Zobrazeno 1 - 10
of 36
pro vyhledávání: '"D.E. Bartine"'
Publikováno v:
Nuclear Science and Engineering. 53:304-318
For s particular fusion-reactor blanket configuration, the changes in the tritium breeding ratio, i.e., in the number of tritium nuclei produced in the blanket per incident neutron, due to changes in nuclear cross-section data are calculated on the b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b3e9398163d7ed21b130b62101d774f6
https://doi.org/10.13182/nse74-a23355
https://doi.org/10.13182/nse74-a23355
Publikováno v:
Nuclear Science and Engineering. 87:96-102
Attempts to devise techniques for rapidly calculating radiation transport in relatively simple shields has led to the development of two calculational models that are based on the use of cross-section sensitivity coefficients and are possible improve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4ed2cf412eb4a1e5ddab5f2449770854
https://doi.org/10.13182/nse84-a17450
https://doi.org/10.13182/nse84-a17450
Publikováno v:
Nuclear Science and Engineering. 93:313-317
Three models, a linear, exponential or BEST, and a power model, developed using sensitivity theory to predict deep-penetration neutron transport in practical shielding problems, have been generalized into a common expression. One can obtain any of th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c8bd216315534b12dbbe26171ccd67a4
https://doi.org/10.13182/nse86-a17760
https://doi.org/10.13182/nse86-a17760
Autor:
R.L. Childs, T.M. Sims, W.W. Engle, D.E. Bartine, J.V. Pace, E.M. Oblow, J.R. Knight, F.R. Mynatt
A review of the progress in cross-section sensitivity analysis of radiation shielding problems is presented. The sensitivity function used in this work is then defined. The information generated in this type of sensitivity analysis may be used to ide
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::15010e1b6c973b7350a6310ae39fe36f
https://doi.org/10.1016/b978-0-08-019610-7.50050-6
https://doi.org/10.1016/b978-0-08-019610-7.50050-6
An integral experiment has been designed for the verification of radiation transport methods and nuclear data used for the design of the radial shield for the proposed 300 MW(e) gas-cooled fast breeder reactor (GCFR). The scope of the experiment was
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::086cf196dff1a814d20fd39cac4a6a04
https://doi.org/10.2172/5944525
https://doi.org/10.2172/5944525
During 1982 the High-Temperature Gas-Cooled Reactor (HTGR) Technology Program at Oak Ridge National Laboratory (ORNL) continued to develop experimental data required for the design and licensing of cogeneration HTGRs. The program involves fuels and m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::64ce6b15cdc711e8d7b3f0253ed0b748
https://doi.org/10.2172/6174841
https://doi.org/10.2172/6174841
Recent advances in accelerator beam technology have made it possible to improve the target/blanket design of the Ternary Metal Fueled Electronuclear Fuel Producer (TMF-ENFP), an accelerator-breeder design concept proposed by Burnss et al. for subcrit
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::38368314e9d196e9e38c0a6e8cb12afa
https://doi.org/10.2172/5596830
https://doi.org/10.2172/5596830
The use of an external neutron source, generated via an accelerator, represents a potential means for producing the fissile isotopes /sup 233/U and /sup 239/Pu. One promising accelerator-breeder concept employs a sodium-cooled ternary metal fertile b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1ad138bd38bef302cc3413ed23681b15
https://doi.org/10.2172/6164310
https://doi.org/10.2172/6164310