Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket
Dell Orco, G.; Ancona, A.; DiMaio, A.
German National Library of Science and Technology (GetInfo) (German)
Thermal Shock Test of Neutron Irradiated Carbon Fiber Reinforced Carbon Composites with OHBIS
M Uda; E Ishitsuka; K Satoh
The effect of neutron dose, irradiation and testing temperature on mechanical properties of copper alloys
Fabritsiev, S. A.; Pokrovsky, A. S.; Edwards, D. J.
The Fifth International Workshop and Summer School on Plasma Physics
Testing of actively cooled high heat flux mock-ups
Roedig, M.; Duwe, R.; Kuehnlein, W.
Suitability and feasibility of the International Fusion Materials Irradiation Facility (IFMIF) for fusion materials studies
A. Möslang; K. Ehrlich; T.E. Shannon
Status of development on 99Mo production technologies in JMTR
Inaba, Yoshitomo; Iimura, Koichi; Hosokawa, Jinsaku
Specimen size effects on ductile-brittle transition temperature in Charpy impact testing
Kurishita, H.; Yamamoto, T.; Narui, M.
Shear punch testing of ^5^9Ni isotopically-doped model austenitic alloys after irradiation in FFTF at different He/dpa ratios
Hankin, G. L.; Toloczko, M. B.; Hamilton, M. L.
Reactor dosimetry : radiation metrology and assessment ; [the Tenth International Symposium on Reactor Dosimetry, held in Osaka, Japan on 12 - 17 September 1999]
International Symposium on Reactor Dosimetry < 10, 1999, Ōsaka>; American Society for Testing and Materials
Radiation-induced electrical degradation experiments in the Japan Materials Testing Reactor
Farnum, E. H.; Shikama, T.; Narui, M.
Properties of precipitation hardened steel irradiated at 323 K in the Japan materials testing reactor
Niimi, M.; Matsui, Y.; Jitsukawa, S.
Niimi, M.; Matsui, Y.; Jilsukawa, S.
Proceedings of the International Workshop on Current Challenges in Liquid and Glass Science, (The Cosener's House, Abingdon 10–12 January 2007)
Alex C Hannon; Philip S Salmon; Alan K Soper
Post irradiation testing of samples from the irradiation experiments PARIDE 3 and PARIDE 4
Roedig, M.; Kuehnlein, W.; Linke, J.
On the Development of In-Situ Monitoring Technique of Corrosion Rate of Zircaloy in Japan Material Testing Reactor
Suzuki, M.; Tsukada, T.; Matsui, Y.
New Facilities in Japan Materials Testing Reactor for Irradiation Test of Fusion Reactor Components
Kawamura, H.; Sagawa, H.; Ishitsuka, E.
Neutron radiography at the HFR Petten : Compilation of HFR Petten contributions to conferences
High Flux Reactor (HFR) Division, Institute for Advanced Materials, Joint Research Centre - Petten, Commission of the European Communities
Modelling Study of Particle Formation Process in the CVD Reactor
Li, C.-Z.; Hu, L.-M.; International Union of Materials Research Societies
Microstructural evolution and hardening of neutron irradiated vanadium alloys at low temperatures in Japan Material Testing Reactor
Candra, Y.; Fukumoto, K.; Kimura, A.
Candra, Y.; Fukumoto, K.; Kimura, A.
Microstructural development and irradiation hardening of W and W–(3–26) wt%Re alloys after high-temperature neutron irradiation to 0.15 dpa
J.C. He; G.Y. Tang; A. Hasegawa
Mechanical properties of austenitic stainless steels irradiated at 323 K in the Japan Materials Testing Reactor
Matsui, Y.; Niimi, M.; Hoshiya, T.
Justification of the new approach to the testing of the candidate ITER materials in fission reactor
Nikolaenko, V. A.; Karpukhin, V. I.; Krusikov, E. A.
Irradiation testing of 316L(N)-IG austenitic stainless steel for ITER
Van Osch, E. V.; Horsten, M. G.; De Vries, M. I.
Irradiation test of diagnostic components for ITER application in the Japan Materials Testing Reactor
Shikama, T.; Nishitani, T.; Kakuta, T.
T. Shikama; T. Nishitani; T. Kakuta
In-beam mechanical testing of CuCrZr
Fabrication and high heat flux testing of plasma sprayed beryllium ITER first wall mock-ups
Castro, R. G.; Elliot, K. E.; Watson, R. D.
Marel Rubel; Tetsuo Tanabe; Michio Yamawaki
Experience: in irradiation testing of low-activation structural materials in fast reactor BOR-60
Kazakov, V. A.; Tsai, H.-C.; Chakin, V. P.
Development of High-temperature Irradiation Techniques Utilising the Japan Materials Testing Reactor
Narui, M.; Shikama, T.; Yamasaki, M.
Development and material testing of OF-Cu/DS-Cu/OF-Cu triplex tube (dispersion strengthened copper clad with oxygen free-copper) and trial fabrication of a vertical target mock-up for ITER divertor
Gotoh, Y.; Okamura, H.; Kajiura, S.
Beryllium neutron irradiation study in the Japan Materials Testing Reactor
Ishitsuka, E.; Kawamura, H.
Assessment of the Fission Power Level in Fuel Rods Irradiated in the High Flux Materials Testing Reactor BR2 with the Aid of Fluence Dosimetry and Comparison with Other Methods
De Raedt, C.; Malambu, E.; Bodart, S.
Analysis of error field due to ferritic steel in the advanced material testing program of JFT-2M
Sato, M.; Miura, Y.; Takeji, S.
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