Enoeda, M.: search on Z-Library

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1

Oxidation of tritium in packed bed of noble metal catalyst for detritiation from system gases

Masabumi Nishikawa, Toshiharu Takeishi, Kenzo Munakata, Kenji Kotoh, Mikio Enoeda

Journal:

Journal of Nuclear Materials

Year:

1985

Language:

english

File:

PDF, 836 KB

english, 1985

2

Experimental Appratus for Cryogenic Hydrogen Isotope Separation Process in the Tritium Process Laboratory

Yamanishi, Toshihiko, Enoeda, Mikio, Yoshida, Hiroshi, Naruse, Yuji, Fukui, Hiroshi, Nagai, Hiroyuki, Imamura, Yutaka, Muta, Kenji

Journal:

Fusion Technology

Year:

1988

Language:

english

File:

PDF, 3.92 MB

english, 1988

3

Chemical form of released tritium from solid breeder materials under the various purge gas conditions

T. Kinjyo, M. Nishikawa, N. Yamashita, T. Koyama, T. Tanifuji, M. Enoeda

Journal:

Fusion Engineering and Design

Year:

2007

Language:

english

File:

PDF, 533 KB

english, 2007

4

Status and perspective of the R&D on ceramic breeder materials for testing in ITER

A. Ying, M. Akiba, L.V. Boccaccini, S. Casadio, G. Dell’Orco, M. Enoeda, K. Hayashi, J.B. Hegeman, R. Knitter, J. van der Laan, J.D. Lulewicz, Z.Y. Wen

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 659 KB

english, 2007

5

Deuterium concentration of co-deposited carbon layer produced at gap of wall tiles

Y. Nobuta, K. Yokoyama, J. Kanazawa, Y. Yamauchi, T. Hino, S. Suzuki, K. Ezato, M. Enoeda, M. Akiba

Journal:

Journal of Nuclear Materials

Year:

2011

Language:

english

File:

PDF, 675 KB

english, 2011

6

Effect of HIP temperature on microstructure and low cycle fatigue strength of CuCrZr alloy

Hiroshi Nishi, Mikio Enoeda

Journal:

Journal of Nuclear Materials

Year:

2011

Language:

english

File:

PDF, 1.06 MB

english, 2011

7

Packing behaviour of a Li2TiO3 pebble bed under cyclic loads

Hisashi Tanigawa, Yuichiro Tanaka, Mikio Enoeda

Journal:

Journal of Nuclear Materials

Year:

2011

Language:

english

File:

PDF, 377 KB

english, 2011

8

Development of the Water Cooled Ceramic Breeder Test Blanket Module in Japan

Mikio Enoeda, Hisashi Tanigawa, Takanori Hirose, Satoshi Suzuki, Kentaro Ochiai, Chikara Konno, Yoshinori Kawamura, Toshihiko Yamanishi, Tsuyoshi Hoshino, Masaru Nakamichi, Hiroyasu Tanigawa, Koichiro

Journal:

Fusion Engineering and Design

Year:

2012

Language:

english

File:

PDF, 1.07 MB

english, 2012

9

High heat loading properties of vacuum plasma spray tungsten coatings on reduced activation ferritic/martensitic steel

Tokunaga, K., Hotta, T., Araki, K., Miyamoto, Y., Fujiwara, T., Hasegawa, M., Nakamura, K., Ezato, K., Suzuki, S., Enoeda, M., Akiba, M., Nagasaka, T., Kasada, R., Kimura, A.

Journal:

Journal of Nuclear Materials

Year:

2013

Language:

english

File:

PDF, 2.43 MB

english, 2013

10

Corrosion behavior of F82H exposed to high temperature pressurized water with a rotating apparatus

Kanai, A., Kasada, R., Nakajima, M., Hirose, T., Tanigawa, H., Enoeda, M., Konishi, S.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.52 MB

english, 2014

11

Recovery of Tritium in Room Air by Precious Metal Catalyst with Hydrophilic Substrate

MUNAKATA, Kenzo, NISHIKAWA, Masabumi, TAKEISHI, Toshiharu, MITSUISHI, Nobuo, ENOEDA, Mikio

Journal:

