Zr2Fe and Zr(Mn0.5Fe0.5)2 particle beds for tritium purification and impurity removal in a fusion fuel cycle (Englisch)
- Neue Suche nach: Fukada, S.
- Neue Suche nach: Toyoshima, Y.
- Neue Suche nach: Nishikawa, M.
- Neue Suche nach: Fukada, S.
- Neue Suche nach: Toyoshima, Y.
- Neue Suche nach: Nishikawa, M.
In:
FUSION ENGINEERING AND DESIGN
;
49-50
;
805 - 809
;
2000
-
ISSN:
- Aufsatz (Zeitschrift) / Print
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Titel:Zr2Fe and Zr(Mn0.5Fe0.5)2 particle beds for tritium purification and impurity removal in a fusion fuel cycle
-
Beteiligte:
-
Erschienen in:FUSION ENGINEERING AND DESIGN ; 49-50 ; 805 - 809
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Verlag:
- Neue Suche nach: ELSEVIER
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Erscheinungsdatum:01.01.2000
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Format / Umfang:5 pages
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ISSN:
-
Medientyp:Aufsatz (Zeitschrift)
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Format:Print
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Sprache:Englisch
- Neue Suche nach: 621.484
- Weitere Informationen zu Dewey Decimal Classification
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Klassifikation:
DDC: 621.484 -
Datenquelle:
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Inhaltsverzeichnis – Band 49-50
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- 1
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Opening remark at the 5th international symposium of fusion nuclear technologies, ISFNT-5Rubbia, C. et al. | 2000
- 5
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Talk delivered on the occasion of the opening session of the 5th International Symposium on Fusion Nuclear Technology, 19 September 1999Rager, J. P. et al. | 2000
- 7
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Opening talkAdreani, R. et al. | 2000
- 9
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Some considerations on the path towards an experimental fusion reactorToschi, R. et al. | 2000
- 13
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The ITER reduced cost designAymar, R. et al. | 2000
- 27
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Status of fusion technology development in JAERI stressing steady-state operation for future reactorsMatsuda, S. et al. | 2000
- 33
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Which are the competitors for a fusion power plant?Miller, R. L. et al. | 2000
- 41
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Research activities on fusion engineering in JapanMiya, K. et al. | 2000
- 53
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EU fusion technology: towards a commercial power reactorPaidassi, S. et al. | 2000
- 65
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An approach to next step device optimisationSalpietro, E. et al. | 2000
- 77
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Advanced welding processes for fusion reactor fabricationSanderson, A. / Punshon, C. S. / Russell, J. D. et al. | 2000
- 89
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Ciel: Tore Supra's new power and particle extraction environmentGarin, P. et al. | 2000
- 97
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Japanese developments of fusion reactor plasma facing componentsHino, T. / Akiba, M. et al. | 2000
- 107
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Overview of the divertor design and its integration into RTO/RC-ITERJaneschitz, G. / Tivey, R. / Antipenkov, A. / Barabash, V. / Chiocchio, S. / Federici, G. / Heidl, H. / Ibbott, C. / Martin, E. et al. | 2000
- 119
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Structural design criteria for high heat flux componentsMajumdar, S. et al. | 2000
- 127
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ALPS-advanced limiter-divertor plasma-facing systemsMattas, R. F. / Allain, J. P. / Bastasz, R. / Brooks, J. N. / Evans, T. / Hassanein, A. / Luckhardt, S. / McCarthy, K. / Mioduszewski, P. / Maingi, R. et al. | 2000
