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Nuclear Engineering Commons

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Nuclear engineering

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Articles 31 - 60 of 75

Full-Text Articles in Nuclear Engineering

Formulation And Analysis Of Higher Order Finite Difference Approximations To The Neutron Diffusion Equation , Mohammed Benghanem Jan 1986

Formulation And Analysis Of Higher Order Finite Difference Approximations To The Neutron Diffusion Equation , Mohammed Benghanem

Retrospective Theses and Dissertations

Analyses have been made of the truncation error for the following finite difference approximations to the eigenvalue and boundary value problems evolving from the one-group neutron diffusion equation: (i) The seven-point relation; (ii) The fifteen-point relation; (iii) The nineteen-point relation; and (iv) The twenty-seven point relation. These methods have been derived using a Taylor series expansion technique and applied to the Laplacian operator contained in that equation in (x,y,z) geometry for various reactor configurations and boundary conditions;It has been shown that for methods ii and iii, a 4th order truncation error can be achieved, whereas for the ...


Energy Balance Calculations For A Multipole Target Plasma Fusion Reactor , Terry Edwin Dix Jan 1985

Energy Balance Calculations For A Multipole Target Plasma Fusion Reactor , Terry Edwin Dix

Retrospective Theses and Dissertations

Thermonuclear fusion reactors have not yet achieved breakeven; high plasma temperatures are required to obtain high reaction rates. Accompanying the high plasma temperatures are high bremsstrahlung radiation losses, plasma instabilities, first wall problems and large amounts of energy for plasma containment. To reduce the detrimental effects and maintain high reaction rates, a two component target plasma system was proposed with one of the fuel species acting as a target plasma magnetically confined at a relatively low temperature. The second fuel species is then injected at high energy into the target plasma to interact with the confined plasma as it slows ...


Reliability Analysis For The Emergency Power System Of A Pressurized Water Reactor Facility During A Loss Of Offsite Power Transient , See-Meng Wong Jan 1984

Reliability Analysis For The Emergency Power System Of A Pressurized Water Reactor Facility During A Loss Of Offsite Power Transient , See-Meng Wong

Retrospective Theses and Dissertations

The anticipated transient involving loss of offsite power has been identified as a major potential contributor of risk for a pressurized water reactor power generating facility. The capability of the emergency power system to supply adequate power to engineering safety systems is important for limiting the progression of the transient event and avoiding reactor core degradation;The evaluation of emergency power system reliability, using probabilistic risk assessment techniques with updated failure data, shows that the unavailability of this system is significantly higher than had been assessed earlier. The significant contributors to system unavailability are diesel generator operability problems, particularly when ...


Quantitative Assessment Of Human Contribution To Risk In Nuclear Power Plants , Abdallah Ahmad Ezzedin Jan 1983

Quantitative Assessment Of Human Contribution To Risk In Nuclear Power Plants , Abdallah Ahmad Ezzedin

Retrospective Theses and Dissertations

It is known from operation history of nuclear power plants (NPPs) that human factors considerations and human reliability analysis (HRA) are necessary for complete safety analysis of NPPs. HRA is usually performed to estimate the influence of human errors on the unavailability of various safety systems of NPPs;The objective of this work is to assess quantitatively the human contribution to the unavailability of those safety systems involved in the S(,2)C accident sequence. S(,2)C sequence is defined as a small loss of coolant accident (LOCA) and core meltdown after containment failure. This sequence is selected for ...


