Dissertations / Theses on the topic 'Nuclear facility'
Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles
Consult the top 50 dissertations / theses for your research on the topic 'Nuclear facility.'
Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.
You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.
Browse dissertations / theses on a wide variety of disciplines and organise your bibliography correctly.
Zakariya, Nasiru Imam. "Development of nuclear-radiological facility monitoring system." Thesis, Cape Peninsula University of Technology, 2016. http://hdl.handle.net/20.500.11838/2182.
Full textThe widespread application of nuclear science and technology has been the subject of much concern as well as nuclear safety issues. And to ensure the safety of public life, property and environment, it is indispensable to improve the emergency system for nuclear accidents and the environmental monitoring system for nuclear radiation, so that the occurrence of nuclear accidents, terrorist incidents and the resulting hazards can be prevented or minimized. Due to the benefits of radiation which were earlier and now recognized in the use of X-rays for medical diagnosis and then later with the discoveries of radiation and radioactivity, there was rush in exploiting the medical benefits which eventually led fairly to the recognition of the risks and induced harm associated with it. Thus, only the most obvious harms resulting from high doses of radiation, such as radiation burns, were initially observed and protection efforts were focused on their prevention, mainly for practitioners rather than patients. Subsequently, it was gradually recognized that there were other, less obvious, harmful radiation effects such as radiation-induced cancer, for which there is certain risk even at low doses of radiation.
Stout, Daniel S. "Project management model of a nuclear facility renovation." Thesis, Massachusetts Institute of Technology, 1998. http://hdl.handle.net/1721.1/9904.
Full textCalderón, Lindsay Lorraine. "Diversion scenarios in an aqueous reprocessing facility." Thesis, Massachusetts Institute of Technology, 2009. http://hdl.handle.net/1721.1/53287.
Full textCataloged from PDF version of thesis.
Includes bibliographical references (p. 59).
The International Atomic Energy Agency requires nuclear facilities around the world to abide by heavily enforced safeguards to prevent proliferation. Nuclear fuel reprocessing facilities are designed to be proliferation-resistant and to use surveillance systems. While experience with small-scale reprocessing facilities has allowed for well understood safeguards, large-scale reprocessing facilities pose a new difficulty because of the larger error margins involved with the large volumes of spent fuel that is being processed. First, a hypothetical spent nuclear fuel reprocessing facility is described along with proliferation resistance methods typically used in actual facilities. This model establishes a foundation for studying diversion scenarios using a success tree method.
by Lindsay Lorraine Calderón.
S.M.and S.B.
Stupay, Robert Irving. "The necessity for permanence : making a nuclear waste storage facility." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/70196.
Full textIncludes bibliographical references (leaves 74-75).
The United States Department of Energy is proposing to build a nuclear waste storage facility in southern Nevada. This facility will be designed to last 10,000 years. It must prevent the waste from contaminating the environment by either natural causes or by human intervention. This thesis investigates techniques of preventing curious or oblivious people from breaking into this highly toxic repository. It is a situation where the form must communicate meaning over many millennia in the absence of a cultural context.
Robert Irving Stupay.
M.Arch.
Heywood, D. I. "Environmental radiation monitoring and the siting of nuclear facilities." Thesis, University of Newcastle Upon Tyne, 1987. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.382436.
Full textAdam, Buthaina Abdalla Suleiman. "Monte Carlo simulations of the iThemba LABS neutron beam facility." Master's thesis, University of Cape Town, 2010. http://hdl.handle.net/11427/6520.
Full textIncludes bibliographical references.
The iThemba LABS neutron beam facility is currently being used for various applications of fast neutron studies, such as measurements of fission cross sections, the biological effectiveness of high-energy neutrons, calibration of detectors used for dose monitoring in space and aircrafts, and the development of neutron dose monitors. Neutron beams with energies up to 200 MeV are produced at iThemba LABS by irradiating thin targets of 7Li and 9Be with protons from the separated-sector cyclotron. The neutrons are collimated to produce a beam with a diameter of about 50 mm at a flight path of 7.7 m from the target. The collimator geometry is designed to maximize the central part of the beam resulting in a beam with a uniform intensity throughout its diameter and a small penumbra. Secondary neutrons produced from the interactions of the primary charged particles with structural parts e.g. beampipes, shielding wall, target holder, etc. have been observed in the measured neutron fluence spectra. The Monte Carlo radiation transport code FLUKA were used to study the effects of secondary neutrons on the neutron fluence spectra. Results obtained from the calculations were compared with those obtained experimentally.
Dalrymple, Nathan Edward. "Simulation of ionospheric plasma heating experiments in the versatile toroidal facility." Thesis, Massachusetts Institute of Technology, 2001. http://hdl.handle.net/1721.1/8866.
Full textIncludes bibliographical references (p. 281-289).
