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

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2010 Fall Meeting

Displaying 251-300 of 996 articles from this issue

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Development of Advanced Component toward the Demonstration Reactor of JSFR

Project Plan and Preliminary Evaluation of SG Component Development test

Masanori Shimazaki, Hiroki Hayafune, Satoshi Futagami, Yasuhiro Enuma, ...

Session ID: P42
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.251.0

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Study on Inspection and Repaire Technologies toward the Demonstration Reactor of JSFR

(1)Project Summary

Takuya Yamashita, Masashi Ueda, Toshihiko Yamaguchi, Akihiro Tagawa, Y ...

Session ID: P43
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.252.0

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Study on Inspection and Repair Technologies toward the Demonstration Reactor of JSFR

Development of Under Sodium Inspection Techniques (Under Sodium Sensor)

Masayuki Takeishi, Masahiro Yui, Yasuhito Oshima, Yohei Uemoto, Takuya ...

Session ID: P44
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.253.0

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Study on Inspection and Repaire Technologies toward the Demonstration Reactor of JSFR

(3)Development of Under Sodium Inspection Techniques(Under Sodium Vehicle)

YOHEI UEMOTO, TAKUYA YAMASHITA, AKIHIRO TAGAWA, JUNGO KATO, AKIRA TOYO ...

Session ID: P45
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.254.0

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Study on Inspection and Repaire technologies toward the Demonstration Reactor of JSFR

(4)Development of Inspection Technologies for SG tubes (UT)

TOMOYUKI HIRAYAMA, KAZUYA KUROME, MASAYOSHI HIGASHI, MASAYA KAWAMURA, ...

Session ID: P46
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.255.0

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Study on Inspection and Repaire technologies toward the Demonstration Reactor of JSFR

MASAYA KAWAMURA, TOMOYUKI HIRAYAMA, KAZUYA KUROME, MASAYOSHI HIGASHI, ...

Session ID: P47
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.256.0

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Study on Inspection and Repair Technologies toward the Demonstration Reactor of JSFR

(6)Development of Inspection Device for FBR Structure Components

Toshihiko Yamaguchi, Ovidiu Mihalache, Masashi Ueda, Takuya Yamashita

Session ID: P48
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.257.0

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Development of Selector-Valve Method Failed Fuel Detection and Location System in Sodium-Cooled Large Reactor

examination on detection capability and operating pattern

Kaoru Fujita, Kosuke Aizawa, Hideki Kamide, Naoto Kasahara

Session ID: P49
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.258.0

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Development of Selector-Valve Method Failed Fuel Detection and Location System in Sodium-Cooled Large Reactor

(2) Detection capability evaluation in UIS slit by numerical analysis

kosuke aizawa, kaoru fujita, hideki kamide, naoto kasahara

Session ID: P50
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.259.0

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Development of fuel handling system in FaCT Project

(4)Evaluation of residual sodium on spent fuel subassembly after cleaning

Hiroyuki Obata, Yoshitaka Chikazaswa, Atsushi Katoh

Session ID: P51
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.260.0

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Development of fuel handling system in FaCT Project

(5) Cooling performance of MA bearing fresh fuel shipping cask

Yoshitaka Chikazawa, Atsushi Katoh, Hiroyuki Obata, Shingo Hirata

Session ID: P52
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.261.0

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Study on increasing in core average burn-up in FBR by optimization of core and blanket fuel

Toshio Wakabayashi, Tsigio Yokayama

Session ID: P53
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.262.0

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Study on long-life FBR with inner blanket by doping MA

Erina HAMASE, Masaki SAITO, Hiroshi SAGARA

Session ID: P54
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.263.0

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Consideration of methods to determine an enrichment of commercial fast reactor fuels

Shuhei MARUYAMA, Shigeo OHKI, Tsutomu OKUBO

Session ID: P55
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.264.0

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Shielding Design of JSFR

Radioactivity Evaluation of the Secondary Sodium in the DRACS

Kenji SASAKI, Katsuaki NAITO, Shigeo OHKI, Tsutomu OKUBO, Shoji KOTAKE

Session ID: P56
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.265.0

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Application of bootstrapping technique using Sn and Monte Carlo methods to IHX analyses

Keiko Tada, Osamu Sato, Ikuo Fukuchi

Session ID: P57
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.266.0

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Development on Compact Intermediate Heat Exchanger Using Advanced Composite Material

(15) Overview of the Project Accomplishment

satoshi konishi, tatsuya hinoki, yasushi yamamoto, kazuyuki noborio, y ...