- 135
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European development of prototypes for ITER high heat flux componentsVieider, G. / Merola, M. / Anselmi, F. / Bonal, J. P. / Chappuis, P. / Dell'Orco, G. / Duglue, D. / Duwe, R. / Erskine, S. / Escourbiac, F. et al. | 2000
- 145
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First plasma experiments in Tore Supra with a new generation of high heat flux limiters for RF antennasAgarici, G. / Beaumont, B. / Bibet, P. / Bremond, S. / Bucalossi, J. / Colas, L. / Durocher, A. / Gargiulo, L. / Ladurelle, L. / Lombard, G. et al. | 2000
- 151
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Material erosion and erosion products in disruption simulation experiments at the MK-200 UG facilityArkhipov, N. I. / Bakhtin, V. P. / Kurkin, S. M. / Safronov, V. M. / Toporkov, D. A. / Vasenin, S. G. / Zhitlukhin, A. M. / Wurz, H. et al. | 2000
- 157
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Novel designs of the ITER gas box liner aimed at reducing tritium codepositionCazzola, C. / Boscary, J. / Matera, R. et al. | 2000
- 163
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Divertor modeling and design for a low-aspect-ratio tokamak transmutation reactorChen, Y. P. / Liu, X. P. / Li, L. / Qiu, L. J. et al. | 2000
- 171
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Studies on modification of some first wall materials using 3-6.8 MeV He ionsConstantinescu, B. / Sarbu, C. et al. | 2000
- 177
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The high heat flux components for ITER neutral beam systemDi Pietro, E. / Inoue, T. / Panasenkov, A. / Krylov, A. / Naumov, V. / Komarov, V. / Bykov, V. et al. | 2000
- 183
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Outgassing from and deuterium retention in beryllium and Be/C mixed-material plasma-facing componentsDoerner, R. P. / Conn, R. W. / Luckhardt, S. C. / Sze, F. C. / Won, J. et al. | 2000
- 189
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Detail design and manufacture of a prototype beryllium covered divertor baffle for ITERErskine, A. / Cheyne, K. / Merola, M. / Turner, J. / King, S. et al. | 2000
- 195
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Energy removal and MHD performance of lithium capillary-pore systems for divertor target applicationEvtikhin, V. A. / Lyublinski, I. E. / Vertkov, A. V. / Yezhov, N. I. / Khripunov, B. I. / Sotnikov, S. M. / Mirnov, S. V. / Petrov, V. B. et al. | 2000
- 201
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Fabrication of the wing and vertical target dummy armour prototypes of the ITER divertorGrattarola, M. / Bet, M. / Biagiotti, B. / Gandini, G. / Merola, M. / Ottonello, G. B. / Riccardi, B. / Vieider, G. / Zacchia, F. et al. | 2000
- 207
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Crack propagation tests of HIPed DSCu/SS joints for plasma facing componentsHatano, T. / Gotoh, M. / Yamada, T. / Nomura, Y. / Saito, M. et al. | 2000
- 213
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Hydrogen retention and erosion of carbon-tungsten mixed materialHino, T. / Hirano, F. / Yamauchi, Y. / Hirohata, Y. et al. | 2000
- 217
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Design issues and cost implications of RTO/RC-ITER divertorIbbott, C. / Antipenkov, A. / Chiocchio, S. / Federici, G. / Heidl, H. / Janeschitz, G. / Martin, E. / Tivey, R. et al. | 2000
- 223
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Irradiation experiments of divertor pebblesIsobe, M. / Matsuhiro, K. / Ueda, Y. / Nishikawa, M. / Ohashi, J. et al. | 2000
- 229
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Crack propagation in first wall by thermal fatigue and creepKikuchi, K. / Ue, K. / Kudo, Y. / Saito, M. et al. | 2000
- 235
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Brittle destruction of carbon based materials under severe thermal loadsLinke, J. / Bolt, H. / Chappuis, P. / Penkalla, H. J. / Scheerer, M. / Schopflin, K. et al. | 2000
- 243