Remote sensing techniques employed to diagnose ionospheric modification experiments are intrinsically ambiguous, uncorrelated with "ground truth." To overcome this limitation, laboratory experiments are performed in the model ionosphere of the Versatile Toroidal Facility (VTF). The VTF contains a thermionically produced, weakly magnetized ( wce < wpe) background plasma of either hydrogen or argon. The HF "pump" wave of ionospheric experiments is modeled by 2.45 GHz microwaves, launched perpendicular to the magnetic field and the density gradient of the VTF in the ordinary mode. The peak plasma density is several times greater than the critical density (nc ~/= 7.4xI0 16 m-3 ), and the microwaves reflect, forming a standing wave Airy pattern. Wave spectra produced near reflection are measured using a miniature double probe and microwave receiver along with a fast oscilloscope. This combination is capable of simultaneously measuring spectra in two 250 MHz bands, one near DC and the other near the 2.45 GHz pump, to μs resolution. In addition, absolute electric field strengths and wavenumber spectra can be estimated. To explore the extent to which the VTF experiments simulate ionospheric heating, similarity rules are derived from the governing equations and applied to the two plasmas. A set of ten dimensionless parameters results, six of which match satisfactorily between the two plasmas. Three others can be neglected, leaving only one unmatched parameter: the ratio T/Ti, which in the VTF is about 12 and in the ionosphere is near unity. Consideration of boundary conditions limits the scope of the simulation to the first Airy maximum. The main observational results of VTF heating experiments are: (1) Langmuir wave sidebands both up- and down-shifted from the pump frequency that decrease monotonically to the noise floor in tens of MHz, (2) lower hybrid waves in a broad band from 35 - 150 MHz, with maximum power occurring at 50 - 90 MHz, (3) both Langmuir and lower hybrid waves appear in bursts of duration and period in the 2- 100 ms range, depending upon radius, (4) Langmuir and lower hybrid bursts are anti-correlated at the edge of the plasma but become uncorrelated in the core, and (5) the electric field, both of the pump and the plasma sidebands, varies by a factor of 100 in a burst period, from 1.3 to 130 kV /m for the pump (expected: 10.8 kV/m). The main features of ionospheric heating were reproduced in these experiments: down- and up-shifted high frequency sidebands, extreme time-variability of electric field amplitude, large pump wave absorption, and significant electron heating. The observed spectral bursts suggest the concentration of electric field into small time-varying regions. The periods and parameter dependencies of the bursts resemble results of three-dimensional simulations of Langmuir turbulence. However, the upshifted Langmuir waves predicted by strong Langmuir turbulence (SLT) and nonlinear scattering theory are not observed in the VTF. A consistent account of the VTF observations is obtained by combining the caviton collapse cycle of SLT and the parametric production of lower hybrid waves by energetic Langmuir waves. As the high frequency electric field concentrates in cavitons, the threshold for the Langmuir decay instability is exceeded, generating lower hybrid waves in anti-correlated bursts. Because of the similarity of the VTF experiments to ionospheric heating, the observation of lower hybrid wave production during heating may also be borne out by future field experiments with diagnostics capable of viewing field-aligned modes.
by Nathan E. Dalrymple.
Sc.D.
Zhou, Wentao. "Integrated Model Development for Safeguarding Pyroprocessing Facility." The Ohio State University, 2017. http://rave.ohiolink.edu/etdc/view?acc_num=osu1492696274361015.
Full textChichkine, Vladimir N. "Super-FRS the next generation exotic nuclear beam facility at GSI /." [S.l. : s.n.], 2003. http://deposit.ddb.de/cgi-bin/dokserv?idn=969786573.
Full textSharpe, John Phillip. "Particulate Generation During Disruption Simulation on the SIRENS High Heat Flux Facility." NCSU, 2000. http://www.lib.ncsu.edu/theses/available/etd-20000323-115005.
