bibliography.bib

@thesis{cisneros_pebble_2013,
	title = {Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor ({PB}-{FHR})},
	url = {http://gradworks.umi.com/36/16/3616613.html},
	institution = {University of California Berkeley},
	type = {phdthesis},
	author = {Cisneros, Anselmo Tomas},
	urldate = {2014-09-23},
	date = {2013},
	keywords = {Anselmo Tomas, {BERKELEY} Ehud Greenspan Cisneros, Jr., Nuclear engineering Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor ({PB}-{FHR}) {UNIVERSITY} {OF} {CALIFORNIA}},
	file = {Cisneros Thesis 3_8.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/E9APZNRH/Cisneros Thesis 3_8.pdf:application/pdf;Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/IP8UJMPV/login.html:text/html},
}

@unpublished{harlan_x-energy_2018,
	location = {Rockville, {MD}},
	title = {X-energy Xe-100 Reactor initial {NRC} meeting},
	url = {https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML18253A109},
	note = {Xe-100 Reactor initial {NRC} meeting},
	author = {Harlan, Bowers},
	urldate = {2019-09-20},
	date = {2018-09-11},
	file = {X-energy Xe-100 Reactor initial NRC meeting:/home/zoe/snap/zotero-snap/common/Zotero/storage/HC5YWNJD/X-energy Xe-100 Reactor initial NRC meeting.pdf:application/pdf},
}

@report{amir_afzali_high_2018,
	title = {High Temperature, Gas-Cooled Pebble Bed Reactor licensing Modernization Project Demonstration},
	url = {https://www.nrc.gov/docs/ML1822/ML18228A779.pdf},
	number = {{SC}-29980-200 Rev 0},
	institution = {Southern Company},
	author = {{Amir Afzali}},
	urldate = {2019-10-10},
	date = {2018-08},
	note = {U.S. Department of Energy ({DOE})
Office of Nuclear Energy
Under {DOE} Idaho Operations Office
Contract {DE}-{AC}07-0SID14517},
	file = {ML18228A779.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/UUQZ8CCP/ML18228A779.pdf:application/pdf},
}

@report{moe_licensing_2018,
	title = {Licensing Modernization Project for Advanced Reactor Technologies: {FY} 2018 Project Status Report},
	shorttitle = {Licensing Modernization Project for Advanced Reactor Technologies},
	institution = {Idaho National Lab.({INL}), Idaho Falls, {ID} (United States)},
	author = {Moe, Wayne},
	date = {2018},
	file = {Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/VAEGRT5E/1471714.html:text/html;Full Text:/home/zoe/snap/zotero-snap/common/Zotero/storage/UXEXXLAC/Moe - 2018 - Licensing Modernization Project for Advanced React.pdf:application/pdf},
}

@online{ho_graphite_1988,
	title = {Graphite design handbook},
	url = {https://www.osti.gov/servlets/purl/714896/},
	author = {Ho, F.H. and Vollmar, R. and Turner, R.},
	urldate = {2019-09-23},
	date = {1988-09},
	file = {Graphite design handbook:/home/zoe/snap/zotero-snap/common/Zotero/storage/TRUMJ6TL/Graphite design handbook.pdf:application/pdf},
}

@online{el-genk_post-operation_2018,
	title = {Post-operation radiological source term and dose rate estimates for the Scalable {LIquid} Metal-cooled small Modular Reactor {\textbar} Elsevier Enhanced Reader},
	url = {https://reader.elsevier.com/reader/sd/pii/S0306454918300550?token=72A5D70FC4A85A4EF41A5E9256B0B120D6DBE8E80266F7BFD35BB528A887F463F8647F134921742AAE435B0A9D635F61},
	author = {El-Genk, Mohamed and Schriener, Timothy},
	urldate = {2019-09-20},
	date = {2018-02-22},
	langid = {english},
	doi = {10.1016/j.anucene.2018.02.001},
	file = {Post-operation radiological source term and dose r.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/9MVSMI2K/Post-operation radiological source term and dose r.pdf:application/pdf;Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/R4W23UY3/S0306454918300550.html:text/html},
}

@online{accuratus_silicon_2013,
	title = {Silicon Carbide {SiC} Material Properties},
	url = {https://www.accuratus.com/silicar.html},
	author = {Accuratus},
	urldate = {2019-09-24},
	date = {2013},
}

