COBRA-SFS (Spent Fuel Storage)

COBRA-SFS (Spent Fuel Storage) PDF Author:
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Languages : en
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This report presents the results of the COBRA-SFS (Spent Fuel Storage) computer code validation effort. COBRA-SFS, while refined and specialized for spent fuel storage system analyses, is a lumped-volume thermal-hydraulic analysis computer code that predicts temperature and velocity distributions in a wide variety of systems. Through comparisons of code predictions with spent fuel storage system test data, the code's mathematical, physical, and mechanistic models are assessed, and empirical relations defined. The six test cases used to validate the code and code models include single-assembly and multiassembly storage systems under a variety of fill media and system orientations and include unconsolidated and consolidated spent fuel. In its entirety, the test matrix investigates the contributions of convection, conduction, and radiation heat transfer in spent fuel storage systems. To demonstrate the code's performance for a wide variety of storage systems and conditions, comparisons of code predictions with data are made for 14 runs from the experimental data base. The cases selected exercise the important code models and code logic pathways and are representative of the types of simulations required for spent fuel storage system design and licensing safety analyses. For each test, a test description, a summary of the COBRA-SFS computational model, assumptions, and correlations employed are presented. For the cases selected, axial and radial temperature profile comparisons of code predictions with test data are provided, and conclusions drawn concerning the code models and the ability to predict the data and data trends. Comparisons of code predictions with test data demonstrate the ability of COBRA-SFS to successfully predict temperature distributions in unconsolidated or consolidated single and multiassembly spent fuel storage systems.

COBRA-SFS (Spent Fuel Storage)

COBRA-SFS (Spent Fuel Storage) PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
This report presents the results of the COBRA-SFS (Spent Fuel Storage) computer code validation effort. COBRA-SFS, while refined and specialized for spent fuel storage system analyses, is a lumped-volume thermal-hydraulic analysis computer code that predicts temperature and velocity distributions in a wide variety of systems. Through comparisons of code predictions with spent fuel storage system test data, the code's mathematical, physical, and mechanistic models are assessed, and empirical relations defined. The six test cases used to validate the code and code models include single-assembly and multiassembly storage systems under a variety of fill media and system orientations and include unconsolidated and consolidated spent fuel. In its entirety, the test matrix investigates the contributions of convection, conduction, and radiation heat transfer in spent fuel storage systems. To demonstrate the code's performance for a wide variety of storage systems and conditions, comparisons of code predictions with data are made for 14 runs from the experimental data base. The cases selected exercise the important code models and code logic pathways and are representative of the types of simulations required for spent fuel storage system design and licensing safety analyses. For each test, a test description, a summary of the COBRA-SFS computational model, assumptions, and correlations employed are presented. For the cases selected, axial and radial temperature profile comparisons of code predictions with test data are provided, and conclusions drawn concerning the code models and the ability to predict the data and data trends. Comparisons of code predictions with test data demonstrate the ability of COBRA-SFS to successfully predict temperature distributions in unconsolidated or consolidated single and multiassembly spent fuel storage systems.

COBRA-SFS (Spent Fuel Storage) : a thermal-hydraulic analysis computer code. Volume 1, mathematical models and solution method

COBRA-SFS (Spent Fuel Storage) : a thermal-hydraulic analysis computer code. Volume 1, mathematical models and solution method PDF Author: D. R. Rector
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ISBN:
Category :
Languages : en
Pages : 0

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COBRA-SFS (Spent-Fuel Storage) Thermal-hydraulic Analyses of the CASTOR-1C and REA 2023 BWR Storage Casks Containing Consolidated Spent Fuel

COBRA-SFS (Spent-Fuel Storage) Thermal-hydraulic Analyses of the CASTOR-1C and REA 2023 BWR Storage Casks Containing Consolidated Spent Fuel PDF Author:
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Languages : en
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Consolidation of spent nuclear fuel rods is being considered as one option for more efficient and compact storage of reactor spent fuel assemblies. In this concept, rods from two disassembled spent fuel assemblies will be consolidated in a space originally intended to store a single unconsolidated assembly. The thermal performance of consolidated fuel rods in dry storage, especially in multiassembly storage systems, is one of the major issues that must be addressed prior to implementation. In this study, Pacific Northwest Laboratory researchers performed thermal-hydraulic analyses for both the REA 2023 cask and the CASTOR-1C cask containing either unconsolidated or consolidated BWR spent fuel assemblies. The objective was to determine the effect of consolidating spent fuel assemblies on the temperature distributions within both types of casks. Two major conclusions resulted from this study. First, a lumping technique (combining rods and flow channels), which reduces the number of computational nodes required to model complex multiassembly geometries, could be used for both unconsolidated and consolidated rods with negligible effect on prediction accuracies. Second, with a relatively high thermal conductivity backfill gas (e.g., helium), the predicted peak fuel rod temperature in a canister of consolidated rods generating the same amount of heat as an unconsolidated assembly is essentially the same as the peak temperature in the unconsolidated assembly. In contrast, with a relatively low thermal conductivity backfill gas (e.g., nitrogen), the opposite is true and the predicted peak temperature in a consolidated canister is significantly higher than in an unconsolidated assembly. Therefore, when rods are consolidated, selection of the backfill gas is important in maintaining peak rod temperatures below allowable values for rods with relatively high decay heat generation rates.

COBRA-SFS

COBRA-SFS PDF Author: Thomas E. Michener
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Category :
Languages : en
Pages :

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COBRA-SFS Predictions of Single Assembly Spent Fuel Heat Transfer Data

COBRA-SFS Predictions of Single Assembly Spent Fuel Heat Transfer Data PDF Author: Nicholas J. Lombardo
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Languages : en
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COBRA-SFS Thermal Analysis of a Sealed Storage Cask for the Monitored Retrievable Storage of Spent Fuel

COBRA-SFS Thermal Analysis of a Sealed Storage Cask for the Monitored Retrievable Storage of Spent Fuel PDF Author: David R. Rector
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ISBN:
Category :
Languages : en
Pages : 35

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COBRA-SFS Modifications and Cask Model Optimization

COBRA-SFS Modifications and Cask Model Optimization PDF Author: David R. Rector
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ISBN:
Category : COBRA-SFS (Computer program)
Languages : en
Pages :

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COBRA-SFS

COBRA-SFS PDF Author: David R. Rector
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ISBN:
Category :
Languages : en
Pages :

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Testing and COBRA-SFS Analysis of the VSC-17 Ventilated Concrete, Spent Fuel Storage Cask

Testing and COBRA-SFS Analysis of the VSC-17 Ventilated Concrete, Spent Fuel Storage Cask PDF Author:
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ISBN:
Category :
Languages : en
Pages : 10

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A performance test of a Pacific Sierra Nuclear VSC-17 ventilated concrete storage cask loaded with 17 canisters of consolidated PWR spent fuel generating approximately 15 kW was conducted. The performance test included measuring the cask surface, concrete, air channel surface, and fuel temperatures, as well as cask surface gamma and neutron dose rates. Testing was performed using vacuum, nitrogen, and helium backfill environments. Pretest predictions of cask thermal performance were made using the COBRA-SFS computer code. Analysis results were within 15°C of measured peak fuel temperature. Peak fuel temperature for normal operation was 321°C. In general, the surface dose rates were less than 30 mrem/h on the side of the cask and 40 mrem/h on the top of the cask.

Spent fuel storage requirements

Spent fuel storage requirements PDF Author: United States. Department of Energy. Division of Spent Fuel Storage and Transfer
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ISBN:
Category :
Languages : en
Pages : 20

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