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.
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.
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category :
Languages : en
Pages : 900
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 900
Book Description
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration. Technical Information Center
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 1066
Book Description
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 1066
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
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 684
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 684
Book Description
Publications of Los Alamos Research
Author: Los Alamos National Laboratory
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 348
Book Description
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 348
Book Description
ERDA.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 144
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 144
Book Description
Publications of LASL Research
Author: Los Alamos Scientific Laboratory
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 200
Book Description
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 200
Book Description
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 670
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 670
Book Description
Review of New Developments in Fusion Reactor Nucleonics
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A review is presented of recent developments in nuclear data, computational methods, and computer codes, especially as pertains to fusion reactor nucleonics. Important nuclear data measurements, evaluations, nuclear model codes and processing codes are discussed. Progress in solution acceleration and deterministic streaming methods for discrete-ordinates codes is covered, along with comments on recent Monte Carlo developments. Finally, sensitivity and uncertainty analysis methods are reviewed.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A review is presented of recent developments in nuclear data, computational methods, and computer codes, especially as pertains to fusion reactor nucleonics. Important nuclear data measurements, evaluations, nuclear model codes and processing codes are discussed. Progress in solution acceleration and deterministic streaming methods for discrete-ordinates codes is covered, along with comments on recent Monte Carlo developments. Finally, sensitivity and uncertainty analysis methods are reviewed.