Výsledky vyhledávání - "J. D. Drischler"

SENDIN and SENTINEL: two computer codes to assess the effects of nuclear data changes

Autor: C. R. Weisbin, J. D. Drischler, J. H. Marable

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9e9d27f817722f11c3e249deef87f1bf
https://doi.org/10.2172/7317679

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Monte Carlo and discrete ordinates calculations for 14-MeV neutrons streaming through a stainless steel duct: comparisons with Experiment II

Autor: R. T. Santoro, J. M. Barnes, R. G. Alsmiller, Jr., J. D. Drischler

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::efd3bae6479c61bb21609f865e898c3c
https://doi.org/10.2172/6413939

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Monte Carlo and discrete ordinates calculations of 14-MeV neutrons streaming through a stainless steel duct: comparison with Experiment I

Autor: R. T. Santoro, J. M. Barnes, R. G. Alsmiller, Jr., J. D. Drischler

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::11f1a2465d88d7a869b79bc22b5e4c04
https://doi.org/10.2172/5959114

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Application of adjoint-sensitivity theory to a liquid-fuels supply model

Autor: R. G. Alsmiller, Jr., J. Barhen, J. E. Horwedel, J. L. Lucius, J. D. Drischler

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9017411e831b424b6e20c00847cf72b3
https://doi.org/10.2172/5789380

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Comparisons of calculated and measured spectral distributions of neutrons from a 14-MeV neutron source inside the Tokamak Fusion Test Reactor

Autor: R. T. Santoro, J. M. Barnes, R. G. Alsmiller, Jr., M. B. Emmett, J. D. Drischler

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d9b72bdad2637f01ff4a347103aa2f7f
https://doi.org/10.2172/6027979

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COVERT and CAVALIER: two computer codes for estimating uncertainties of calculated neutronics parameters using standard interface files SENPRO and COVERX

Autor: J. H. Marable, J. D. Drischler, C. R. Weisbin

A description is given of the computer code CAVALIER, which provides a simple means for estimating the uncertainties in calculated neutronics parameters that result from uncertainties in nuclear data. This code uses predetermined detailed multigroup

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::0cc0936d70765dfca7fa405f4dd6768b
https://doi.org/10.2172/6704872

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