Full textSuccessful implementation of advanced electrical power generation technology into the global marketplace requires at least two fundamental ideals: cost effectiveness and the guarantee of public safety. These requirements can be met by thorough design and development of technologies in which safety is emphasized and demonstrated. A detailed understanding of the many physical processes and their synergistic effects in a complicated fusion energy system is necessary for a defensible safety analysis. One general area of concern for fusion devices is the production of particulate, often referred to as dust or aerosol, from material exposed to high energy density fusion plasma. This dust may be radiologically activated and/or chemically toxic, and, if released to the environment, could become a hazard to the public. The goal of this investigation was to provide insight into the production and transport of particulate generated during the event of extreme heat loads to surfaces directly exposed to high energy density plasma. A step towards achieving this goal was an experiment campaign carried out with the Surface InteRaction Experiment at North Carolina State (SIRENS), a facility used for high heat flux experiments. These experiments involved exposing various materials, including copper, stainless steel 316, tungsten, aluminum, graphite (carbon), and mixtures of carbon and metals, to the high energy density plasma of the SIRENS source section. Material mobilized as a result of this exposure was collected from a controlled expansion chamber and analyzed to determine physical characteristics important to safety analyses (e.g., particulate shape, size, chemical composition, and total mobilized mass). Key results from metal-only experiments were: the particles were generally spherical and solid with some agglomeration, greater numbers of particles were collected at increasing distances from the source section, and the count median diameter of the measured particle size distributions were of similar value at different positions in the expansion chamber, although the standard deviation was found to increase with increasing distances from the source section, and the average count median diameters were 0.75 micron for different metals. Important results from the carbon and carbon/metals tests were: particle size distributions for graphite tests were bi-modal (i.e. two distributions were present in the particle population), particles were generally smaller than those from metals-only tests (average of 0.3 micron), and the individual particles were found to contain both carbon and metal material. An associated step towards the goal involved development of an integrated mechanistic model to understand the role of different particulate phenomena in the overall behavior observed in the experiment. This required a detailed examination of plasma/fluid behavior in the plasma source section, fluid behavior in the expansion chamber, and mechanisms responsible for particulate generation and growth. The model developed in this work represents the first time integration of these phenomena and was used to simulate mobilization experiments in SIRENS. Comparison of simulation results with experiment observations provides an understanding of the physical mechanisms forming the particulate and indicates if mechanisms other than those in the model were present in the experiment. Key results from this comparison were: the predicted amount of mass mobilized from the source section was generally much lower than that measured, the calculated and measured particle count median diameters were similar at various locations in the expansion chamber, and the measured standard deviations were larger than those predicted by the model. These results implicate that other mechanisms (e.g., mobilization of melted material) in addition to ablation were responsible for mass removal in the source section, a large number of the measured particles were formed by modeled mechanisms of nucleation and growth, and, as indicated by the large measured standard deviations, the larger particles found in the measurement were from an aerosol source not included in the model. From this model, a detailed understanding of the production of primary particles from the interaction of a high energy density plasma and a solid material surface has been achieved. Enhancements to the existing model and improved/extended experimental tests will yield a more sophisticated mechanistic model for particulate production in a fusion reactor.
Martin, Jerry Lynn. "DABLE--a facility for measuring fission product transport in gas-cooled reactors." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/13906.
Full textDuraski, Robert F. (Robert Franklin). "Design and construction of the versatile toroidal facility for ionospheric chamber research." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/97783.
Full textMoriarty, Daniel T. (Daniel Timothy). "Laboratory studies of ionospheric plasma processes with the Versatile Toroidal Facility (VTF)." Thesis, Massachusetts Institute of Technology, 1996. http://hdl.handle.net/1721.1/40001.
Full textLedesma, Michelle N. (Michelle Nicole) 1975. "Medical room design for a fission converter-based boron neutron capture therapy facility." Thesis, Massachusetts Institute of Technology, 1998. http://hdl.handle.net/1721.1/50533.
Full textYoo, Chan. "Plasma confinement optimization of the versatile toroidal facility for ionospheric plasma simulation experiments." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/97781.
Full textHartnick, Megan Donna. "Evaluation of nuclear spent fuel dry storage casks and storage facility designs." Master's thesis, University of Cape Town, 2017. http://hdl.handle.net/11427/25279.
Full textBurns, Joe 1966. "On selection and operation of an international interim storage facility for spent nuclear fuel." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/16642.
Full textIncludes bibliographical references.
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
Disposal of post-irradiation fuel from nuclear reactors has been an issue for the nuclear industry for many years. Most countries currently have no long-term disposal strategy in place. Therefore, the concept of an intermediate nuclear spent fuel storage facility has been introduced as a method of temporarily storing the spent fuel in a central location until long-term disposal of the spent nuclear fuel is made available. General criteria that can be used to compare potential international sites for an intermediate nuclear spent fuel storage facility have been identified and elucidated. Those criteria were then utilized to compare four potential international intermediate nuclear spent fuel storage facility (IINSFSF) sites. Two of the sites are in Russia (one in the area of the old nuclear city of Krasnoyarsk-26 currently known as Zheleznogorsk and one on Sakhalin Island in the area of the town of Kholmsk), one is in China (in the area of the town of Xilinhot in the Nei Mongol province) and one in Australia (in the area of the city of Meekatharra in Western Australia). Safety and safeguard regulations for nuclear facilities were reviewed and appropriate portions that could be applied to a potential IINSFSF are recommended. An analysis was conducted to determine legal issues pertinent to an IINSFSF and a brief, limited overview of the most important legal issues is presented. The effects that nuclear fuels subjected to higher burnups (than practiced now) will have on dry cask storage was examined and recommendations for storage strategies are proposed.
