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

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2004 Fall Meeting

Displaying 151-200 of 669 articles from this issue

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Reevaluation of the criticality safety analyses for MOX powder fuel system

Yoshinori MIYOSHI, Tomoyuki TAKADA, Toshihiro YAMAMOTO, Hiroshi OKUNO

Session ID: B54
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.151.0

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Study on Molten Salt Reactor using Pu fuel pin

Improvement of power density

SHINICHI NAKAZAWA, KOSHI MITACHI, TAKAHISA YAMAMOTO, FUMIKAZU MATSUMOT ...

Session ID: C10
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.152.0

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Effect of fuel salt flow rate on core characteristics of small Molten Salt Reactor

KOJI IKEUCHI, TAKAHISA YAMAMOTO, KOSHI MITACHI

Session ID: C11
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.153.0

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A study of molten-salt reactor with annular core

(3) Burn-up characteristics

Koshi Mitachi, Takahisa Yamamoto, Shinichi Nakazawa

Session ID: C12
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.154.0

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Characteristics for Different Moderation Ratios of the Reactor with Light and Heavy Water Coolant in Equilibrium State

Sidik Permana, Hiroshi Sekimoto, Obara Toru

Session ID: C13
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.155.0

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Characteristics for different moderation ratios are investigated with light water and heavy water coolant. Equilibrium state was implemented by four typical fuel cycles. Design parameters are the same for standard PWR design with different moderation ratios and different coolant as shown in table 1 Calculation method was performed by using ECICS (Equilibrium Cycle Iterative Calculation System) to get nuclide densities and uranium supply in equilibrium state and to estimate the required uranium enrichment to keep the reactor on the critical condition. Obtained results are shown in Fig.1 for both light water and heavy water coolant. In required uranium enrichment point of view the light water case has better performance than heavy water case, but in the lower moderator to fuel volume ratio the heavy water coolant has better conversion ratio than light water coolant.

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Applications of "CANDLE" Burnup Strategy to Various Nuclear Reactors

Hiroshi Sekimoto, Toru Obara

Session ID: C14
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.156.0

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Development of Monju Easy-to-Introduce System for Total Evaluation of Reactor Core MEISTER (8)

Study on a Heterogeneous model of Control Rod

Hidehiko Teruyama, Hiroshi Nishi, Akihiro Kitano, Yasuyuki Moriki

Session ID: C15
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.157.0

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Development of Monju Easy-to-Introduce System for Total Evaluation of Reactor Core MEISTER (9)

Study on Control Rod Modified Homogenization Model for start-up Test Results

Akihiro Kitano, Hidehiko Teruyama, Hiroshi Nishi, Yasuyuki Moriki

Session ID: C16
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.158.0

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R&D Issues in Structural Design Standard for Fast Reactor (No8)

Development of Guidelines for Thermal Load Modeling

Naoto KASAHARA, Hiroshi SHIBAMOTO, Kazuhiko INOUE, Masakazu JINBO

Session ID: C17
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.159.0

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R&D Issues in Structural Design Standard of Fast Reactor (No.9)

Ratchet and Creep-Fatigue Tests of Cylindrical model Subjected to Moving Temperature Distribution

Hideaki Nagashima, Hiroshi Shibamoto, Kazuhiko Inoue, Naoto Kasahara, ...

Session ID: C18
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.160.0

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R&D Issues in Structural Design Standard of Fast Reactor (No.10)

Settlement of Loading History for the Guideline on Inelastic Analysis for Design

Hiroshi Shibamoto, Yoshihiko Tanaka, Hideaki Nagashima, Kazuhiko Inoue ...

Session ID: C19
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.161.0

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Development of plate type heat exchanger for steam generator of fast reactors

(2) Test fabrication by HIP

Yoshihisa Nishi, Izumi Kinoshita

Session ID: C20
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.162.0

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Nuclear Power Plant Design 'Friendly to People'

Proposal on the Primary Containment Configuration for the Simplified BWR

Kanehiro Ochiai, Mitsuo Katayama, Tsuyoshi Niino

Session ID: C21
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.163.0

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Study of Self Actuated Shutdown System

(1) Whole plan

masato uchida, shoji kotake, masatoshi soroi, akihiro yoshida, iwao ik ...

Session ID: C22
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.164.0

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Study of Self Actuated Shutdown System

(2) Material Characteristic Test

Kiyoshi HARADA, Yuuichi SAWAHATA , Shoji KOTAKE, Masato UCHIDA , Iwao ...

Session ID: C23
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.165.0

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Study of Self Actuated Shutdown System

(3) Element Tests and System Tests

Jungo KATOH, Iwao IKARIMOTO, Shoji KOTAKE, Masato UCHIDA, Kiyoshi HARA ...

