Sumita, Junya: search on Z-Library

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1

Reactor internals design

Junya Sumita, Masahiro Ishihara, Shigeaki Nakagawa, Takayuki Kikuchi, Tatsuo Iyoku

Journal:

Nuclear Engineering and Design

Year:

2004

Language:

english

File:

PDF, 345 KB

english, 2004

2

HTTR Demonstration Program for Nuclear Cogeneration of Hydrogen and Electricity

Sato, Hiroyuki, Yan, Xing L., Sumita, Junya, Terada, Atsuhiko, Tachibana, Yukio

Journal:

Journal of Nuclear Engineering and Radiation Science

Year:

2016

Language:

english

File:

PDF, 656 KB

english, 2016

3

Study on Structural Integrity of C/C Composite Using as Core Restraint Mechanism in HTGR

Tsuji, Nobumasa, Shibata, Taiju, Sumita, Junya, Ishihara, Masahiro, Iyoku, Tatsuo

Journal:

Key Engineering Materials

Year:

2005

Language:

english

File:

PDF, 977 KB

english, 2005

4

An Investigation of the Effects of Water Content on the Shielding Performance of the Primary Upper Shield in the High Temperature Engineering Test Reactor (HTTR)

Sumita, Junya, Sawa, Kazuhiro, Takada, Eiji, Tada, Keiko

Journal:

Journal of Nuclear Science and Technology

Year:

2000

Language:

english

File:

PDF, 1.88 MB

english, 2000

5

Oxidation Damage Evaluation by Non-Destructive Method for Graphite Components in High Temperature Gas-Cooled Reactor

SHIBATA, Taiju, TADA, Tatsuya, SUMITA, Junya, SAWA, Kazuhiro

Journal:

Journal of Solid Mechanics and Materials Engineering

Year:

2008

Language:

english

File:

PDF, 1.74 MB

english, 2008

6

Development of Atrioventricular Block and Diagnostic Value of Stored Electrograms in Patients With Sick Sinus Syndrome and Implanted Pacemaker

Hosoda, Junya, Ishikawa, Toshiyuki, Sumita, Shinichi, Matsushita, Kohei, Matsumoto, Katsumi, Kimura, Yuichiro, Ogino, Yutaka, Taguchi, Yuka, Matsushita, Hirooki, Nakagawa, Takeshi, Sugano, Teruyasu, I

Journal:

Circulation Journal

Year:

2015

Language:

english

File:

PDF, 681 KB

english, 2015

7

Principle design and data of graphite components

Masahiro Ishihara, Junya Sumita, Taiju Shibata, Tatsuo Iyoku, Tatsuo Oku

Journal:

Nuclear Engineering and Design

Year:

2004

Language:

english

File:

PDF, 279 KB

english, 2004

8

Non-destructive evaluation methods for degradation of IG-110 and IG-430 graphite

Taiju Shibata, Junya Sumita, Tatsuya Tada, Satoshi Hanawa, Kazuhiro Sawa, Tatsuo Iyoku

Journal:

Journal of Nuclear Materials

Year:

2008

Language:

english

File:

PDF, 534 KB

english, 2008

9

Investigation of Microstructural Change by X-ray Tomography and Anisotropic Effect on Thermal Property of Thermally Oxidized 2D-C/C Composite for Very High Temperature Reactor

SUMITA, Junya, SHIVARA, Taiju, KUNIMOTO, Eiji, YAMAJI, Masatoshi, KONISHI, Takashi, SAWA, Kazuhiro

Journal:

Journal of Nuclear Science and Technology

Year:

2010

Language:

english

File:

PDF, 2.33 MB

english, 2010

10

Characterization of 2D-C/C Composite for Application of Very High Temperature Reactor(M & M 2009 Conference)

SHIBATA, Taiju, SUMITA, Junya, MAKITA, Taiyo, TAKAGI, Takashi, KUNIMOTO, Eiji, SAWA, Kazuhiro, KIM, W. J., JUNG, C. H., PARK, J. Y.