(cont.) The selected criteria involve the areas of Geological Suitability, Seismic Stability, Land Area Suitability, Site Infrastructure Suitability, Transportation Infrastructure Suitability, Meteorological Suitability, Willingness of the Host Nation and Population Density. Application of the criteria to the suggested sites revealed that Krasnoyarsk - 26 is the best alternative. This is mainly due to the willingness of the host nation of Russia to accept this type of facility. Krasnoyarsk - 26 also rates as the best site with respect to the criteria of geological suitability and seismic suitability. Without consideration for the willingness of the host nation, Meekatharra would be the ideal site. Xilinhot was evaluated as the third best alternative followed by the Sakhalin Island site of Kholmsk. The legal issue that would be of most concern to an IINSFSF would be potential liability. It would be best if the host nation were a signatory of an international treaty limiting the liability of the IINSFSF operator. Of the two major international nuclear liability treaties in existence the one preferable is the Paris Convention. Economics are driving nuclear power plants in the United States to look to implement more highly enriched fuels to achieve higher burnupsHow these higher burnup spent fuels will affect dry cask storage of spent fuels at reactor sites should be examined. To determine this, the decay heat output of higher burnup spent fuels was compared to the storage capacity of a typical dry cask storage system ...
by Joe Burns.
S.M.
Martin, Christine Marie. "The design of a high temperature gas reactor fuel testing facility for MITR-II." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/13438.
Full textRodewald, Oliver Russell. "Use of Bayesian inference to estimate diversion likelihood in a PUREX facility." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76951.
Full textCataloged from PDF version of thesis.
Includes bibliographical references (p. 66-67).
Nuclear Fuel reprocessing is done today with the PUREX process, which has been demonstrated to work at industrial scales at several facilities around the world. Use of the PUREX process results in the creation of a stream of pure plutonium, which allows the process to be potentially used by a proliferator. Safeguards have been put in place by the IAEA and other agencies to guard against the possibility of diversion and misuse, but the cost of these safeguards and the intrusion into a facility they represent could cause a fuel reprocessing facility operator to consider foregoing standard safeguards in favor of diversion detection that is less intrusive. Use of subjective expertise in a Bayesian network offers a unique opportunity to monitor a fuel reprocessing facility while collecting limited information compared to traditional safeguards. This work focuses on the preliminary creation of a proof of concept Bayesian network and its application to a model nuclear fuel reprocessing facility.
by Oliver Russell Rodewald.
S.M.and S.B.
Jiang, Kai. "An Experimental Facility for Studying Heat Transfer in Supercritical Fluids." Thesis, Université d'Ottawa / University of Ottawa, 2015. http://hdl.handle.net/10393/32063.
Full textGao, Wei Ph D. "Lithium-6 filter for a fission converter-based Boron Neutron Capture Therapy irradiation facility beam." Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/34653.
Full textThesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.
(cont.) A storage system was designed to contain the lithium-6 filter safely when it is not in use. A mixed field dosimetry method was used to measure the photon, thermal neutron and fast neutron dose. The measured advantage depth is 9.3 ± 0.1cm without filter and 9.9 ± 0.1cm with 8mm lithium-6 filter. The result is consistent with the result of Monte Carlo calculation.
The design of a lithium-6 filter to be used in Boron Neutron Capture Therapy was developed. The lithium-6 filter increases the average energy of the epithermal neutrons in the epithermal neutron beam. This filter allows the beam to be used for effective BNCT treatment at greater depth in tissue. Based on Monte Carlo calculations, 8mm thick lithium-6 filter was found to be the optimum filter thickness for the MIT fission converter based epithermal neutron beam (FCB). The highly reactive lithium metal filter is sealed with aluminum covers against the humidity and surrounding air. A well shielded and convenient frame was also designed to hold the lithium-6 filter. The frame is separated into two parts. The fixed part of the frame will be mounted into the patient collimator of the FCB and provides a slot for the lithium-6 filter. The filter itself will be connected to the movable part of the frame and slid in and out of the beam through a pair of roller bearing tracks like a vertical drawer. Both parts of the frame are built with borated polyethylene (RICORAD) and steel to insure good shielding. Many safety issues have been considered in the design including tritium production, nuclear heating, pressure from released gases and radiation leakage on the side of the collimator.
by Wei Gao.
S.M.
Cramer, Lori A. "Community Responses to Siting a Hazardous Waste Facility: The Case of the High-Level Nuclear Waste Facility at Yucca Mountain, Nevada." DigitalCommons@USU, 1993. https://digitalcommons.usu.edu/etd/6165.
Full textIamsumang, Chonlagarn. "A framework for nuclear facility safeguard evaluation using probabilistic methods and expert elicitation." Thesis, Massachusetts Institute of Technology, 2010. http://hdl.handle.net/1721.1/76528.
Full textCataloged from PDF version of thesis.
Includes bibliographical references (p. 99-100).
