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

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2007 Annual Meeting

Displaying 151-200 of 660 articles from this issue

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Application of Nodal BWR Transient Code TRACG05 for Scram Analysis

Masatoshi Sugawara, Tatsuya Iwamoto, Shingo Fujimaki

Session ID: E28
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.151.0

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Development of the New Pin-by-Pin Core Calculation Method based on the Heterogeneous 2D Assembly Calculation Embedded in 3D Core Calculation

(2) Computaional Method of SPH factor in Fuel Lattice

Toshikazu TAKEDA, Kazuki KIRIMURA, Makoto NAKANO, Hideki MATSUMOTO, Ka ...

Session ID: E29
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.152.0

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Development of the New Pin-by-Pin Core Calculation Method based on the Heterogeneous 2D Assembly Calculation Embedded in 3D Core Calculation

(3) Application of SPH Method to Arbitary Geometries

KAZUYA YAMAJI, HIDEKI MATSUMOTO, MAKOTO NAKANO, TOSHIKAZU TAKEDA, KAZU ...

Session ID: E30
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.153.0

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Acceleration of kinetics calculation based on micro-reactor physics

Toshiki Okamoto, Toshikazu Takeda

Session ID: E31
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.154.0

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Analysis of neutron diffusion problem by boundary element method

I. Theoretical aspect

Takuo FUKUI, Takayuki ISHIDA

Session ID: E32
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.155.0

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Analysis of neutron diffusion problem by boundary element method

2. Analysis example

Takayuki ISHIDA, Takuo FUKUI

Session ID: E33
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.156.0

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A Monte Carlo variance reduction method using the Kalman filter

Toshihisa Yamamoto, Toshikazu Takeda

Session ID: E34
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.157.0

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Estimation of Higher-Order Terms in the Taylor Series Expansion for Change in the Effective Multiplication Factor with the Differential Operator Sampling Method

Yasunobu Nagaya, Takamasa Mori

Session ID: E35
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.158.0

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Compact expression of the third-order neutron correlation method taking spatial and energy effect into account

Tomohiro Endo, Hitoki Iwase, Yoshihiro Yamane, Akio Yamamoto

Session ID: E36
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.159.0

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Validation of BWR Core Simulator COS3D in MOX Core

Mikio TOKASHIKI, Takuya ITO

Session ID: E37
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.160.0

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Development of Erbia-Bearing Super High Burnup Fuel

(4)Summary of Project in 2006FY

Masatoshi Yamasaki, Takeshi Kuroishi, Toshikazu Takeda, Akio Yamamoto, ...

Session ID: E38
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.161.0

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Development of Erbia-Bearing Super High Burnup Fuel

(5)Critical Experiment using KUCA

Hironobu Unesaki, Toshikazu Takeda, Akio Yamamoto, Masaaki Mori, Masat ...

Session ID: E39
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.162.0

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Development of Erbia-Bearing Super High Burnup Fuel

(6)Improvement of Generalized Bias Factor Method

Toshikazu Takeda, Tadafumi Sano, Takanori Kitada, Masatoshi Yamasaki

Session ID: E40
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.163.0

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Development of Erbia-Bearing Super High Burnup Fuel

(7)Neutronics Design of Fuel Assembly

Michitaka Imamura, Naoki Sugimura, Masaaki Mori, Toshikazu Takeda, Aki ...

Session ID: E41
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.164.0

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Detailed Burnup calculation with Krylov subspace method

Application to detailed chain in ORIGEN library

DAISUKE FUJIAWARA, SHINYA KOSAKA

Session ID: E42
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.165.0

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Effect of Fuel Composition Errors on Core Characteristics in Burn up Calculations

Yamamoto Toru, Kawashima Katsuyuki, Kanayama Yuichiro

Session ID: E43
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.166.0

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Effect of Pu-rich Agglomerate on Latice Analysis in MOX Fuel (II)

Katsuyuki Kawashima, Toru Yamamoto, Masakazu Namekawa

Session ID: E44
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.167.0

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Modification of MONTEBURNS2 to raise the limitation on the number of materials to irradiate

TADASHI IKEHARA, AKIKO TOISHIGAWA, MUNENARI YAMAMOTO

Session ID: E45
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.168.0

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Nuclear Criticality Safety for the MOX Fuel Facility

(1) Estalishing Critical Limits

Yuichi Suitsu, Yoshio Shimizu, Tatsutoshi Murakami, Akiya Yuri

Session ID: E46
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.169.0

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Nuclear Criticality Safety for the MOX Fuel Facility

(2) Parametric Evaluation of Plutonium Isotopic Composition for Mass Control Limits

Yoshio Shimizu, Yuichi Suitsu, Tatsutoshi Murakami, Akiya Yuri

Session ID: E47
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.170.0

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Nuclear Criticality Safety for the MOX Fuel Facility

(3) Commitiment to the Double Contingency Principle

Akiya Yuri, Yoshio Shimizu, Yuichi Suitsu, Tatsutoshi Murakami, Junich ...

