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Dissertations / Theses on the topic 'SPENT FUELS'

Author: Grafiati

Published: 4 June 2021

Last updated: 5 February 2022

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1

ROMANATO, LUIZ S. "Armazenagem de combustivel nuclear queimado." reponame:Repositório Institucional do IPEN, 2005. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11204.

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2

ROMANATO, LUIZ S. "Estudo de um casco nacional e sua instalacao para armazenagem seca de combustivel nuclear queimado gerado em reatores PWR." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9476.

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3

Zino, John Frederick. "Analysis of subcritical experiments using fresh and spent research reactor fuel assemblies." Diss., Georgia Institute of Technology, 1999. http://hdl.handle.net/1853/17507.

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4

Araya, Pablo E. "Design of an experiment that simulates spent nuclear fuel within transport casks." abstract and full text PDF (free order & download UNR users only), 2007. http://0-gateway.proquest.com.innopac.library.unr.edu/openurl?url_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&res_dat=xri:pqdiss&rft_dat=xri:pqdiss:1442846.

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5

Sommer, Christopher Michael. "Subcritical transmutation of spent nuclear fuel." Diss., Georgia Institute of Technology, 2011. http://hdl.handle.net/1853/41205.

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A series of fuel cycle simulations were performed using CEA's reactor physics code ERANOS 2.0 to analyze the transmutation performance of the Subcritical Advanced Burner Reactor (SABR). SABR is a fusion-fission hybrid reactor that combines the leading sodium cooled fast reactor technology with the leading tokamak plasma technology based on ITER physics. Two general fuel cycles were considered for the SABR system. The first fuel cycle is one in which all of the transuranics from light water reactors are burned in SABR. The second fuel cycle is a minor actinide burning fuel cycle in which al

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6

Sommer, Christopher. "Fuel cycle design and analysis of SABR subrcritical advanced burner reactor /." Thesis, Atlanta, Ga. : Georgia Institute of Technology, 2008. http://hdl.handle.net/1853/24720.

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7

Szakaly, Frank Joseph. "Assessment of uranium-free nitride fuels for spent fuel transmutation in fast reactor systems." Thesis, Texas A&M University, 2003. http://hdl.handle.net/1969.1/31.

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The purpose of this work is to investigate the implementation of nitride fuels containing little or no uranium in a fast-spectrum nuclear reactor to reduce the amount of plutonium and minor actinides in spent nuclear fuel destined for the Yucca Mountain Repository. A two tier recycling strategy is proposed. Thermal spectrum transmutation systems converted from the existing LWR fleet were modeled for the first tier, and the Japanese fast reactor MONJU was used for the fast-spectrum transmutation. The modeling was performed with the Monteburns code. Transmutation performance was investigated

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8

Casella, Andrew M. "Modeling of molecular and particulate transport in dry spent nuclear fuel canisters." Diss., Columbia, Mo. : University of Missouri-Columbia, 2007. http://hdl.handle.net/10355/4695.

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Thesis (Ph. D.)--University of Missouri-Columbia, 2007.<br>The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file. Title from title screen of research.pdf file (viewed on November 26, 2007 Vita. Includes bibliographical references.

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9

Stevenson, Anthony John. "Development of a novel electrochemical pyroprocessing methodology for spent nuclear fuels." Thesis, University of Nottingham, 2017. http://eprints.nottingham.ac.uk/39300/.

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Nuclear power remains the most dense and reliable primary form of energy supply worldwide. Electricity generation via fission is also inherently carbon free, with environmental footprints rivalling modern renewable options. However issues arise from the production of highly irradiated spent fuels, with current management options limited to geological repository storage or, more desirably, closing of the fuel cycle by partitioning to recover fissionable species. Extensive research has been pursued over the past half century in an effort to address an accumulating oxide spent fuel inventory and

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10

Venigalla, Venkata Vijaya Raghava. "Computational fluid dynamic simulations of natural convection/radiation heat transfer within the fuel regions of a truck cask for normal transport." abstract (free order & download UNR users only), 2007. http://0-gateway.proquest.com.innopac.library.unr.edu/openurl?url_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&res_dat=xri:pqdiss&rft_dat=xri:pqdiss:1447694.

