Author:
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ISBN:
Category :
Languages : en
Pages :
Book Description
A review is presented of neutron cross-section sensitivity and uncertainty studies as applied to fusion reactor concepts. General observations are made concerning the applicability and potential value of such studies, as well as their current limitations. While literature is cited relative to sensitivities to D-D and D-T cross sections, as well as to temperature of the D-T reaction, these topics are excluded from discussion. After a brief review of cross-section and secondary-energy-distribution sensitivity theory, most emphasis is focused upon published studies of the TFTR, experimental power reactors, and a conceptual commercial reactor (NUWMAK). Salient results of these studies, as they pertain to cross-section measurement and evaluation requirements, are summarized. Lastly, some comments are made relative to cross-section data requirements in the 14 to 50 MeV region.
Cross-section Sensitivity and Uncertainty Analysis for Fusion Reactors (a Review).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A review is presented of neutron cross-section sensitivity and uncertainty studies as applied to fusion reactor concepts. General observations are made concerning the applicability and potential value of such studies, as well as their current limitations. While literature is cited relative to sensitivities to D-D and D-T cross sections, as well as to temperature of the D-T reaction, these topics are excluded from discussion. After a brief review of cross-section and secondary-energy-distribution sensitivity theory, most emphasis is focused upon published studies of the TFTR, experimental power reactors, and a conceptual commercial reactor (NUWMAK). Salient results of these studies, as they pertain to cross-section measurement and evaluation requirements, are summarized. Lastly, some comments are made relative to cross-section data requirements in the 14 to 50 MeV region.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A review is presented of neutron cross-section sensitivity and uncertainty studies as applied to fusion reactor concepts. General observations are made concerning the applicability and potential value of such studies, as well as their current limitations. While literature is cited relative to sensitivities to D-D and D-T cross sections, as well as to temperature of the D-T reaction, these topics are excluded from discussion. After a brief review of cross-section and secondary-energy-distribution sensitivity theory, most emphasis is focused upon published studies of the TFTR, experimental power reactors, and a conceptual commercial reactor (NUWMAK). Salient results of these studies, as they pertain to cross-section measurement and evaluation requirements, are summarized. Lastly, some comments are made relative to cross-section data requirements in the 14 to 50 MeV region.
Two-dimensional Cross-section Sensitivity and Uncertainty Analysis for Fusion Reactor Blankets
Author: Mark Julien Embrechts
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 386
Book Description
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 386
Book Description
Application of Sensitivity and Uncertainty Analysis in Fusion Reactor Design
Author: Tang Wu
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 480
Book Description
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 480
Book Description
Application of the Sensitivity and Uncertainty Analysis System LASS to Fusion Reactor Nucleonics
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Sensitivity analysis, as applied to both nuclear design and data uncertainty, has developed into a valuable tool for fusion reactor nuclear analysis. Several such studies have been undertaken with the LASL sensitivity system LASS, which includes as its principal modules SENSIT-1D, ONETRAN, and ALVIN. These modules function in a multigroup environment using standard flux and data interface files for communication. The input multigroup cross-section data and uncertainties are obtained primarily from ENDF/B using the NJOY processing system. In particular cases, the input library can be modified by the ALVIN module to improve consistency with available integral experiments. The primary output from LASS is the uncertainty (or change) in important reactor parameters, as calculated in the SENSIT-1D module. Applications of LASS and its component parts have been made to the Tokamak Fusion Test Reactor (TFTR), the Reference Theta-Pinch Reactor (RTPR), and to an Experimental Power Reactor (EPR). This paper emphasizes the initial assessment of cross-section sensitivity for an EPR design. Nucleonic responses examined include neutron and gamma-ray kerma in the toroidal field coils and Mylar superinsulation, displacement damage and transmutation in the copper of the toroidal field coils, and activation of the outboard dewar. These sensitivities are now being used to narrow the range of uncertainty analyses required to quantitatively assess cross-section adequacy for EPR design calculations. Acceptable target uncertainties in nucleonic design parameters are simultaneously being formulated. Experience at LASL with sensitivity and uncertainty analysis techniques incorporated in LASS has provided convincing evidence of their value for fusion reactor studies. Many of these studies are of a shielding nature; e.g., deep penetrations of high-energy neutrons through steel, lead, boron carbide, and graphite, with responses such as activation and kerma.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Sensitivity analysis, as applied to both nuclear design and data uncertainty, has developed into a valuable tool for fusion reactor nuclear analysis. Several such studies have been undertaken with the LASL sensitivity system LASS, which includes as its principal modules SENSIT-1D, ONETRAN, and ALVIN. These modules function in a multigroup environment using standard flux and data interface files for communication. The input multigroup cross-section data and uncertainties are obtained primarily from ENDF/B using the NJOY processing system. In particular cases, the input library can be modified by the ALVIN module to improve consistency with available integral experiments. The primary output from LASS is the uncertainty (or change) in important reactor parameters, as calculated in the SENSIT-1D module. Applications of LASS and its component parts have been made to the Tokamak Fusion Test Reactor (TFTR), the Reference Theta-Pinch Reactor (RTPR), and to an Experimental Power Reactor (EPR). This paper emphasizes the initial assessment of cross-section sensitivity for an EPR design. Nucleonic responses examined include neutron and gamma-ray kerma in the toroidal field coils and Mylar superinsulation, displacement damage and transmutation in the copper of the toroidal field coils, and activation of the outboard dewar. These sensitivities are now being used to narrow the range of uncertainty analyses required to quantitatively assess cross-section adequacy for EPR design calculations. Acceptable target uncertainties in nucleonic design parameters are simultaneously being formulated. Experience at LASL with sensitivity and uncertainty analysis techniques incorporated in LASS has provided convincing evidence of their value for fusion reactor studies. Many of these studies are of a shielding nature; e.g., deep penetrations of high-energy neutrons through steel, lead, boron carbide, and graphite, with responses such as activation and kerma.
