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Preliminary Test Design and Plan for a Canister Deposition Field Demonstration

Durbin, S.G.; Lindgren, Eric R.

This report provides a high-level test plan for deploying three commercial 32PTH2 spent nuclear fuel (SNF) canisters inside NUHOMS Advanced Horizontal Storage Modules (AHSM) from Orano (formerly Transnuclear Inc.). The details contained in this report represent the best designs and approaches explored for testing as of this publication. Given the rapidly developing nature of this test program, some of these plans may change to accommodate new objectives or adapt in response to conflicting requirements. The goal of the testing is to collect highly defensible and detailed surface deposition measurements from the surface of dry storage systems in a marine coastal environment to guide chloride-induced stress corrosion crack (CISCC) research. To facilitate surface sampling, the otherwise highly prototypic dry storage systems will not contain SNF but rather will be electrically heated to mimic the thermal-hydraulic environment. Instrumentation throughout the canister, storage module, and environment will provide an extensive amount of information for the use of model validation. Manual sampling over a comprehensive portion of the canister surface at regular time intervals will offer a high-fidelity quantification of the conditions experienced in a harsh yet realistic environment.

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Thermal-hydraulic investigations of a horizontal dry cask simulator

International Conference on Nuclear Engineering, Proceedings, ICONE

Pulido, Ramon P.; Lindgren, Eric R.; Durbin, S.G.; Salazar, Alex S.

Recent advances in horizontal cask designs for commercial spent nuclear fuel have significantly increased maximum thermal loading. This is due in part to greater efficiency in internal conduction pathways. Carefully measured data sets generated from testing of full-sized casks or smaller cask analogs are widely recognized as vital for validating thermal-hydraulic models of these storage cask designs. While several testing programs have been previously conducted, these earlier validation studies did not integrate all the physics or components important in a modern, horizontal dry cask system. The purpose of this investigation is to produce data sets that can be used to benchmark the codes and best practices presently used to calculate cladding temperatures and induced cooling air flows in modern, horizontal dry storage systems. The horizontal dry cask simulator (HDCS) has been designed to generate this benchmark data and complement the existing knowledge base. Transverse and axial temperature profiles along with induced-cooling air flow are measured using various backfills of gases for a wide range of decay powers and canister pressures. The data from the HDCS tests will be used to host a blind model validation effort.

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Analysis of water retention in isothermal vacuum drying test

International Conference on Nuclear Engineering, Proceedings, ICONE

Salazar, Alex; Pulido, Ramon P.; Lindgren, Eric R.; Durbin, S.G.

Validation of the extent of water removal in a dry storage system using an industrial vacuum drying procedure is needed. Water remaining in casks upon completion of vacuum drying can lead to cladding corrosion, embrittlement, and breaching, as well as fuel degradation. In order to address the lack of time-dependent industrial drying data, this study employs a vacuum drying procedure to evaluate the efficiency of water removal over time in a scaled system. Isothermal conditions are imposed to generate baseline pressure and moisture data for comparison to future tests under heated conditions. A pressure vessel was constructed to allow for the emplacement of controlled quantities of water and connections to a pumping system and instrumentation. Measurements of pressure and moisture content were obtained over time during sequential vacuum hold points, where the vacuum flow rate was throttled to draw pressures from 100 torr down to 0.7 torr. The pressure rebound, dew point, and water content were observed to eventually diminish with increasingly lower hold points, indicating a reduction in retained water.

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Characterization of through-wall aerosol transmission for SCC-like geometries

International High-Level Radioactive Waste Management 2019, IHLRWM 2019

Durbin, S.G.; Lindgren, Eric R.; Pulido, Ramon P.

The flow rates and aerosol transmission properties were evaluated for an engineered microchannel with characteristic dimensions similar to those of stress corrosion cracks (SCCs) capable of forming in dry cask storage systems (DCSS) for spent nuclear fuel. Pressure differentials covering the upper limit of commercially available DCSS were also examined. These preliminary data sets are intended to demonstrate a new capability to characterize SCCs under well-controlled boundary conditions.

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Results 26–50 of 125
Results 26–50 of 125