Validation of calculational methods for nuclear criticality safety
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DOWNLOAD EBOOKRead and Download eBook Full
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DOWNLOAD EBOOKAuthor: American Nuclear Society
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Published: 1976
Total Pages: 5
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Published: 2001*
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DOWNLOAD EBOOKAuthor:
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Published: 1998
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DOWNLOAD EBOOKAuthor: J. C. Dean
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Published: 2001
Total Pages: 42
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DOWNLOAD EBOOKAuthor: American Nuclear Society. Standards Committee Working Group ANS-8.24
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Published: 2017
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DOWNLOAD EBOOKANS 8.24-2017 provides requirements and recommendations for validation, including establishing applicability, of neutron transport calculational methods used in determining critical or subcritical conditions for nuclear criticality safety analyses.
Author: Berry F. Estes
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Published: 1980
Total Pages: 448
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DOWNLOAD EBOOKAuthor: U.S. Nuclear Regulatory Commission. Office of Standards Development
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Total Pages: 1100
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DOWNLOAD EBOOKContents: 1. Power reactors.--2. Research and test reactors.--3. Fuels and materials facilities.--4. Environmental and siting.--5. Materials and plant protection.--6. Products.--7. Transportation.--8. Occupational health.--9. Antitrust reviews.--10. General.
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Published: 1996
Total Pages: 114
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DOWNLOAD EBOOKWhenever a decision is made to newly install the SCALE nuclear criticality safety software on a computer system, the user should run a set of verification and validation (V & V) test cases to demonstrate that the software is properly installed and functioning correctly. This report is intended to serve as a guide for this V & V in that it specifies test cases to run and gives expected results. The report describes the V & V that has been performed for the nuclear criticality safety software in a version of SCALE-4. The verification problems specified by the code developers have been run, and the results compare favorably with those in the SCALE 4.2 baseline. The results reported in this document are from the SCALE 4.2P version which was run on an IBM RS/6000 workstation. These results verify that the SCALE-4 nuclear criticality safety software has been correctly installed and is functioning properly. A validation has been performed for KENO V.a utilizing the CSAS25 criticality sequence and the SCALE 27-group cross-section library for 233U, 235U, and 239Pu fissile, systems in a broad range of geometries and fissile fuel forms. The experimental models used for the validation were taken from three previous validations of KENO V.a. A statistical analysis of the calculated results was used to determine the average calculational bias and a subcritical k{sub eff} criteria for each class of systems validated. Included the statistical analysis is a means of estimating the margin of subcriticality in k{sub eff}. This validation demonstrates that KENO V.a and the 27-group library may be used for nuclear criticality safety computations provided the system being analyzed falls within the range of the experiments used in the validation.
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Published: 1991
Total Pages: 11
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DOWNLOAD EBOOKRecent hardware and operating system changes at Westinghouse Savannah River Site (WSRC) have necessitated review of the validation for JOSHUA criticality safety computer codes. As part of the planning for this effort, a policy for validation of JOSHUA and other criticality safety codes has been developed. This policy will be illustrated with the steps being taken at WSRC. The objective in validating a specific computational method is to reliably correlate its calculated neutron multiplication factor (K{sub eff}) with known values over a well-defined set of neutronic conditions. Said another way, such correlations should be: (1) repeatable; (2) demonstrated with defined confidence; and (3) identify the range of neutronic conditions (area of applicability) for which the correlations are valid. The general approach to validation of computational methods at WSRC must encompass a large number of diverse types of fissile material processes in different operations. Special problems are presented in validating computational methods when very few experiments are available (such as for enriched uranium systems with principal second isotope 236U). To cover all process conditions at WSRC, a broad validation approach has been used. Broad validation is based upon calculation of many experiments to span all possible ranges of reflection, nuclide concentrations, moderation ratios, etc. Narrow validation, in comparison, relies on calculations of a few experiments very near anticipated worst-case process conditions. The methods and problems of broad validation are discussed.