@report{johnson_properties_1976,
	title = {Properties of unirradiated fuel element graphites H-451 and {TS}-1240},
	url = {http://www.osti.gov/servlets/purl/7283150-NEjJgM/},
	pages = {GA--A--13752, 7283150},
	number = {{GA}-A-13752, 7283150},
	author = {Johnson, W.R. and Engle, G.B.},
	urldate = {2019-09-24},
	date = {1976-01-31},
	langid = {english},
	doi = {10.2172/7283150},
	file = {Johnson and Engle - 1976 - Properties of unirradiated fuel element graphites .pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/3GBQMDNT/Johnson and Engle - 1976 - Properties of unirradiated fuel element graphites .pdf:application/pdf},
}

@article{richards_reaction_1990,
	title = {Reaction of nuclear-grade graphite with low concentrations of steam in the helium coolant of an {MHTGR}},
	volume = {15},
	issn = {0360-5442},
	url = {http://www.sciencedirect.com/science/article/pii/036054429090112F},
	doi = {10.1016/0360-5442(90)90112-F},
	abstract = {The fuel elements for the {MHTGR} are manufactured from nucleargrade graphite and have core-residence times of about 1000 days that are determined from considerations based on nuclear-design criteria. To ensure structural integrity and minimize the risk to plant investment, a potential limitation of fuel-element life may result from graphite corrosion in the high-temperature regions of the core (T ≅ 1100 °C). This corrosion is caused primarily by reactions of graphite with the low concentrations of steam (0.01–0.1 ppm) that are normally present in the helium coolant Economical operation of the reactor requires that the steam concentrations be maintained at such low levels that corrosion rates will not impact the normal fuel cycle. In this paper, we develop a graphite-corrosion model and address this important practical problem.},
	pages = {729--739},
	number = {9},
	journaltitle = {Energy},
	shortjournal = {Energy},
	author = {Richards, M. B.},
	urldate = {2019-09-23},
	date = {1990-09-01},
	file = {ScienceDirect Full Text PDF:/home/zoe/snap/zotero-snap/common/Zotero/storage/FQI6AW4D/Richards - 1990 - Reaction of nuclear-grade graphite with low concen.pdf:application/pdf;ScienceDirect Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/T8R6YN5K/036054429090112F.html:text/html},
}

@article{nagley_fabrication_2010,
	title = {Fabrication of Uranium Oxycarbide Kernels for {HTR} Fuel},
	abstract = {Babcock and Wilcox (B\&W) has been producing high quality uranium oxycarbide ({UCO}) kernels for Advanced Gas Reactor ({AGR}) fuel tests at the Idaho National Laboratory. In 2005, 350-μm, 19.7\% 235U-enriched {UCO} kernels were produced for the {AGR}-1 test fuel. Following coating of these kernels and forming the coated-particles into compacts, this fuel was irradiated in the Advanced Test Reactor ({ATR}) from December 2006 until November 2009. B\&W produced 425-μm, 14\% enriched {UCO} kernels in 2008, and these kernels were used to produce fuel for the {AGR}-2 experiment that was inserted in {ATR} in 2010. B\&W also produced 500μm, 9.6\% enriched {UO}2 kernels for the {AGR}-2 experiment. Kernels of the same size and enrichment as {AGR}-1 were also produced for the {AGR}-3/4 experiment. In addition to fabricating enriched {UCO} and {UO}2 kernels, B\&W has produced more than 100 kg of natural uranium {UCO} kernels which are being used in coating development tests. Successive lots of kernels have demonstrated consistent high quality and also allowed for fabrication process improvements. Improvements in kernel forming were made subsequent to {AGR}-1 kernel production. Following fabrication of {AGR}-2 kernels, incremental increases in sintering furnace charge size have been demonstrated. Recently small scale sintering tests using a small development furnace equipped with a residual gas analyzer ({RGA}) have increased understanding of how kernel sintering parameters affect sintered kernel properties. The steps taken to increase throughput and process knowledge have reduced kernel production costs. Studies have been performed of additional modifications toward the goal of increasing capacity of the current fabrication line to use for production of first core fuel for the Next Generation Nuclear Plant ({NGNP}) and providing a basis for the design of a full scale fuel fabrication facility.},
	pages = {10},
	author = {Nagley, Scott G and Barnes, Charles M and Husser, {DeWayne} L and Nowlin, Melvin L and Richardson, W Clay},
	date = {2010},
	langid = {english},
	file = {Nagley et al. - 2010 - Fabrication of Uranium Oxycarbide Kernels for HTR .pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/YNVEHCAU/Nagley et al. - 2010 - Fabrication of Uranium Oxycarbide Kernels for HTR .pdf:application/pdf},
}