Session ID: P58
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.267.0

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Development on Compact Intermediate Heat Exchanger Using Advanced Composite Material

(16) Evaluation of Heat Excjange Performance

kazuyuki noborio, yuto takeuchi, yasushi yamamoto, satoshi konishi

Session ID: P59
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.268.0

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Development on Compact Intermediate Heat Exchanger Using Advanced Composite Material

(17)Compatibility examinations of NITE-SiC/SiC composites with supercritical water etc.

Yasushi Yamamoto, Chang Ho Park, Kazuyuki Noborio, Satoshi Konishi

Session ID: P60
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.269.0

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Development on Compact Intermediate Heat Exchanger Using Advanced Composite Material

(18) Development of Fabrication Technique of Compact Intermediate Heat Exchanger utilizing NITE-SiC/SiC Composites

TATSUYA HINOKI, YI-HYUN PARK, SATOSHI KONISHI

Session ID: P61
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.270.0

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Successful Complition of Long Term High Temperature Operation of HTTR (High Temperature Engineering Test Reactor)

(1) Outlin of Test Plan

SHOJI TAKADA, KENJI SEKITA, YASUHIKO KAMEYAMA, KENJI SAITO, KAZUHIKO I ...

Session ID: Q01
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.271.0

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Successful Completion of Long Term High Temperature Operation of HTTR (High Temperature Engineering Test Reactor)

(2)Nuclear characteristics

Minoru Goto, Yukio Tachibana, Masanori Shinohara, Naoki Nojiri

Session ID: Q02
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.272.0

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Successful Completion of Long Term High Temperature Operation of HTTR (High Temperature Engineering Test Reactor)

(3) Fuel Behavior

Shohei Ueta, Jun Aihara, Hiroyuki Inoi, Masayuki Umeda, Kazuhiro Sawa

Session ID: Q03
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.273.0

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Successful Completion of Long Term High Temperature Operation of HTTR (High Temperature Engineering Test Reactor)

(4)Characteristics of coolant gas impurities

Shimpei Hamamoto, Hirofumi Ohashi, Yosuke Shimazaki, Tetsuo Nishihara

Session ID: Q04
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.274.0

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Successful Completion of Long Term High Temperature Operation of HTTR(High Temperature Engineering Test Reactor)

(5)Operation and Maintenance of HTTR

ATSUSHI SHIMIZU, TAIKI KAWAMOTO, DAISUKE TOCHIO, FUMITAKA HONMA, HIROA ...

Session ID: Q05
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.275.0

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A Study on Nuclear Characteristics of METMET Fuel

Yuta Takada, Yoichiro Shimazu, Tadashi Narabayashi, Masashi Tsuji

Session ID: Q06
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.276.0

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Optimised BWR Core Design for extended cycle operation

(1)High Enrichment 9x9 Fuel Core

Kenmi Narita, Hirohisa Kaneko, Akihiro Yamanaka, Mamoru Nagano, Kazuhi ...

Session ID: Q07
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.277.0

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Optimized BWR Core Design for extended cycle operation

High Enrichment 9x9 Fuel and Current MOX Fuel Core

Kazuhisa Matsumoto, Hiroko Hayakawa, Akihiro Yamanaka, Mamoru Nagano, ...

Session ID: Q08
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.278.0

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Analysis of Nuclear Characteristics for a Float-type Control Rod

Hiroto Saito, Toshio Wakabayashi, Makoto Takahashi

Session ID: Q09
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.279.0

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Thermal-design Method for modified-FAIDUS type Fuel Assembly of the JSFR based on Sub-channel Analysis

Yasushi OKANO, Hiroyuki OHSHIMA, Tsutomu OHKUBO

Session ID: Q10
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.280.0

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Study of thermal-hydraulics characteristics in small fast reactor 4S

Evaluation of natural convection in reflector area under water flow test

Mitsuo Wakamatsu, Tetsuzo Yamamoto, Nobuhiko Usui, Jun Ohno, hisao wat ...

Session ID: Q11
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.281.0

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Quantitative Evaluation on Difference between Heterogeneous Model and Homogeneous One

Kuniyoshi Takamatsu

Session ID: Q12
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.282.0

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Investigation on the thorium high conversion ratio reactor in a BWR

Yoshitaka Funahashi, tadashi Narabayashi, Masashi Tsuji, Yoichiro Shim ...

Session ID: Q13
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.283.0

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Feasibility study of gas cooled thorium breeder reactors

argala srivastava, Deby Mardiansah, Naoyuki Takaki

Session ID: Q14
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.284.0

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Feasibility studies of thorium breeder gas cooled reactors will be discussed. Parameters that will be studied are reactivity and conversion ratio as a fuction of burnup for different enrichment and moderator to fuel ratio.