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Measurements of heat transfer coefficients at low contact pressures for actively cooled bolted armour concepts in Tore SupraLipa, M. / Chappuis, P. / Dufayet, A. et al. | 2000
- 249
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Material response due to simulated plasma disruption loadsLitunovsky, V. N. / Kuznetsov, V. E. / Lyublin, B. V. / Ovchinnikov, I. B. / Titov, V. A. / Hassanein, A. et al. | 2000
- 255
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High heat flux components with Be armour before and after neutron irradiationLodato, A. / Derz, H. / Duwe, R. / Linke, J. / Rodig, M. et al. | 2000
- 263
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Main achievements of the EU HT test programme of ITER primary wall small scale mock upsLorenzetto, P. / Cardella, A. / Chappuis, P. / Daenner, W. / Erskine, A. / Febvre, M. / Hofmann, G. / Le Gallo, P. / Stamm, H. / Tahtinen, S. et al. | 2000
- 269
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Outgassing of plasma facing antenna front for lower hybrid wave launcherMaebara, S. / Goniche, M. / Kazarian, F. / Seki, M. / Ikeda, Y. / Imai, T. / Bibet, P. / Froissard, P. / Rey, G. et al. | 2000
- 275
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Design of a radiative semi-transparent liner for the ITER divertor cassetteMakhankov, A. / Arkhipov, I. / Federici, G. / Gorodetsky, A. / Ibbott, C. / Komarov, V. M. / Kuzmin, Y. / Lipko, A. / Markin, A. / Mazul, I. et al. | 2000
- 283
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Pumping performance of pebble drop divertorMatsuhiro, K. / Isobe, M. / Ueda, Y. / Nishikawa, M. et al. | 2000
- 289
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Manufacturing of a full scale baffle prototype for ITER with a CFC and W plasma spray armourMerola, M. / Bobin-Vastra, I. / Cardella, A. / Febvre, M. / Giancarli, L. / Plochl, L. / Salavy, J. F. / Salito, A. / Schedler, B. / Vieider, G. et al. | 2000
- 295
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Examination of codeposited a-C:D-layers in oxygenMoormann, R. / Alberici, S. / Hinssen, H. K. / Wu, C. H. et al. | 2000
- 303
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High heat flux tests on heat sinks armored with tungsten rodsNygren, R. E. / Youchison, D. L. / Watson, R. D. / O'Dell, S. et al. | 2000
- 309
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Failure analysis of beryllium tile assemblies following high heat flux testing for the ITER programOdegard Jr., B. C. / Cadden, C. H. / Yang, N. Y. / Watson, R. D. / Youchison, D. L. et al. | 2000
- 317
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Fabrication of monoblock high heat flux components for ITER divertor upper vertical target using hot isostatic pressing diffusion weldingRigal, E. / Bucci, P. / Le Marois, G. et al. | 2000
- 323
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Molybdenum limiters for Extrap-T2 upgrade: surface properties and high heat flux testingRubel, M. / Brunsell, P. / Duwe, R. / Linke, J. et al. | 2000
- 331
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Thermomechanical behaviour of actively cooled divertor elements with internal coolant flow returnScheerer, M. / Bolt, H. / Linke, J. / Lison, R. / Sauer, H. / Smid, I. / Uhlemann, R. et al. | 2000
- 337
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Power deposition and margins on the Tore Supra pump limiter and fabrication of the high heat flux componentsSchlosser, J. / Mitteau, R. / Plochl, L. / Depit, C. / Tsitrone, E. et al. | 2000
- 343
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Thermal fatigue damage of the divertor plateSuzuki, S. / Ezato, K. / Sato, K. / Nakamura, K. / Akiba, M. et al. | 2000
- 349
-
Forced convective heat transfer in square-ribbed coolant channels with helium gas for fusion power reactorsTakase, K. et al. | 2000
- 355
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Material mixing on W/C twin limiter in TEXTOR-94Tanabe, T. / Ohgo, T. / Wada, M. / Rubel, M. / Philipps, V. / von Seggern, J. / Ohya, K. / Huber, A. / Pospieszczyk, A. / Schweer, B. et al. | 2000