@collection{internationale_atomenergie-organisation_accident_2008,
	location = {Vienna},
	title = {Accident analysis for nuclear power plants with modular high temperature gas cooled reactors},
	isbn = {978-92-0-100108-5},
	series = {Safety reports series},
	pagetotal = {45},
	number = {54},
	publisher = {{IAEA}},
	editor = {Internationale Atomenergie-Organisation},
	date = {2008},
	langid = {english},
	note = {{OCLC}: 637106283},
	file = {Internationale Atomenergie-Organisation - 2008 - Accident analysis for nuclear power plants with mo.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/LKCQLZUZ/Internationale Atomenergie-Organisation - 2008 - Accident analysis for nuclear power plants with mo.pdf:application/pdf},
}

@article{rainer_fission_2008,
	title = {Fission Product Transport and Source Terms in {HTRs}: Experience from {AVR} Pebble Bed Reactor},
	volume = {2008},
	doi = {10.1155/2008/597491},
	shorttitle = {Fission Product Transport and Source Terms in {HTRs}},
	abstract = {Fission products deposited in the coolant circuit outside of the active core play a dominant role in source term estimations for advanced small pebble bed {HTRs}, particularly in design basis accidents ({DBA}). The deposited fission products may be released in depressurization accidents because present pebble bed {HTR} concepts abstain from a gas tight containment. Contamination of the circuit also hinders maintenance work. Experiments, performed from 1972 to 88 on the {AVR}, an experimental pebble bed {HTR}, allow for a deeper insight into fission product transport behavior. The activity deposition per coolant pass was lower than expected and was influenced by fission product chemistry and by presence of carbonaceous dust. The latter lead also to inconsistencies between Cs plate out experiments in laboratory and in {AVR}. The deposition behavior of Ag was in line with present models. Dust as activity carrier is of safety relevance because of its mobility and of its sorption capability for fission products. All metal surfaces in pebble bed reactors were covered by a carbonaceous dust layer. Dust in {AVR} was produced by abrasion in amounts of about 5 kg/y. Additional dust sources in {AVR} were ours oil ingress and peeling of fuel element surfaces due to an air ingress. Dust has a size of about 1  μm, consists mainly of graphite, is partly remobilized by flow perturbations, and deposits with time constants of 1 to 2 h ours. In future reactors, an efficient filtering via a gas tight containment is required because accidents with fast depressurizations induce dust mobilization. Enhanced core temperatures in normal operation as in {AVR} and broken fuel pebbles have to be considered, as inflammable dust concentrations in the gas phase.},
	journaltitle = {Science and Technology of Nuclear Installations},
	shortjournal = {Science and Technology of Nuclear Installations},
	author = {Rainer, Moormann},
	date = {2008-07-14},
	file = {Full Text:/home/zoe/snap/zotero-snap/common/Zotero/storage/MHWF9P4D/Rainer - 2008 - Fission Product Transport and Source Terms in HTRs.pdf:application/pdf},
}

@article{eaves_can_2017,
	title = {Can North America’s advanced nuclear reactor companies help save the planet?},
	volume = {73},
	issn = {00963402},
	url = {http://search.ebscohost.com/login.aspx?direct=true&db=ulh&AN=120392537},
	doi = {10.1080/00963402.2016.1265353},
	abstract = {The advanced nuclear reactor industry in North America includes more than 50 companies and labs, which collectively have attracted some \$1.3 billion in private capital, as well as government grants and other assistance. Proponents of advanced nuclear reactors say that they are essential to help humans stop heating the planet with carbon dioxide emissions, and that they can do so without the safety, security, and cost concerns posed by older nuclear technology. Detractors say the advanced nuclear industry will never take off, and particularly not without government action that puts a price on carbon dioxide emissions, helping low- and no-carbon energy sources compete economically with fossil fuels. The author interviews company leaders, academics, scientists, and regulators to determine which companies are most likely to succeed.},
	pages = {27},
	number = {1},
	journaltitle = {Bulletin of the Atomic Scientists},
	shortjournal = {Bulletin of the Atomic Scientists},
	author = {Eaves, Elisabeth},
	urldate = {2019-09-20},
	date = {2017-01},
	keywords = {{NORTH} America, {NUCLEAR} {reactorsCARBON} dioxide {mitigationNUCLEAR} energy {policyNUCLEAR} energy -- Economic aspects},
	file = {EBSCO Full Text:/home/zoe/snap/zotero-snap/common/Zotero/storage/FE9SUQFP/Eaves - 2017 - Can North America’s advanced nuclear reactor compa.pdf:application/pdf},
}

