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

Search
Browse

All issues

2007 Fall Meeting

Displaying 201-250 of 936 articles from this issue

Download citation

Show all abstracts

Core Physics Experiment and Analysis of Irradiated Fuel

[6]Irradiated High Burnup MOX Core Experiment and Analysis

Toru Yamamoto, Yoshihira Ando, Yamato Hayashi

Session ID: M38
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.204.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract

BWR Loading Pattern Optimization Code FINELOAD-3

MASATO WATANABE, HIDETSUGU OKADA, YOSHIO KIMURA, AKIHIRO FUKAO, TAKASH ...

Session ID: M39
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.205.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
BWR Loading Pattern Optimization Code FINELOAD-3

Hideto Yamauchi, Shozo Kato, Suetsugu Jagawa, Masato Watanabe, Hidetsu ...

Session ID: M40
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.206.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Study of the three-dimensional analytic nodal method

Yoshio Kimura, Shozo Kato, Hiroshi Noda, Hiroshi Shimotani, Akio Yamam ...

Session ID: M41
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.207.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Performance and applicability of the BWR pin-by-pin core analysis method with nodal method

Kenichi Tada, Akio Yamamoto, Yasunori Kitamura, Yoshihiro Yamane

Session ID: M42
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.208.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of multi-dimensional transport calculation method by polynomial approximation collision probability method

Tetsuo Matsumura, Takanori Kameyama, Akihiro Sasahara

Session ID: M43
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.209.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Neutronic characteristics of fast reactor cores by using SPH method

Toshikazu Takeda, Shinichi Asamoto, kazuki Kirimura

Session ID: M44
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.210.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract

Experiment of Subcriticality Measurement by using Imaginary Source Multiplication Method

Shinichi Kawaguchi, Tsuyoshi Misawa, Cheol Ho Pyeon, Seiji Shiroya

Session ID: M45
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.211.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Reactor Experiments for Accelerator-Driven System at FCA

Measurements of Fission Rate Distribution in Subcritical Core with Central Test Zone of Lead

Tsuyoshi Yamane, Shigeaki Okajima

Session ID: M46
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.212.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of metering means for analysis of energy dependence of neutron time decay in the reacter core

Masahiro Shintani, Yasunori Kitamura, Yoshihiro Yamane, Akio Yamamoto

Session ID: M47
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.213.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Measument of neutron spectrum in high energy proton irradiation field

Hiroshi Shiga, Hiroshi Yashima, Cheol Ho Pyeon, Tsuyoshi Misawa, Tomoh ...

Session ID: M48
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.214.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Measurement and Analysis of Reactivity Worth of Np-237 Sample in Water-moderated UO₂ Fuel Lattices at TCA of JAEA

Takeshi Sakurai, Takamasa Mori, Takenori Suzaki, Masaki Saito

Session ID: M49
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.215.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Approximate expression for maximum power at slow transient criticality accident

YUICHI YAMANE

Session ID: M50
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.216.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Evaluation of operating power history for the intensity of BWR start-up neutron source (Cm242 and Cm244)

Masato Watanabe, Hidetsugu Okada, Akio Yamamoto, Yoshiro Yamane

Session ID: M51
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.217.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract

Extended Bias Factor Method for Improvement of Prediction Accuracy of Neutronic Characteristics

Teruhiko KUGO, Takamasa MORI, Toshikazu TAKEDA

Session ID: M52
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.218.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Evaluation of uncertainty due to variation in plate weight and in isotope ratio in experimental analysis result for FCA

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

Session ID: M53
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.219.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Application of Extended Bias Factor Method to Neutronic Characteristics of Light Water Breeding Reactor using FCA Experiments

Teruhiko KUGO, Masaki ANDOH, Kensuke KOJIMA, Takamasa MORI, Yoshihiro ...

Session ID: M54
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.220.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract

Study on CANDLE Burnup

Analysis for Solution of Material Issue by Recladding (2)

Akito Nagata, Hiroshi Sekimoto

Session ID: D13
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.221.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Design of ultra-light weight space nuclear reactor with Am-242m

Hiroki Koike, Akio Yamamoto, Yosihiro Yamane, Yasunori Kitamura

Session ID: D14
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.222.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Nuclear Electric Propulsion System for Jupiter Exploration

Hideki Nakashima, Hidetaka Nagata, Makoto Miyoshi, Yusuke Kotani, Naoj ...