Cross Section Sensitivity and Uncertainty Analysis for European INTOR and U.S. FED Designs
Author: Sandro Pelloni
Publisher:
ISBN:
Category :
Languages : en
Pages : 85
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 85
Book Description
Fusion Energy Update
Author:
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 100
Book Description
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 100
Book Description
Fusion-fission Systems Analysis and the Impact of Nuclear Data Uncertainties on Design
Author: Mahmoud Zaky H. M. Youssef
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 326
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 326
Book Description
Two-dimensional Cross-section and SED Uncertainty Analysis for the Fusion Engineering Device (FED).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The theory of two-dimensional cross-section and secondary-energy-distribution (SED) sensitivity was implemented by developing a two-dimensional sensitivity and uncertainty analysis code, SENSIT-2D. Analyses of the Fusion Engineering Design (FED) conceptual inboard shield indicate that, although the calculated uncertainties in the 2-D model are of the same order of magnitude as those resulting from the 1-D model, there might be severe differences. The more complex the geometry, the more compulsory a 2-D analysis becomes. Specific results show that the uncertainty for the integral heating of the toroidal field (TF) coil for the FED is 114.6%. The main contributors to the cross-section uncertainty are chromium and iron. Contributions to the total uncertainty were smaller for nickel, copper, hydrogen and carbon. All analyses were performed with the Los Alamos 42-group cross-section library generated from ENDF/B-V data, and the COVFILS covariance matrix library. The large uncertainties due to chromium result mainly from large convariances for the chromium total and elastic scattering cross sections.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The theory of two-dimensional cross-section and secondary-energy-distribution (SED) sensitivity was implemented by developing a two-dimensional sensitivity and uncertainty analysis code, SENSIT-2D. Analyses of the Fusion Engineering Design (FED) conceptual inboard shield indicate that, although the calculated uncertainties in the 2-D model are of the same order of magnitude as those resulting from the 1-D model, there might be severe differences. The more complex the geometry, the more compulsory a 2-D analysis becomes. Specific results show that the uncertainty for the integral heating of the toroidal field (TF) coil for the FED is 114.6%. The main contributors to the cross-section uncertainty are chromium and iron. Contributions to the total uncertainty were smaller for nickel, copper, hydrogen and carbon. All analyses were performed with the Los Alamos 42-group cross-section library generated from ENDF/B-V data, and the COVFILS covariance matrix library. The large uncertainties due to chromium result mainly from large convariances for the chromium total and elastic scattering cross sections.
Application of Sensitivity Analysis to a Quantitative Assessment of Neutron Cross-section Requirements for the TFTR
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A computational method to determine cross-section requirements quantitatively is described and applied to the Tokamak Fusion Test Reactor (TFTR). In order to provide a rational basis for the priorities assigned to new cross- section measurements or evaluations, this method includes quantitative estimates of the uncertainty of currently available data, the sensitivity of important nuclear design parameters to selected cross sections, and the accuracy desired in predicting nuclear design parameters. Perturbation theory is used to combine estimated cross-section uncertainties with calculated sensitivities to determine the variance of any nuclear design parameter of interest. (auth).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A computational method to determine cross-section requirements quantitatively is described and applied to the Tokamak Fusion Test Reactor (TFTR). In order to provide a rational basis for the priorities assigned to new cross- section measurements or evaluations, this method includes quantitative estimates of the uncertainty of currently available data, the sensitivity of important nuclear design parameters to selected cross sections, and the accuracy desired in predicting nuclear design parameters. Perturbation theory is used to combine estimated cross-section uncertainties with calculated sensitivities to determine the variance of any nuclear design parameter of interest. (auth).
Sensitivity and Uncertainty Analysis of the Nuclear Heating in the Coils of a Fusion Reactor
Author: A. Hogenbirk
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description