Zobrazeno 1 - 10
of 29
pro vyhledávání: '"J.L. Lucius"'
Publikováno v:
Nuclear Science and Engineering. 66:307-333
This paper presents the first results of a comprehensive application of the sensitivity theory developed for the FORSS code system to the analysis of fast reactor integral experiments. A variety of...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5da2054135264bea180f841165c61a9f
https://doi.org/10.13182/nse78-3
https://doi.org/10.13182/nse78-3
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
Publikováno v:
Operations Research. 31:915-937
This paper discusses a nonlinear equation theory of sensitivity analysis and demonstrates its applicability to a large energy-economics model by applying it to a specific calculation carried out with the Long-Term Energy Analysis Program (LEAP). It p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ac01645bf71a6ef948f25b8fcc07846f
https://doi.org/10.1287/opre.31.5.915
https://doi.org/10.1287/opre.31.5.915
Energy-dependent sensitivity profiles for five responses calculated for the TRX-2 thermal lattice with the ORNL sensitivity code system FORSS are presented here both in graphical form and in SENPRO format. The responses are the multiplication factor,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7df98b02c70b6ee5a81eefa6d0bc9dbf
https://doi.org/10.2172/5241719
https://doi.org/10.2172/5241719
Cross section sensitivity analysis of a proposed streaming experiment for a typical penetration in a fusion reactor shield has been performed using a two-dimensional sensitivity method. The neutron streaming was shown to be determined mostly by the 4
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::89d4621a83fc7d1dd0bc1c97789263fb
https://doi.org/10.2172/6196479
https://doi.org/10.2172/6196479
JULIET is the FORSS module that calculates generalized sources, responses (e.g., criticality, reaction rate ratios, reactivity worths), normalization parameters and sensitivity coefficients. JULIET is organized into execution paths which are in effec
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a623081e3a0667fd965e0772dac1a8f5
https://doi.org/10.2172/6332811
https://doi.org/10.2172/6332811
Adjoint sensitivity theory can be used to determine the sensitivity of results of interest to each of the data elements that enter into the calculations. In this paper adjoint sensitivity theory is discussed, and its applicability to a large energy-e
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::77368eff567f154260087bba803fc50a
https://doi.org/10.2172/6531891
https://doi.org/10.2172/6531891
Autor:
John M. Ryskamp, J. J. Wagschal, R.A. Anderl, J.L. Lucius, W.E. Ford, J.H. Marable, B. L. Broadhead
The Coupled Fast Reactor Measurement Facility (CFRMF), is a zoned-core critical assembly with a fast-neutron-spectrum zone in the center of an enriched U-235, water-moderated thermal driver. The central neutron spectrum is a Cross-Section Evaluation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::35e65a9b3333f0c5f186f147c1265e4d
https://doi.org/10.2172/5135066
https://doi.org/10.2172/5135066
AMPX is a modular system for producing coupled multigroup neutron-gamma cross section sets. Basic neutron and gamma cross-section data for AMPX are obtained from ENDF/B libraries. Most commonly used operations required to generate and collapse multig
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cdc97c24ed8aaccca78230e2b0d10623
https://doi.org/10.2172/7342486
https://doi.org/10.2172/7342486