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Results: 1-14 |
Results: 14
ITER test-blanket safety assessment
Authors: Bartels, HW Enoeda, M Futterer, M Kleefeldt, K McCarthy, K
Citation: Hw. Bartels et al., ITER test-blanket safety assessment, FUSION ENG, 54(3-4), 2001, pp. 331-336
Effective thermal conductivity measurement of the candidate ceramic breeder pebble beds by the hot wire method
Authors: Enoeda, M Ohara, Y Roux, N Ying, A Pizza, G Malang, S
Citation: M. Enoeda et al., Effective thermal conductivity measurement of the candidate ceramic breeder pebble beds by the hot wire method, FUSION TECH, 39(2), 2001, pp. 612-616
Adsorption isotherms for tritium on various adsorbents at liquid nitrogen temperature
Authors: Kawamura, Y Enoeda, M Willms, RS Zielinski, PM Wilhelm, RH Nishi, M
Citation: Y. Kawamura et al., Adsorption isotherms for tritium on various adsorbents at liquid nitrogen temperature, FUSION TECH, 37(1), 2000, pp. 54-61
Development of a tritium fuel processing system using an electrolytic reactor for ITER
Authors: Yamanishi, T Kawamura, Y Iwai, Y Arita, T Maruyama, T Kakuta, T Konishi, S Enoeda, M Ohira, S Hayashi, T Nakamura, H Kobayashi, K Tadokoro, T Nakamura, H Ito, T Yamada, M Suzuki, T Nishi, M Nagashima, T Ohta, M
Citation: T. Yamanishi et al., Development of a tritium fuel processing system using an electrolytic reactor for ITER, NUCL FUSION, 40(3Y), 2000, pp. 515-518
Improvement of tritium accountancy technology for ITER fuel cycle safety enhancement
Authors: O'hira, S Hayashi, T Nakamura, H Kobayashi, K Tadokoro, T Nakamura, H Itoh, T Yamanishi, T Kawamura, K Iwai, Y Arita, T Maruyama, T Kakuta, T Konishi, S Enoeda, M Yamada, M Suzuki, T Nishi, M Nagashima, T Ohta, M
Citation: S. O'Hira et al., Improvement of tritium accountancy technology for ITER fuel cycle safety enhancement, NUCL FUSION, 40(3Y), 2000, pp. 519-525
High heat flux test of a HIP-bonded first wall panel of reduced activationferritic steel F-82H
Authors: Hatano, T Suzuki, S Yokoyama, K Kuroda, T Enoeda, M
Citation: T. Hatano et al., High heat flux test of a HIP-bonded first wall panel of reduced activationferritic steel F-82H, J NUCL MAT, 283, 2000, pp. 685-688
ITER reference breeding blanket design
Authors: Ferrari, M Bianchi, A Celentano, G Danner, W Enoeda, M Gerber, A Gohar, Y Gulden, W Ioki, K Kuroda, T Lopatkin, A Lucca, F Masson, X Mattas, R Mazzone, G Mustoe, J Parker, R Petrizzi, L Pizzuto, A Plenteda, R Poitevin, Y Raffray, R Roccella, M Roux, N Scaffidi-Argentina, F Simoneau, JP Strebkov, Y Zacchia, F
Citation: M. Ferrari et al., ITER reference breeding blanket design, FUSION ENG, 46(2-4), 1999, pp. 177-183
Effective thermal conductivity measurements of the binary pebble beds by hot wire method for the breeding blanket
Authors: Enoeda, M Furuya, K Takatsu, H Kikuchi, S Hatano, T
Citation: M. Enoeda et al., Effective thermal conductivity measurements of the binary pebble beds by hot wire method for the breeding blanket, FUSION TECH, 34(3), 1998, pp. 877-881
High heat flux testing and post-mortem observation of small-scale ITER first wall mock-up made by HIP joining
Authors: Kanari, M Hatano, T Sato, S Furuya, K Kuroda, T Enoeda, M Takatsu, H
Citation: M. Kanari et al., High heat flux testing and post-mortem observation of small-scale ITER first wall mock-up made by HIP joining, FUSION TECH, 34(3), 1998, pp. 882-886
Fabrication of an ITER shielding blanket prototype
Authors: Sato, S Hatano, T Takatsu, H Osaki, T Kuroda, T Yamada, K Enoeda, M Sato, S Furuya, K Ohara, Y
Citation: S. Sato et al., Fabrication of an ITER shielding blanket prototype, FUSION TECH, 34(3), 1998, pp. 892-897
Low cycle fatigue lifetime of HIP bonded Bi-metallic first wall structuresof fusion reactors
Authors: Hatano, T Sato, S Hashimoto, T Kitamura, K Furuya, K Kuroda, T Enoeda, M Takatsu, H
Citation: T. Hatano et al., Low cycle fatigue lifetime of HIP bonded Bi-metallic first wall structuresof fusion reactors, J NUC SCI T, 35(10), 1998, pp. 705-711
Development of joining technology for Be/Cu-alloy and Be/SS by HIP
Authors: Kuroda, T Hatano, T Enoeda, M Sato, S Furuya, K Takatsu, H Iwadachi, T Nishida, K
Citation: T. Kuroda et al., Development of joining technology for Be/Cu-alloy and Be/SS by HIP, J NUCL MAT, 263, 1998, pp. 258-264
Optimization of HIP bonding conditions for ITER shielding blanket first wall made from austenitic stainless steel and dispersion strengthened copper alloy
Authors: Sato, S Hatano, T Kuroda, T Furuya, K Hara, S Enoeda, M Takatsu, H
Citation: S. Sato et al., Optimization of HIP bonding conditions for ITER shielding blanket first wall made from austenitic stainless steel and dispersion strengthened copper alloy, J NUCL MAT, 263, 1998, pp. 265-270
Fracture strengths of HIPed DS-Cu/SS joints for ITER shielding blanket first wall
Authors: Hatano, T Kanari, M Sato, S Gotoh, M Furuya, K Kuroda, T Saito, M Enoeda, M Takatsu, H
Citation: T. Hatano et al., Fracture strengths of HIPed DS-Cu/SS joints for ITER shielding blanket first wall, J NUCL MAT, 263, 1998, pp. 950-954
Risultati: 1-14 |