The Effect Of Rare-Earth Element Additions On Microstructural Properties And Irradiation Behavior Of An Fe-Ni-Cr Alloy For Lmfbr And Fusion Reactor Applications , Jin-Young Park Jan 1983

The Effect Of Rare-Earth Element Additions On Microstructural Properties And Irradiation Behavior Of An Fe-Ni-Cr Alloy For Lmfbr And Fusion Reactor Applications , Jin-Young Park

Retrospective Theses and Dissertations

This study consists of a survey of the effect of yttrium, lanthanum, and cerium rare-earth additions on the microstructure and radiation swelling behavior of an Fe-25.6Ni-8.7Cr-3.3Ti-1.6Al alloy. The undoped alloy was investigated in the as-received, annealed, and arc-melted conditions, and twelve arc melted and rare-earth doped alloys were prepared (doping levels of 0.05, 0.1, 0.5, and 1.0 wt % for each of the three rare earths). The ion bombardments were carried out at 570 and 600(DEGREES)C with 4 MeV Ni or Fe ions to nominal 100 dpa and to 100 and ...


Analysis Of The Nine-Point Finite Difference Approximation For The Heat Conduction Equation In A Nuclear Fuel Element , Mohamed Kadri Jan 1983

Analysis Of The Nine-Point Finite Difference Approximation For The Heat Conduction Equation In A Nuclear Fuel Element , Mohamed Kadri

Retrospective Theses and Dissertations

The time dependent heat conduction equation in the x-y Cartesian geometry is formulated in terms of a nine-point finite difference relation using a Taylor series expansion technique. The accuracy of the nine-point formulation over the five-point formulation has been tested and evaluated for various reactor fuel-cladding plate configurations using a computer program. The results have been checked against analytical solutions for various model problems;The following cases were considered in the steady-state condition: (a) The thermal conductivity and the heat generation were uniform. (b) The thermal conductivity was constant, the heat generation variable. (c) The thermal conductivity varied linearly with ...


Development And Application Of A Decision Methodology For The Planning Of Nuclear Research And Development In Saudi Arabia , Waleed Hussain Abulfaraj Jan 1983

Development And Application Of A Decision Methodology For The Planning Of Nuclear Research And Development In Saudi Arabia , Waleed Hussain Abulfaraj

Retrospective Theses and Dissertations

The present study involves adapting two formal decision methodologies to the selection of alternative nuclear energy strategies. Multiattribute utility theory and fuzzy set theory are selected to accommodate for decision makers' preferences and for imprecisions in evaluation of factors impacting a decision, respectively;Multiattribute Utility theory (MAU) is here employed to evaluate four appropriate research reactor facilities to determine the optimal choice in order to meet the needs of Saudi Arabia. These facilities are similar to University of Michigan Ford Nuclear Reactor (FNR), Massachusetts Institute of Technology Reactor (MITR), Georgia Institute of Technology Research Reactor (GTRR), and University of Wisconsin ...


Simulation Of Plenum Thermo-Hydraulics In A Liquid Metal Fast Breeder Reactor Under A Buoyancy-Affected Condition , Min-Jen Chen Jan 1983

Simulation Of Plenum Thermo-Hydraulics In A Liquid Metal Fast Breeder Reactor Under A Buoyancy-Affected Condition , Min-Jen Chen

Retrospective Theses and Dissertations

The thermohydraulics of the LMFBR upper plenum under buoyancy - affected condition has been investigated. It was found that under low flow, thermal stratified conditions, reduced-scale sodium simulation cannot accurately predict the full-scale LMFBR upper plenum behavior. However, water is an adequate test fluid for prediction of full-scale LMFBR thermohydraulic behavior. It was also found that the threshold Peclet number above which convection dominates the heat transfer is about 10;A three-dimensional transient computer code PLENMIX which is a simplified version of COMMIX-1A has been used for the analysis. It was found that the PLENMIX code can accurately predict temperature transients ...


Analysis And Modeling Of Human Performance In Nuclear Power Plants , Abdel-Mohsen Morsy Metwally Jan 1982

Analysis And Modeling Of Human Performance In Nuclear Power Plants , Abdel-Mohsen Morsy Metwally

Retrospective Theses and Dissertations

This work investigates two important areas in human reliability engineering: models for human performance analysis, and reliable data for these models. In the first area, the author addresses the two modeling techniques "THERP" and "SAINT" showing that the flexibility and nuclear relevance of the second give it the merit to be used in modeling and analyzing human tasks in complex man-machine systems such as nuclear systems. A case study is investigated and simulated by the "SAINT" to explore its dynamic capabilities;In the second area, the author evaluates all the available human data sources, develops a new description format for ...


