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Full-Text Articles in Nuclear Engineering

Nuclear Security Education At Pakistan Institute Of Engineering And Applied Sciences (Pieas): Current Status, Future Prospects And The Lessons Learnt, Tariq Majeed Dr. Nov 2016

Nuclear Security Education At Pakistan Institute Of Engineering And Applied Sciences (Pieas): Current Status, Future Prospects And The Lessons Learnt, Tariq Majeed Dr.

International Journal of Nuclear Security

In this paper, the details of nuclear security education at Pakistan Institute of Engineering and Applied Sciences (PIEAS) have been discussed. Nuclear Security education was initiated at PIEAS as a sub-specialty of its MS Nuclear Engineering Program in October 2009. Two courses, Nuclear Security (NE-581) and Physical Protection Systems (NE-582) have been offered on regular basis in the 3rd and 4th semesters. To date, 72 students have been graduated with this sub-specialty. The most important lesson learnt is that introduction of nuclear security related courses in nuclear engineering program has opened up new venues of applications of nuclear ...


Developing Professional Skills In Stem Students: Data Information Literacy, Lisa Zilinski, Megan R. Sapp Nelson, Amy S. Van Epps Dec 2014

Developing Professional Skills In Stem Students: Data Information Literacy, Lisa Zilinski, Megan R. Sapp Nelson, Amy S. Van Epps

Lisa Zilinski

Undergraduate STEM students are increasingly expected to have some data use skills upon graduation, whether they pursue post-graduate education or move into industry. This project was an initial foray into the application of data information literacy competencies to training undergraduate students to identify markers of data and information quality. The data consumer training appeared within two courses to help students evaluate data objects, including databases and datasets available on the Internet. The application of the Data Credibility Checklist provides a foundation for developing data reuse competencies. Based upon the initial presentation of the content, it became obvious that students need ...


Developing Professional Skills In Stem Students: Data Information Literacy, Lisa Zilinski, Megan R. Sapp Nelson, Amy S. Van Epps Sep 2014

Developing Professional Skills In Stem Students: Data Information Literacy, Lisa Zilinski, Megan R. Sapp Nelson, Amy S. Van Epps

Libraries Faculty and Staff Scholarship and Research

Undergraduate STEM students are increasingly expected to have some data use skills upon graduation, whether they pursue post-graduate education or move into industry. This project was an initial foray into the application of data information literacy competencies to training undergraduate students to identify markers of data and information quality. The data consumer training appeared within two courses to help students evaluate data objects, including databases and datasets available on the Internet. The application of the Data Credibility Checklist provides a foundation for developing data reuse competencies. Based upon the initial presentation of the content, it became obvious that students need ...


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 ...


Nuclear Plant Diagnostics Using Neural Networks With Dynamic Input Selection , Anujit Basu Jan 1995

Nuclear Plant Diagnostics Using Neural Networks With Dynamic Input Selection , Anujit Basu

Retrospective Theses and Dissertations

The work presented in this dissertation explores the design and development of a large scale nuclear power plant (NPP) fault diagnostic system based on artificial neural networks (ANNs). The viability of detecting a large number of transients in a NPP using ANNs is demonstrated. A new adviser design is subsequently presented where the diagnostic task is divided into component parts, and each part is solved by an individual ANN. This new design allows the expansion of the diagnostic capabilities of an existing adviser by modifying the existing ANNs and adding new ANNs to the adviser;This dissertation also presents an ...


Modeling X-Ray Scattering Process And Applications Of The Scattering Model , Taher Lutfi Al-Jundi Jan 1995

Modeling X-Ray Scattering Process And Applications Of The Scattering Model , Taher Lutfi Al-Jundi

Retrospective Theses and Dissertations

Computer modeling of nondestructive inspections with x-rays is proving to be a very useful tool for enhancing the performance of these techniques. Two x-ray based inspection techniques are considered in this study. The first is "Radiographic Inspection", where an existing simulation model has been improved to account for scattered radiation effects. The second technique is "Inspection with Compton backscattering", where a new simulation model has been developed;The effect of scattered radiation on a simulated radiographic image can be insignificant, equally important, or more important than the effect of the uncollided flux. Techniques to account for the scattered radiation effects ...


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 ...


Reliability Assessment Of Nuclear Power Plant Fault-Diagnostic Systems Using Artificial Neural Networks , Keehoon Kim Jan 1994

Reliability Assessment Of Nuclear Power Plant Fault-Diagnostic Systems Using Artificial Neural Networks , Keehoon Kim

Retrospective Theses and Dissertations

The assurance of the diagnosis obtained from a nuclear power plant (NPP) fault-diagnostic advisor based on artificial neural networks (ANNs) is essential for the practical implementation of the advisor to transient detection and identification. The objectives of this study are to develop a validation and verification technique suitable for ANNs and apply it to the fault-diagnostic advisor. The validation and verification is realized by estimating error bounds on the advisor's diagnoses. The two different partition criteria are developed to create computationally effective partitions for generating the error information associated with the advisor performance. The bootstap partition criterion (BPC) and ...


Knowledge Base Expert System Control Of Spatial Xenon Oscillations In Pressurized Water Reactors , Serhat Alten Jan 1992

Knowledge Base Expert System Control Of Spatial Xenon Oscillations In Pressurized Water Reactors , Serhat Alten

Retrospective Theses and Dissertations

Nuclear reactor operators are required to pay special attention to spatial xenon oscillations during the load-follow operation of pressurized water reactors. They are expected to observe the axial offset of the core, and to estimate the correct time and amount of necessary control action based on heuristic rules given in axial offset control strategies;Current control methods of axial xenon oscillations are knowledge intensive, and heuristic in nature. An expert system, ACES (Axial offset Control using Expert Systems) is developed to implement a heuristic constant axial offset control procedure to aid reactor operators in increasing the plant reliability by reducing ...


Design Of An Expert System For Failed Fuel Identification And Surveillance In Ebr-Ii , Ramin Mikaili Jan 1990

Design Of An Expert System For Failed Fuel Identification And Surveillance In Ebr-Ii , Ramin Mikaili

Retrospective Theses and Dissertations

Since 1977, a program has been underway at experimental breeder reactor-II (EBR-II) to evaluate the performance of metal and mixed-oxide liquid metal reactor (LMR) fuel elements after clad failure (breach). The motivation for this activity, called run beyond cladding breach (RBCB) testing, is to continue safe operation of EBR-II after occurrence of a single or multiple clad failures. Principal safety concerns are excessive release of fission gas (FG) and mixed-oxide fuel/sodium interaction, which result in release of by-products to the sodium and may result in blockage of coolant flow. Excessive release of FG is controlled by the cover gas ...


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.