Zobrazeno 1 - 10
of 37
pro vyhledávání: '"W.S. Neef"'
The purpose of this work was to demonstrate that creep tests could be performed on beryllium in the same pressurized tube geometry as is commonly used in the FFTF/MOTA.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c947c85f7e9554468f5f8952b90a86dc
https://doi.org/10.2172/6204936
https://doi.org/10.2172/6204936
Autor:
W.S. Neef
Beryllium has interesting applications in magnetic fusion experimental machines and future power-producing fusion reactors. Chief among the properties of beryllium that make these applications possible is its ability to act as a neutron multiplier, t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bf0908b1e9530014e54f8f924f401b86
https://doi.org/10.2172/6681479
https://doi.org/10.2172/6681479
Autor:
G.A. Carlson, W.S. Neef
Publikováno v:
Journal of Nuclear Materials. :17-28
Recent conceptual reactor designs based on mirror confinement are described. Four components of mirror reactors for which materials considerations and structural mechanics analysis must play an important role in successful design are discussed. The r
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::011ed8c6cf0c216763396b5b6eb57210
https://doi.org/10.1016/0022-3115(79)90465-3
https://doi.org/10.1016/0022-3115(79)90465-3
Autor:
Mohamed E. Sawan, W. L. Barr, D.S. Slack, B. M. Johnston, L.T. Summers, W.S. Neef, C. E. Wagner, J. D. Lee, R. H. Bulmer, J.R. Miller, B. G. Logan, J.N. Doggett, C.D. Henning, G. Listvinsky, L. J. Perkins, R. S. Devoto, M.E. Fenstermacher
Publikováno v:
Fusion Technology. 10:1079-1087
The authors are designing a minimum-size Tokamak Ignition/Burn Reactor (TIBER II). This design incorporates physics requirements, neutron wall loading and fluence parameters that will make it compatible with a nuclear testing mission. Reactor relevan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fa149f6948c22b8f767a269d1355560b
https://doi.org/10.13182/fst86-a24877
https://doi.org/10.13182/fst86-a24877
Autor:
C.B. Baxi, K.R. Schultz, J.A. Koshi, R. Gallix, L. Creedon, W. L. Barr, G. Listvinsky, Rion A. Causey, R.F. Bourque, D. Vance, J. Haines, R.T. McGrath, W.S. Neef, C. Carson
Publikováno v:
Fusion Engineering and Design. 9:9-13
TIBER-II is a compact, high-power-density, steady-state current-drive engineering test reactor that uses a double-null divertor configuration, operating in the high recycle mode with low particle temperature. The nominal peak heat flux is 3.3 MW/m2,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::63d73a767a575df0b4b3b5dab62bae33
https://doi.org/10.1016/s0920-3796(89)80003-1
https://doi.org/10.1016/s0920-3796(89)80003-1
Autor:
W. R. Grimes, W.S. Neef, F. J. Fulton, J. D. Lee, Albert E. Sherwood, Ralph W. Moir, Jackson H. DeVan, S. K. Ghose, F. Huegel, C.P.C. Wong, D. H. Berwald, R. H. Whitley
Publikováno v:
Fusion Technology. 8:465-473
A new conceptual blanket design for a fusion reactor produces fissile material for fission power plants. Fission is suppressed by using beryllium, rather than uranium, to multiply neutrons and also by minimizing the fissile inventory. The molten-salt
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae85c1acc95d3fcd1b2f3d7b1acfa019
https://doi.org/10.13182/fst85-a40086
https://doi.org/10.13182/fst85-a40086
Autor:
R. Botwin, I.R. Clarkson, W.S. Neef, B. G. Logan, R. B. Campbell, C.D. Henning, Ralph W. Moir, Grumman, G. A. Carlson, T.J. Carpenter
Publikováno v:
Nuclear Technology - Fusion. 4:67-72
As a satellite to the MARS (Mirror Advanced Reactor Study) a smaller, near-term device has been scoped, called the FPD (Fusion Power Demonstration). Envisioned as the next logical step toward a power reactor, it would advance the mirror fusion progra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::52500fa051b06f62385f5b58e6efb059
https://doi.org/10.13182/fst83-a22847
https://doi.org/10.13182/fst83-a22847
Autor:
Jackson H. DeVan, P.Y. Hsu, R. H. Whitley, C.P.C. Wong, R. P. Rose, N. J. Hoffman, J. S. Karbowski, D. L. Jassby, L.G. Miller, Nasr M. Ghoniem, J. Ogren, J. D. Lee, Peter F. Tortorelli, K.R. Schultz, J.M. Beeston, R.L. Creedon, J.K. Garner, Edward T. Cheng, I. Maya, V. H. Pierce, M. S. Coops, W.S. Neef, J. B. Strand, Y. Saito, B. A. Flanders, D. H. Berwald, R. B. Campbell, F. J. Fulton, G. E. Benedict, A. Slomovik, Ralph W. Moir
Publikováno v:
Nuclear Technology - Fusion. 4:589-598
Studies of the technical and economic feasibility of producing fissile fuel in tandem mirrors and in tokamaks for use in fission reactors are presented. Fission-suppressed fusion breeders promise u...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3b0ca9710e8b7e5556562d49227d1c1d
https://doi.org/10.13182/fst4-2p2-589
https://doi.org/10.13182/fst4-2p2-589
Autor:
W.S. Neef, H. H. Fleischmann, Terry Kammash, Adrian C. Smith, George R. Hopkins, G. A. Carlson, Clinton P. Ashworth, David M. Woodall, Kenneth E. Abreu, K.R. Schultz, William Grossmann, R. Lewis Creedon, C.P.C. Wong, Edward T. Cheng, Dilip K. Bhadra
Publikováno v:
Fusion Technology. 9:136-170
A design of a prototype moving-ring reactor was completed, and a development plan for a pilot reactor is outlined. The fusion fuel is confined in current-carrying rings of magnetically field-reversed plasma (''compact toroids''). The plasma rings, fo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3301a3608f2b122265a14517f2948e5c
https://doi.org/10.13182/fst86-a24708
https://doi.org/10.13182/fst86-a24708
Autor:
D. H. Berwald, Jungchung Jung, Albert E. Sherwood, W.S. Neef, R. Carroll Maninger, J. D. Lee, Ralph W. Moir, Jackson H. DeVan
Publikováno v:
Fusion Technology. 8:133-148
The concept described for the blanket surrounding a fusion reaction chamber is based on the use of molten fluoride salts to convert fusion energy into electricity and to breed the tritium fuel for the fusion power plant. Helium cools the first-wall a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::075b258fc2dd5b2a2c45b4875e7eea76
https://doi.org/10.13182/fst85-a24678
https://doi.org/10.13182/fst85-a24678