With the advancement of the next generation of nuclear fuel cycle facilities, concerns of the effectiveness of nuclear facility safeguards have been increasing due to the inclusion of highly enriched material and reprocessing capability into fuel cycles. Therefore, an extensive and quantitative safeguard evaluation is required in order for the decision makers to have a consistent measure to verify safeguards level of protection, and to effectively improve the current safeguard scheme. The framework presented in this study provides a systematic method for safeguard evaluation of any nuclear facility. Using scenario analysis approach, a diversion scenario consists of target material, target location, diversion technique, set of tactics to help elude the safeguards, and the amount of material diverted per attempt. The success tree methodology and expert elicitation is used to construct logical models and obtain the probabilities of basic events. Then proliferator diversion success probabilities can be derived from the model for all possible scenarios in a given facility. Using Rokkasho reprocessing facility as an example, diversion pathways, uncertainty, sensitivity, and importance measure analyses are shown. Results from the analyses can be used by the safeguarder to gauge the level of protection provided by the current safeguard scheme, and to identify the weak points for improvements. The safeguarder is able to further analyze the effectiveness of the safeguard scheme for different facility designs, and the cost effectiveness analysis will help the safeguarder allocate limited resources for maximum possible protection against a material diversion.
by Chonlagarn Iamsumang.
S.M.
Champagne, Christian. "Characterizing and optimizing the TITAN facility from energy spread determinations with a retarding energy field analyzer." Thesis, McGill University, 2010. http://digitool.Library.McGill.CA:80/R/?func=dbin-jump-full&object_id=86571.
Full textAn energy resolution ∆E/E ≈ 10e-3 was expected from to simulated RFQ ion extraction longitudinal energy spread measurements. An experimental energy resolution ∆E/E = 2.4 x 10e-3 was obtained. Suggestions to improve the energy resolution are provided. Two testing sessions were undertaken using the RFQ and TITAN ion source to provide a singly charged pulsed ion beam. The first session used a 6Li+ beam with a 1 - 4 keV energy range. The RFA collimating slits were removed to insure the beam entered the RFA, increasing the energy resolution to ∆E/E = 5 x 10e-3. An energy resolution ∆E/E = (1.4 ± 0.5) x 10e-2 was obtained from the longitudinal energy spread measurements as a function of the beam energy. No correlation between the RFQ buffer gas pressure and the longitudinal energy spread was observed. The second session used 6;7Li, 23Na, 39;41K beams with a 1 - 5 keV energy range and the slits were reincorporated. A linear correlation with the RFQ extraction potentials magnitude is visible with both 2.5 keV 7Li+ and 23Na+ beams. No correlations between the RFQ buffer gas pressure, the space charge, beamgate size and beam composition with respect to the longitudinal energy spread were otherwise found. Further reduction of the RFA energy resolution is necessary to resolve longitudinal energy spread variations under different RFQ parameter settings.
L'expérience TITAN (Piège ionique pour la science atomique et nucléaire de TRIUMF) utilise un piège Penning (MPET) pour effectuer des mesures de masse de haute précision (∆m/m ≈ 10e-8) sur des isotopes radioactifs de courte demi-vie (t1/2 ≈ 10 ms). L'installation ISAC (Isotope Separation and Acceleration) à TRIUMF produit un 60 keV faisceau d'isotopes rares vers divers expériences. Un piège ionique quadrupôle linéaire à radio-fréquences (RFQ) refroidit et accumule le faisceau d'ions radioactifs. Un piège ionique à faisceau d'électrons (EBIT) augmente la charge ionique des ions simplement chargés à une haute charge q. Puisque la résolution de masse de MPET est proportionnelle à la charge ionique q, une augmentation de la résolution jusqu'à deux ordres de grandeur est possible. Des améliorations additionnelles sont fait par la réduction des sources d'erreurs sur les mesures du MPET, comme la dispersion longitudinale de l'énergie cinétique des ions pulsés. Un analyseur d'énergie cinétique à champ retardé (RFA) fut conçu et construit dans le but de mesurer cette erreur.
