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Filtering by: Subject Nuclear reactors -- Safety measures -- Cost effectiveness Remove constraint Subject: Nuclear reactors -- Safety measures -- Cost effectiveness Non-Academic Affiliation Oregon State University. Graduate School Remove constraint Non-Academic Affiliation: Oregon State University. Graduate School

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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

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Figure Page 1.1 SNAP-10 Nuclear Space Reactor 2 1.2 SP-100 Nuclear Space Reactor Configuration

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Academic Affiliation

Nuclear Engineering and Radiation Health Physics10
Nuclear Engineering2
Chemical Engineering1
Chemistry1
General Science1
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Advisor

Klein, Andrew C.4
Wu, Qiao3
Woods, Brian G.2
Binney, Stephen E.1
Johnson, Arthur G.1
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Commencement Year

Commencement Year range begin – Commencement Year range end

Current results range from 1970 to 2017

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Committee Member

Marcum, Wade R.4
Woods, Brian G.3
Klein, Andrew2
Krane, Kenneth2
Palmer, Todd S.2
more Committee Members »

Creator

Al Kheliewi, Abdullah S.1
Bowser, Christopher Jordan1
Casey, Jason R.1
Castaneda, Juan A.1
Hallee, Brian Todd1
more Creators »

Date

Date range begin – Date range end

Current results range from 1970 to 2016

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Decade

2010-20198
2000-20092
1990-19991
1980-19893
1970-19791

Degree Field

Nuclear Engineering12
Chemical Engineering1
Chemistry1
General Science1

Degree Level

Master's10
Doctoral5

Degree Name

Master of Science (M.S.)10
Doctor of Philosophy (Ph.D.)5

File Format

application/pdf1

Language

English [eng]15

License

All rights reserved10

Non-Academic Affiliation

Oregon State University. Graduate School[remove]15

Peer Reviewed

No15

Resource Type

Masters Thesis10
Dissertation5

Rights Statement

In Copyright10
Copyright Not Evaluated5

Subject

Nuclear reactors -- Safety measures5
Nuclear reactors -- Containment4
Light water reactors -- Safety measures3
Condensation2
Nuclear reactors -- Fluid dynamics2
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