamu Kawabata, Kazuo Haga, Masaaki Inoue, Tomoko Ishizu ...

Session ID: N54
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.377.0

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Safety Design Criteria of Sodium-cooled Fast Reactor as a Generation-IV Reactor System

(1) Background, Motivation and Roadmap for the Safety Design Criteria Establishment

Yasushi OKANO, Takaaki SAKAI, Ryodai Nakai

Session ID: N55
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.378.0

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Safety Design Criteria of Sodium-cooled Fast Reactor as a Generation-IV Reactor System

(2) Fundamental Approach of the Safety Design Criteria for SFR

Satoshi FUJITA, Yasushi OKANO, Takaaki SAKAI, Ryodai NAKAI

Session ID: N56
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.379.0

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Safety Design Criteria of Sodium-cooled Fast Reactor as a Generation-IV Reactor System

(3) Approach for Design Extension Condition in the Safety Design Criteria of the SFR

Shigenobu Kubo, Hidemasa Yamano, Yasushi Okano, Takaaki Sakai, Ryodai ...

Session ID: N57
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.380.0

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Computational Science and Engineering

R&D of Three-dimensional Vibration Simulator for a Nuclear Power Plant

(1) Overall

Akemi Nishida, Yoshio Suzuki, Chiaki Kino, Ken Uzawa

Session ID: K01
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.381.0

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R&D of Three-dimensional Vibration Simulator for a Nuclear Power Plant

(2) Framework for Assembly Structure - Assembly Fluid Coupling Analysis

Yoshio Suzuki, Ken Uzawa, Akemi Nishida, Norihiro Nakajima

Session ID: K02
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.382.0

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R&D of Three-dimensional Vibration Simulator for a Nuclear Power Plant

(3) Development of fluid-structure interaction analysis based on Immersed Boundary method

Chiaki Kino, Tadashi Watanabe, Akemi Nishida, Hiroshi Takemiya

Session ID: K03
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.383.0

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R&D of Three-dimensional Vibration Simulator for a Nuclear Power Plant

(4) Validation of turbulence model near interface of two-phase flow

Ken Uzawa

Session ID: K04
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.384.0

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Fundamental research of 3-dimensional mesh-particle hybrid method

Toshihiro Kawakami, Yuki Ishiwatari

Session ID: K05
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.385.0

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Development of Evaluation Method for Boron Deposition on PWR Fuel Rod Surface

Influence of AOA controlling factors on Boron Deposition

HIROAKI SUZUKI, SHUNSUKE UCHIDA, MASANORI NAITOH, HIDETOSHI OKADA

Session ID: K06
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.386.0

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Numerical study on effect of contact angle for behavior of a bubble departured from a heating surface in subcooled pool boiling

Yasuo OSE, Tomoaki KUNUGI

Session ID: K07
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.387.0

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Development of Evaluation Method on Flow-induced Vibration and Corrosion of Components in Two-phase Flow by Coupled Analysis

53. Computer Models for Prediction of FAC/LDI Occurrence and Wall Thinning Rate

Seiichi Koshizuka, Masanori Naitoh, Shunsuke Uchida, Hidetoshi Okada

Session ID: K08
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.388.0

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Development of Evaluation Method on Flow-induced Vibration and Corrosion of Components in Two-phase Flow by Coupled Analysis

54. Validation of Evaluation Accuracy of Wall Thinning due to Flow Accelerated Corrosion Based on V&V Method

Masanori Naitoh, Shunsuke Uchida, Hidetoshi Okada, Seiichi Koshizuka

Session ID: K09
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.389.0

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Development of Evaluation Method on Flow-induced Vibration and Corrosion of Components in Two-phase Flow by Coupled Analysis

55. Validation of Evaluation Accuracy of Local Wall Thinning due to Liquid Droplet Impingement Based on V&V Method

Hidetoshi Okada, Masanori Naitoh, Shunsuke Uchida, Seiichi Koshizuka

Session ID: K10
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.390.0

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Development of Evaluation Method on Flow-induced Vibration and Corrosion of Components in Two-phase Flow by Coupled Analysis

56. Evaluation of Ferrous Ion Transport in the Cooling System and Its Effects on FAC Wall Thinning Rate

Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Seiichi Koshizuka

Session ID: K11
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.391.0

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Development of Evaluation Method on Flow-induced Vibration and Corrosion of Components in Two-phase Flow by Coupled Analysis

57. Modeling Mass Transfer in the Flow through an Orifice with Wall Functions

Jinbiao Xiong, Seiichi Koshizuka, Mikio Sakai

Session ID: K12
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.392.0

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Category IV: Nuclear Fuel Cycle and Nuclear Materials

Basic Properties

development of evaluation technique of O/M in sintering process of MOX pellets

SHUN HIROOKA, MASATO KATO, TETSUYA TAMURA

Session ID: D01
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.393.0

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XAFS measurement on uranium and americium mixed oxide

Tsuyoshi Nishi, Masami Nakada, Chikashi Suzuki, Hiroki Shibata, Yoshih ...

Session ID: D02
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.394.0

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Quantitative measurement of material strain phenomena after SHPB impact

Masayoshi Kawai, Masatoshi Futakawa, Takashi Naoe, Hiroshi Yamada, Cao ...

Session ID: D03
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.395.0

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Vaporization of Rare-earth (Nd) Molten Salt

YUJI ARITA, AKIYUKI SHIROSHITA, MASATO OHTSUKA, TSUNEO MATSUI

Session ID: D04
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.396.0

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Non-stoichiometry evaluation using Raman spectroscopy in Ceria

Tatsuya Sakurahara, Takuji Oda, Satoru Tanaka

Session ID: D05
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.397.0

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Phase Transition of Hafnium Hydride (II)

YUJI ARITA, YASUTAKA SHIOHAMA, AKIYUKI SHIROSHITA, TSUNEO MATSUI

Session ID: D06
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.398.0

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First-principles study on magnetic structure of UO2

Nanako TAMARI, Tatsumi ARIMA, Yaohiro INAGAKI, Kazuya IDEMITSU

Session ID: D07
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.399.0

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Nuclear Fuels

Fabrication of metallic fuel elements for irradiation test at Joyo

(1) Irradiation test plan and fuel elements design

Takanari Ogata, Kinya Nakamura, Wataru Itagaki, Tomonori Soga, Takafum ...

Session ID: F17
Published: 2011
Released on J-STAGE: October 19, 2011

DOIhttps://doi.org/10.11561/aesj.2011f.0.400.0

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