Session ID: D15
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.223.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Study on Nuclear Reactors for Nulcear-Pumped Laser (IV)

A Solution of Space-dependent Kinetic Equations for Pulse Cores and Laser Module Coupled System

Hiroki TAKEZAWA, Toru OBARA

Session ID: D16
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.224.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Study on Behavior of Polonium Produced from Bismuth

(VIII) Basic Experiment on Polonium Filter

Yu Yamazawa, Toru Obara, Toshinobu Sasa

Session ID: D17
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.225.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract

Research and Development of Super Fast Reactor

1. Overview of Research Program

Yoshiaki Oka, Yuuki Ishiwatari, Masanori Yamakawa, Hajime Akimoto, Sho ...

Session ID: D18
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.226.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Research and Development of Super Fast Reactor

2. Fuel and Core Developments (1)

Liangzhi Cao, Yoshiaki Oka, Yuki Ishiwatari, Tomofumi Ikejiri

Session ID: D19
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.227.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Research and Development of Super Fast Reactor

3. Detailed Numerical Simulation of Heat Transfer and Fluid Flow (1)

Zhi Shang, Junli Gou, Jue Yang, Jie Liu, Tomofumi Ikejiri, Yuki Ishiwa ...

Session ID: D20
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.228.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Research and Development of Super Fast Reactor

4. Plant Control (1)

Yuki Ishiwatari, Changhong Peng1, Yun Guo, Tomofuki Ikejiri, Yosiaki O ...

Session ID: D21
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.229.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Research and Development of Super Fast Reactor

5. High temperature structural design (1)

Masanori Yamakawa, Yuki Ihiwatari, Yosiaki Oka

Session ID: D22
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.230.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Research and Development of Super Fast Reactor

6. Development of reactor constants for transmutation analyses

Keisuke OKUMURA, Takamasa MORI

Session ID: D23
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.231.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Research and Development of Super Fast Reactor

Hideo Mori, Masaki Ohno, Yoshinori Hamamoto

Session ID: D24
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.232.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Research and Development of Super Fast Reactor

8. Heat Transfer Experiment of Supercritical Pressure Water Around Single Rod Heater

Koichiro Ezato, Satoshi Suzuki, Masayuki Dairaku, Mikio Enoeda, Masato ...

Session ID: D25
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.233.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Research and Development of Super Fast Reactor

9. Enhancement of the two-fluid model code ACE-3D to supercritical pressure

Hiroyuki Yoshida, Takeharu Misawa, Hidesada Tamai, Kazuyuki Takase, Ha ...

Session ID: D26
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.234.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Research and Development of Super Fast Reactor

10. Numerical analysis of heat transfer test of supercritical water in a tube

Takeharu Misawa, Hiroyuki Yoshida, Hidesada Tamai, Kazuyuki Takase, Ha ...

Session ID: D27
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.235.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of Materials for Supercritical-Water-Cooled Reactor (2)

1. Improvement of Fuel and Reactor Core Design (Nuclear Design)

Shungo SAKURAI, Katsumi YAMADA, Shinnichi MOROOKA, Kazuaki KITOU

Session ID: D28
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.236.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of Materials for Supercritical-Water-Cooled Reactor (2)

2. Improvement of Fuel and Reactor Core Design (Thermal Design)

Kazuaki Kitou, Kumiaki Moriya, Shungo Sakurai, Katsumi Yamada, Shinich ...

Session ID: D29
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.237.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of Materials for Supercritical-Water-Cooled Reactor (2)

3. Evaluation of Fuel Rod Behavior

SHINICHI HIGUCHI, SHUNGO SAKURAI, MASAHIRO OOKAWA

Session ID: D30
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.238.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of Materials for Supercritical-Water-Cooled Reactor (2)

4. High Temperature Strength Property of SCWR Fuel Claddings

Fumihisa Kano, Yumiko Tsuchiya, Norihisa Saito, Masahiro Ookawa, Junya ...

Session ID: D31
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.239.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of Materials for Supercritical-Water-Cooled Reactor (2)

5. Temperature Dependence of General Corrosion Property in Spercritical Water

Junya Kaneda, Shigeki Kasahara, Norihisa Saito, Masahiro Ookawa, Hidek ...