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11

Foster, Jack Warren. "Development and implementation of a response-function concept for spent nuclear fuel cask analysis." Thesis, Georgia Institute of Technology, 1993. http://hdl.handle.net/1853/17275.

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12

FORBICINI, CHRISTINA A. L. G. de O. "Procedimentos eletroquimicos no tratamento do combustivel nuclear irradiado." reponame:Repositório Institucional do IPEN, 1994. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10395.

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13

Casella, Amanda J. Miller William Hughes Hanson Brady D. "The dissolution rate of unirratiated UO₂ under repository conditions the influence of fuel and water chemistry, dissolved oxygen, and temperature /." Diss., Columbia, Mo. : University of Missouri--Columbia, 2008. http://hdl.handle.net/10355/6625.

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Title from PDF of title page (University of Missouri--Columbia, viewed on Feb 24, 2010). The entire thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file; a non-technical public abstract appears in the public.pdf file. Dissertation supervisors: Dr. William H. Miller, Dr. Brady D. Hanson. Vita. Includes bibliographical references.

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14

Ilas, Germina. "A Monte Carlo based nodal diffusion model for criticality analysis and application of high-order cross section homogenization method of two-group nodal diffusion." Diss., Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/16092.

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15

Mohun, Ritesh. "Raman spectroscopy for the characterization of defective spent nuclear fuels during interim storage in pools." Thesis, Aix-Marseille, 2017. http://www.theses.fr/2017AIXM0288/document.

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Une signature spécifique des dommages d’irradiation dans le dioxyde d’uranium, le combustible nucléaire le plus utilisé, dénommé « triplet de défauts » a été récemment mis en évidence par spectroscopie Raman. Ce travail vise à savoir comment cette signature peut être utilisée afin de caractériser les combustibles nucléaires irradiés qui sont entreposés sous eau. Pour cela, trois études à effets séparés sont menées. Tout d’abord, une expérience d’irradiation aux électrons montre que le triplet de défauts est dû à des interactions balistiques et est associé aux déplacements dans le sous-réseau d

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16

FERREIRA, RAFAEL V. de P. "Biodegradacao de rejeitos radioativos liquidos organicos provenientes do processamento do combustivel nuclear." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11740.

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17

Crawford, Phillip Grant. "Zeolite membranes for the separation of krypton and xenon from spent nuclear fuel reprocessing off-gas." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/50383.

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The goal of this research was to identify and fabricate zeolitic membranes that can separate radioisotope krypton-85 (half-life 10.72 years) and xenon gas released during spent nuclear fuel reprocessing. In spent nuclear fuel reprocessing, fissionable plutonium and uranium are recovered from spent nuclear fuel and recycled. During the process, krypton-85 and xenon are released from the spent nuclear fuel as process off-gas. The off-gas also contains NO, NO2, 129I, 85Kr, 14CO2, tritium (as 3H2O), and air and is usually vented to the atmosphere as waste without removing many of the radioactive

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18

Huang, Lloyd Michael. "Analysis of multi-recycle thorium fuel cycles in comparison with once-through fuel cycles." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/47662.

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The purpose of this research is to develop a methodology for a thorium fuel recycling analysis that provides results for isotopics and radio-toxicity evaluation and analysis. This research is motivated by the need to reduce the long term radiological hazard in spent nuclear fuel, which mitigates the mixing hazard (radiotoxicity and chemical toxicity) and decay heat load on the repository. The first part of the thesis presents comparison of several once-through cases with uranium and thorium fuels to show how transuranics build up as fuel is depleted. The once-through analysis is performed f

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19

Bopp, Andrew T. "The calculation of fuel bowing reactivity coefficients in a subcritical advanced burner reactor." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/50295.

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The United States' fleet of Light Water Reactors (LWRs) produces a large amount of spent fuel each year; all of which is presently intended to be stored in a fuel repository for disposal. As these LWRs continue to operate and more are built to match the increasing demand for electricity, the required capacity for these repositories grows. Georgia Tech's Subcritical Advanced Burner Reactor (SABR) has been designed to reduce the capacity requirements for these repositories and thereby help close the back end of the nuclear fuel cycle by burning the long-lived transuranics in spent nuclear fuel.

