Zobrazeno 1 - 10
of 16
pro vyhledávání: '"J. H. Kittel"'
Autor:
L. C. Walters, J. H. Kittel
Publikováno v:
Nuclear Technology. 48:273-280
The reduction in projected sodium outlet temperatures for commercial liquid-metal fast breeder reactors has renewed the interest in metal fuels. The U-Pu-Zr or Th-Pu-U-Zr metal fuel pins, sodium bo...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bd970f09cf847b639f056f8229fc7f98
https://doi.org/10.13182/nt80-a32473
https://doi.org/10.13182/nt80-a32473
Autor:
R. G. Alsmiller, J. Barish, R. T. Santoro, R. A. Lillie, J. M. Barnes, M. M. H. Ragheb, Michio Murase, Isao Sumida, Norio Nagase, Kazuo Mukai, Osamu Onuki, Shigehiro An, Akira Furuhashi, Yoshiaki Oka, Masatsugu Akiyama, Hiroyuki Kuga, Harukuni Tanaka, M. J. Saltmarsh, Paul Sasa, August W. Cronenberg, Michael G. Stevenson, J. M. Cano, R. Caro, J. M. Martínez-Val, D. M. Ligon, R. H. Brogli, L. C. Walters, J. H. Kittel, Vincent P. Manno, Andreas Pritzker, Jürg Gassmann, Otto Demel, J. F. Bates, M. K. Korenko
Publikováno v:
Nuclear Technology. 48:181-186
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::07744bef9d95999e317bff2905a382fd
https://doi.org/10.13182/nt80-a32465
https://doi.org/10.13182/nt80-a32465
Publikováno v:
Nuclear Science and Engineering. 2:431-449
Three corrosion-resistant uranium-base alloys, U-3 weight per cent Nb, U-5 weight per cent weight per cent Nb, and U-3.8 weight per cent Si (U3Si) were irradiated to burnups of 0.1 atomic per cent ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae525db269ebd992e908421a4444cdcb
https://doi.org/10.13182/nse57-a25408
https://doi.org/10.13182/nse57-a25408
Autor:
J. H. Kittel
Publikováno v:
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 5:693-698
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f1817352df51df344ed0880c10d1f29c
https://doi.org/10.3327/jaesj.5.693
https://doi.org/10.3327/jaesj.5.693
Publikováno v:
Journal of the American Ceramic Society. 41:117-123
Thoria-urania fuels were irradiated bare and clad in metal jackets of stainless steel, Zircaloy-II, and aluminum-1 weight % nickel alloy. These specimens were irradiated in NaK (a sodium-potassium eutectic alloy) and in water. Irradiation severity wa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::49edd3758b4f190d2316cd2abb962ad9
https://doi.org/10.1111/j.1151-2916.1958.tb13524.x
https://doi.org/10.1111/j.1151-2916.1958.tb13524.x
Publikováno v:
Nuclear Science and Engineering. 4:180-199
As a result of the partial meltdown which occurred in EBR-I on November 29, 1955, it was necessary to remove the core assembly from the reactor and to separate the enriched fuel section from upper ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c5784bf6e86a15b54928e69d5a66d832
https://doi.org/10.13182/nse58-a15361
https://doi.org/10.13182/nse58-a15361
Publikováno v:
Journal of the American Ceramic Society. 46:219-224
Randomly oriented fibers of either molybdenum or niobium were incorporated into hot-pressed pellets of 10, 30, and 50 wt% UO2 in ThO2 to improve the thermal conductivity and the thermalshock resistance. Pellets 3/8 in. in diameter and about 3/8 in. l
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c27b6c203d59dc795d46b57e6f907426
https://doi.org/10.1111/j.1151-2916.1963.tb19776.x
https://doi.org/10.1111/j.1151-2916.1963.tb19776.x
Autor:
S. H. Paine, J. H. Kittel
Publikováno v:
Nuclear Science and Engineering. 3:250-268
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::12f0ae3c17d77c82765127ff9d502e18
https://doi.org/10.13182/nse58-a25465
https://doi.org/10.13182/nse58-a25465
Autor:
Y. I. Chang, J. H. Kittel, M. J. Lineberry, K. D. Dance, H. K. Fauske, C. E. Till, M. G. Stevenson, P. I. Amundson
This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9da31f5a215c784e7c901ce4ba83cb05
https://doi.org/10.2172/5143328
https://doi.org/10.2172/5143328
Autor:
W. N. Beck, J. H. Kittel
Irradiation experiments are in progress to determine the suitability of cladding made of refractory metals and alloys as a means of restraining the high- temperature swelling of metallic plutonium fuels for fast reactors. Tubing materials based on ni
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9ae10177b1f593b51aacefa5c7953ff5
https://doi.org/10.2172/4111995
https://doi.org/10.2172/4111995