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 36 for “"reactor power"”.
-
The energy analysis of burner reactor power systems
Currently most commercial nuclear power stations are based on thermal reactor designs called burner reactors which are. net consumers of fissile material. These power stations form one part of a larger system that generates electricity from uraniura. However, in addition to producing energy, such …
-
First-Flight Effects on Reactor Power Shapes and Neutron Leakage
Made available in DSpace on 2017-07-06T18:55:52Z (GMT). No. of bitstreams: 3 Polich_Timothy_J_MS.pdf: 24183567 bytes, checksum: 27f4e23c0cc79dba37c0833bbd66c606 (MD5) Polich_Timothy_J_MS_ABS.pdf: 453613 bytes, checksum: 2d8988ab0c50536bb28a23682aac29e3 (MD5) license.txt: 4813 bytes, checksum: …
-
Numerical Investigations of the Fluid Flow and Heat Transfer and Construction of Control System for the Canadian Supercritical Water-Cooled Reactor Power Plant
Canada participated in the Generation IV nuclear reactors with the Supercritical Water-Cooled Reactor (SCWR) concept. This work focuses on the numerical studies of the fluid flow and heat transfer of the supercritical water in the nuclear reactor fuel bundle, and the construction of the linear …
-
Quantifying measurement uncertainties of MIT Research Reactor's new digital nuclear safety system
Accurate measurement of reactor power is one of the most important requirements in order to ensure the reliable and safe operation of a nuclear reactor. The MIT research reactor, (MITR-II), currently has outdated analog reactor period and power monitoring instruments that are difficult to read and …
-
The Determination of the Thermal Neutron Flux in a Research Reactor
Since a research reactor serves as a neutron source for a large number of experiments, knowledge of the neutron flux, and of its spatial and spectral energy distribution is of great importance, not only for purposes of experimental reactor physics (e.g., determination of specific data with regard …
-
Sensitivity analysis of the secondary heat balance at Koeberg Nuclear Power Station
At Koeberg Nuclear Power Station, the reactor thermal power limit is one of the most important quantities specified in the operating licence, which is issued to Eskom by the National Nuclear Regulator (NNR). The reactor thermal power is measured using different methodologies, with the most …
-
Transient flow boiling CHF under exponentially escalating heat inputs
… (RIAs) are a potential concern for nuclear reactor safety. In RIA scenarios, following the insertion of positive reactivity, e.g. by an unanticipated extraction of the control rods, the reactor power may increase exponentially. The period of the exponential rise, τ, depends on the amount of …
-
PREDICTING ACTIVATION OF EXPERIMENTS INSIDE THE ANNULAR CORE RESEARCH REACTOR
… conducted inside of the Annular Core Research Reactor (ACRR) at Sandia National Laboratories and eliminate the need for users to write code. This estimation is achieved by using MCNP to model the neutron fluxes in the reactors central cavity where experiments are conducted using one of the four …
-
Development and evaluation of Nuclear-Renewable Hybrid Energy System simulator with load following
… enhance the operational flexibility of nuclear reactors to adapt to dynamic power demands. A dynamic simulation tool was developed for different nuclear reactor technologies, including Pressurized Water Reactors (PWR) and Molten Salt Reactors (MSR), enabling detailed analysis of reactor power …
-
Conceptual design of a lead-bismuth cooled fast reactor with in-vessel direct-contact steam generation
… of a lead-bismuth (Pb-Bi) cooled fast reactor that eliminates the need for steam generators and coolant pumps was explored. The working steam is generated by direct contact vaporization of water and liquid metal in the chimney above the core and then is sent to the turbine. The presence …
-
The effect of steam generator tube plugging on its overall thermal performance - A Systems CFD-Based Study
The steam generator in a pressurized water reactor power plant acts as a fission product barrier between primary and secondary system. Material failure of the tube bundle barrier could therefore lead to a release of radioactive product into the secondary side. Several repair methods have been used …
-
Control strategies for supercritical carbon dioxide power conversion systems
… recompression cycle is a promising advanced power conversion cycle which couples well to numerous advanced nuclear reactor designs. This thesis investigates the dynamic simulation of, control strategies for, and selected transient results for an indirect S-CO2 recompression cycle. The cycle …
-
Nuclear Computations under Uncertainty New methods to infer and propagate nuclear data uncertainty across Monte Carlo simulations
… infers the uncertainty in nuclear codes inputs (reactor geometry, nuclear data, etc.) from samples of noisy outputs (e.g. experimental observations), and in turn propagates this uncertainty back to the simulation outputs(reactor power, reaction rates, flux, multiplication factor, etc.), without …
-
Design and characterization of a strong positron source at the MSTR beam port
… purpose of this work is to design and optimize a reactor-based positron source at the Missouri University of Science and Technology Reactor (MSTR) beam port and quantify its intensity. Monte Carlo simulations using the MCNP6 code were used to model the positron production and moderation processes …
-
Exclusions Zones for Small Modular Reactors
… of the exclusion zone around a small modular reactor (SMR). The aim of such zone is to provide an atmospheric space sufficient to dilute any radioactive releases during an accident, to a level below the safe regulated radiation dose for the public. A hypothetical severe accident is considered …
-
Thermal hydraulic limits analysis for the MIT Research Reactor low enrichment uranium core conversion using statistical propagation of parametric uncertainties
The MIT Research Reactor (MITR) is evaluating the conversion from highly enriched uranium (HEU) to low enrichment uranium (LEU) fuel. In addition to the fuel element re-design from 15 to 18 plates per element, a reactor power upgraded from 6 MW to 7 MW is proposed in order to maintain the same …
-
Safety implications of a sensitivity analysis of the reactor kinetics parameters for fast breeder reactors
… was performed to study the sensitivity of the reactor power and power density to uncertainties in the delayed neutron spectra during a rod ejection accident. The generalised methodology, developed by Cacuci et. al., was used to derive a set of sensitivity derivatives. This method is based on …
-
Molten Regolith Electrolysis reactor modeling and optimization of in-situ resource utilization systems
… significant uncertainty as to the mass, power, and performance of such ISRU systems has prohibited a rigorous quantitative analysis. To this end, parametric sizing models of several ISRU systems are developed to better understand their mass, power, and performance. Special focus is given …
-
Experimental study of heat flux partitioning in pressurized subcooled flow boiling
… and profitability of pressurized water nuclear reactors since they are major factors in the determination of the reactor power rating. Motivated by the emergence of a new wall boiling model by Gilman [3] and previous experimental insights from Phillips [12], a first-of-a-kind experimental …
-
Feasibility Assessment of Adopting the ADDER Computer Code for the MIT Research Reactor Fuel Management
The Massachusetts Institute of Technology Reactor (MITR) is a 6 MW research reactor currently operating with highly enriched uranium (HEU) plate-type fuel. Fuel management calculations for this reactor are performed using MCODE, which allows for the coupling of a neutron transport code and a …
Page 1 of 2