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20

Pitts, Michelle Lynn. "Design and analysis of subcritical experiments using fresh fuel assemblies." Diss., Georgia Institute of Technology, 1999. http://hdl.handle.net/1853/18375.

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21

Wantz, Olivier. "A study of in-package nuclear criticality in possible Belgian spent nuclear fuel repository designs." Doctoral thesis, Universite Libre de Bruxelles, 2005. http://hdl.handle.net/2013/ULB-DIPOT:oai:dipot.ulb.ac.be:2013/211019.

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About 60 percent of the electricity production in Belgium originates from nuclear power plants. Belgium owns 7 nuclear pressurized water reactors, which are located in two sites: 4 reactors in Doel and 3 reactors in Tihange. Together they have a capacity of approximately 5900 MWe. All these reactors use classical uranium oxide fuel assemblies. Two of them (Doel3, Tihange2) have also accepted a limited number of mixed (uranium and plutonium) oxide fuel assemblies. These mixed fuel assemblies came from the reprocessing of spent uranium oxide fuel assemblies in La Hague (France). The reprocessing

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22

Adeniyi, Abiodun I. "Impact of separation capacity on transition to advanced fuel cycles." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/47589.

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One of the proposed solutions to the issue of nuclear waste volume is to transition from once through nuclear fuel cycle to advanced fuel cycles with used fuel recycling option. In any advanced fuel cycles with recycling options, the type and amount of separation technology deployed play a crucial role in the overall performance of the fuel cycle. In this work, a scenario study involving two advanced fuel cycles in addition to the once through fuel cycle were evaluated using VISION nuclear fuel cycle simulation code. The advanced fuel cycles were setup to transition completely to full recyclin

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23

Ferreira, Rafael Vicente de Padua. "Biodegradação de rejeitos radioativos líquidos orgânicos provenientes do reprocessamento do combustível nuclear." Universidade de São Paulo, 2008. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-10102011-160303/.

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O reprocessamento do elemento combustível constitui uma das etapas do ciclo do combustível e tem por objetivo separar U 235, U238 e Pu239 dos produtos de fissão contidos no elemento combustível queimado para reutilizá -los na fabricação de novos elementos combustíveis. No Brasil, o desenvolvimento do reprocessamento teve início nos anos 70 com a implantação de uma planta piloto de reprocessamento, no Instituto de Pesquisas Energéticas e Nucleares Comissão Nacional de Energia Nuclear/São Paulo (I PEN-CNEN/SP), dando origem à uma instalação, em escala de laboratório, que operou até o início da

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24

SARKIS, JORGE E. de S. "Aplicacao da tecnica de correlacao isotopica para determinacao da concentracao dos nuclideos AM-241 e AM234 em combustiveis nucleares irradiados." reponame:Repositório Institucional do IPEN, 1990. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10228.

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25

ARAUJO, LEANDRO G. de. "Degradação da resina de troca iônica utilizando o reagente de Fenton." reponame:Repositório Institucional do IPEN, 2013. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10534.

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26

Khoza, 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.

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The continual increase in electricity dependence for the advancement of society has led to increased demand in electricity globally. This increased demand, among other things such as global warming interventions and energy security have encouraged the need to diversify electricity generation sources. Civilian use of nuclear power dates back to the 1950s. The United States of America and France are currently leading with the highest nuclear power generation in the world, generating 101 GWe and 63 GWe, respectively. Several countries such as China and the United Arab Emirates have committed to n

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27

Reese, Drew A. (Drew Amelia). "Dependence of transuranic content in spent fuel on fuel burnup." Thesis, Massachusetts Institute of Technology, 2007. http://hdl.handle.net/1721.1/41692.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007.<br>Includes bibliographical references (p. 33).<br>As the increasing demand for nuclear energy results in larger spent fuel volume, implementation of longer fuel cycles incorporating higher burnup are becoming common. Understanding the effect of higher burnup on the spent fuel composition and radioactive properties is essential to ensure that spent fuel receives proper cooling in storage before it is sent to a disposal site or proper treatment and reprocessing if its useful content is to be ex

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28

Nimander, Fredrik. "Investigation of Spent Nuclear Fuel Pool Coolability." Thesis, KTH, Reaktorteknologi, 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-42440.