Session ID: E48
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.171.0

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Nuclear Criticality Calculations in Considering Non-uniformity of MOX, UO2 and Additive

(1) Background, Formulation and Calculation Model

Hiroshi Okuno, Shohei Sato, Gunzo Uchiyama, Tomohiro Sakai

Session ID: E49
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.172.0

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Nuclear Criticality Calculation in Considering Non-uniformity of MOX,UO2 and Additive

(2)Calculation Code and Results, and Further Investigations

Shohei Sato, Hiroshi Okuno, Gunzo Uchiyama, Tomohiro Sakai

Session ID: E50
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.173.0

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Risk-Informed Criticality Analysis

-Basic Concept-

TAKESHI SEINO, HITOSHI TAMAKI

Session ID: E51
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.174.0

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Pre-examination of Measurement of Initial Temperature Effect to Transient Criticality Phenomena using TRACY

YUICHI YAMANE, GUNZO UCHIYAMA

Session ID: E52
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.175.0

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A study about output control of three core Molten Salt Reactor by fuel salt flow quantity operation

atsushi ishihara

Session ID: D01
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.177.0

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Characteristics of Thorium Molten-Salt Reactor with Fuel Sustainability

Koshi MITACHI, Tetsuya SUGIMOTO, Takahisa YAMAMOTO

Session ID: D02
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.178.0

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Feasibility Study on Water Cooled Thorium Breeder Reactor

-4- Power output and power density Effects on Feasible Breeding Regions

Sidik Permana, Naoyuki TAKAKI, Hiroshi SEKIMOTO

Session ID: D03
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.179.0

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The different power outputs and power densities are evaluated in order to estimate the effect of that parameter to the breeding capability. The significant effect of MFR and power density for required enrichment and conversion ratio are when the MFR is low and the breeding capability of the reactor increases with increasing power output.

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Study on Nuclear Reactors for Nuclear Pumped Laser

(III) Study of Kinetic Analysis Method for Pulse Cores and Laser Module Coupled System

Toru OBARA, Hiroki TAKEZAWA

Session ID: D04
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.180.0

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Transmutation of Sn-126 Using Spallation Reaction

Chi Young HAN, Masaki SAITO, Hiroshi SAGARA, Yoji TANAKA

Session ID: D05
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.181.0

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The feasibility of Sn-126 transmutation using spallation reaction in ADS was evaluated in viewpoints of proton utilization, neutron production, support ratio, effective half-life, equilibrium toxicity, and radioactivity. Parametric studies on spallation target and proton beam sizes were also performed for effective transmutation. It was found that the spallation target gives better transmutation properties than other transmutation systems.

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Study on the flatting of power distribution for Accelerator Driven System

Kohei Iwanaga, Kenji Nishihara, kazufumi Tsujimoto, Toshinobu Sasa, hi ...

Session ID: D06
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.182.0

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Burnup characteristics optimization of ADS reactor

Kazuhiro EGUCHI, Hiroshi SEKIMOTO, Kohei IWANAGA, T SASA

Session ID: D07
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.183.0

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Study on Innovative Water Reactor for Flexible Fuel Cycle (FLWR)

(8)Conceptual Design of Breeder Type FLWR Core using Recovered Uranium as Blanket Fuel

Sadao Uchikawa, Yoshihiro Nakano, Kenji Tatematsu, Tsutomu Okubo

Session ID: D08
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.184.0

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Development of LWR for Long Term Energy Supply

(XI)Outline of Core by Applying RBWR-T3 Concept to ABWR

Junichi Miwa, Renzo Takeda, Kumiaki Moriya

Session ID: D09
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.185.0

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Development of LWR for Long Term Energy Supply

(XII)RBWR-TB Core for Fissioning Almont All Transuraniums Generated by LWRs

Renzo Takeda, Junichi Miwa, Kumiaki Moriya

Session ID: D10
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.186.0

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Analysis on reactor performance and safety characteristics of HTGR

(1) Project overview of development and validation of analytical methods

Tetsuaki Takeda, Shigeaki Nakagawa, Minoru Goto, Kuniyoshi Takamatsu, ...