- 363
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ARIES-ST plasma-facing component design and analysisTillack, M. S. / Wang, X. R. / Pulsifer, J. / Sviatoslavsky, I. et al. | 2000
- 371
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High heat flux test of actively cooled tungsten-coated carbon divertor mock-upsTokunaga, K. / Yoshida, N. / Kubota, Y. / Noda, N. / Imamura, Y. / Oku, T. / Kurumada, A. / Sogabe, T. / Kato, T. / Plochl, L. et al. | 2000
- 377
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Thermal fatigue equipment to test joints of materials for high heat flux componentsVisca, E. / Libera, S. / Orsini, A. / Riccardi, B. / Sacchetti, M. et al. | 2000
- 383
-
Neutron effects on properties and annealing of low-Z materialsWu, C. H. / Bonal, J. P. / Werle, H. et al. | 2000
- 389
-
Plasma shield dynamics and target erosion in disruption simulation experimentsWurz, H. / Pestchanyi, S. / Kappler, F. et al. | 2000
- 397
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Free surface heat transfer and innovative designs for thin and thick liquid wallsYing, A. Y. / Morley, N. / Smolentsev, S. / Gulec, K. / Fogarty, P. et al. | 2000
- 407
-
Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor moduleYouchison, D. L. / North, M. T. / Lindemuth, J. E. / McDonald, J. M. / Lutz, T. J. et al. | 2000
- 417
-
Thermal and mechanical behaviour of diagnostic windows subjected to intense heat fluxesZaccaria, P. / Dal Bello, S. et al. | 2000
- 425
-
Major achievements of the European shield blanket R&D during the ITER EDA, and their relevance for future next step machinesDanner, W. / Cardella, A. / Jones, L. / Lorenzetto, P. / Maisonnier, D. / Malavasi, G. / Peacock, A. / Rodgers, E. / Tavassoli, F. et al. | 2000
- 435
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The international fusion materials irradiation facility IFMIF - an overview of user aspectsDaum, E. / Ehrlich, K. / Jitsukawa, S. / Matsui, H. / Moslang, A. et al. | 2000
- 445
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Candidate blanket concepts for a European fusion power plant studyGiancarli, L. / Ferrari, M. / Futterer, M. A. / Malang, S. et al. | 2000
- 457
-
Lithium cooled blanket of RF DEMO reactorKirillov, I. R. et al. | 2000
- 467
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FW/Blanket and vacuum vessel for RTO/RC ITERIoki, K. / Barabash, V. / Cardella, A. / Elio, F. / Iida, H. / Johnson, G. / Kalinin, G. / Miki, N. / Onozuka, M. / Sannazzaro, G. et al. | 2000
- 477
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The blanket technology investigation in ChinaQian, J. P. et al. | 2000
- 483
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Isotope exchange reaction on solid breeder materialsBaba, A. / Nishikawa, M. / Eguchi, T. / Kawagoe, T. et al. | 2000
- 491
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Advanced helium cooled pebble bed blanket with SiCf/SiC as structural materialBoccaccini, L. V. / Fischer, U. / Gordeev, S. / Malang, S. et al. | 2000
- 499
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Mechanical behavior of Li4SiO4 in a blanket typical geometryBuhler, L. / Reimann, J. / Arbogast, E. / Thomauske, K. et al. | 2000
- 507
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Conceptual study on high performance blanket in a spherical tokamak fusion-driven transmuterChen, Y. / Wu, Y. et al. | 2000
- 513
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Measurements of the effective thermal conductivity of a Li4SiO4 pebble bedDalle Donne, M. / Goraieb, A. / Piazza, G. / Sordon, G. et al. | 2000
- 521
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Experimental investigations on the thermal and mechanical behaviour of a binary beryllium pebble bedDalle Donne, M. / Goraieb, A. / Piazza, G. / Scaffidi-Argentina, F. et al. | 2000
- 529
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Long-term activation potential of the steel eurofer as structural material of a demo breeder blanketDaum, E. / Fischer, U. et al. | 2000