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The natural catastrophe at Fukushima Dai-ichi 2011 enlightened the nuclear community. This master thesis reveals the non-negligible risks regarding the short term storage of spent nuclear fuel. The thesis has also investigated the possibility of using natural circulation of air in a passive safety system to cool the spent nuclear fuel pools. The results where conclusive: The temperature difference between the heated air and ambient air is far too low for natural circulation of air to remove any significant amount of heat from the spent nuclear fuel pool in a worst case scenario. Air, as with a

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29

Alajo, Ayodeji Babatunde. "Impact of PWR spent fuel variations on TRU-fueled VHTRS." Thesis, [College Station, Tex. : Texas A&M University, 2007. http://hdl.handle.net/1969.1/ETD-TAMU-2556.

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30

Li, Junyi. "Stability of studtite under spent nuclear fuel repository conditions." Thesis, KTH, Skolan för kemi, bioteknologi och hälsa (CBH), 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-260076.

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31

Yee, Shannon K. "Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel." The Ohio State University, 2008. http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425.

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32

Lundkvist, Niklas. "AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements." Thesis, Uppsala universitet, Tillämpad kärnfysik, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-130011.

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This report is concerned with the question whether Accelerator mass spectrometry (AMS) is asuitable technique for measuring actinide inventory in spent nuclear fuel, and if it is better thanpresent techniques for these measurements. AMS is a kind of Mass spectrometry (MS) and has alot of applications where radio carbon dating is one of the most common. AMS has been used formaking measurements on actinides before but mostly from traces in bioassay that could have beenin contact with weapon plutonium, and in bioassay near enrichment plants and reprocessingplants. It is shown in this report that

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33

Sihm, Kvenangen Karen. "Alternative measuring approaches in gamma scanning on spent nuclear fuel." Thesis, Uppsala universitet, Institutionen för fysik och astronomi, 2007. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-162795.

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In the future, the demand for energy is predicted to grow and more countries plan to utilize nuclear energy as their source of electric energy. This gives rise to many important issues connected to nuclear energy, such as finding methods that can verify that the spent nuclear fuel has been handled safely and used in ordinary power producing cycles as stated by the operators. Gamma ray spectroscopy is one method used for identification and verification of spent nuclear fuel. In the specific gamma ray spectroscopy method called gamma scanning the gamma radiation from the fission products Cs-137,

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34

Lambert, Hugues. "Molten salt spectroscopy and electrochemistry for spent nuclear fuel treatment." Thesis, University of Manchester, 2017. https://www.research.manchester.ac.uk/portal/en/theses/molten-salt-spectroscopy-and-electrochemistry-for-spent-nuclear-fuel-treatment(89862aa1-a98d-4b5f-9052-91cc9dd4eda3).html.

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Pyroprocessing, via electrorefining in a molten salt bath, is a promising treatment route for spent nuclear fuel reprocessing. In order to implement such a technology and ensure its safe operation it is vital to develop on-line techniques to understand and monitor the molten salt and its contents. These tools are technically challenging because of the high temperatures and corrosive environment experienced in molten salt media. Electrochemical, spectroscopic and spectroelectrochemical methods were developed and used to study actinide and fission product behaviour in molten LiCl-KCl eutectic. A

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35

Chen, Xinhui 1966. "Thermal analysis of dry spent fuel transportation and storage casks." Thesis, Massachusetts Institute of Technology, 1996. http://hdl.handle.net/1721.1/38395.

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36

Delandar, Arash Hosseinzadeh. "Modeling defect structure evolution in spent nuclear fuel container materials." Doctoral thesis, KTH, Materialteknologi, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-206175.