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Study on CANDLE Burnup(XXVI)

Power Flattening by Dividing Fuel Region into Three

Shinsuke Nakayama, Hiroshi Sekimoto

Session ID: Q15
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.285.0

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Core design of heavy water cooled thorium breeder reactor -Study on control rod patttern and power flattening-

Ayumu Takeda, Naoyuki Takaki

Session ID: Q16
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.286.0

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Concept Study of Ultra Long-Life Space Reactor Loaded with Am and Cm

MASANORI NAKAMURA, MASAKI SAITO, HIROSHI SAGARA

Session ID: Q17
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.287.0

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Neutronic design of small reactor for lunar base using curium

Rei Kimura, Tadashi Yoshida

Session ID: Q18
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.288.0

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Study on the valuable element production technology by neutron nuclear transmutation

Daiki Iwahashi, Naoyuki Takaki

Session ID: Q19
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.289.0

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Minimizing Burnup Reactivity of TRU Fuel by its Resonance Capture

Takeshi SAKAI, Hiroshi SAGARA, Masaki SAITO

Session ID: Q20
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.290.0

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Increase in transmutation rate of LLFP with Deuteride Modertor

Tsugio Yokoyama, Toshio Wakabayashi, Yoshiaki Tachi

Session ID: Q21
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.291.0

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Research Reactor, Application of Neutron

Characteristics Measurements of Kyoto University Research Reactor with Low-Enriched Uranium Core

(1) Outline

KEN NAKAJIMA, HIRONOBU UNESAKI, TSUYOSHI MISAWA, TADAFUMI SANO, YOSHIY ...

Session ID: O01
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.292.0

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Characteristics Measurements of Kyoto University Research Reactor with Low-Enriched Uranium Core

(2) Approach to Critical and control rod worth measurments

Yasuyuki Fujihara, Tadahumi Sano, Jian Zhang, Yoshiyuki Takahashi, Tat ...

Session ID: O02
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.293.0

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Characteristics Measurements of Kyoto University Research Reactor with Low-Enriched Uranium Core

(3) Measrments of Reactivity Worth

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

Session ID: O03
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.294.0

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Characteristics Measurements of Kyoto University Research Reactor with Low-Enriched Uranium Core

(4) Reactor Neutron Noise Measurement

Tsuyoshi Misawa, Yoshiyuki Takahashi, Ken Nakajima

Session ID: O04
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.295.0

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Characteristics Measurements of Kyoto University Research Reactor with Low-Enriched Uranium Core

(5) Neutron Flux Distribution and Output Power Calibration

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

Session ID: O05
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.296.0

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Experimental Verification of Silicon Cross sections for Neutron Transmutation Doping

Haksung KIM, Cheol Ho PYEON, Jae-Yong LIM, Tsuyoshi MISAWA

Session ID: O06
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.297.0

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A numerical evaluation of radial uniformity in Neutron Transmutation Doping of silicon is largely affected by silicon cross sections. In this study, the exact use of silicon cross sections in numerical analysis is investigated through the neutron irradiation experiments of Si-ingot. And the numerical results with silicon single cross sections revealed the good agreement with experiment results within 4% error, whereas the discrepancy is approximately 20% at the maximum in case of free gas cross section.

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Characterization Measurement of 12inch NTD Silicon in JRR-4

Jun Motohashi, Masahiro Yagi, Toshiaki Kishi, Takanori Kashimura

Session ID: O07
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.298.0

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Examination of silicon doping technology in high temperature engineering test reactor (HTTR)(2)

-Irradiation characteristic in the movable reflector area-

Masaya SEKI, Naoyuki TAKAKI

Session ID: O08
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.299.0

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Research Reactor, Application of Neutron / Nuclear Fuel Cycles, Nuclear Energy Strategy

Design of Transition Cores of RSG GAS (MPR-30) with Higher Loading Silicide Fuel

Peng Hong Liem, Tagor Malem Sembiring

Session ID: O09
Published: 2010
Released on J-STAGE: October 18, 2010

DOIhttps://doi.org/10.11561/aesj.2010f.0.300.0

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A procedure for designing transition cores to achieve the equilibrium silicide core of RSG GAS with higher fuel loading of 300 g U/fuel element (FE) (meat density of 3.55 g U/cm3) has been proposed. In the proposed procedure, the EOC excess reactivity of each transition core is minimized in order to satisfy the safety design limit of one-stuck-rod sub-criticality margin while keeping the maximum of radial power peaking factor below the allowable value.

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