- 535
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Improved modules for the blanket of RTO/RC ITERElio, F. / Ioki, K. / Cardella, A. et al. | 2000
- 543
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Potential and limits of water-cooled Pb-17Li blankets and divertors for a fusion power plantFutterer, M. A. / Barleon, L. / Giancarli, L. / Puma, A. L. / Ogorodnikova, O. V. / Poitevin, Y. / Salavy, J. F. / Szczepanski, J. / Vella, G. et al. | 2000
- 551
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High power density self-cooled lithium-vanadium blanketGohar, Y. / Majumdar, S. / Smith, D. et al. | 2000
- 559
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Performance of the TAURO blanket system associated with a liquid-metal cooled divertorGolfier, H. / Aiello, G. / Futterer, M. A. / Gasse, A. / Giancarli, L. / Poitevin, Y. / Salavy, J. F. / Severi, Y. / Szczepanski, J. et al. | 2000
- 567
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Novel liquid blanket configurations and their hydrodynamic analyses for innovative confinement conceptsGulec, K. / Abdou, M. A. / Moir, R. W. / Morley, N. B. / Ying, A. et al. | 2000
- 577
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HIP technologies for fusion reactor blankets fabricationLe Marois, G. / Federzoni, L. / Bucci, P. / Revirand, P. et al. | 2000
- 585
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Manufacturing of a semi-scale blanket box mock-up of the European HCPB blanketLechler, T. / Fiek, H. J. / Gordeev, S. / Schleisiek, K. et al. | 2000
- 591
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Ceramic helium-cooled blanket test moduleLeshukov, A. / Kovalenko, V. / Shatalov, G. / Goroshkin, G. / Obukhov, A. et al. | 2000
- 599
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Evaluation of mock-ups before manufacture of a shield block prototype by powder HIPLind, A. / Hjorth, C. G. / Hakansson, U. / Lorenzetto, P. et al. | 2000
- 605
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Numerical and experimental prediction of the thermomechanical performance of pebble beds for solid breeder blanketLu, Z. / Ying, A. Y. / Abdou, M. A. et al. | 2000
- 613
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EVOLVE-an advanced first wall/blanket systemMattas, R. F. / Malang, S. / Khater, H. / Majumdar, S. / Mogahed, E. / Nelson, B. / Sawan, M. / Sze, D. K. et al. | 2000
- 621
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Enhancement of tritium release from ceramic breeders with impregnated catalytic additivesMunakata, K. / Baba, A. / Kawagoe, T. / Takeishi, T. / Yokoyama, Y. / Nishikawa, M. / Dieter Penzhorn, R. / Moriyma, H. / Kawamoto, K. / Okuno, K. et al. | 2000
- 629
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The fracture mechanics behaviour of the WCLL blanket segmentNardi, C. / Palmieri, A. et al. | 2000
- 637
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Neutronic shielding analysis of the water-cooled lithium lead test blanket module in the ITER machineRapisarda, M. et al. | 2000
- 643
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Thermomechanical behaviour of ceramic breeder and beryllium pebble bedsReimann, J. / Arbogast, E. / Behnke, M. / Muller, S. / Thomauske, K. et al. | 2000
- 651
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Development of FM steels diffusion bonding technologies for blanket manufacturing applicationsRigal, E. / Le Marois, G. / Lechler, T. / Reimann, G. / Schleisiek, K. / Schafer, L. / Weimar, P. et al. | 2000
- 657
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Effect of ITER blanket manufacturing process on the properties of the 316L(N)-IG steelRodchenkov, B. S. / Strebkov, Y. S. / Kalinin, G. M. / Golosov, O. A. et al. | 2000
- 661
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Design and development of the Flibe blanket for helical-type fusion reactor FFHRSagara, A. / Yamanishi, H. / Imagawa, S. / Muroga, T. / Uda, T. / Noda, T. / Takahashi, S. / Fukumoto, K. / Yamamoto, T. / Matsui, H. et al. | 2000