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Materials intended for disposal of spent nuclear fuel require a particular combination of physical and chemical properties. The driving forces and mechanisms underlying the material’s behavior must be scientifically understood in order to enable modeling at the relevant time- and length-scales. The processes that determine the mechanical behavior of copper canisters and iron inserts, as well as the evolution of their mechanical properties, are strongly dependent on the properties of various defects in the bulk copper and iron alloys. The first part of the present thesis deals with precipitatio

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37

Fairlie, Ian. "Radioactive waste : international examination of storage and reprocessing of spent fuel." Thesis, Imperial College London, 1997. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.268029.

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38

Owen, Paul E. (Paul Edward) 1968. "Waste characteristics of spent nuclear fuel from a pebble bed reactor." Thesis, Massachusetts Institute of Technology, 1999. http://hdl.handle.net/1721.1/9548.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1999.<br>Includes bibliographical references.<br>A preliminary comparative assessment is made of the spent fuel characteristics and disposal aspects between a high-temperature, gas cooled, reactor with a pebble bed core (PBR) and a pressurized water reactor (PWR). There are three significant differences which impact the disposal characteristics of PBR spent pebble fuel from PWR spent fuel assemblies. Pebble bed fuel has bum-up as high as 100,000 MWD(t)/MTHM and thus, there is significantly less activity and dec

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39

Taniuchi, Hiroaki. "STUDY ON SHIELDING PERFORMANCE OF SPENT FUEL TRANSPORT AND STORAGE PACKAGES." Kyoto University, 1999. http://hdl.handle.net/2433/182372.

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40

Hugo, Bruce Robert. "Modeling evaporation from spent nuclear fuel storage pools| A diffusion approach." Thesis, Washington State University, 2016. http://pqdtopen.proquest.com/#viewpdf?dispub=10043059.

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<p> Accurate prediction of evaporative losses from light water reactor nuclear power plant (NPP) spent fuel storage pools (SFPs) is important for activities ranging from sizing of water makeup systems during NPP design to predicting the time available to supply emergency makeup water following severe accidents. Existing correlations for predicting evaporation from water surfaces are only optimized for conditions typical of swimming pools. This new approach modeling evaporation as a diffusion process has yielded an evaporation rate model that provided a better fit of published high temperature

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41

Jacobsson, Staffan, Ane Håkansson, Camilla Andersson, Peter Jansson, and Anders Bäcklin. "A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel." Uppsala universitet, Tillämpad kärnfysik, 1998. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-200297.

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A tomographic method for experimental investigation of the integrity of usedLWR fuel has been developed. It is based on measurements of the gamma radiation fromthe fission products in the fuel rods. A reconstruction code of the algebraic type has beenwritten. The potential of the technique has been examined in extensive simulationsassuming a gamma-ray energy of either 0.66 MeV (137Cs) or 1.27 MeV (154Eu).The resultsof the simulations for BWR fuel indicate that single fuel rods or groups of rods replacedwith water or fresh fuel can be reliably detected independent of their position in the fuela

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42

Bobolea, Ruxandra. "A Study of Continuous Electrochemical Processing Operation Feasibility for Spent Nuclear Fuel." NCSU, 2009. http://www.lib.ncsu.edu/theses/available/etd-02272009-172349/.

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Several methods of reprocessing are currently available to separate recyclable materials from spent nuclear fuel. Electrochemical processing, also known as pyroprocessing, represents a non-aqueous method of reprocessing that uses high temperature molten-salt based electrochemical technology. This method provides several advantages over conventional aqueous processing with respect to proliferation resistance. With electrochemical processing there is no pure plutonium separation and the presence of large decay heat and high radiation barriers dissuades diversion attempts. As the current electroc

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43

Goode, James Bruce. "Transitioning of spent advanced gas reactor fuel from wet to dry storage." Thesis, University of Leeds, 2017. http://etheses.whiterose.ac.uk/20585/.

