Results 261 to 270 of about 201,032 (307)

SEAL Studies of Variant Blanket Concepts and Materials

Journal of Fusion Energy, 1997
Within the European SEAL (Safety and Environmental Assessment of fusion power, Long-term) program, safety and environmental assessments have been performed which extend the results of the earlier SEAFP (Safety and Environmental Assessment of Fusion Power) program to a wider range of blanket designs and material choices.
I. Cook, N. P. Taylor, C. B. A. Forty, W. E. Han   +3 more
openaire   +1 more source

Structural materials for fusion reactor blanket systems

Journal of Materials for Energy Systems, 1985
The blanket is one of the largest and most complex systems in a fusion power reactor. In a D-T fueled reactor the blanket system recovers the energy produced by the fusion reaction and provides for breeding and recovery of tritium for the fuel cycle.
E. E. Bloom, D. L. Smith
openaire   +1 more source

ITER-Test blanket module functional materials

Journal of Nuclear Materials, 2007
Abstract Solid breeder and liquid breeder blanket concepts are being developed for testing in ITER. In addition to fundamental investigations on the use of reduced activation ferritic/ferritic–martensitic steels (RAFMS) or V-alloys as the structural material, tritium breeder and neutron multiplier materials, and corresponding corrosion issues, there ...
C.P.C. Wong, V. Chernov, A. Kimura, Y. Katoh, N. Morley, T. Muroga, K.W. Song, Y.C. Wu, M. Zmitko   +8 more
openaire   +1 more source

Fusion reactor blanket and coolant material compatibility

Journal of Nuclear Materials, 1981
Abstract Fusion reactor blanket and coolant reaction tests are being conducted to aid in the selection and design of compatible blanket and coolant systems for future fusion reactors. Results of scoping compatibility tests to date are reported for blanket material and water interactions at near operating temperatures.
D.W. Jeppson, R.F. Keough
openaire   +1 more source

Thermal response characteristics of fire blanket materials

Fire and Materials, 2013
SUMMARYThe thermal response characteristics of over 50 relatively thin (0.15–3.7 mm) fire blanket materials from four different fiber groups (aramid, fiberglass, amorphous silica, and pre‐oxidized carbon) and their composites have been investigated. A plain or coated fabric sample was subjected to a predominantly convective or radiant heat flux (up to ...
Fumiaki Takahashi, Amber Abbott, Timothy M. Murray, James S. T'ien, Sandra L. Olson   +4 more
openaire   +1 more source

Testing of lithium titanate as an alternate blanket material

Journal of Nuclear Materials, 1994
Abstract Lithium titanate (Li2TiO3) has been investigated as an alternate ceramic blanket material to Li2ZrO3. Relatively high density 1.2 mm spheres have been produced using an extrusion/tumbling method. High-strength spheres were obtained as determined by testing following thermal cycling.
J.M. Miller, H.B. Hamilton, J.D. Sullivan   +2 more
openaire   +1 more source

Compatibility of materials for advanced blanket with liquid LiPb

2009 23rd IEEE/NPSS Symposium on Fusion Engineering, 2009
Parametric data of the corrosion (or erosion) behavior of blanket structural materials by LiPb liquid metals in flow conditions at high temperature with LiPb stream were measured to evaluate the compatibility. That is essential for the feasibility of high temperature blanket.
C. Park, K. Noborio, R. Kasada, Y. Yamamoto, G. Nam, S. Konishi   +5 more
openaire   +1 more source

Assessment of materials data for blanket materials within the European contribution to ITER

Journal of Nuclear Materials, 2013
In recent years, material development for ITER blanket components has been fervent; yet, a lack of materials data has been identified by the ITER International Organization (IO) and other ITER parties. Therefore, extensive work on assessment of materials data and qualification of the materials with all the relevant interfaces (joints) has been ...
Wikman, S., Peacock, A., Zlamal, O., Öijerholm, J., Tähtinen, Seppo, Rödig, M., Marmy, P., Gillia, O., Lorenzetto, P., Heikkinen, S.   +10 more
openaire   +2 more sources

Materials development for ITER shielding and test blanket in China

Journal of Nuclear Materials, 2011
Abstract China is a member of the ITER program and is developing her own materials for its shielding and test blanket modules. The materials include vacuum-hot-pressing (VHP) Be, CuCrZr alloy, 316L(N) and China low activation ferritic/martensitic (CLF-1) steels.
J.M. Chen, J.H. Wu, X. Liu, P.H. Wang, Z.H. Wang, Z.N. Li, X.S. Wang, P.C. Zhang, N.M. Zhang, H.Y. Fu, D.H. Liu   +10 more
openaire   +1 more source

Two Fusion Reactor Blankets with Vanadium as Structural Material

Nuclear Technology, 1974
Calculations of the tritium breeding ratio and heating rates for two proposed blanket designs are obtained by using the Monte Carlo method. The materials used for the blanket are vanadium and lithium. Lithium is used to slow down the neutrons and produce tritium by the /sup 6/Li(n,T)/sup 4/He and /sup 7/ Li(n,n',T)/sup 4/He reactions.
James E. Struve, Nick Tsoulfanidis
openaire   +1 more source