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Articles 1 - 27 of 27

Full-Text Articles in Nuclear Engineering

Use Of The Local-Global Concept In Detecting Component Vibration In Reactors , Mansur A. Al-Ammar Jan 1981

Use Of The Local-Global Concept In Detecting Component Vibration In Reactors , Mansur A. Al-Ammar

Retrospective Theses and Dissertations

The local-global concept, based on the detector adjoint function, was used to develop the response of a detector to an absorber vibrating in one dimension. A one-dimensional two-group diffusion code was developed to calculate the frequency dependent detector response as a function of detector and absorber positions for the coupled-core UTR-10 reactor. Results from this code indicated the best possible detector and absorber locations, where more detailed calculations were made using a two-group, three-dimensional diffusion code with finite detector and absorber volumes. An experiment was then designed, for the chosen positions, using a vibrating cadmium absorber with a detector on ...


Perturbation Theory In Nuclear Fuel Management Optimization , Li-Wei Ho Jan 1981

Perturbation Theory In Nuclear Fuel Management Optimization , Li-Wei Ho

Retrospective Theses and Dissertations

Nuclear in-core fuel management involves all the physical aspects which allow optimal operation of the nuclear fuel within the reactor core. In most nuclear power reactors, fuel loading patterns which have a minimum power peak are economically desirable to allow the reactors to operate at the highest power density and to minimize the possibility of fuel failure;In this study, perturbation theory along with a binary fuel shuffling technique is applied to predict the effects of various core configrations, and hence, the optimization of in-core fuel management. The computer code FULMNT has been developed to shuffle the fuel assemblies in ...


Two-Phase Flow Characterization Using Reactor Noise Techniques , Mikdam Mahmood Saleh Jan 1980

Two-Phase Flow Characterization Using Reactor Noise Techniques , Mikdam Mahmood Saleh

Retrospective Theses and Dissertations

No abstract provided.


Development And Application Of A Formal Methodology For The Selection Of Fusion Energy Options , Rasool Kenarangui Jan 1980

Development And Application Of A Formal Methodology For The Selection Of Fusion Energy Options , Rasool Kenarangui

Retrospective Theses and Dissertations

No abstract provided.


A Toroidal Fusion Reactor Design Based On The Reversed-Field Pinch , Randy Lee Hagenson Jan 1978

A Toroidal Fusion Reactor Design Based On The Reversed-Field Pinch , Randy Lee Hagenson

Retrospective Theses and Dissertations

No abstract provided.


Interpretation Of Neutron Noise Spectra Measured In The Presence Of Fluctuating Voids , Massoud Nabavian Jan 1977

Interpretation Of Neutron Noise Spectra Measured In The Presence Of Fluctuating Voids , Massoud Nabavian

Retrospective Theses and Dissertations

No abstract provided.


Detection Of Void Fluctuations In Reactor Coolant Channels By Neutron Noise Analysis , Jerry Tong-Huei Lu Jan 1976

Detection Of Void Fluctuations In Reactor Coolant Channels By Neutron Noise Analysis , Jerry Tong-Huei Lu

Retrospective Theses and Dissertations

No abstract provided.


The Formulation And Analysis Of The Nine-Point Finite Difference Approximation For The Neutron Diffusion Equation In Cylindrical Geometry , Hamza Khudhair Al-Dujaili Jan 1975

The Formulation And Analysis Of The Nine-Point Finite Difference Approximation For The Neutron Diffusion Equation In Cylindrical Geometry , Hamza Khudhair Al-Dujaili

Retrospective Theses and Dissertations

No abstract provided.


Reactor Anomaly Detection Based On Noise Analysis , George William Hannaman Jr. Jan 1974

Reactor Anomaly Detection Based On Noise Analysis , George William Hannaman Jr.

Retrospective Theses and Dissertations

No abstract provided.


Measurement Of Transient Critical Heat Flux By Fluid Modeling , Tien-Dun Shih Jan 1974

Measurement Of Transient Critical Heat Flux By Fluid Modeling , Tien-Dun Shih

Retrospective Theses and Dissertations

No abstract provided.


Neutron Penetration Using The Transfer Matrix Method , Te-Chang Chan Jan 1974

Neutron Penetration Using The Transfer Matrix Method , Te-Chang Chan

Retrospective Theses and Dissertations

No abstract provided.


Application Of Differential Dynamic Programming To Nuclear Fuel Management Optimization , Larry Edgar Fennern Jan 1974

Application Of Differential Dynamic Programming To Nuclear Fuel Management Optimization , Larry Edgar Fennern

Retrospective Theses and Dissertations

No abstract provided.


