This report documents establishment of bias, bias trends and uncertainty for validation of the CSAS25 control module from the SCALE 4.4a computer code system for use in evaluating criticality safety of uranium systems. The 27-group ENDF/B-IV, 44-group ENDF/B-V, and 238-group ENDF/B-V cross-section libraries were used. The criticality validation calculations were performed using over 500 benchmark cases from Volumes II and IV of the ''International Handbook of Evaluated Criticality Safety Benchmark Experiments,'' published by the Nuclear Energy Agency Organization for Economic Cooperation and Development (NEA/OECD). Based on statistical analysis of the calculation results, the bias, bias trends and uncertainty of the benc...
The ANS/ANS-8.1 standard requires that calculational methods used in determining criticality safety ...
The original validation report, POEF-T-3636, was documented in August 1994. The document was based o...
Criticality experiments are the foundation of the criticality safety validation, the reactor paramet...
This report considers the methods for determination of an upper safety limit, and incorporating unce...
A systematic approach has been developed to determine benchmark biases and apply those biases to cod...
[ES]El artículo presenta la validación del módulo de control CSAS26 de SCALE 4.4a para el cálculo en...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
Section 1 of this report documents the validation of KENO V.a against 258 critical experiments. Expe...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
The use of cross-section covariance data has long been a key part of traditional sensitivity and unc...
The purpose of this analysis is to validate the Monte Carlo N-Particle 5 (MCNP5) code Version 1.40 (...
This paper presents the application of sensitivity and uncertainty (S/U) analysis methodologies to t...
The ANS/ANS-8.1 standard requires that calculational methods used in determining criticality safety ...
The ANS/ANS-8.1 standard requires that calculational methods used in determining criticality safety ...
The original validation report, POEF-T-3636, was documented in August 1994. The document was based o...
Criticality experiments are the foundation of the criticality safety validation, the reactor paramet...
This report considers the methods for determination of an upper safety limit, and incorporating unce...
A systematic approach has been developed to determine benchmark biases and apply those biases to cod...
[ES]El artículo presenta la validación del módulo de control CSAS26 de SCALE 4.4a para el cálculo en...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
Section 1 of this report documents the validation of KENO V.a against 258 critical experiments. Expe...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
The use of cross-section covariance data has long been a key part of traditional sensitivity and unc...
The purpose of this analysis is to validate the Monte Carlo N-Particle 5 (MCNP5) code Version 1.40 (...
This paper presents the application of sensitivity and uncertainty (S/U) analysis methodologies to t...
The ANS/ANS-8.1 standard requires that calculational methods used in determining criticality safety ...
The ANS/ANS-8.1 standard requires that calculational methods used in determining criticality safety ...
The original validation report, POEF-T-3636, was documented in August 1994. The document was based o...
Criticality experiments are the foundation of the criticality safety validation, the reactor paramet...