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 21 for “"TRISO fuel"”.
-
Comprehensive fuel performance model development and simulation for triso fuel
Item withdrawn by Alexis Thompson (athmpsn1@illinois.edu) on 2011-01-13T19:58:31Z Item was in collections: University of Illinois Theses & Dissertations (ID: 1) No. of bitstreams: 1 Hu_Jianwei.pdf: 5191894 bytes, checksum: 702afe062ec7e3d71c3ef29c7b15f21a (MD5)
-
Experimental investigations of the thermodynamic properties of Nd-C and Ce-C binary systems for TRISO fuel applications
TRISO fuels are proposed for modular and niche nuclear power reactor technologies, expanding the global nuclear power inventory to meet increasing energy demands through small scale applications. Expansion is dependent upon the improvements to safety through thorough understanding of fission …
-
Levelized Cost of Fuel (LCOF) studies for microreactors using TRISO fuel in hydride and beryllium-based composite moderators in open and closed fuel cycles
… gas-cooled 10 MW_th microreactors (HTGRs) with TRISO fuel in prismatic- and pebble-bed cores—using four composite moderator concepts (MgO–Be, MgO–BeO, MgO–YH, MgO–ZrH). These options are compared against a prismatic graphite benchmark, under both once-through and continuous-recycle fuel cycles. …
-
Reactivity-equivalent physical transformation model for pin cell arrays
The behavior of TRISO fuel used in high temperature gas reactors in order to achieve high fuel performance is difficult to model using traditional lattice codes due to the double-heterogeneity effect created by the multi-coated fuel kernels in a graphite matrix. A simple volume-weighted …
-
Tritium transport, corrosion, and Fuel performance modeling in the Fluoride Salt-Cooled High-Temperature Reactor (FHR)
… (FHR) is a pebble bed nuclear reactor concept fueled by tristructural isotropic (TRISO) fuel particles embedded in graphite spheres and cooled by a liquid fluoride salt known as "flibe" (7LiF-BeF2). A system of models was developed which enabled analyses of the performance of a prototypical …
-
Coating Parameters of Zirconium Carbide On Advanced Triso Fuels
… greatly depends on the tri-structural isotropic (TRISO) fuel particles reliability to retain both gaseous and metallic fission products created in irradiated UO2. Most research devoted to TRISO fuel particles has focused on the characteristics and retention ability of silicon carbide as the main …
-
Thermodynamic and Thermochemical Investigation of Advanced Triso Coated Particle Fuels
… the next several decades. Research into advanced fuels is an important part of GenIV development. The coated particle fuel concept has been considered since the 1940s and the zirconium carbide layer of the advanced coated particle fuel has been considered to solve the specific problems such as …
-
Helium-Air mixing in simulated reactor cavities of Very High Temperature Reactors
… reactors use graphite containing U-235 TRISO fuel particles in their core, as a moderator to slow down neutrons for fission chain reactions and for general core support. In the event of a primary circuit pipe break, the coolant gas escapes into the surrounding reactor cavity until the …
-
Design and Modeling of Offshore Nuclear Platform Fuel and Transfer System
The design and modeling of the fuel and transfer system aboard the Offshore Nuclear Platform (OFNP) aims to integrate Small Modular Reactors (SMRs) into an offshore setting. This endeavor is in line with global initiatives to mitigate temperature rise by 2050, using nuclear energy for electrical …
-
The Effect of Coating Parameters On Advanced TRISO Fuels With Zirconium Carbide
<p>Recent studies of TRISO fuel behavior have shown a number of problems with the conventional SiC TRISO coating system at very high temperature, not unlike the temperatures obtainable in the very high temperature reactor (VHTR) design. These problems include but are not limited to over …
-
Development of a High Temperature Gas-Cooled Reactor TRISO-coated particle fuel chemistry model
… in a High Temperature Gas-Cooled Reactor TRISO fuel particle. Fission product inventory versus burnup is calculated. Based on those results a thermodynamic analysis is performed to determine fission product vapor pressures, oxygen partial pressure, and carbon monoxide and carbon dioxide …
-
The Deposition Characteristics of Zrc On Uo2 Kernels Produced For Advanced Triso Fuels In Gen-Iv Reactors
… by the ability of the tri-structural isotropic fuel (TRISO) to maintain its structural integrity under irradiation at temperatures of normal operation and accident scenarios. The silicon carbide (SiC) layer typical of most TRISO fuels acts as both a diffusion barrier and a pressure vessel for …
-
Investigation of the hydrodynamics and scale-up of advanced TRISO nuclear fuel manufacturing using sophisticated measurement techniques
… (VHTR) extremely depend on the quality of the TRISO nuclear fuel coated particles. However, the coating of the TRISO particles is delicate process and impacted by the hydrodynamics of spouted beds. Therefore, in this work, we applied advanced non-invasive measurement techniques which are …
-
OXIDATION OF SILICON CARBIDE AND GRAPHITE FOR HIGH TEMPERATURE GAS-COOLED REACTOR APPLICATIONS
… of the SiC layer of tristructural isotropic (TRISO) fuel particles demonstrated different oxidation behavior than that of typical flat-plate chemical vapor deposited SiC and that of SiC fibers with regards to stress relief and devitrification in the SiO<sub>2</sub> scale. By comparing the …
-
Nuclear Electric Propulsion with Low Enriched Uranium
Most space missions have used monopropellant or fuel-oxidiser propulsion systems to provide the required delta-v for orbital transfers and other in-space manoeuvres. Electric propulsion offers an alternative means of providing thrust that makes much more economical use of propellant due to its very …
-
Design optimization and analysis of a fluoride salt cooled high temperature test reactor for accelerated fuels and materials testing and nonproliferation and safeguards evaluations
… salt coolants together with solid microparticle TRISO fuel. Since no FHR has been built, an important technology development step is the design, construction, and operation of a FHR test reactor (FHTR). The FHTR's strategic goals cannot be satisfied using small-scale experiments or test loops: …
-
Modelling of Graphite Elements and Low Enriched Fuel Assemblies for a High Temperature Gas-Cooled Reactor
… leverages the safety advantages of gas- cooled, TRISO fuelled reactors, and the economic advantages of a horizontal compact layout. Graphite assembly blocks create the channels that guide the helium coolant flow and contain the fuel compacts in the HC-HTGR. Given the low tensile strength of …
-
Analysis and optimization of a new accident tolerant fuel called fuel-in-fibers
… highlighted the weakness of the current nuclear fuel and motivated R&D of accident tolerant fuels. Accident tolerant fuels (ATF) are fuels that can tolerate loss of active cooling in the core of light water reactors (LWRs) for a considerably longer period of time while maintaining or improving …
Page 1 of 2