Zobrazeno 1 - 10
of 22
pro vyhledávání: '"J.A. Conlin"'
Publikováno v:
Journal of Nuclear Materials. 65:96-106
A series of irradiation tests was designed to evaluate the creep characteristics at elevated temperatures and to high fast fluences of various graphites of interest to HTGR designers. The series encompasses the irradiation of 28 specimens, each 15.24
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::46360adb0bdc58b246d726cae78b8a66
https://doi.org/10.1016/0022-3115(77)90046-0
https://doi.org/10.1016/0022-3115(77)90046-0
Autor:
D.B. Trauger, J.A. Conlin
Publikováno v:
Nuclear Science and Engineering. 9:346-356
A compact forced-circulation test loop for obtaining corrosion data applicable to molten-salt-fueled reactors were operated in the MTR (HB-3) beam hole. Several tests were conducted with two fused-salt mixtures, NaF- Z rF/sub 4/ -- UF/sub 4/ and Li/s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::02b117cee69b37d872436930789061bb
https://doi.org/10.13182/nse61-a25886
https://doi.org/10.13182/nse61-a25886
Experience has shown that the most valid test for HTGR fuels is one in which the fuel particles are bonded into a matrix and tested with temperatures and temperature gradients simulating those which will exist in the real reactor. A series of tests w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::71ac20ae49aa0c0e9daf0794ed44ee2a
https://doi.org/10.2172/4253937
https://doi.org/10.2172/4253937
Autor:
S.S. Hurt, A.F. Rowcliffe, E. Newman, R.M. Moon, K.R. Thoms, C.W. Alexander, J.A. Conlin, C.D. West
Engineering materials irradiations form a substantial program at Oak Ridge National Laboratory (ORNL), relying mainly on the High-Flux Isotope Reactor (HFIR) and the Oak Ridge Research Reactor (ORR). The HFIR neutron flux is high, but the reactor was
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::633121cb24c653bc57460f23b3f3bd05
https://doi.org/10.2172/5115442
https://doi.org/10.2172/5115442
A series of 12 irradiation experiments was designed to evaluate the creep characteristics of graphites when exposed to elevated temperatures and high fast fluences. Various graphites of interest to HTGR designers are to be examined. The series encomp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::455ec0a1c48b30f4d3d70a5674ebee49
https://doi.org/10.2172/7312372
https://doi.org/10.2172/7312372
Candidate high-temperature gas-cooled reactor fissile and fertile particles were irradiated in the High Flux Isotope Reactor removable beryllium reflector facility (RB-5) for eight reactor cycles. The experiment contained 18 different ''types'' of fi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2119f1061dcb5697f40528bc1949db73
https://doi.org/10.2172/5750901
https://doi.org/10.2172/5750901