Global ETD Search
Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
Results
Showing 1 to 20 of 60 for “"thermal-hydraulics"”.
-
Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback
… Monte Carlo reactor physics code, Serpent, with thermal-hydraulics safety analysis code RELAP5-3D. Thermal-hydraulics and reactor physics coupling is commonly used in deterministic methods, for example RELAP5/PARCS and TRACE/PARCS. It has been well-validated for a number of steady and transient …
-
Thermal hydraulics of high heat flux components
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1995.
-
A Computation Thermal-Hydraulics Analysis of a Heragonal-Geometry Reactor
Made available in DSpace on 2017-07-06T18:55:04Z (GMT). No. of bitstreams: 3 Laughton_Terrill_R_MS.pdf: 47062356 bytes, checksum: f3492e3b4407e61f500243c8327e7f25 (MD5) Laughton_Terrill_R_MS_ABS.pdf: 538197 bytes, checksum: c934365c2f66913e222478758ad8fcf6 (MD5) license.txt: 4813 bytes, checksum: …
-
Tightly coupled neutronics and thermal-hydraulics using open-source software
Coupling the neutronic and thermal-hydraulic analyses of a nuclear reactor core is important because it helps identify the most relevant safety issues. Currently all coupled computations solve the same set of governing equations using different coupling methods, which can be sorted into two …
-
Scale adaptive turbulence modeling for in-vessel sodium thermal hydraulics
… reactors. In these reactors, the phenomenon of thermal striping -- characterized by oscillatory turbulent mixing of non-isothermal coolant flows -- has the potential to damage the structural integrity of reactor instrumentation and structural materials. At present, large eddy simulation is the …
-
A Semi-Analytical Method for the Thermal-Hydraulics of a Boiling Water Reactor
Made available in DSpace on 2017-07-06T18:59:14Z (GMT). No. of bitstreams: 3 Vandermyde_Mark_A_MS.pdf: 46312150 bytes, checksum: 094a60daa2636d18573e970c85add0ce (MD5) Vandermyde_Mark_A_MS_ABS.pdf: 451063 bytes, checksum: dac8cd25f58984ef8720768fc460b356 (MD5) license.txt: 4813 bytes, checksum: …
-
An Effective Methodology for Thermal-Hydraulics Analysis of a VHTR Core and Fuel Elements
… it ideal for generating electricity at a plant thermal efficiency upwards of 48% and the co-generation of process heat for hydrogen production and other industrial uses. Extensive thermal-hydraulics and safety analyses of VHTRs are being conducted using Computational Fluid Dynamics (CFD) and …
-
A hierarchical Bayesian calibration framework for quantifying input uncertainties in thermal-hydraulics simulation models
… uncertainty information in nuclear best-estimate Thermal-Hydraulics (TH) codes are not always available and are mostly based on expert judgment, especially for parameters in closure laws or empirical correlations that are used to describe complex two-phase flow and heat transfer phenomena. The …
-
Analysis of the thermal hydraulics of a multiphase oxygen production reactor in the Cu-Cl cycle
… salt and solid reactant. In this thesis, the thermal hydraulics of the oxygen slurry bubble column reactor (SBCR) is investigated experimentally and numerically. In the experiments, lower temperature alternative materials, such as helium gas at 90°C and water at 22°C, are used to mimic the …
-
Experimental investigation of the thermal-hydraulics of gas jet expansion in a two-dimensional liquid pool.
Thesis. 1978. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
-
Advanced framework for assessment and reduction of model form uncertainty of the closure laws in thermal-hydraulics codes
… two-fluid model is a basis of many nuclear thermal-hydraulics codes used in design, licensing, and safety analysis of nuclear reactors. However, the averaging process introduces new turbulent and interfacial terms that require sub-grid models to close the system of equations. These closure …
-
Neutronics and thermal-hydraulics analysis of transatomic power molten salt reactor (TAP MSR) core under load following operations
This work analyzed the neutronics and thermal-hydraulics behavior of the Transatomic Power Molten Salt Reactor (TAP MSR) core under load-following operations using a Monte Carlo code, Serpent 2, as well as a UIUC-developed MOOSE-based code, Moltres. A simulation method was developed to determine …
-
Thermal hydraulics analysis of the MIT research reactor in support of a low enrichment uranium (LEU) core conversion
… computer code for the MITR, and to perform the thermal hydraulic analyses in support of the LEU design studies. The in-house multi-channel thermal-hydraulics code, MULCH-II, was developed specifically for the MITR. This code was validated against PLTEMP for steady-state analysis, and RELAP5 and …
-
Heat and Mass Transfer in Reactor Core During a Loca-Single Channel Analysis (Mixed Convection, Numerical, Flow, Thermal-Hydraulics)
Ability to predict the scenario following a loss-of-coolant accident (LOCA) is of central importance in the safety analysis of water reactors. During LOCA, the reactor core is uncovered and the residual water inventory is boiled off by fission products decay heating. For the Three Mile Island …
-
Inverse uncertainty quantification of input model parameters for thermal-hydraulics simulations using expectation-maximization under non-Bayesian and Bayesian framework
… However, like most system codes, nuclear thermal-hydraulics code TRACE does not provide any information on statistical properties of input model parameters. Moreover, the input model parameters in TRACE code are built using correlations from experiments performed under steady-state low …
-
Stability analysis of a natural circulation lead-cooled fast reactor
This dissertation is aimed at nuclear-coupled thermal hydraulics stability analysis of a natural circulation lead cooled fast reactor design. The stability concerns arise from the fact that natural circulation operation makes the system susceptible to flow instabilities similar to those observed in …
-
TRACE code validation of boiling water reactor spray cooling injection into a SVEA fuel assembly
… validity, particularly with modeling the complex thermal-hydraulics phenomena associated with Loss-of-Coolant Accident (LOCA) scenarios. Emergency spray cooling injection is a safety feature implemented in many Boiling Water Reactor (BWR) designs to re-flood a reactor during an accident. …
-
A numerical study on parameters affecting boric acid transport and chemistry within fuel corrosion deposits during crud induced power shift
… This study aims to advance previously developed thermal hydraulics model to study boric acid transport within crud; and develop a 2-D coupled crud-chemistry and thermal hydraulics model to serve as a framework for development of advanced crud deposition and growth model. Various parameters …
-
On the use of high performance annular fuel in PWRs
… 50% while maintaining or improving its existing thermal and safety margins. Each annular fuel assembly is arranged in a 13x13 array but has the same side dimensions as a 17x17 solid fuel assembly. Even at much higher power densities, the peak fuel temperatures are substantially lower and the …
-
A novel framework for data-driven modeling, uncertainty quantification, and deep learning of nuclear reactor simulations
… as neutronics, reactor kinetics, fuel depletion, thermal-hydraulics, and fuel performance as well as outside the reactor such as spent fuel and criticality safety. The framework utilizes various computer models in the nuclear area, which are already validated and known to provide accurate results. …
Page 1 of 3