Assessment Of The Impact Of Fueling Machine Failure On The Safety Of Candu-Phwr, Tawfik Ahmed Al-Kusayer Jan 1982

Assessment Of The Impact Of Fueling Machine Failure On The Safety Of Candu-Phwr, Tawfik Ahmed Al-Kusayer

Retrospective Theses and Dissertations

A survey of possible LOCA (Loss-of-Coolant Accident) initiating events that might take place for CANDU-PHWRs (Canadian Deuterium Uranium-Pressurized Heavy Water Reactors) has been conducted covering both direct and indirect initiators. Among the 22 initiating events that were surveyed in this study, four direct initiators have been selected and analyzed briefly. Those selected were a pump suction piping break, an isolation valve piping break, a bleed valve failure, and a fueling machine interface failure. These were selected as examples of failures that could take place in the inlet side, outlet side, or PHTS (Primary Heat Transport System) interfaces. The Pickering NGS ...


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 ...


Reliability And System Analysis Of Nuclear Desalination Plants Based On Operation Experience , Ibrahim Ismail Kutbi Jan 1981

Reliability And System Analysis Of Nuclear Desalination Plants Based On Operation Experience , Ibrahim Ismail Kutbi

Retrospective Theses and Dissertations

The prospects of using nuclear energy in Saudi Arabia for desalination and electric power generation represent a challenging engineering problem. Three specific issues have been considered for a dual-purpose plant, namely: (1) Impact of the availability and reliability of the desalination plants, (2) Integration of the desalination and power production stages, and, (3) Safety considerations of dual systems;The operational history data of the Jeddah desalination plants are studied, to determine the reliability of a multi-stage flash (MSF) desalination plant and of a reverse osmosis plant (RO);MSF plant performance, operation conditions, and the most common causes of deviation from ...


Development And Application Of A Methodology For The Analysis Of Significant Human Related Event Trends In Nuclear Power Plants , Hang Youn Cho Jan 1981

Development And Application Of A Methodology For The Analysis Of Significant Human Related Event Trends In Nuclear Power Plants , Hang Youn Cho

Retrospective Theses and Dissertations

A methodology is developed to identify and flag significant trends related to the safety and availability of U.S. commercial nuclear power plants. The development is intended to aid in reducing likelihood of human errors. To assure that the methodology can be easily adapted to various types of classification schemes of operation data, a data bank classified by the Transient Analysis Classification and Evaluation (TRACE) scheme is selected for the methodology;The significance criteria for human-initiated events affecting the systems and for events caused by human deficiencies were developed;Clustering analysis was used to verify the learning trend in multi-dimensional ...


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.


Fast Neutron Spectrum Measurement With Threshold Detectors, Mohammad Moghari Jan 1979

Fast Neutron Spectrum Measurement With Threshold Detectors, Mohammad Moghari

Retrospective Theses and Dissertations

No abstract provided.


Use Of Adjoint Space Models For Predicting The Response Of A Neutron Detector To Core Parametric Fluctuations, Lung-Rui Huang Jan 1979

Use Of Adjoint Space Models For Predicting The Response Of A Neutron Detector To Core Parametric Fluctuations, Lung-Rui Huang

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.


Precipitation Kinetics Of A Continuous Precipitator, With Application To The Precipitation Of Ammonium Polyuranate, Richard Conrad Hoyt Jan 1978

Precipitation Kinetics Of A Continuous Precipitator, With Application To The Precipitation Of Ammonium Polyuranate, Richard Conrad Hoyt

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.


Subsurface Void Contrast By Scanning Electron Microscopy: Theory And Applications , Joseph Kirk Gasper Jan 1974

Subsurface Void Contrast By Scanning Electron Microscopy: Theory And Applications , Joseph Kirk Gasper

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.