Journal of Nuclear Science and Technology

Year:

1988

Language:

english

File:

PDF, 555 KB

english, 1988

12

First wall and divertor engineering research for power plant in JAERI

S. Suzuki, K. Ezato, T. Hirose, K. Sato, H. Yoshida, M. Enoeda, M. Akiba

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 843 KB

english, 2006

13

Consideration on blanket structure for fusion DEMO plant at JAERI

S. Nishio, J. Ohmori, T. Kuroda, K. Tobita, M. Enoeda, D. Tsuru, T. Hirose, S. Sato, Y. Kawamura, H. Nakamura, M. Sato

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 356 KB

english, 2006

14

Overview of design and R&D of test blankets in Japan

Mikio Enoeda, Masato Akiba, Satoru Tanaka, Akihiko Shimizu, Akira Hasegawa, Satoshi Konishi, Akihiko Kimura, Akira Kohyama, Akio Sagara, Takeo Muroga

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 571 KB

english, 2006

15

Introduction of tritium transfer step at surface layer of breeder grain for modeling of tritium release behavior from solid breeder materials

T. Kinjyo, M. Nishikawa, T. Tanifuji, M. Enoeda

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 233 KB

english, 2006

16

Structural concept of Japanese solid breeder test blanket modules for ITER

Yasunobu Nomoto, Satoshi Suzuki, Koichiro Ezato, Takanori Hirose, Daigo Tsuru, Hisashi Tanigawa, Toshihisa Hatano, Mikio Enoeda, Masato Akiba

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 233 KB

english, 2006

17

Feasibility study on the blanket tritium recovery system using the palladium membrane diffuser

Yoshinori Kawamura, Mikio Enoeda, Toshihiko Yamanishi, Masataka Nishi

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 242 KB

english, 2006

18

Case study on tritium inventory in the fusion DEMO plant at JAERI

Hirofumi Nakamura, Shinji Sakurai, Satoshi Suzuki, Takumi Hayashi, Mikio Enoeda, Kenji Tobita

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 318 KB

english, 2006

19

Six-party qualification program of FW fabrication methods for ITER blanket module procurement

K. Ioki, F. Elio, V. Barabash, V. Chuyanov, V. Rozov, X. Wang, J. Chen, L. Wang, P. Lorenzetto, A. Peacock, M. Enoeda, H. Nishi, B.G. Hong, Y.H. Jeong, A. Gervash, I. Mazul, T. Tanaka, M. Ulrickson

Journal:

Fusion Engineering and Design

Year:

2007

Language:

english

File:

PDF, 715 KB

english, 2007

20

Pressurizing behavior on ingress of coolant into pebble bed of blanket of Fusion DEMO reactor

Daigo Tsuru, Mikio Enoeda, Masato Akiba

Journal:

Fusion Engineering and Design

Year:

2007

Language:

english

File:

PDF, 794 KB

english, 2007

21

Measurement of thermal expansion of Li2TiO3 pebble beds

Hisashi Tanigawa, Mikio Enoeda, Masato Akiba

Journal:

Fusion Engineering and Design

Year:

2007

Language:

english

File:

PDF, 395 KB

english, 2007

22

Tritium diffusivity in crystal grain of Li2TiO3 and tritium release behavior under several purge gas conditions

T. Kinjyo, M. Nishikawa, M. Enoeda, S. Fukada

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 1.07 MB

english, 2008

23

ITER vacuum vessel, in-vessel components and plasma facing materials

K. Ioki, V. Barabash, J. Cordier, M. Enoeda, G. Federici, B.C. Kim, I. Mazul, M. Merola, M. Morimoto, M. Nakahira, M. Pick, V. Rozov, M. Shimada, S. Suzuki, M. Ulrickson, Yu. Utin, X. Wang, S. Wu, J.