Session ID: D32
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.240.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of Materials for Supercritical-Water-Cooled Reactor (2)

6. Evaluation of SCC Property

Norihisa Saito, Yumiko Tsuchiya, Fumihisa Kano, Masahiro Ookawa, Junya ...

Session ID: D33
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.241.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract

A Design Study of Sodium-Cooled Core with MOX Fuel Containing MA

(2)Development of the core that can accept a wide range of TRU composition recovered from LWR spent fuel

Shigeo OHKI, Takashi OGAWA, Noboru KOBAYASHI, Masayuki NAGANUMA, Tomoy ...

Session ID: D34
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.242.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Improvement of FBR core characteristics with two different TRU-composition zones.

Shuhei Maruyama

Session ID: D35
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.243.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
A Design Study of the Enhancement of Sodium Cooled Metal Fuel High Temperature Plant Core Safety

Takashi Ogawa, Noboru Kobayashi, Masayuki Naganuma, Shigeo Ohki, Tomoy ...

Session ID: D36
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.244.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
A Design Study of Sodium Cooled Metal Fuel Core for High Temperature Plant with SiC Moderator

Noboru KOBAYASHI, Takashi OGAWA, Masayuki NAGANUMA, Kazuya OHGAMA, Shi ...

Session ID: D37
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.245.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Improvement effect for Neutronics Design Accuracy by Conducting Critical Experiments Loaded with MA fuels

Takanori Sugawara, Toshinobu Sasa, Hiroyuki Oigawa

Session ID: D38
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.246.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
MA Loaded FBR Core Concept suitable for the Transient Period

Koji Fujimura, Junichi Yamashita, Tetsuo Fukasawa, Akira Sasahira, Kun ...

Session ID: D39
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.247.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Core Characteristics of Small Lead Alloy Cooled Fast Reactor For Various Fuel Types and Cladding-Structure Materials

Abu Khalid Rivai, Minoru Takahashi

Session ID: D40
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.248.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

Effects of various fuel types and cladding-structure materials on neutronics of reactor core for a high temperature small lead alloy cooled fast reactor have been investigated analytically. The fuel types were nitride fuel, oxide fuel and metal fuel. The cladding-structure materials were steel and ceramic. Different enrichment in inner core and outer core was done for relatively flat neutron flux distributions and power density distribution. The core design was optimized using natural uranium blanket and fuel for long life-core with reshuffling interval of 10 years. The neutronic characteristics considered are the neutron energy spectrum, the criticality, the neutron flux distribution, the power density distribution, the void coefficient and the fuel burn up.

View full abstract
A study of ULOF Initiating phase of FBR by using phenomenological event tree

(1) Investigation of evaluating plan

TOMOKO ISHIZU, HIROSHI ENDO, KAZUO HAGA, YOSHIHISA SHINDO, YOSHIHIRO K ...

Session ID: D41
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.249.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of plate type heat exchanger for steam generator of fast reactors

(5) Design of the leakage detection layer

Yoshihisa Nishi, Izumi Kinoshita

Session ID: D42
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.250.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract

Development of LWR for Long Term Energy Supply

(XIII)Design of Gadolinia Rod and Control Rod Scheduling on Core by Applying RBWR-T3 Concept to ABWR

Junichi Miwa, Renzo Takeda, Yoshihiko Ishii, Kumiaki Moriya

Session ID: D43
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.251.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract
Development of LWR for Long Term Energy Supply

(XIV)RBWR for Fissioning All Depleted Uranium and Almost All Transuraniums

Renzo Takeda, Junichi Miwa, Yoshihiko Ishii, Kumiaki Moriya

Session ID: D44
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.252.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

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

(9) Overview of FLWR Research Status

Tsutomu Okubo, Sadao Uchikawa, Takamichi Iwamura

Session ID: D45
Published: 2007
Released on J-STAGE: October 29, 2007

DOIhttps://doi.org/10.11561/aesj.2007f.0.253.0

CONFERENCE PROCEEDINGS FREE ACCESS

Show abstractHide abstract

[in Japanese]

View full abstract

feedback

Top

Register with J-STAGE for free!