Index Catalog // ScholarsArchive@OSU

Cost-Benefit Analysis : Proposed Safety Upgrades to Currently Operating Nuclear Power Plants

Creator:: Jordahl, Jonathan T.
Abstract:: In the wake of nuclear accidents such as Three Mile Island Unit 2 and Fukushima, the nuclear power industry’s safety record is scrutinized. Today the main concerns lies with hydrogen production in a nuclear reactor core when the zirconium fuel cladding reacts with the water coolant during an accident, creating...
Resource Type:: Masters Thesis
Full Text:: Engineering presented on September 13, 2016. Title: Cost-Benefit Analysis: Proposed Safety Upgrades to

Absorption of methyl iodide by aqueous hydrazine solutions within spray chambers

Creator:: Postma, A. K.
Abstract:: Absorption of methyl iodide by aqueous hydrazine solutions within spray chambers was studied theoretically and experimentally. The objective of this work was to evaluate the absorption rate of airborne methyl iodide by sprays of hydrazine solutions under conditions expected to exist in post-accident nuclear reactor containment atmospheres. Experimental effort included...
Resource Type:: Dissertation
Full Text:: consequences in nuclear power plants is very low, safety facilities have been incorporated into reactor

Chemical analysis for boron in nuclear reactor coolant water

Creator:: McDaniel, Dawn Marie
Resource Type:: Masters Thesis
Full Text:: : Chemical Analysis for Boron in Nuclear Reactor Coolant Water Signature redacted for privacy. John C

Simulated antineutrino signatures of nuclear reactors for nonproliferation applications

Creator:: Misner, Alex C.
Abstract:: Antineutrino detectors could provide a valuable addition to current safeguards regimes. Antineutrinos are an attractive emission to monitor due to their low interaction cross-section that prevents them from being shielded and the dependence of their spectrum on the power level and isotopic content of a reactor core. While there are...
Resource Type:: Dissertation
Full Text:: reactor, such observations cannot predict the effect of the diversion of nuclear material on the

High pressure condensation heat transfer in the evacuated containment of a small modular reactor

Creator:: Casey, Jason R.
Abstract:: At Oregon State University the Multi-Application Small Light Water Reactor (MASLWR) integral effects testing facility is being prepared for safety analysis matrix testing in support of the NuScale Power Inc. (NSP) design certification progress. The facility will be used to simulate design basis accident performance of the reactor's safety systems....
Resource Type:: Masters Thesis
Full Text:: Nuclear Regulatory Commission SMR Small Modular Reactor NSSS Nuclear Steam Supply System LOCA Loss of

Routine and post-accident analysis of nuclear power plant reactor coolant

Creator:: Jolma, Eva I.
Abstract:: The 1979 incident at Three Mile Island drew attention to weaknesses in the capability to obtain and analyze reactor coolant samples in an environment where the reactor core incurs significant damage. As a result, the U.S. Nuclear Regulatory Commission promulgated regulations requiring that reactor coolant analytical capabilities be upgraded so...
Resource Type:: Masters Thesis
Full Text:: research effort. Routine and Post-Accident Analysis of Nuclear Power Plant Reactor Coolant by Eva I

Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

Creator:: Lenhof, Renae
Abstract:: A limited scope Probabilistic Risk Assessment (PRA) of a vented nuclear fuel system for a Generation IV Gas-Cooled Fast Reactor Plant was performed. The goal of the study was to better understand the safety and licensing implications of vented fuel technology. A Level 1 PRA was performed to determine the...
Resource Type:: Masters Thesis
Full Text:: Utilized in a Generation IV Gas-Cooled Fast Reactor Nuclear Power Plant AN ABSTRACT OF THE

Flow Dynamics and Condensation of Film Flows in Small Modular Reactors

Creator:: Lee, Dongyoung
Abstract:: There is renewed interest in the reliability and safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9 magnitude earthquake and Tsunami with the height of 15 m on March 11, 2011. Small Modular Reactors (SMRs) have been developed to improve safety systems by utilizing passive...
Resource Type:: Dissertation
Full Text:: safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9

An investigative approach to study the RETRAN modeling concepts in the analysis of a safety valve discharge transient

Creator:: Youssefnia, Mohammad Hossein
Abstract:: This study focuses on investigation of the RETRAN modeling concepts in the analysis of a safety valve discharge transient. Three safety valve tests conducted at the Combustion Engineering test facility were chosen for evaluation with RETRAN. It was essential to apply the critical flow boundary condition at the downstream nodes...
Resource Type:: Dissertation
Full Text:: measure incorporated in the design of reactor safety systems, further pressure relief is also provided

Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactors

Creator:: Al-Kheliewi, Abdullah S.
Abstract:: A transient code (TFETC) for calculating the temperature distribution throughout the radial and axial positions of a thermionic fuel element (TFE) has been successfully developed. It accommodates the variations of temperatures, thermal power, electrical power, voltage, and current density throughout the TFE as a function of time as well as...
Resource Type:: Dissertation
Full Text:: Figure Page 1.1 SNAP-10 Nuclear Space Reactor 2 1.2 SP-100 Nuclear Space Reactor Configuration

ScholarsArchive@OSU

Cost-Benefit Analysis : Proposed Safety Upgrades to Currently Operating Nuclear Power Plants

Absorption of methyl iodide by aqueous hydrazine solutions within spray chambers

Chemical analysis for boron in nuclear reactor coolant water

Simulated antineutrino signatures of nuclear reactors for nonproliferation applications

High pressure condensation heat transfer in the evacuated containment of a small modular reactor

Routine and post-accident analysis of nuclear power plant reactor coolant

Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

Flow Dynamics and Condensation of Film Flows in Small Modular Reactors

An investigative approach to study the RETRAN modeling concepts in the analysis of a safety valve discharge transient

Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactors

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