Author: E. D. Waters
Publisher:
ISBN:
Category :
Languages : en
Pages : 109
Book Description
Heat Transfer Experiments for the Advanced Test Reactor
The Advanced Test Reactor (ATR)
Author:
Publisher:
ISBN:
Category : Engineering test reactors
Languages : en
Pages : 232
Book Description
Publisher:
ISBN:
Category : Engineering test reactors
Languages : en
Pages : 232
Book Description
Fuel Melting and Relocation in the Advanced Test Reactor
A Selection Study for an Advanced Engineering Test Reactor
Author: Ford Motor Company. Aeronutronic Systems, Inc
Publisher:
ISBN:
Category : Engineering test reactors
Languages : en
Pages : 152
Book Description
Publisher:
ISBN:
Category : Engineering test reactors
Languages : en
Pages : 152
Book Description
Nuclear Safety
Proposed Heat Transfer Experiments with Direct Application to Testing Reactors
Nuclear Science Abstracts
Scientific and Technical Aerospace Reports
Scaling, Experiments, and Simulations of Condensation Heat Transfer for Advanced Nuclear Reactors Safety
Author: Palash Kumar Bhowmik
Publisher:
ISBN:
Category :
Languages : en
Pages : 199
Book Description
"The purpose of this research was to perform scaled experiments and simulations to validate computational fluid dynamics (CFD) and empirical models of condensation heat transfer (CHT) for the passive containment cooling system (PCCS) of Small Modular Reactors (SMRs). SMRs are the futuristic candidates for clean, economic, and safe energy generation; however, reactor licensing requires safety system evaluations, such as PCCS. The knowledge in the reviewed relevant literature showed a gap in experimental data for scaling SMR's safety systems and validating computational models. The previously available test data were inconsistent due to unscaled geometric and varying physics conditions. These inconsistencies lead to inadequate test data benchmarking. This study developed three scaled (different diameters) test sections with annular cooling for scale testing and analysis to fill this research gap. First, tests were performed for pure steam and steam with non-condensable gases (NCGs), like nitrogen and helium, at different mass fractions, inlet mass flow rates, and pressure ranges. Second, detailed CFD simulations and validations were performed using STAR-CCM+ software with scaled geometries and experimental parameters (e.g., flow rate, pressure, and steam-NCG mixtures), thus mimicking reactor accident cases. The multi-component gases, multiphase mixtures, and fluid film condensation models were applied, verified, and optimized in the CFD simulations with associated turbulence models. Third, the physics-based and data-driven condensation models and empirical correlations were assessed to quantify the scaling distortions. Finally, the experiments, simulations, and modeling results were evaluated for critical insights into the physics conditions, scaling effects, and multi-component gas mixture parameters. This study supported improvements to nuclear reactor safety systems' modeling capabilities irrespective of size (small or big), and findings were equally applicable to other non-nuclear energy applications"--Abstract, page iii.
Publisher:
ISBN:
Category :
Languages : en
Pages : 199
Book Description
"The purpose of this research was to perform scaled experiments and simulations to validate computational fluid dynamics (CFD) and empirical models of condensation heat transfer (CHT) for the passive containment cooling system (PCCS) of Small Modular Reactors (SMRs). SMRs are the futuristic candidates for clean, economic, and safe energy generation; however, reactor licensing requires safety system evaluations, such as PCCS. The knowledge in the reviewed relevant literature showed a gap in experimental data for scaling SMR's safety systems and validating computational models. The previously available test data were inconsistent due to unscaled geometric and varying physics conditions. These inconsistencies lead to inadequate test data benchmarking. This study developed three scaled (different diameters) test sections with annular cooling for scale testing and analysis to fill this research gap. First, tests were performed for pure steam and steam with non-condensable gases (NCGs), like nitrogen and helium, at different mass fractions, inlet mass flow rates, and pressure ranges. Second, detailed CFD simulations and validations were performed using STAR-CCM+ software with scaled geometries and experimental parameters (e.g., flow rate, pressure, and steam-NCG mixtures), thus mimicking reactor accident cases. The multi-component gases, multiphase mixtures, and fluid film condensation models were applied, verified, and optimized in the CFD simulations with associated turbulence models. Third, the physics-based and data-driven condensation models and empirical correlations were assessed to quantify the scaling distortions. Finally, the experiments, simulations, and modeling results were evaluated for critical insights into the physics conditions, scaling effects, and multi-component gas mixture parameters. This study supported improvements to nuclear reactor safety systems' modeling capabilities irrespective of size (small or big), and findings were equally applicable to other non-nuclear energy applications"--Abstract, page iii.
Atomic energy commission
Author: United States. Congress. House. Committee on Appropriations
Publisher:
ISBN:
Category : Public works
Languages : en
Pages : 432
Book Description
Publisher:
ISBN:
Category : Public works
Languages : en
Pages : 432
Book Description