Application of the Sensitivity and Uncertainty Analysis System LASS to Fusion Reactor Nucleonics

Application of the Sensitivity and Uncertainty Analysis System LASS to Fusion Reactor Nucleonics PDF Author:
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Category :
Languages : en
Pages :

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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

Application of the Sensitivity and Uncertainty Analysis System LASS to Fusion Reactor Nucleonics PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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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

ERDA Energy Research Abstracts PDF Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category :
Languages : en
Pages : 900

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ERDA Energy Research Abstracts

ERDA Energy Research Abstracts PDF Author: United States. Energy Research and Development Administration. Technical Information Center
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 1066

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Application of Sensitivity and Uncertainty Analysis in Fusion Reactor Design

Application of Sensitivity and Uncertainty Analysis in Fusion Reactor Design PDF Author: Tang Wu
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ISBN:
Category : Fusion reactors
Languages : en
Pages : 480

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Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 684

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Publications of Los Alamos Research

Publications of Los Alamos Research PDF Author: Los Alamos National Laboratory
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 348

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ERDA.

ERDA. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 144

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Publications of LASL Research

Publications of LASL Research PDF Author: Los Alamos Scientific Laboratory
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 200

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ERDA Energy Research Abstracts

ERDA Energy Research Abstracts PDF Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 670

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Review of New Developments in Fusion Reactor Nucleonics

Review of New Developments in Fusion Reactor Nucleonics PDF Author:
Publisher:
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Category :
Languages : en
Pages :

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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.