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Articles 1 - 29 of 29

Full-Text Articles in Nuclear Engineering

Total System Performance Assessment Of The Proposed High Level Radioactive Waste Repository Site At Genting Island, Karimunjawa, Indonesia , Yudi Utomo Imardjoko Jan 1995

Total System Performance Assessment Of The Proposed High Level Radioactive Waste Repository Site At Genting Island, Karimunjawa, Indonesia , Yudi Utomo Imardjoko

Retrospective Theses and Dissertations

Indonesia is about to enter the nuclear era by building several nuclear power plants in the near future. Numerous issues must be addressed to evaluate the impact on the environment of high-level radioactive waste (HLRW) generated by these plants. This consideration of HLRW management must be done in a timely manner;This dissertation discusses the methodology for the Genting repository site development plan. The approach to the development of the repository is divided into three main areas, the inventory of HLRW, the barrier systems (natural and engineered), and the physical conditions of the site. The radionuclide inventory and waste form ...


Performance Assessment Modeling Of Alternative High Level Nuclear Wasteforms , William Mark Nutt Jan 1995

Performance Assessment Modeling Of Alternative High Level Nuclear Wasteforms , William Mark Nutt

Retrospective Theses and Dissertations

Performance assessment (PA) analyses have been completed for high level nuclear waste forms derived from once through Light Water Reactor (LWR) spent fuel (SF), defense high level waste (DHLW), the closed advanced liquid metal reactor (ALMR) pyroprocess fuel cycle, and the front end processing of LWR spent fuel for possible recycling of the actinides in the closed ALMR fuel cycle. The IMARC (Integrated Multiple Assumptions and Release Calculations) and RIP (Repository Integration Program) PA tools were utilized to predict the performance of these wasteforms for emplacement in the proposed Yucca Mountain Repository;A model was developed to predict the time ...


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.


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.


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.


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.


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 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.


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 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.


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.


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.


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.


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.


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.


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.


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.