Year:

2010

File:

PDF, 592 KB

2010

11

Basic Concept on Structural Design Criteria for Zirconia Ceramics Applying to Nuclear Components

Shibata, Taiju, Sumita, Junya, Baba, Sinichi, Yamaji, Masatoshi, Ishihara, Masahiro, Iyoku, Tatsuo, Tsuji, Nobumasa

Journal:

Key Engineering Materials

Year:

2005

Language:

english

File:

PDF, 249 KB

english, 2005

12

Design of HTTR-GT/H 2 test plant

Yan, Xing L., Sato, Hiroyuki, Sumita, Junya, Nomoto, Yasunobu, Horii, Shoichi, Imai, Yoshiyuki, Kasahara, Seiji, Suzuki, Koichi, Iwatsuki, Jin, Terada, Atsuhiko, Tachibana, Yukio, Oono, M., Yamada, S.

Journal:

Nuclear Engineering and Design

Year:

2017

Language:

english

File:

PDF, 2.02 MB

english, 2017

13

Development of an Evaluation Model for the Thermal Annealing Effect on Thermal Conductivity of IG-110 Graphite for High-Temperature Gas-Cooled Reactors

SUMITA, Junya, SHIBATA, Taiju, NAKAGAWA, Shigeaki, IYOKU, Tatsuo, SAWA, Kazuhiro

Journal:

Journal of Nuclear Science and Technology

Year:

2009

Language:

english

File:

PDF, 178 KB

english, 2009

14

Investigation on structural integrity of graphite component during high temperature 950 °C continuous operation of HTTR

Sumita, Junya, Shimazaki, Yosuke, Shibata, Taiju

Journal:

Journal of Nuclear Science and Technology

Year:

2014

Language:

english

File:

PDF, 749 KB

english, 2014

15

R&D plan for development of oxidation-resistant graphite and investigation of oxidation behavior of SiC coated fuel particle to enhance safety of HTGR

Ueta, Shohei, Sumita, Junya, Shibata, Taiju, Aihara, Jun, Fujita, Ichiro, Ohashi, Jun, Nagaishi, Yoshihide, Muto, Takenori, Sawa, Kazuhiro, Sakaba, Nariaki

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 1.35 MB

english, 2014

16

Development of evaluation method with X-ray tomography for material property of IG-430 graphite for VHTR/HTGR

Sumita, Junya, Shibata, Taiju, Fujita, Ichiro, Kunimoto, Eiji, Yamaji, Masatoshi, Eto, Motokuni, Konishi, Takashi, Sawa, Kazuhiro

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 1.02 MB

english, 2014

17

HTTR-GT/H 2 test plant – System performance evaluation for HTTR gas turbine cogeneration plant

Sato, Hiroyuki, Nomoto, Yasunobu, Horii, Shoichi, Sumita, Junya, Yan, Xing L

Journal:

Nuclear Engineering and Design

Year:

2017

Language:

english

File:

PDF, 1.38 MB

english, 2017

18

Development of non-destructive evaluation methods for degradation of HTGR graphite components

Taiju Shibata, Junya Sumita, Tatsuya Tada, Kazuhiro Sawa

Journal:

Journal of Nuclear Materials

Year:

2008

Language:

english

File:

PDF, 822 KB

english, 2008

19

Reprocessing Technologies of the High Temperature Gas-Cooled Reactor (HTGR) Fuel

SUMITA, Junya, UETA, Shohei, KUNITOMI, Kazuhiko, YOSHIMUTA, Shigeharu, SAWA, Kazuhiro

Journal:

Transactions of the Atomic Energy Society of Japan

Year:

2003

Language:

english

File:

PDF, 5.83 MB

english, 2003

20

Integrity Confirmation Tests and Post-irradiation Test Plan of the HTTR First-Loading Fuel

SAWA, Kazuhiro, SUMITA, Junya, UETA, Shouhei, SUZUKI, Shuichi, TOBITA, Tsutomu, SAITO, Takashi, MINATO, Kazuo, KOYA, Toshio, SEKINO, Hajime

Journal:

Journal of Nuclear Science and Technology

Year:

2001

Language:

english

File:

PDF, 166 KB

english, 2001

21

A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries

Ohashi, Hirofumi, Sato, Hiroyuki, Goto, Minoru, Yan, Xing, Sumita, Junya, Tazawa, Yujiro, Nomoto, Yasunobu, Aihara, Jun, Inaba, Yoshitomo, Fukaya, Yuji, Noguchi, Hiroki, Imai, Yoshiyuki, Tachibana, Yu