Session ID: C24
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.166.0

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Self Actuated Shutdown System Demonstration Test in JOYO

- (1) Test Program -

MISAO TAKAMATSU, TAKASHI SEKINE, MASATO UCHIDA, SHOJI KOTAKE

Session ID: C25
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.167.0

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Self Actuated Shutdown System Demonstration Test in JOYO

-(2) Installation and Initial Performance Test-

SHIGEHARU TOBITA, AKINORI NAGAI, KAZUNARI NISHINO, SATORU NAKAI, MASAT ...

Session ID: C26
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.168.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor (_II_)

_-_(1) Outline of Technical Studies for Development of PBWFR_-_

TAKAHSHI MINORU, TORU OBARA, SYOJI UCHIDA, KOJI HATA, KUNIAKI ARA

Session ID: C27
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.169.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor(_II_)

(2) Experimental Study on Chemical Interaction in Pb-Bi by Steam-Injection

KOJI HATA, KAZUYUKI HARA, MINORU TAKAHASHI

Session ID: C28
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.170.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor (_II_)

_-_(3) Experiment of Two-phase Flow in Chimney and Flow Analysis_-_

TOYOU AKASHI, MINORU TAKAHASHI, AKIRA YAMADA, KAZUYUKI HARA, MASATOSHI ...

Session ID: C29
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.171.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor (_II_)

_-_(4) Pb-Bi-Water Direct Contact Boiling_-_

MEGUMI MATSUIMOTO, MINORU TAKAHASHI, HIROSHI SOFUE, YUDI PRAMONO, HIRO ...

Session ID: C30
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.172.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor

Study on Ultrasonic Flow Measurement Technique for Lead-Bismuth Eutectic

KUNIAKI ARA, MASARU HIRABAYASHI, KEIICHI NAGAI, MINORU TAKAHASHI

Session ID: C31
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.173.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor (_II_)

(6)Conceptual Study of Electrostatic Precipitators for Removing Pb-Bi Droplets In Steam Line

ELIN YUSIBANI, MINORU TAKAHASHI, YUDI PRAMONO

Session ID: C32
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.174.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor (_II_)

(7) Design Evaluation of Polonium in PBWFR

TAKAHARU MATSUZAWA, SHOJI UCHIDA, MINORU TAKAHASHI, TORU OBARA

Session ID: C33
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.175.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor (II)

(8) Removal of Polonium surface contamination on 316 stainless steel

Terumitsu Miura, Toru Obara, Hiroshi Sekimoto

Session ID: C34
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.176.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor (II)

(9) Evaluation of Core Void Reactivity

Akira Otsubo, Minoru Takahashi

Session ID: C35
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.177.0

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Development of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor (II)

(10) Safety Characteristics of PBWFR

Yumi YAMADA, Kazuya KOYAMA, Syouji UCHIDA

Session ID: C36
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.178.0

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Development of Cost-Reduced Low-Moderation Spectrum BWR(15)

_-_Modification of Critical Power Correlation_-_

Yasushi Yamamoto, Kenetsu Shirakawa, Shinji Kubo, Shinich Morooka

Session ID: C37
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.179.0

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Development of Cost-Reduced Low Moderation Spectrum BWR(16)

Design of Equilibrium Core

Shungo SAKURAI, Kouji HIRAIWA, Mitsuaki YAMAOKA, Yasushi YAMAMOTO

Session ID: C38
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.180.0

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Development of Cost-reduced Low-Moderation Spectrum BWR (17)

Three Dimensional Transient Analysis by TRACG02modT1

NOBUAKI ABE, YUTAKA TAKEUCHI, SYUNGO SAKURAI, KOUJI HIRAIWA, SHIN-ICHI ...

Session ID: C39
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.181.0

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Study on Reduced-Moderation Water Reactor (RMWR) (45)

Design of 1350MWe BWR Core under TRUs Multiple Recycling with Natural Circulation

Renzo Takeda, Motoo Aoyama, Junichi Miwa, Tomohiko Ikegawa, Tsutomu Ok ...

Session ID: C40
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.182.0

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Neutron reaction behavior in water cooled reactors adopting tight lattice fuel

Koki Hibi, Hiroshi Sekimoto

Session ID: C41
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.183.0

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Development of Neutronic Analysis Technique for Non-refuelling Reactor Core(4)

Study on Critical Experimental Core with FCA

Mitsuaki Yamaoka, Tsugio Yokoyama, Yasuyuki Moriki, Shigeaki Okajima, ...