Une résolution énergétique ∆E/E ≈ 10e-3 fut visée à la suite des résultats obtenus de simulations numériques de l'extraction d'ions du RFQ. Une résolution énergétique expérimentale ∆E/E = 2.4 x 10e-3 a été obtenue. Des suggestions pour améliorer la résolution énergétique sont données. Le RFA fut testé au cours de deux séances en utilisant le RFQ et la source d'ions de TITAN pour fournir un faisceau d'ions simplement chargés. Durant la première séance, un faisceau de 6Li+ avec énergies entre 1 et 4 keV fut utilisé. Les fentes du collimateur furent enlevées pour assurer que le faisceau pénètre dans le RFA, augmentant la résolution énergétique à ∆E/E = 5 x 10e-3. Une résolution énergétique ∆E/E = (1.4 ± 0.5) x 10-e2 a été obtenue de la relation entre la dispersion longitudinale de l'énergie cinétique et de l'énergie cinétique du faisceau. Aucune corrélation entre la pression du gaz tampon du RFQ et la dispersion longitudinale de l'énergie cinétique a été observée. La seconde séance utilisait des faisceaux de 6;7Li, 23Na, 39;41 K avec des énergies cinétiques entre 1 et 5 keV et les fentes du collimateur furent ré-incorporées. Une corrélation linéaire avec la grandeur des potentiels extraction du RFQ fut observée avec les deux faisceaux de 7Li+ et 23Na+ à 2.5 keV utilisés. Aucune corrélation entre la charge spatiale, pression du gaz tampon du RFQ, la durée du barrière d'ions et la composition du faisceau avec la dispersion longitudinale de l'énergie cinétique furent autrement notées. Des réduction supplémentaires à la résolution énergétique du RFA sont nécessaire pour observer des variations dans la dispersion longitudinale de l'énergie cinétique du faisceau sous différent paramètres du RFQ.
Lee, Terry Tak-Keon. "Safety analysis report and technical specifications of the MITR fission converter facility for neutron capture therapy." Thesis, Massachusetts Institute of Technology, 1997. http://hdl.handle.net/1721.1/43345.
Full textO'Donnell, Jeffrey R. (Jeffrey Robert). "Design, construction, and commissioning of an in-core materials testing facility for slow strain rate testing." Thesis, Massachusetts Institute of Technology, 1994. http://hdl.handle.net/1721.1/28129.
Full textMeredith, Shaun Lee. "Construction of a gridded energy analyzer for measurements of ion energy distribution in the versatile toroidal facility." Thesis, Massachusetts Institute of Technology, 1998. http://hdl.handle.net/1721.1/50545.
Full textIncludes bibliographical references (p. 80-82).
The Versatile Toroidal Facility (VTF) at MIT's Plasma Science and Fusion Center provides a laboratory environment for studying ionospheric plasmas. Various plasma diagnostic devices have been created and used to study the VTF plasma since 1991. An accurate method for measuring VTF's ion characteristics has never been designed or installed in the laboratory facility. Gridded Energy Analyzers (GEA) are useful diagnostic tools for determining plasma ion energy distributions and ion temperature. Research was done on the theory behind Gridded Energy Analyzers and their applicability for use in the Versatile Toroidal Facility. A design and method for constructing a miniaturized GEA for VTF was developed and documented. The construction method covers material selection, machining, and assembly of VTF's miniature GEA. The miniature GEA is a non-perturbing probe used in VTF's plasma, which is approximately 3 cm in diameter. The GEA was constructed and preliminary experimental data was obtained. From this data VTF's ion temperature was found to be approximately 8eV and an ion distribution function was determined to be roughly Maxwellian in nature.
by Shaun L. Meredith.
S.M.
J, Labossière-Hickman Travis. "Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods." Thesis, Massachusetts Institute of Technology, 2019. https://hdl.handle.net/1721.1/123360.
Full textThesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2019
Cataloged from student-submitted PDF version of thesis.
Includes bibliographical references (pages 111-113).
The Transient Reactor Test Facility (TREAT) has regained the interest of the nuclear engineering community in recent years. While TREAT's design makes it uniquely suited to transient fuel testing, it also makes the reactor very challenging to model and simulate. In this thesis, we build a Monte Carlo model of TREAT's Minimum Critical Mass core to examine the effects of fuel impurities, calculate a reference solution, and analyze a number of multigroup cross section generation approaches. Several method of characteristics (MOC) simulations employing these cross sections are then converged in space and angle, corrected for homogenization, and compared to the Monte Carlo reference solution. The thesis concludes with recommendations for future analysis of TREAT using MOC.
by Travis J. Labossière-Hickman.
S.M.
S.M. Massachusetts Institute of Technology, Department of Nuclear Science and Engineering
Novick, Vincent John. "Aerosol measurement techniques developed for nuclear reactor accident simulations /." Thesis, Connect to this title online; UW restricted, 1989. http://hdl.handle.net/1773/10112.
Full textGlosup, Richard Edwin. "Characterization of the High-Temperature Helium Facility in the Thermal Hydraulics Laboratory." The Ohio State University, 2011. http://rave.ohiolink.edu/etdc/view?acc_num=osu1313248382.
Full textBargalló, Font Enric. "IFMIF accelerator facility RAMI analyses in the engineering design phase." Doctoral thesis, Universitat Politècnica de Catalunya, 2014. http://hdl.handle.net/10803/144657.
Full textRojas, Jimmy A. (Rojas Herrera). "Impact of x-ray dose on the response of CR-39 nuclear track detector to 1-5.5 MeV alphas and 0.5-9.1 MeV protons for spectroscopy at the OMEGA Laser Facility and the National Ignition Facility." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/106770.
