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.
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Showing 1 to 20 of 101 for “"burnup"”.
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Fuel burnup in the MITR
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1964.
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The fuel cycle economics of PWR extended burnup
Thesis: M.S., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1986
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A one-dimensional fuel burnup model of a PWR
A fuel burnup model of a Pressurized Water Reactor (PWR) was developed based on one-group diffusion theory and used simple thermal cross sections. A computer program which simulates the depletion of the core of a PWR was written based on this model. The basic idea was to develop a fuel depletion …
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Dependence of transuranic content in spent fuel on fuel burnup
… of longer fuel cycles incorporating higher burnup are becoming common. Understanding the effect of higher burnup on the spent fuel composition and radioactive properties is essential to ensure that spent fuel receives proper cooling in storage before it is sent to a disposal site or proper …
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Modeling the performance of high burnup thoria and urania PWR fuel
… of ThO₂-UO₂ fuels that can be operated to a high burnup up to 80-100MWd/kgHM in current and future Light Water Reactors (LWRs). Among the various issues raised in high burnup fuel applications, the pellet rim effect, fission gas release (FGR), and response to reactivity initiated accidents (RIA) …
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Design strategies for optimizing high burnup fuel in pressurized water reactors
… is focused on the strategy for utilizing high-burnup fuel in pressurized water reactors (PWR) with special emphasis on the full array of neutronic considerations. The historical increase in batch-averaged discharge fuel burnup, from ~30 MWd/kg in the 1970s to ~50 MWd/kg today, was achieved …
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Assessment of high-burnup LWR fuel response to reactivity-initiated accidents
… the nuclear industry to pursue higher discharge burnup of Light Water Reactor (LWR) fuel. A design basis accident, the Reactivity Initiated Accident (RIA), became a concern for further increase of burnup as simulated RIA tests revealed lower enthalpy threshold for fuel failure associated with …
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Fluence-limited burnup as a function of fast reactor core parameters
… emphasis on minimizing enrichment and maximizing burnup. Sodium was chosen as a coolant because of its extensive experience based compared to the other options, as well as its heat transfer properties. Inverted fuel was found to be better neutronically, in both clad lifetime and burnup than …
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Fuel performance modeling of high burnup mixed oxide fuel for hard spectrum LWRs
… physical phenomena at high temperature and high burnup typically ignored in most LWR fuel performance codes can potentially become active under RBWR's operating conditions. These phenomena involve migration of fuel constituents and fission products, the evolution of O/M ratio with burnup, high …
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RFD-1, a 1-D, 4-group code to calculate burnup cycles using mechanical spectral shift
Increased conversion ratios and burnup can be achieved by mechanically changing the fuel-to-water volume ratio of a reactor over the core lifetime. As the fuel-to-water ratio decreases, the neutron spectrum softens, thereby increasing core reactivity. Proposed mechanical spectral shift reactors …
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Development of a Novel Fuel Burnup Methodology and Algorithm in RAPID and its Benchmarking and Automation
Fuel burnup calculations provide material concentrations and intrinsic neutron and gamma source strengths as a function of irradiation and cooling time. Detailed, full-core 3D burnup calculations are critical for nuclear fuel management studies, including core design and spent fuel storage safety …
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Effects of Thermal-Hydraulic Feedback on Burnup Modeling of the Deep Burn Modular High Temperature Reactor (DB-MHR)
Made available in DSpace on 2017-07-06T18:59:35Z (GMT). No. of bitstreams: 3 Ye_Bei_MS.pdf: 1045414 bytes, checksum: 5f391596dd3c9718291113127ba27c12 (MD5) Ye_Bei_MS_ABS.pdf: 26802 bytes, checksum: 8d516635e97ee4cb3df9cd653f65e18f (MD5) license.txt: 4813 bytes, checksum: …
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Analysis and Improvement of the bRAPID Algorithm and its Implementation
… presents a detailed analysis of the bRAPID (burnup for RAPID – Real Time Analysis for Particle transport and In-situ Detection) code system, and the implementation and validation of two new algorithms for improved burnup simulation. bRAPID is a fuel burnup algorithm capable of performing full …
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General analysis of breed-and-burn reactors and limited-separations fuel cycles
… need for a full core design, including minimum burnup/irradiation damage and reactor fleet doubling time. Two general configurations of B&B reactors are considered: a "minimum-burnup" version in which fuel elements can be shuffled in three dimensions, and a "linear-assembly" version composed of …
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The design of high power density annular fuel for LWRs
… than the current operating LWRs, and to a burnup of 80-100MWd/kgU. The models are used to optimize the fuel design so that it is able to achieve high power density and high burnup, and to identify the features of this fuel that will impact its operation limits. The annular fuel performance …
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Numerical simulation of nuclear reactor isotope depletion
… in Python to simulate nuclide reactions and burnup in a thermal fission reactor numerically. The program focused on the depletion calculations and used a simplified neutron flux equation. Nuclide data like cross-sections and fission products were read in from ENDF format files that have …
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Testing the EPRI reactivity depletion decrement uncertainty methods
… fuel assembly reactivity decrements versus burnup. The analytical techniques used to infer measured assembly reactivities required perturbation calculations using 3D nodal diffusion core models. Subsequently, questions have arisen within the Nuclear Regulatory Commission (NRC) as to …
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Monte Carlo study of pebble bed reactor fuel reactivity and isotopics
… and bumup isotopics for a cold 100 MWD/kgU burnup scenario. The results of these calculations showed that the methods employed in this thesis are in good agreement with work previously published regarding benchmarking of codes on LEUPRO-1: k-inf differences are generally less than 0.5%. The …
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Optimization of DUPIC cycle environmental and economic performance
… PWR fuel management practices in order to extend burnup in the CANDU portion of the cycle. A policy analysis regarding potential implementation of the DUPIC cycle in North America, between the U.S. and Canada, was also made. CASMO computer models of PWR, CANDU, and CANFLEX fuel assemblies were …
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Optimal initial fuel distribution in a thermal reactor for maximum energy production
Using the fuel burnup as objective function, it is desired to determine the initial distribution of the fuel in a reactor in order to obtain the maximum energy possible, for which, without changing a fixed initial fuel mass, the results for different initial fuel and control poison configurations …
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