- 667
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Nuclear analysis for a flowing Li2O particulate blanket without structural first wallSawan, M. E. / Khater, H. Y. / Sze, D. K. et al. | 2000
- 675
-
Hydrogen and deuterium permeation measurements on the double-wall tubes material for the water-cooled Pb-17Li DEMO blanketSerra, E. / Rigal, E. / Benamati, G. et al. | 2000
- 681
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Application of high temperature mass spectrometry and work function measurement to evaluation of thermochemical performance of ceramic breedersSuzuki, A. / Yamaguchi, K. / Terai, T. / Yamawaki, M. et al. | 2000
- 689
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ARIES-ST breeding blanket design and analysisTillack, M. S. / Wang, X. R. / Pulsifer, J. / Malang, S. / Sze, D. K. et al. | 2000
- 697
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Tritium inventory and permeation in the ITER breeding blanketViolante, V. / Tosti, S. / Sibilia, C. / Felli, F. / Casadio, S. / Alvani, C. et al. | 2000
- 703
-
Neutronic, thermal-hydraulic and stress analysis of RF lithium cooled test blanket module for ITERVitkovsky, I. V. / Golovanov, M. M. / Divavin, V. A. / Kirillov, I. R. / Lipko, A. V. / Malkov, A. A. / Kartashev, I. A. / Komarov, V. M. / Ogorodnikov, A. P. / Schipakin, O. L. et al. | 2000
- 709
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Helium-cooled refractory alloys first wall and blanket evaluationWong, C. P. / Nygren, R. E. / Baxi, C. B. / Fogarty, P. / Ghoniem, N. / Khater, H. / McCarthy, K. / Merrill, B. / Nelson, B. / Reis, E. E. et al. | 2000
- 719
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Heat deposition, damage, and tritium breeding characteristics in thick liquid wall blanket conceptsYoussef, M. Z. / Abdou, M. A. et al. | 2000
- 727
-
Neutronics performance of high-temperature refractory alloy helium-cooled blankets for fusion applicationYoussef, M. Z. / Wong, C. et al. | 2000
- 735
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Tritium technology for blankets of fusion power plantsFutterer, M. A. / Albrecht, H. / Giroux, P. / Glugla, M. / Kawamura, H. / Kveton, O. K. / Murdoch, D. K. / Sze, D. K. et al. | 2000
- 745
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Tritium inventory in the first wall of JETPeacock, A. T. / Andrew, P. A. / Brennan, D. / Coad, J. P. / Hemmerich, H. / Knipe, S. / Penzhorn, R. D. / Pick, M. et al. | 2000
- 753
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Status and research progress at the Tritium Laboratory KarlsruhePenzhorn, R. D. / Bekris, N. / Coad, P. / Dorr, L. / Friedrich, M. / Glugla, M. / Haigh, A. / Lasser, R. / Peacock, A. et al. | 2000
- 769
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Tritium recovery from an ITER ceramic test blanket module - process options and critical R&D issuesAlbrecht, H. / Hutter, E. et al. | 2000
- 775
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Hydrogen extraction from Pb-17Li: results with a 800 mm high packed columnAlpy, N. / Terlain, A. / Lorentz, V. et al. | 2000
- 781
-
On the thermal stability of the zirconium/cobalt-hydrogen systemBekris, N. / Besserer, U. / Sirch, M. / Penzhorn, R. D. et al. | 2000
- 791
-
H2O trapping on various materials studied by AFM and XPSChiba, K. / Ohmori, R. / Tanigawa, H. / Yoneoka, T. / Tanaka, S. et al. | 2000
- 799
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Model about the separation of molecular species of hydrogen isotopes by cryogenic distillation using the elementary theory of transport phenomenaCristescu, I. / Poenariu, V. / Preda, I. / Stefan, L. et al. | 2000
- 805
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Zr2Fe and Zr(Mn0.5Fe0.5)2 particle beds for tritium purification and impurity removal in a fusion fuel cycleFukada, S. / Toyoshima, Y. / Nishikawa, M. et al. | 2000
- 811
-
Experience gained during the modification of the Caprice system to CaperGlugla, M. / Lasser, R. / Le, T. L. / Penzhorn, R. D. / Simon, K. H. et al. | 2000