Effects Of Distortion In A River Model For Temperature Prediction , Yau-Ming Chien Jan 1973

Effects Of Distortion In A River Model For Temperature Prediction , Yau-Ming Chien

Retrospective Theses and Dissertations

No abstract provided.


Prediction Of Reactor Coolant Blowdown By Similitude Theory , Dug Kwang Choi Jan 1973

Prediction Of Reactor Coolant Blowdown By Similitude Theory , Dug Kwang Choi

Retrospective Theses and Dissertations

No abstract provided.


Study Of Ames Laboratory Research Reactor Physics Characteristics By Few Group Design Techniques , Joseph Samuel Crudele Jan 1973

Study Of Ames Laboratory Research Reactor Physics Characteristics By Few Group Design Techniques , Joseph Samuel Crudele

Retrospective Theses and Dissertations

No abstract provided.


Delayed Neutron Emission From Mass-Separated Fission Products , Jay Harold Norman Jan 1973

Delayed Neutron Emission From Mass-Separated Fission Products , Jay Harold Norman

Retrospective Theses and Dissertations

No abstract provided.


Prediction Of Heated Effluent Dispersion In A Stream Using Similitude Techniques , Max Myron Delong Jan 1972

Prediction Of Heated Effluent Dispersion In A Stream Using Similitude Techniques , Max Myron Delong

Retrospective Theses and Dissertations

No abstract provided.


The Response Of A Coupled Core Reactor To A Localized Oscillation Of The Absorption Cross Section , Walter Charles Nodean Jan 1969

The Response Of A Coupled Core Reactor To A Localized Oscillation Of The Absorption Cross Section , Walter Charles Nodean

Retrospective Theses and Dissertations

No abstract provided.


Weight Optimization Of Reactor Shielding Using Transmission Matrix Methods , William Dale Leech Jan 1969

Weight Optimization Of Reactor Shielding Using Transmission Matrix Methods , William Dale Leech

Retrospective Theses and Dissertations

No abstract provided.


Preliminary Design And Feasibility Study Of A Nuclear-Powered Agro-Industrial Complex In Iran , Ebrahim Jalali-Mossallam Jan 1969

Preliminary Design And Feasibility Study Of A Nuclear-Powered Agro-Industrial Complex In Iran , Ebrahim Jalali-Mossallam

Retrospective Theses and Dissertations

No abstract provided.


Green's Function Formulation Of Laplace Transformed Multigroup Diffusion Equations , Michael Richard Ringham Jan 1969

Green's Function Formulation Of Laplace Transformed Multigroup Diffusion Equations , Michael Richard Ringham

Retrospective Theses and Dissertations

No abstract provided.


Electron Transport Theory Using Methods Of Invariant Imbedding , Robert Jay Barrett Jan 1968

Electron Transport Theory Using Methods Of Invariant Imbedding , Robert Jay Barrett

Retrospective Theses and Dissertations

No abstract provided.


Spatially Dependent Frequency Response Of Coupled Core Reactors , Ira Wilson Merritt Jr. Jan 1968

Spatially Dependent Frequency Response Of Coupled Core Reactors , Ira Wilson Merritt Jr.

Retrospective Theses and Dissertations

No abstract provided.


Applications Of The Transmission Matrix Method To Neutron And Gamma Transport , Ervin Thomas Boulette Jan 1968

Applications Of The Transmission Matrix Method To Neutron And Gamma Transport , Ervin Thomas Boulette

Retrospective Theses and Dissertations

No abstract provided.


Application Of Invariant Imbedding To Radiation Transport Theory , John Lou Ridihalgh Jan 1968

Application Of Invariant Imbedding To Radiation Transport Theory , John Lou Ridihalgh

Retrospective Theses and Dissertations

No abstract provided.


Analysis Of Coupled Core Reactors Using The Natural Mode Approximation , Joaquin Manuel Betancourt Jan 1968

Analysis Of Coupled Core Reactors Using The Natural Mode Approximation , Joaquin Manuel Betancourt

Retrospective Theses and Dissertations

No abstract provided.


Design Of A Marine Nuclear Power Plant Utilizing The Direct Brayton Cycle , Bruce Stephen Gathy Jan 1967

Design Of A Marine Nuclear Power Plant Utilizing The Direct Brayton Cycle , Bruce Stephen Gathy

Retrospective Theses and Dissertations

No abstract provided.