Session ID: D11
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.187.0

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Analysis on reactor performance and safety characteristics of HTGR

(2) Comparison of analysis methods of nuclear characteristics

Minoru Goto, Tetsuaki Takeda, Shigeaki Nakagawa, Kuniyoshi Takamatsu, ...

Session ID: D12
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.188.0

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Analysis on reactor performance and safety characteristics of HTGR

(3) Development and validation of analytical methodology for reactor kinetics

Kuniyoshi Takamatsu, Tetsuaki Takeda, Shigeaki Nakagawa, Minoru Goto, ...

Session ID: D13
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.189.0

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Analysis on reactor performance and safety characteristics of HTGR

(4) Development and validation of analytical methodology for coolant flow reduction test

Shigeaki Nakagawa, Kuniyoshi Takamatsu, Tetsuaki Takeda, Minoru Goto, ...

Session ID: D14
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.190.0

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Analysis on reactor performance and safety characteristics of HTGR

(5)Temperature analysis of the concentric hot gas duct of coolant flow reduction test

Hiroyuki Saito, Tetsuaki Takeda, Shigeaki Nakagawa, Yoshitomo Inaba

Session ID: D15
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.191.0

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Once-Through Refueling in a Pebble Bed HTGR Core with Burnable Poison for Attaining Low Axial Power Peaking

NAM HOAI TRAN, Yasuyoshi Kato

Session ID: D16
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.192.0

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In a once-through refueling pebble bed core, fresh pebbles with large k-inf in the upper part of the core leads to an excessively high axial power peaking factor. An attempt has been done to minimize axial power peaking through controling axial k-inf distribution by adding burnable poison into the fuel pebbles.

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Helium Chemistry in High-Temperature Gas-Cooled Reactors

Control of Chemical Impurity Composition by Temperature and Flow Rate Control of Helium Purification System

Shimpei Hamamoto, Nariaki Sakaba, Yoichi Takeda

Session ID: D17
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.193.0

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Evaluation of Thermal Displacement Behavior of High Temperature Piping System

Masanori Shinohara, Shimpei Hamamoto, Nozomu Fujimoto

Session ID: D18
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.194.0

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Development of Fuel Design System for BWR based on Open Computer Code

(3)Connection of fuel design system to BWR core calculation

TAKAMICHI YOSHIKAWA, HIDEKI ENDO, TOMOHIKO IWASAKI, KEIJI SHIKODA, KOH ...

Session ID: D19
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.195.0

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Development of Fuel Design System for BWR based on Open Computer Code

(4)Verification of fuel design system by BWR core calculation

KEIJI SHIKODA, KOHEI YAMADA, YOSHIKI HAMAHATA, SHIN OEDA, TAKAMICHI YO ...

Session ID: D20
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.196.0

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Monte Carlo Simulation Models for Randomly Distributed Particle Fuels with Packing Fraction Variability Based on a Sub-Fine Lattice System

Nam Zin Cho

Session ID: D21
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.197.0

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For realistic analysis of very high temperature reactors, there is strong desire to explicitly model the double heterogeneity of the fuel and stochastic geometry in the core. Sub-fine lattice stochastic (Sub-FLS) modeling recently developed is described. It gives more random distribution of particle fuels, which results in more accurate criticality calculation with acceptable efficiency. Furthermore, packing fraction variability concept is newly proposed and successfully imbedded into the Sub-FLS model to reflect the manufacturing quality. We compare the model with the truly random Metropolis model derived from the Metropolis algorithm.

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Linear heat rate evaluation of MA-MOX fuel irradiation test in Joyo using MCNP

Wootan David, Takashi Sekine, Tomonori Soga, Takafumi Aoyama

Session ID: D22
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.198.0

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Research for Developping Visualization Software for Nuclear Reactor.

Shoji KASUGA, Hiroshi Sekimo

Session ID: D23
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.199.0

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RAPID-L Fast Reactor for Lunar Base Power System

(1) Reactivity Control Systems

Mitsuru Kambe, Osamu Sato, Hirokazu Tsunoda

Session ID: D24
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.200.0

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RAPID-L Fast Reactor for Lunar Base Power System

(2) Startup Plant Dynamics Analyses

OSAMU SATO, MITSURU KAMBE, HIROKAZU TSUNODA

Session ID: D25
Published: 2007
Released on J-STAGE: April 18, 2007

DOIhttps://doi.org/10.11561/aesj.2007s.0.201.0

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