- 817
-
A Permcat reactor for impurity processing in the JET Active Gas Handling SystemGlugla, M. / Perevezentsev, A. / Niyongabo, D. / Penzhorn, R. D. / Bell, A. / Herrmann, P. et al. | 2000
- 825
-
Counterflow hydrogen isotope separation facility - data on tritium activitiesGolubkov, A. N. / Vedeneev, A. I. / Tenyaev, B. N. / Andreev, B. M. / Selivanenko, I. N. et al. | 2000
- 831
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Kinetics and mechanism of hydrogen-induced disproportionation of ZrCoHara, M. / Okabe, T. / Mori, K. / Watanabe, K. et al. | 2000
- 839
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Design of a membrane atmosphere detritiation system using super high permeation moduleIshida, T. / Hayashi, T. / Mori, S. / Suzuki, T. / Nishi, M. et al. | 2000
- 847
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A design study of water detritation and hydrogen isotope separation systems for ITERIwai, Y. / Yoshida, H. / Yamanishi, T. / Senrui, S. / Nishi, M. et al. | 2000
- 855
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Analysis of hydrogen isotopes with a micro gas chromatographKawamura, Y. / Iwai, Y. / Yamanishi, T. / Konishi, S. / Nishi, M. et al. | 2000
- 863
-
Methane decomposition properties of ZrNi alloy in flowing gas systemKawano, T. / Sakurna, Y. / Kabutomori, T. / Shibuya, M. et al. | 2000
- 873
-
The impact of tritium on the structure and properties of Pd-membranesKlevtsov, V. G. / Boitsov, I. E. / Vedeneev, A. I. / Glagolev, M. V. / Lobanov, V. N. / Malkov, I. L. / Pimanikhin, S. A. / Stengach, A. V. et al. | 2000
- 879
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Progress of fusion fuel processing system development at the Japan Atomic Energy Research InstituteNishi, M. / Yamanishi, T. / Kawamura, Y. / Iwai, Y. / Isobe, K. / O'Hira, S. / Hayashi, T. / Nakamura, H. / Kobayashi, K. / Suzuki, T. et al. | 2000
- 885
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In situ observation of tritium interactions with Pd and Zr by b-ray induced X-ray spectrometryMatsuyama, M. / Ueda, S. / Watanabe, K. et al. | 2000
- 893
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Fuel cycle design evolution from FDR-ITER to RTO/RC-ITERMurdoch, D. K. / Glugla, M. / Kveton, O. et al. | 2000
- 899
-
Development of divertor pumping system with superpermeable membraneNakamura, Y. / Ohyabu, N. / Suzuki, H. / Nakahara, Y. / Livshits, A. / Notkin, M. / Alimov, V. / Busnyuk, A. et al. | 2000
- 905
-
Beta induced reaction study on T2-CO systemO'hira, S. / Isobe, K. / Suzuki, T. / Oya, Y. / Nishi, M. et al. | 2000
- 915
-
Development of pellet injector system for large helical deviceYamada, H. / Sakamoto, R. / Oda, Y. / Hiramatsu, T. / Kinoshita, M. / Ogino, M. / Matsuda, R. / Sudo, S. / Kato, S. / Fisher, P. W. et al. | 2000
- 921
-
Tritium permeation through the first wall of the EU-HCPB blanketOgorodnikova, O. V. / Raepsaet, X. / Futterer, M. A. et al. | 2000
- 927
-
Radiochemistry of an equimolar deuterium-tritium mixture or of T2 with COPenzhorn, R. D. / Berndt, U. / Caldwell-Nichols, C. / Grunhagen, S. / Kirste, E. / Lasser, R. / Wendel, J. et al. | 2000
- 939
-
Development of tritium cleanup system for LHDSakuma, Y. / Kawano, T. / Shibuya, M. / Kabutomori, T. et al. | 2000
- 945
-
Tritium recovery from Pb-17Li alloy using a 2D-SiCf/SiC composite permeator columnSedano, L. A. / Perujo, A. et al. | 2000
- 953
-
Catalytic membrane reactors for tritium recovery from tritiated water in the ITER fuel cycleTosti, S. / Violante, V. / Basile, A. / Chiappetta, G. / Castelli, S. / De Francesco, M. / Scaglione, S. / Sarto, F. et al. | 2000
- 959
-
Status of the Russian pellet injector R&D program for plasma fuellingViniar, I. et al. | 2000
- 963
-
Initial testing of a low pressure permeator for tritium processingWillms, R. S. / Arzu, P. R. / Honnell, K. G. / Birdsell, S. A. et al. | 2000
- 971
-
Visualization of tritium distribution by autoradiography techniqueZouev, Y. N. / Podgornova, I. V. / Sagaragze, V. V. et al. | 2000