Results 61 to 70 of about 967,607 (110)

Blanket materials for DT fusion reactors [PDF]

, 1981
This paper presents an overview of the critical materials issues that must be considered in the development of a tritium breeding blanket for a tokamak fusion reactor that operates on the D-T-Li fuel cycle.
Smith, D. L.
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Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system

Nuclear Engineering and Technology, 2018
A feasibility of reusing option of spent nuclear fuel in a fusion-fission hybrid system without partitioning was checked as an alternative option of pyro-processing with critical reactor system. Neutronic study was performed with MCNP 6.1 for this option,
Seong Hee Hong, Myung Hyun Kim
doaj   +1 more source

Vacation request for Sophia Good Blanket (Drunkard)

, 1919
Vacation request for Sophia Good Blanket (Drunkard) from her ...
Good Blanket, Irving (Drunkard)
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US-DOE Fusion-Breeder Program: blanket design and system performance [PDF]

, 1983
Conceptual design studies are being used to assess the technical and economic feasibility of fusion's potential to produce fissile fuel. A reference design of a fission-suppressed blanket using conventional materials is under development.
Lee, J. D.
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RFP based fusion-fission hybrid reactor model for nuclear applications

, 2019
The Reversed Field Pinch (RFP) configuration looks to be an attractive option for fusion-fission hybrid reactors: the toroidal magnetic systems would be made of copper coils instead of more expensive superconductive magnets; fusion conditions could be ...
Zollino, G., Escande, D., Ricco, G., Osipenko, M., Zuin, M., Agostinetti, P., Bettini, P., Casagrande, Riccardo0001716726208020027997979735644790060000-0002-3137-426225C86F76-FA48-11E7-96FE-86B611A95AF2, Ripani, M., Piovan, R., Puiatti, M. E., Bustreo, C., Cavazzana, R., Casagrande, Riccardo, Valisa, M., Panza, F.   +15 more
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Objectives and status of EUROfusion DEMO blanket studies [PDF]

, 2015
International audienceThe design of a DEMO reactor requires the design of a blanket system suitable of reliable T production and heat extraction for electricity production. In the frame of the EUROfusion Consortium activities the Breeding Blanket Project
Forest, L., Nevo, A. Del, Aubert, J., Sardain, P, Aiello, G., Porempovic, G, Bachmann, C., Sardain, P., Vala, L., Norajitra, P., Porempovic, G., Demange, D, Boccaccini, L. V., Rapisarda, David, Demange, D., Utili, M, Boccaccini, L.-V., Aubert, J, Hern??ndez, F, del Nevo, A., Aiello, G, Barrett, T, Vala, L, Del Nevo, A, Utili, M., Rapisarda, D., Boccaccini, L.V., Hernandez, F., Forest, L, Barrett, T., Bachmann, C, Hernández, F   +31 more
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Fusion technologies for Laser Inertial Fusion Energy (LIFE)∗

EPJ Web of Conferences, 2013
The Laser Inertial Fusion-based Energy (LIFE) engine design builds upon on going progress at the National Ignition Facility (NIF) and offers a near-term pathway to commercial fusion.
Kramer K.J., Latkowski J.F., Abbott R.P., Anklam T.P., Dunne A.M., El-Dasher B.S., Flowers D.L., Fluss M.J., Lafuente A., Loosmore G.A., Morris K.R., Moses E., Reyes S.   +12 more
doaj   +1 more source

Study on fission blanket fuel cycling of a fusion–fission hybrid energy generation system

, 2011
This paper presents a preliminary study on neutron physics characteristics of a light water cooled fission blanket for a new type subcritical fusion–fission hybrid reactor aiming at electric power generation with low technical limits of fission fuel. The
Y. Yang, H. Xu, Z. Zhou
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Impact of high-fidelity temperature feedback modeling on fusion blanket neutronics

Nuclear Fusion
Accurate modeling and simulation of neutron and gamma transport and interactions within fusion tokamaks represents a critical area of research for fusion energy development.
Jin Whan Bae, Arpan Sircar, Katarzyna Borowiec, Vittorio Badalassi, Cami Collins   +4 more
doaj   +1 more source

Improved Design of a Cartridge-Type Helical Blanket System for the Helical Fusion Reactor FFHR-b1 [PDF]

0000-0002-7901-6077The cartridge-type helical blanket system called the CARDISTRY-B has been proposed for the helical fusion reactor FFHR-d1. The CARDISTRY-B is aimed at easy construction and maintenance.
NAKAGAWA, Sho, The FFHR, Design Group, MIYAZAWA, Jun-ichi, HAMAJI, Yukinori, KOBAYASHI, Makoto, TANAKA, Teruya, YANAGI, Nagato, TAMURA, Hitoshi, MIYAZAWA, Junichi, MURASE, Takanori, GOTO, Takuya, SAGARA, Akio   +11 more
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