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Articles 1 - 30 of 53

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.


Engineering And Safety Analysis Of Dual-Purpose Nuclear Desalination Plants: A Case Study (Saudi Arabia) , Abdul-Rahman Ahmed-Foad Abdul-Fattah Jan 1978

Engineering And Safety Analysis Of Dual-Purpose Nuclear Desalination Plants: A Case Study (Saudi Arabia) , Abdul-Rahman Ahmed-Foad Abdul-Fattah

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.


Containment Systems For Storage Of Solidified High-Level Radioactive Wastes In Bedded Salt Deposits , Terence Joseph Sullivan Jan 1972

Containment Systems For Storage Of Solidified High-Level Radioactive Wastes In Bedded Salt Deposits , Terence Joseph Sullivan

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.


Performance Characteristics For Optimized Core Module Of Liquid Metal Fast Breeder Reactor , Satoshi Minakuchi Jan 1972

Performance Characteristics For Optimized Core Module Of Liquid Metal Fast Breeder Reactor , Satoshi Minakuchi

Retrospective Theses and Dissertations

No abstract provided.


Analysis Of Burnup Effect On Thermal Conductivity Of Uo2 During Irradiation , Chern Hwa Tsai Jan 1971

Analysis Of Burnup Effect On Thermal Conductivity Of Uo2 During Irradiation , Chern Hwa Tsai

Retrospective Theses and Dissertations

No abstract provided.


Preparation Of Uranium Metal And Dense Uo2 Shapes By The Carbon Reduction Of U3o8 , James Keith Mcclusky Jan 1971

Preparation Of Uranium Metal And Dense Uo2 Shapes By The Carbon Reduction Of U3o8 , James Keith Mcclusky

Retrospective Theses and Dissertations

No abstract provided.


Thermal, Radiation And Mechanical Analysis Of Cylindrical Oxide Fuel Elements Of Fast Reactor In Unsteady State , Chi-Kang Cheng Jan 1970

Thermal, Radiation And Mechanical Analysis Of Cylindrical Oxide Fuel Elements Of Fast Reactor In Unsteady State , Chi-Kang Cheng

Retrospective Theses and Dissertations

No abstract provided.


Simulation Of Heated Effluent Dispersion In An Open Channel , James Robert Bull Jan 1970

Simulation Of Heated Effluent Dispersion In An Open Channel , James Robert Bull

Retrospective Theses and Dissertations

No abstract provided.


Applications Of Heat Pipes To Nuclear Reactor Engineering , Monte Bryce Parker Jan 1970

Applications Of Heat Pipes To Nuclear Reactor Engineering , Monte Bryce Parker

Retrospective Theses and Dissertations

No abstract provided.


Applications Of Optimal Control Theory To Space-Time Reactor Kinetics , Steven Robert Specker Jan 1970

Applications Of Optimal Control Theory To Space-Time Reactor Kinetics , Steven Robert Specker

Retrospective Theses and Dissertations

No abstract provided.


Spatially Dependent Stochastic Behaviour Of Coupled Core Reactors , Mohamed El-Sayed Nagy Jan 1970

Spatially Dependent Stochastic Behaviour Of Coupled Core Reactors , Mohamed El-Sayed Nagy

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.