Full textPage 47 blank. Cataloged from PDF version of thesis.
Includes bibliographical references (pages 45-46).
The CR-39 nuclear track detector is used in many nuclear diagnostics fielded at inertial confinement fusion (ICF) facilities. Large x-ray fluences generated by ICF experiments may impact the CR-39 response to incident charged particles. To determine the impact of x-ray exposure on the CR-39 response to protons and alpha particles, a thick-target bremsstrahlung x-ray generator was used to expose CR-39 to various doses of 30 and 8keV Cu-K[alpha] and K[beta] x-rays. The CR-39 detectors were then exposed to 1-5.5 MeV alphas or 0.5- 9.1 MeV protons. The regions of the CR-39 exposed to x-rays showed a smaller track diameter than those not exposed to x-rays: for example, a dose of 3.0±0.1 Gy causes a decrease of (19±2)% in the track diameter of a 5.5 MeV alpha, while a dose of 6.0±0.1 Gy results in a decrease of (29±1)% in the track diameter of a 3.0 MeV proton. The reduced track diameters were found to be predominantly caused by a comparable reduction in the bulk etch rate of the CR-39 with x-ray dose. A residual effect, due to changes in track etch rate and dependent on incident particle energy, was characterized by an empirical formula.
by Jimmy A. Rojas.
S.B.
Sandberg, Alexander Jerome. "Shielding design for the time-resolving Magnetic Recoil Spectrometer (MRSt) on the National Ignition Facility (NIF)." Thesis, Massachusetts Institute of Technology, 2019. https://hdl.handle.net/1721.1/127703.
Full textThesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2019
Cataloged from the official PDF of thesis.
Includes bibliographical references (pages 49-50).
Abstract The National Ignition Facility (NIF) is one of the premier inertial confinement fusion (ICF) experiments active today, with the goal of acheiving ignition in a laboratory for the first time. Multiple diagnostics are needed to generate the scientific data necessary for guiding these experiments at the NIF toward this goal. The time-resolving Magnetic Recoil Spectrometer (MRSt) aims to provide time-resolved measurements of the neutron spectrum, to determine time evolution of ion temperature, areal density, and neutron yield, at a time resolution of 20ps and an energy resolution of 100 keV. This would be the first time-resolved measurement of these quantities, and is crucial to understanding the dynamics of the implosion and possible deviations from optimal performance. The MRSt's unique ability to diagnose the hot-spot formation, fuel assembly, and alpha heating will open a new door to ICF. This work establishes a conceptual shielding design for the MRSt that meets the signal-to-background requirements. The finalized design is composed of 65cm of 30% borated polyethylene shielding for the neutron background, and a 2.5cm layer of tungsten gamma shielding with a 5.5cm layer of shielding on the last 20cm of the pulse dilation drift tube (PDDT) detector. This design reduces the background about 300 times, from 0.12 for the unshielded design to 35 for the finalized shielding design, thus exceeding the requirement of S/B > 5 for the down-scattered-neutron measurement. Neutron background has been reduced nearly to zero, but further gamma reduction could be a future avenue of research, specifically surrounding the graded-Z shielding design.
by Alexander Jerome Sandberg.
S.M.
S.M. Massachusetts Institute of Technology, Department of Nuclear Science and Engineering
Arcilesi, David J. Jr. "Developmental Analysis and Design of a Scaled-down Test Facility for a VHTR Air-ingress Accident." The Ohio State University, 2012. http://rave.ohiolink.edu/etdc/view?acc_num=osu1338387523.
Full textFrancis, Michael Craig. "A techno–economic analysis of an integrated GTL, nuclear facility with utilities production / Francis M.C." Thesis, North-West University, 2011. http://hdl.handle.net/10394/7347.
Full textThesis (M.Sc. Engineering Sciences (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2012.
Gilbert, Matthew G. "Group and societal decision making : an exploration of modelling paradigms applied to nuclear facility siting." Thesis, University of Warwick, 2017. http://wrap.warwick.ac.uk/95975/.
Full textFortkamp, Jonathan C. "Characterization of the radiation environment for a large area interim spent nuclear fuel storage facility /." The Ohio State University, 1999. http://rave.ohiolink.edu/etdc/view?acc_num=osu1488188894437725.
Full textKhoza, Best. "Physics and engineering aspects of South Africa's proposed dry storage facility for spent nuclear fuel." Master's thesis, Faculty of Engineering and the Built Environment, 2019. https://hdl.handle.net/11427/31697.
Full textOrton, Christopher Robert. "The Multi-Isotope Process Monitor: Non-destructive, Near-Real-Time Nuclear Safeguards Monitoring at a Reprocessing Facility." The Ohio State University, 2009. http://rave.ohiolink.edu/etdc/view?acc_num=osu1259101113.