Session ID: C42
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.184.0

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Development of Neutronic Analysis Technique for Non-refueling Reactor Core(5)

Improvement Prediction Accuracy of Na Void Worth

Masakazu Toishikawa, Toshikazu Takeda

Session ID: C43
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.185.0

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Development of Neutronic Analysis Technique for Non-refueling Reactor Core(6)

Sensitivity evaluation of cross sections for burn-up reactivity depletion

Tetsuo MATSUMURA, Yasushi NAUCHI, Tsugio YOKOYAMA, Toshikazu TAKEDA, S ...

Session ID: C44
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.186.0

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High Temperature Supercritical-Pressure Light Water Reactor (6) ATWS Analysis

YOSHIAKI ISHIWATARI, YOSHIAKI OKA, SEIICHI KOSHIZUKA

Session ID: C45
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.187.0

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High-Temperature Supercritical-Pressure Light Water Reactor (7) Stability

Tin Tin Yi, Seiichi Koshizuka, Yuki Ishiwatari, Jie Liu, Yoshiaki Oka

Session ID: C46
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.188.0

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The stability characteristics of high temperature supercritical pressure light water cooled reactors (SCLWR-H) are studied by a linear frequency domain analysis. The thermal-hydraulic stability and coupled neutronic thermal-hydraulic stability are investigated for full power normal operation as well as partial power operations at constant supercritical pressure.

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High Temperature Supercritical-Pressure Light Water Reactor (8) Improved Core Design

AKIFUMI YAMAJI, KAZUHIRO KAMEI, YOSHIAKI OKA, SEIICHI KOSHIZUKA

Session ID: C47
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.189.0

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Development of Small Medium Reactor:DMS(1)

Plant Target & Concept

Kenji TOMINGA, Kumiaki MORIYA, Masayoshi MATSUURA, Yoshinori IIMURA, T ...

Session ID: C48
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.190.0

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Development of Small Medium Reactor: DMS (2)

Conceptual Design of Reactor System & Safety System

Shigeru Yokouchi, Kenichi Yasuda, Yukio Hatakeyama, masayoshi matsuura ...

Session ID: C49
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.191.0

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Development of Small Medium Reactor : DMS (3)

Conceptual Layout and Construction Method

Yusuke SHIMIZU, Yoshinori IIMURA, SHIZUKA HIRAKO, Takashi OKANO, Yuji ...

Session ID: C50
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.192.0

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AN INVESTIGATION OF FUEL AND FISSION PRODUCT BEHAVIOR IN HIGH TEMPERATURE TEST OPERATION OF THE HTTR

Shohei Ueta, Masayuki Umeda, Koichi Emori, Shigeaki Nakagawa, Kazuhiro ...

Session ID: C51
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.193.0

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Safety Demonstration Test using HTTR

Test Result of Coolant Flow Reduction Test from Reactor Power at 60%

NARIAKI SAKABA, SHIGEAKI NAKAGAWA, KUNIYOSHI TAKAMATSU, DAISUKE TOCHIO ...

Session ID: C52
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.194.0

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ECONOMICAL EVALUATION ON GAS TURBINE HIGH TEMPERATURE REACTOR 300 (GTHTR300)

Masanobu Takei, Shinichi Kosugiyama, Kazuhiko Kunitomi

Session ID: C53
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.195.0

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Helium-cooled Fast Reactor employing Coated-Particle Fuel in Hexagonal Matrix

Yasushi Okano, Masayuki Naganuma, Tomoyasu Mizuno, Naoyuki Takaki

Session ID: C54
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.196.0

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Core Concept of Compound Process Fuel Cycle

Tetsuo Ikegami

Session ID: C55
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.197.0

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Development of Accelerator Driven Transmutation System II

(1) Overall Progress of the Program

Hiroyuki Oigawa, Nobuo Ouchi, Kenji Kikuchi, Kazufumi Tsujimoto

Session ID: C56
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.198.0

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Development of Accelerator Driven Transmutation System II

(2) Development of Superconducting Accelerator

Nobuo Ouchi, Nobuo Akaoka, Hiroyuki Asano, Tomoaki Ueno, Kazuo Hasegaw ...

Session ID: C57
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.199.0

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DEVBELOPMENT OF ACCELERATOR DRIVEN TRANSMUTATION SYSTEM II

(3) Stucy on Corroosion Behavior of Steels in Liauid Lead-Bismuth

Kin-ya Kamata, Teruaki Kitano, Mikinori Ono, Kenji Kikuchi, YuJi Kurat ...

Session ID: C58
Published: 2004
Released on J-STAGE: November 19, 2004

DOIhttps://doi.org/10.11561/aesj.2004f.0.200.0

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