Journal:

International Journal of Nuclear Energy

Year:

2013

Language:

english

File:

PDF, 11.64 MB

english, 2013

22

Evaluation of fracture toughness of fine-grained isotropic graphites for HTGR

Yamada, Teruaki, Matsushima, Yuki, Kuroda, Masatoshi, Sumita, Junya, Shibata, Taiju, Fujita, Ichiro, Sawa, Kazuhiro

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 649 KB

english, 2014

23

Obituary.

Yamada, Teruaki, Matsushima, Yuki, Kuroda, Masatoshi, Sumita, Junya, Shibata, Taiju, Fujita, Ichiro, Sawa, Kazuhiro

Journal:

Year:

1870

Language:

english

File:

PDF, 395 KB

english, 1870

24

Long-term effect of cardiac pacing on sleep-disordered breathing in patients with conventional indications for a permanent pacemaker

Matsushita, MD, Kohei, Ishikawa, MD, Toshiyuki, Toda, MD, Noritaka, Sumita, MD, Shinnichi, Matsumoto, MD, Katsumi, Hosoda, MD, Junya, Kimura, MD, Yuuichirou, Ogino, MD, Yutaka, Taguchi, MD, Yuka, Ishi

Journal:

Journal of Arrhythmia

Year:

2014

Language:

english

File:

PDF, 1.92 MB

english, 2014

25

Design of core components

Tatsuo Iyoku, Shohei Ueta, Junya Sumita, Masayuki Umeda, Masahiro Ishihara

Journal:

Nuclear Engineering and Design

Year:

2004

Language:

english

File:

PDF, 234 KB

english, 2004

26

Evaluation of Fuel Temperature on High Temperature Test Operation at High Temperature Gas-Cooled Reactor 'HTTR'

TOCHIO, Daisuke, SUMITA, Junya, TAKADA, Eiji, FUJIMOTO, Nozomu, NAKAGAWA, Shigeaki

Journal:

Transactions of the Atomic Energy Society of Japan

Year:

2006

File:

PDF, 4.15 MB

2006

27

Annealing Effect of Thermal Conductivity on Thermal Stress Induced Fracture of Nuclear Graphite

Sumita, Junya, Shibata, Taiju, Ishihara, Masahiro, Iyoku, Tatsuo, Tsuji, Nobumasa

Journal:

Key Engineering Materials

Year:

2005

Language:

english

File:

PDF, 451 KB

english, 2005

28

Principle Design of Graphite Components for HTTR and R&D on Nuclear Graphite for HTGR in JAEA

Sumita, Junya, Shibata, Taiju, Iyoku, Tatsuo, Ishihara, Masahiro, Nishihara, Tetsuo

Journal:

Key Engineering Materials

Year:

2016

Language:

english

File:

PDF, 4.58 MB

english, 2016

29

Prediction of Fuel Performance and Fission Gas Release Behavior during Normal Operation of the High Temperature Engineering Test Reactor by JAERI and FZJ Modeling Approach

SAWA, Kazuhiro, UETA, Shouhei, SUMITA, Junya, VERFONDERN, Karl

Journal:

Journal of Nuclear Science and Technology

Year:

2001

Language:

english

File:

PDF, 187 KB

english, 2001

30

Anisotropic Deformation Effect on the Fracture of Core Components Made of Two-Dimensional C/C Composite

Sumita, Junya, Shibata, Taiju, Ishihara, Masahiro, Iyoku, Tatsuo, Tsuji, Nobumasa

Journal:

Key Engineering Materials

Year:

2005

Language:

english

File:

PDF, 374 KB

english, 2005

31

Fuel and Fission Gas Behavior during Rise-to-Power Test of the High Temperature Engineering Test Reactor (HTTR)

UETA, Shohei, SUMITA, Junya, EMORI, Koichi, TAKAHASHI, Masashi, SAWA, Kazuhiro

Journal:

Journal of Nuclear Science and Technology

Year:

2003

Language:

english

File:

PDF, 387 KB

english, 2003

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