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 1.78 MB

english, 2008

24

Structural material properties and dimensional stability of components in first wall components of a breeding blanket module

Takanori Hirose, Mikio Enoeda, Hiroyuki Ogiwara, Hiroyasu Tanigawa, Masato Akiba

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 1.06 MB

english, 2008

25

Recent progress in safety assessments of Japanese water-cooled solid breeder test blanket module

Daigo Tsuru, Mikio Enoeda, Masato Akiba

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 891 KB

english, 2008

26

Heatup event analyses of the Water Cooled Solid Breeder Test Blanket Module

Daigo Tsuru, Mikio Enoeda, Masato Akiba

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 947 KB

english, 2008

27

Development of water-cooled solid breeder test blanket module in JAEA

Masato Akiba, Mikio Enoeda, Daigo Tsuru, Hisashi Tanigawa, Takanori Hirose, Kensuke Mohri, Yohji Seki, Koichiro Ezato, Satoshi Suzuki, Hiroshi Nishi, Seiji Mori

Journal:

Fusion Engineering and Design

Year:

2009

Language:

english

File:

PDF, 860 KB

english, 2009

28

Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA

K. Ezato, Y. Seki, H. Tanigawa, T. Hirose, D. Tsuru, H. Nishi, M. Dairaku, K. Yokoyama, S. Suzuki, M. Enoeda

Journal:

Fusion Engineering and Design

Year:

2010

Language:

english

File:

PDF, 1.38 MB

english, 2010

29

Search for reality of solid breeder blanket for DEMO

K. Tobita, H. Utoh, C. Liu, H. Tanigawa, D. Tsuru, M. Enoeda, T. Yoshida, N. Asakura

Journal:

Fusion Engineering and Design

Year:

2010

Language:

english

File:

PDF, 1007 KB

english, 2010

30

Overview of the TBM R&D activities in Japan

Masato Akiba, Mikio Enoeda, Satoru Tanaka

Journal:

Fusion Engineering and Design

Year:

2010

Language:

english

File:

PDF, 1.14 MB

english, 2010

31

Operation of a simulated non-steady tokamak fuel loop using the tritium systems test assembly

S Konishi, Y Yamanishi, M Enoeda, T Hayashi, S O'Hira, M Yamada, T Suzuki, K Okuno, R.H Sherman, R.S Willms, D.J Taylor, R.V Carlson, J.E Nasise, J.W Barnes, J.R Bartlit, J.L Anderson

Journal:

Fusion Engineering and Design

Year:

1995

Language:

english

File:

PDF, 678 KB

english, 1995

32

The role of sidestream recycle in hydrogen isotope separation and column cascade design

Robert H Sherman, David J Taylor, T Yamanishi, M Enoeda, S Konishi, K Okuno

Journal:

Fusion Engineering and Design

Year:

1995

Language:

english

File:

PDF, 337 KB

english, 1995

33

Practical-scale tests of cryogenic molecular sieve for separating low-concentration hydrogen isotopes from helium

R.Scott Willms, David J Taylor, Mikio Enoeda, Kenji Okuno

Journal:

Fusion Engineering and Design

Year:

1995

Language:

english

File:

PDF, 392 KB

english, 1995

34

ITER nuclear components, preparing for the construction and R&D results

K Ioki, M Akiba, P Barabaschi, V Barabash, S Chiocchio, W Daenner, F Elio, M Enoeda, K Ezato, G Federici, A Gervash, D Grebennikov, L Jones, S Kajiura, V Krylov, T Kuroda, P Lorenzetto, S Maruyama, M

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 796 KB

english, 2004

35

Reduced activation martensitic steels as a structural material for ITER test blanket

K Shiba, M Enoeda, S Jitsukawa

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 305 KB

english, 2004

36

FT-IR study on interaction of irradiated deuteron with defects in Li2O

Hisashi Tanigawa, Satoru Tanaka, Mikio Enoeda, Masato Akiba

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 272 KB

english, 2004

37

In situ tritium recovery behavior from Li2TiO3 pebble bed under neutron pulse operation

K Tsuchiya, A Kikukawa, T Hoshino, M Nakamichi, H Yamada, D Yamaki, M Enoeda, E Ishitsuka, H Kawamura, H Ito, K Hayashi

