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Dissertations / Theses on the topic 'Spent nuclear fuel storage'

Author: Grafiati

Published: 5 June 2025

Last updated: 1 August 2025

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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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Made available in DSpace on 2014-10-09T12:49:28Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:01:16Z (GMT). No. of bitstreams: 0<br>Dissertacao (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares, IPEN/CNEN-SP

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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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Made available in DSpace on 2014-10-09T12:27:08Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:56:18Z (GMT). No. of bitstreams: 0<br>Tese (Doutoramento)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

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3

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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4

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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5

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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6

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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7

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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8

Burns, 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.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.<br>Includes bibliographical references.<br>This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.<br>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 storin

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9

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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10

Fortkamp, 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.

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11

Romanato, Luiz Sergio. ""Armazenagem de combustível nuclear queimado"." Universidade de São Paulo, 2005. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-15052006-220434/.

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Quando um país se torna auto-suficiente em uma parte do ciclo nuclear, quanto à produção de combustível que será usado em suas centrais nucleares para a geração de energia, precisa voltar sua atenção para a melhor forma de armazenar este combustível após a sua utilização. A armazenagem do combustível nuclear queimado é uma prática necessária e utilizada nos dias atuais em todo o mundo como temporária, tanto por países que não têm definido o plano de destinação final, isto é, o repositório definitivo, como também por aqueles que já o possuem. Existem dois aspectos principais que envolvem os com

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12

Solis, Dominic (Dominic R. ). "COMSOL finite-element analysis : residual stress measurement of representative 304L/308L weld in spent fuel storage containers." Thesis, Massachusetts Institute of Technology, 2014. http://hdl.handle.net/1721.1/97965.

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Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2014.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (pages 30-31).<br>The ultimate storage destination for spent nuclear fuel in the United States is currently undecided. Spent fuel will be stored indefinitely in dry cask storage systems typically located on-site at the reactor or at a dedicated independent spent fuel storage installation (ISFSI). Since these canisters were not originally designed or qualified for indefinite storage, there is a need to quantify

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13

Sharifi, Brojerdi Fatemeh. "Analysis of Seismic Data Acquired at the Forsmark Site for Storage of Spent Nuclear Fuel, Central Sweden." Doctoral thesis, Uppsala universitet, Geofysik, 2015. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-251621.

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The Forsmark area, the main study area in this thesis, is located about 140 km north of Stockholm, central Sweden. It belongs to the Paleoproterozoic Svecokarelian orogen and contains several major ductile and brittle deformation zones including the Forsmark, Eckarfjärden and Singö zones. The bedrock between these zones, in general is less deformed and considered suitable for a nuclear waste repository. While several site investigations have already been carried out in the area, this thesis focuses primarily on (i) re-processing some of the existing reflection seismic lines to improve imaging

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14

Weirich, Timothy Douglas. "Evaluating the Potential for Atmospheric Corrosion of 304 Stainless Steel Used for Dry Storage of Spent Nuclear Fuel." The Ohio State University, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1557098372186951.

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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

Mičian, Peter. "Bezpečnost skladování paliva ve vodním prostředí." Master's thesis, Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií, 2018. http://www.nusl.cz/ntk/nusl-377026.

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This diploma thesis deals with storing the spent nuclear fuel and reviewing its safety. The theoretical part analyzes the processes taking place while the fuel is being used, such as fission, isotopic changes, fission gas release, cracking, swelling and densification of fuel pellet. The thesis is also focused on handling the spent fuel and on the way it makes from the reactor, through the spent fuel pool, the transportation, various kinds of storing, till the reprocessing and final deep geological repository. Furthermore, this part of the thesis briefly discusses computing code MCNP, its main

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17

Hlatký, Pavel. "Studium tepelných a fyzikálních vlastností skladovacích kontejnerů pro použité jaderné palivo." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2011. http://www.nusl.cz/ntk/nusl-229829.

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This work deals with questions of spent fuel storage casks thermal and physical properties investigation. Foundations of mathematics which are necessary for describing field of temperature are included. The work itself contains calculation methods which are split into two parts. The first one deals with simplified analytic solution and the second part solves the whole problem by the numerical computation.

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18

RODRIGUES, ANTONIO C. I. "Estudo e projeto de novos cestos com boro para o armazenamento de elementos combustíveis queimados do reator IEA-R1." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26823.