Full textQuinn, Bruce David 1955. "Dose rate measurements in the cobalt-60 gamma irradiation facility using thermoluminescent dosimeters." Thesis, The University of Arizona, 1991. http://hdl.handle.net/10150/277923.
Full textWink, Christopher William. "Characterization and optimization of signal and background for the time-resolving magnetic recoil spectrometer on the National Ignition Facility." Thesis, Massachusetts Institute of Technology, 2017. http://hdl.handle.net/1721.1/112366.
Full textThis electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
"June 2017." Cataloged from student-submitted PDF version of thesis.
Includes bibliographical references (pages 47-48).
The evolution of fuel assembly, hot-spot formation, and nuclear burn in an Inertial Confinement Fusion (ICF) implosion at the National Ignition Facility (NIF) can be quantified through time-resolved measurements of the neutron spectrum. This information will be obtained with the next-generation Magnetic Recoil Spectrometer (MRSt) that will measure the neutron spectrum (12-16 MeV) with high accuracy (~5%), unprecedented energy resolution (~100 keV) and, for the first time ever, time resolution (~20 ps). To successfully implement the MRSt on the NIF for this measurement, the signal and background distributions at the MRSt detector must be characterized; the detector response to the signal and background must be determined; and the shielding enclosing MRSt must be designed and implemented to reduce the background to the required level. These things have been done, which constitute the main results of this thesis. First, an MCNP model of the MRSt in the NIF target bay was implemented to assess the neutron- and gamma-background fluxes at an unshielded MRSt. Second, models of the MRSt-detector response to the signal protons (or deuterons), and neutron and gamma background were implemented to assess the signal-to-background (S/B) for the unshielded MRSt case. Using these models, it is discussed in this thesis that the combined neutron and gamma background in the MRSt data needs to be reduced 100-400 times. Third, a shielding design, consisting of polyethylene, tungsten, and stainless steel, fully enclosing the MRSt, was developed to reduce the background to the required level. This design reduces the background 100-200 times, and meets the requirement of S/B > 5 for the down-scattered-neutron measurement. Obviously, this design depends on the MRSt-detector response to the signal and background, and some minor adjustments to the design might be applied depending on the results from the upcoming measurements of the MRSt-detector response to signal and background. As the shielding design depends on the engineering design of the MRSt system, which has not been fully defined yet, some adjustments to the design will most likely be made when the MRSt engineering design is finalized.
by Christopher William Wink.
S.M.
Giuliano, Dominic Richard. "Neutron Flux Measurements and Calculations in the Gamma Irradiation Facility Using MCNPX." University of Cincinnati / OhioLINK, 2010. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1282570075.
Full textChiuta, Steven. "The potential utilization of nuclear hydrogen for synthetic fuels production at a coal–to–liquid facility / Steven Chiuta." Thesis, North-West University, 2010. http://hdl.handle.net/10394/4840.
Full textThesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2011.
Lavelle, Christopher M. "The neutronic design and performance of the Indiana University Cyclotron Facility (IUCF) Low Energy Neutron Source (LENS)." [Bloomington, Ind.] : Indiana University, 2007. http://gateway.proquest.com/openurl?url_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&res_dat=xri:pqdiss&rft_dat=xri:pqdiss:3255512.
Full textTitle from PDF t.p. (viewed Nov. 20, 2008). Source: Dissertation Abstracts International, Volume: 68-03, Section: B, page: 1688. Adviser: David V. Baxter.
Rong, Xiujiang. "Development of a neutron depth profiling facility at the University of Missouri Research Reactor center /." free to MU campus, to others for purchase, 1996. http://wwwlib.umi.com/cr/mo/fullcit?p9821337.
Full textZapp, Andrew M. "Design and Development of an External Fast Neutron Beam Facility at the Ohio State University Research Reactor." The Ohio State University, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1545075104197272.
Full textBarner, Robert Buckner. "Power conversion unit studies for the next generation nuclear plant coupled to a high-temperature steam electrolysis facility." Texas A&M University, 2006. http://hdl.handle.net/1969.1/4835.
Full textTurkoglu, Danyal J. "Design, Construction and Characterization of an External Neutron Beam Facility at The Ohio State University Nuclear Reactor Laboratory." The Ohio State University, 2011. http://rave.ohiolink.edu/etdc/view?acc_num=osu1325228897.
Full textInyang, Otu Effiong. "Development of a prompt-gamma, neutron-activation analysis facility at the Texas A&M University Nuclear Science Center." Thesis, [College Station, Tex. : Texas A&M University, 2008. http://hdl.handle.net/1969.1/ETD-TAMU-2980.
Full textReinke, Benjamin T. "Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool." The Ohio State University, 2015. http://rave.ohiolink.edu/etdc/view?acc_num=osu1437746576.
Full text