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Upon removal from a reactor spent nuclear fuel is placed into water storage for a period of time since water provides both a decay heat sink and radiation shielding. In the UK this fuel has traditionally been reprocessed however the decision has been made that this will cease in 2018 in favour of an open fuel cycle and direct disposal to a degological disposal facility, although this is not expected to be available until 2075. Current experience with pond storage has found that fuel can be safely stored in caustic dosed ponds for at least 25 years and therefore the current plan is to extend wa

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44

Hartnick, 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.

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Koeberg Nuclear Power Station (KNPS) is the only nuclear power station in Africa and it stores its spent nuclear fuel (SNF) onsite in the spent fuel pool (SFP). Additional aged SNF assemblies are stored in dry storage casks in a facility located on the KNPS site. This minor research dissertation aims at evaluating various dry storage cask found in open literature. The dissertation provides an overview of cask types, heat transfer, radiation shielding and storage facility types. Specific criteria are required in the selection of casks and the storage facility to house the casks on site. The sel

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45

Lundkvist, Niklas. "Investigation of possible non-destructive assay (NDA) techniques for at the future Swedish encapsulation facility." Thesis, Uppsala universitet, Tillämpad kärnfysik, 2012. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-178133.

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A geological repository for spent nuclear fuel (SNF) and an associated encapsulation facility will be built in Sweden. The encapsulation facility is planned to be in operation in 2025 and it will be the last place where verifying safeguards measurements of SNF can be performed. It is not clear what types of measurements that will be performed, because such requirements are not yet posed by national and international authorities and inspecting organizations. This report describes the objective and most recent results of a master thesis project, whereby a few existing non-destructive assay tech

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46

Nilsson, Kristina. "Oxidative dissolution of doped UO2 and H2O2 reactivity towards oxide surfaces : A kinetic and mechanistic study." Licentiate thesis, KTH, Tillämpad fysikalisk kemi, 2014. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-145691.

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Oxidative dissolution of std. UO2 and UO2 doped with Cr2O3 and Al2O3, i.e. ADOPT, induced by H2O2 and γ radiation has been the main focus in this licentiate thesis. The catalytic decomposition of H2O2 on oxides like Gd2O3, HfO2, CeO2, Fe2O3 and CuO were also investigated. A kinetic study was performed by determining first and second order rate constants together with Arrhenius parameters for the decomposition of H2O2. The reactivity of H2O2 towards the oxides mentioned was observed to differ significantly despite their similarities. In the mechanistic study, the yields and dynamics of the form

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Scott, Mark Robert. "Nuclear forensics: attributing the source of spent fuel used in an RDD event." Texas A&M University, 2005. http://hdl.handle.net/1969.1/2368.

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An RDD attack against the U.S. is something America needs to prepare against. If such an event occurs the ability to quickly identify the source of the radiological material used in an RDD would aid investigators in identifying the perpetrators. Spent fuel is one of the most dangerous possible radiological sources for an RDD. In this work, a forensics methodology was developed and implemented to attribute spent fuel to a source reactor. The specific attributes determined are the spent fuel burnup, age from discharge, reactor type, and initial fuel enrichment. It is shown that by analyzing the

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48

Willman, Christofer. "Applications of Gamma Ray Spectroscopy of Spent Nuclear Fuel for Safeguards and Encapsulation." Doctoral thesis, Uppsala : Acta Universitatis Upsaliensis, 2006. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-7116.

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Hoggett-Jones, Craig. "Modelling and assessment of partitioning and transmutation approaches to spent nuclear fuel management." Thesis, University of Strathclyde, 2001. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.248302.

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Park, Yongsoo S. M. Massachusetts Institute of Technology. "Improving heat transfer in spent nuclear fuel disposal packages using metallic void fillers." Thesis, Massachusetts Institute of Technology, 2016. http://hdl.handle.net/1721.1/107320.

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Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2016.<br>Cataloged from student-submitted PDF version of thesis.<br>Includes bibliographical references (pages 71-75).<br>Disposal packages containing high heat generating spent nuclear fuels (SNF) require improved heat transfer to keep the peak cladding temperature from going above the tolerance limit. Filling the accessible void spaces between the container and the SNF with a high heat conducting metal is a potential solution. In metal casting, it is well known that a gap forms at the metal-mo

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