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 375 KB

english, 2004

38

Release behavior of bred tritium from LiAlO2

M. Nishikawa, T. Kinjyo, T. Ishizaka, S. Beloglazov, T. Takeishi, M. Enoeda, T. Tanifuji

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 562 KB

english, 2004

39

Torus configuration and materials selection on a fusion DEMO reactor, SlimCS

K. Tobita, S. Nishio, H. Tanigawa, M. Enoeda, T. Isono, H. Nakamura, D. Tsuru, S. Suzuki, T. Hayashi, K. Tsuchiya, T. Hayashi, T. Nishitani

Journal:

Journal of Nuclear Materials

Year:

2009

Language:

english

File:

PDF, 752 KB

english, 2009

40

High heat flux test of a HIP-bonded first wall panel of reduced activation ferritic steel F-82H

T Hatano, S Suzuki, K Yokoyama, T Kuroda, M Enoeda

Journal:

Journal of Nuclear Materials

Year:

2000

Language:

english

File:

PDF, 350 KB

english, 2000

41

In-pile test of Li2TiO3 pebble bed with neutron pulse operation

K. Tsuchiya, M. Nakamichi, A. Kikukawa, Y. Nagao, M. Enoeda, T. Osaki, K. Ioki, H. Kawamura

Journal:

Journal of Nuclear Materials

Year:

2002

Language:

english

File:

PDF, 380 KB

english, 2002

42

Development of joining technology for Be/Cu-alloy and Be/SS by HIP

Toshimasa Kuroda, Toshihisa Hatano, Mikio Enoeda, Satoshi Sato, Kazuyuki Furuya, Hideyuki Takatsu, Takaharu Iwadachi, Kiyotoshi Nishida

Journal:

Journal of Nuclear Materials

Year:

1998

Language:

english

File:

PDF, 920 KB

english, 1998

43

Fracture strengths of HIPed DS-Cu/SS joints for ITER shielding blanket/first wall

T Hatano, M Kanari, S Sato, M Gotoh, K Furuya, T Kuroda, M Saito, M Enoeda, H Takatsu

Journal:

Journal of Nuclear Materials

Year:

1998

Language:

english

File:

PDF, 313 KB

english, 1998

44

Effects of hydrogen atmosphere on mechanical properties and surface conditions of a reduced activation ferritic steel F82H

S. Hara, T. Abe, M. Enoeda, H. Takatsu

Journal:

Journal of Nuclear Materials

Year:

1998

Language:

english

File:

PDF, 265 KB

english, 1998

45

Optimization of HIP bonding conditions for ITER shielding blanket/first wall made from austenitic stainless steel and dispersion strengthened copper alloy

S Sato, T Hatano, T Kuroda, K Furuya, S Hara, M Enoeda, H Takatsu

Journal:

Journal of Nuclear Materials

Year:

1998

Language:

english

File:

PDF, 287 KB

english, 1998

46

Application of HIP bonding to first wall panel fabrication made from reduced activation ferritic steel F82H

K. Furuya, M. Enoeda, T. Hatano, S. Sato, T. Kuroda, H. Takatsu

Journal:

Journal of Nuclear Materials

Year:

1998

Language:

english

File:

PDF, 1.43 MB

english, 1998

47

ITER test-blanket safety assessment

H.-W. Bartels, M. Enoeda, M. Fütterer, K. Kleefeldt, K. McCarthy

Journal:

Fusion Engineering and Design

Year:

2001

Language:

english

File:

PDF, 92 KB

english, 2001

48

Measurements of effective thermal conductivity of ceramic breeder pebble beds

Piazza, G, Enoeda, M, Ying, A

Journal:

Fusion Engineering and Design

Year:

2001

Language:

english

File:

PDF, 351 KB

english, 2001

49

In-situ tritium release behavior from Li2TiO3 pebble-bed

Tsuchiya, K, Kikukawa, A, Yamaki, D, Nakamichi, M, Enoeda, M, Kawamura, H

Journal:

Fusion Engineering and Design

Year:

2001

Language:

english

File:

PDF, 101 KB

english, 2001

50

Characteristic evaluation of HIP bonded SS/DSCu joints for surface roughness

Sato, S, Enoeda, M, Kuroda, T, Ohara, Y, Mohri, K, Cardella, A

Journal:

Fusion Engineering and Design

Year:

2001

Language:

english

File:

PDF, 197 KB

english, 2001

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