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Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2016-11-11T16:39:02Z No. of bitstreams: 0<br>Made available in DSpace on 2016-11-11T16:39:02Z (GMT). No. of bitstreams: 0<br>O reator de pesquisas IEA-R1 opera em regime de 40 h semanais à potência de 4,5 MW. Nestas condições, os cestos disponíveis para o armazenamento dos elementos combustíveis irradiados possuem menos de metade da sua capacidade inicial. Assim, nestas condições de operação, teremos apenas cerca de seis anos de capacidade para armazenamento. Considerando que a vida útil desejada do IEA-R1 seja de pelo menos mais 20 anos,

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19

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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20

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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21

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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22

Шевченко, Валентина Владимировна, Алла Викторовна Дон та Татьяна Геннадиевна Кононова. "Проблемы современной электроэнергетики, пути ее развития и оценка источников электроэнергии". Thesis, Accent Graphics Communications & Publishing, Canada, 2019. http://repository.kpi.kharkov.ua/handle/KhPI-Press/46945.

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23

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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24

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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25

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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26

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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27

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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28

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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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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30

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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31

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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32

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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33

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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34

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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35

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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36

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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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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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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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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40

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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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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42

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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43

Martinik, Tomas. "Development of Differential Die-Away Instrument for Characterization of Swedish Spent Nuclear Fuel." Licentiate thesis, Uppsala universitet, Tillämpad kärnfysik, 2016. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-268143.

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The Next Generation Safeguards Initiative Spent Fuel (NGSI-SF) project was established in 2009 by the U.S. Departmentof Energy with main objective to investigate, and potentially develop and test new technologies for spent nuclearfuel (SNF) characterization. In Sweden the SNF is currently being considered to be verified and encapsulated in canistersand deposited into a geological repository. The need for an independent instrument for SNF verification by theSwedish operator turned into the collaborative effort with NGSI-SF to develop an instrument for future deployment inSweden.One of the techn

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Lundqvist, Tobias. "Investigation of Algebraic Reconstruction Techniques for Tomographic Measurements on Spent Nuclear Fuel Assemblies." Thesis, Uppsala universitet, Institutionen för strålningsvetenskap, 2004. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-307832.

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A non-destructive tomographic measurement technique for application on nuclear fuel assemblies has beendeveloped at the Uppsala University. Using this technique, the rod-by-rod distribution of selectedradioactive isotopes is determined experimentally. In the present work, the numerical technique to reconstruct the activity distribution inside the fuelassemblies has been analyzed. Three iterative reconstruction algorithms have been investigated, ART(Additive Reconstruction Technique), ML (Maximum Likelihood) and ASIRT (Additive SimultaneousIterative Reconstruction Technique). It was found that

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45

Larsson, Cecilia. "Upgrade and validation of PHX2MCNP for criticality analysis calculations for spent fuel storage pools." Thesis, Uppsala University, Applied Nuclear Physics, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-113572.

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<p>A few years ago Westinghouse started the development of a new method for criticality calculations for spent nuclear fuel storage pools called “PHOENIX-to–MCNP” (PHX2MCNP). PHX2MCNP transfers burn-up data from the code PHOENIX to use in MCNP in order to calculate the criticality. This thesis describes a work with the purpose to further validate the new method first by validating the software MCNP5 at higher water temperatures than room temperature and, in a second step, continue the development of the method by adding a new feature to the old script. Finally two studies were made to examine

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46

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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47

Lovett, Phyllis Maria. "An experiment to simulate the heat transfer properties of a dry, horizontal spent nuclear fuel assembly." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/17294.

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Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1991.<br>Science hard copy bound in 1 v.<br>Includes bibliographical references (leaves 163-165).<br>by Phyllis Maria Lovett.<br>M.S.

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48

Burdo, James. "Monte Carlo Characterization of PWR Spent Fuel Assemblies to Determine the Detectability of Pin Diversion." University of Cincinnati / OhioLINK, 2010. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1267546076.

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49

Lundström, Tim. "Radiation chemistry of aqueous solutions related to nuclear reactor systems and spent fuel management /." Linköping : Univ, 2003. http://www.bibl.liu.se/liupubl/disp/disp2003/tek840s.pdf.

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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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