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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Numerical Investigation of Deformation Mass Flow and Heat Transfer During a Criticality Event in a Dual-Purpose Canister.
Abstract not provided.
Dual-Purpose Canister Direct Disposal ? Development of Cement Fillers.
Abstract not provided.
MELCOR Input Model for Spent Fuel Transportation and Storage Canister
This report documents the progress and current results of the MELCOR spent fuel cask input model. The MELCOR model is being developed to investigate aerosol transport and deposition given the aerosol physical phenomena models within MELCOR. To perform the analyses, a general portrayal of the MAGNASTOR® cask system has been employed; however, this system was selected based on available information to provide a reasonable representation of a spent fuel cask. The analytical results are not intended to characterize the performance of the MAGNASTOR® cask. Instead, the provided results are intended to enhance our general understanding of the aerosol behavior within casks and the validity of current models. The current model efforts are being performed to investigate hypothetical UO 2 release from failed fuel pins within a spent fuel cask. The existing MELCOR model of the MAGNASTOR® cask system has been adapted to permit future comparative analyses with the GOTHIC representation of the MAGNASTOR® cask. To support this comparison, the PNNL model characteristics that are unrelated to the aerosol modeling were applied to the MELCOR model. These characteristics included improved comparability of the axial fidelity, total spent fuel power, fuel pin axial power profile, and heat losses from cannister. The thermal-hydraulic solutions are improved within the capability of the MELCOR code and will permit better overall agreement with the GOTHIC results. Detailed results are presented on the thermal-hydraulic analysis of the MELCOR cask as well as characterization of UO 2 aerosol dispersion and deposition within the cask.
Introduction to Mitigation and Repair of Spent Nuclear Fuel Canisters.
Abstract not provided.
DOE?s Disposal Research Activities: Geologic Disposal Safety Assessment (GDSA) and Direct Disposal of Dual-Purpose Canisters (DPCs).
Abstract not provided.
Postclosure Transient Criticality Analysis for a Dual-Purpose Canister.
Abstract not provided.
Postclosure Transient Criticality Analysis for a Dual-Purpose Canister.
Abstract not provided.
Understanding and Predicting Stress Corrosion Cracking of SNF Dry Storage Canisters.
Abstract not provided.
Developments into Understanding Spent Nuclear Fuel Canister Surface Environment.
Abstract not provided.
Corrosion Resistant Coatings for Application on Spent Nuclear Fuel Canisters.
Abstract not provided.
Thermal and Radiolytic Behavior of Mitigation and Repair Coatings for SNF Canisters
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Probabilistic Model for Stress Corrosion Cracking of SNF Dry Storage Canisters
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First Do No Harm: A Wholistic Approach to Identifying Feasible Commercial Corrosion Mitigation Coatings for Use on Spent Nuclear Fuel Storage Canisters
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Evaluating the Corrosivity of Relevant Environments that can form on the Surface of Spent Nuclear Fuel Canisters
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Research Overview: Canister Stress Corrosion Cracking
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