Zobrazeno 1 - 10
of 72
pro vyhledávání: '"R.G. Clemmer"'
Publikováno v:
Journal of Nuclear Materials. :908-911
Lithium oxide (Li 2 O) is a candidate material for solid breeder blankets in d-t fusion reactors. Radiation damage in Li 2 O was investigated in IEA BEATRIX-II phase 1 irradiation tests using the Fast Flux Test Facility (FFTF). Li 2 O single crystal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c9f47c5154f24830798c0978e93f5de1
https://doi.org/10.1016/0022-3115(94)90967-9
https://doi.org/10.1016/0022-3115(94)90967-9
Autor:
Yuji Naruse, R.G. Clemmer, James L. Anderson, John R. Bartlit, K. Okuno, Hiroshi Yoshida, D.K. Sze, R. H. Sherman, Patricia A. Finn, Mikio Enoeda
Publikováno v:
IEEE Thirteenth Symposium on Fusion Engineering.
The Tritium Systems Test Assembly (TSTA) project at Los Alamos National Laboratory is charged with developing and demonstrating the fusion fuel processing requirement for the magnetic fusion energy program. The key fusion fuel streams are the plasma
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d2b24a8edc5e83b0ba20f2f929209fa1
https://doi.org/10.1109/fusion.1989.102339
https://doi.org/10.1109/fusion.1989.102339
Autor:
John R. Bartlit, K. Okuno, James L. Anderson, L.R. Greenwood, R. H. Sherman, Mikio Enoeda, Yuji Naruse, D.K. Sze, Patricia A. Finn, R.G. Clemmer, Hiroshi Yoshida
Publikováno v:
IEEE Thirteenth Symposium on Fusion Engineering.
The Tritium Systems Test Assembly (TSTA) at Los Alamos, New Mexico, is a full-scale facility dedicated to testing tritium processing for fusion reactors. Adding a breeder blanket interface (BBI) to the TSTA is being studied. The BBI is to test the pr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::99d35568f633f6afe49cdfe34fcc10e0
https://doi.org/10.1109/fusion.1989.102176
https://doi.org/10.1109/fusion.1989.102176
Decontamination solution testing constitutes a task of the Hanford Grout Technology Program (HGTP) at Pacific Northwest Laboratory (PNL). The HGTP provides technical support to the Westinghouse Hanford Company (WHC) Grout Disposal Program. Cementitio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b832e292dff515deb6156686a8f06131
https://doi.org/10.2172/10151652
https://doi.org/10.2172/10151652
Autor:
R.G. Clemmer, H. Elbel, H. Werle, W. Breitung, M. Briec, M. Masson, G. Schumacher, H.E. Häfner, Horst Wedemeyer
Publikováno v:
Journal of Nuclear Materials. :538-543
The second experiment of the LISA series in-situ tritium release tests concentrated on lithium orthosilicate (Li4SiO4) and, to meet the requirements of the KfK pebble-bed design for a NET blanket, especially on high density (97% TD) spheres and low t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::09dae690fd409943a5a16a17415283b8
https://doi.org/10.1016/0022-3115(88)90306-6
https://doi.org/10.1016/0022-3115(88)90306-6
Autor:
Charles C. Baker, Jeffrey N. Brooks, Gilbert Emmert, Robert W. Conn, J. Alcorn, Dai-Kai Sze, D. Graumann, L.R. Turner, R.G. Clemmer, C. Dillow, B. Misra, J. Jung, D.L. Smith, C.A. Trachsel, R. Prater, D.A. De Freece, Yousry Gohar, Charles D. Boley, Mohamed A. Abdou, A.E. Bolon, R.E. Fields, Howard L. Schreyer, G.D. Morgan, Patricia A. Finn, I.N. Sviatoslavsky, R.E. Fuja, Richard F. Mattas, M. Cherry, J. Kokoszenski, David A. Ehst, H.C. Stevens, H. Klumpe, W.J. Kann, K. Barry, K. Evans
Publikováno v:
Nuclear Engineering and Design. 63:199-231
STARFIRE is a design for a conceptual commercial tokamak electrical power plant based on the deuterium/tritium/lithium fuel cycle. In addition to the goal of being technologically credible, the design incorporates safety and environmental considerati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::36ed3bdfc352255f8d7b0fe9281d7411
https://doi.org/10.1016/0029-5493(81)90044-3
https://doi.org/10.1016/0029-5493(81)90044-3
Autor:
A.G. Hins, R.G. Clemmer, J.R. Summers, L.R. Greenwood, J.R. Krsul, Richard F. Mattas, Victor A. Maroni, M.M. Hall, Yousry Gohar, R.L. Senn
Publikováno v:
Journal of Nuclear Materials. 118:275-285
A specimen of Li 7 Pb 2 (lithium in natural abundance) contained in a Zircaloy capsule was irradiated in the Oak Ridge Research Reactor Poolside Facility for ~ 700 h. The design of the irradiation assembly (designated TBC-07) permitted operational co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9fc3c906e77e35e8e2feb3c79d18c236
https://doi.org/10.1016/0022-3115(83)90235-0
https://doi.org/10.1016/0022-3115(83)90235-0
Publikováno v:
Nuclear Engineering and Design. 39:85-98
Tritium is an essential component of near-term controlled thermonuclear reactor systems. Since tritium is not likely to be available on a large scale at a modest cost, fusion reactor designs must incorporate blanket systems which will be capable of b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0bcf66004ae6539afa8cf7b2069dfdd8
https://doi.org/10.1016/0029-5493(76)90124-2
https://doi.org/10.1016/0029-5493(76)90124-2
Publikováno v:
Journal of Nuclear Materials. :275-281
This paper discusses phenomena that have been observed during tritium extraction from y-lithium aluminate, specifically: - Increase of rate of extraction when adding hydrogen to the sweep gas - formation of tritiated water in all cases - permeation o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5134dd1ae19209f601604ef3dc01ee5e
https://doi.org/10.1016/s0022-3115(86)80050-2
https://doi.org/10.1016/s0022-3115(86)80050-2