@article{englert_accident_2017,
	title = {Accident Scenarios Involving Pebble Bed High Temperature Reactors},
	volume = {25},
	issn = {0892-9882, 1547-7800},
	url = {https://www.tandfonline.com/doi/full/10.1080/08929882.2017.1275320},
	doi = {10.1080/08929882.2017.1275320},
	abstract = {Proponents of high temperature gas cooled reactors argue that the reactor type is inherently safe and that severe accidents with core damage and radioactive releases cannot occur. The argument is primarily based on the safety features of the special form of the fuel. This paper examines some of the assumptions underlying the safety case for high temperature gas cooled reactors and highlights ways in which there could be fuel failure even during normal operations of the reactor; these failures serve to create a radioactive inventory that could be released under accident conditions. It then describes the severe accident scenarios that are the greatest challenge to high temperature gas cooled reactor safety: ingress of air or water into the core. Then, the paper offers an overview of what could be learned from the experiences with high temperature gas cooled reactors that have been built; their operating history indicates differences between actual operations and theoretical behavior. Finally, the paper describes some of the multiple priorities that often drive reactor design, and how safety is compromised in the process of optimizing other priorities.},
	pages = {42--55},
	number = {1},
	journaltitle = {Science \& Global Security},
	shortjournal = {Science \& Global Security},
	author = {Englert, Matthias and Frieß, Friederike and Ramana, M. V.},
	urldate = {2019-09-20},
	date = {2017-01-02},
	langid = {english},
	file = {Englert et al. - 2017 - Accident Scenarios Involving Pebble Bed High Tempe.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/QP969VJM/Englert et al. - 2017 - Accident Scenarios Involving Pebble Bed High Tempe.pdf:application/pdf},
}

@article{brits_control_2018,
	title = {A control approach investigation of the Xe-100 plant to perform load following within the operational range of 100 – 25 – 100\%},
	volume = {329},
	issn = {0029-5493},
	url = {http://www.sciencedirect.com/science/article/pii/S0029549317305630},
	doi = {10.1016/j.nucengdes.2017.11.041},
	series = {The Best of {HTR} 2016: International Topical Meeting on High Temperature Reactor Technology},
	abstract = {This paper describes the Xe-100 plant load following analyses done in Flownex® thermal-fluid system simulation software for normal operation from 100 – 25 – 100\% electrical power. The plant model encompasses all major components in the Xe-100 plant’s primary helium side including the pebble bed reactor, helium circulator, and steam generator, which transfers heat to the secondary steam side feeding steam to a steam-turbine in the Rankine cycle. The requirement for load following was to have a ramp rate of 5\% per minute when the turbine-generator power level ramps down from full power to 25\% power level and back to full power. The control approach, which pairs selected manipulated variables namely the: reactor control rods; helium circulator speed; feed water pump speed; turbine throttle valve to selected controlled variables namely the: reactor outlet temperature; main steam temperature; main steam pressure; turbine-generator power, is discussed in this paper. The controller actions on the manipulated variables and their response during the load following signal are illustrated. The deviation of the controlled variables during load following are shown within their required limits. This paper shows that the Xe-100 plant can achieve a 100 – 25 – 100\% electrical load ramp at a rate of 5\% per minute.},
	pages = {12--19},
	journaltitle = {Nuclear Engineering and Design},
	shortjournal = {Nuclear Engineering and Design},
	author = {Brits, Yvotte and Botha, Frikkie and van Antwerpen, Herman and Chi, Hans-Wolfgang},
	urldate = {2019-09-20},
	date = {2018-04-01},
	keywords = {Load-following, 100 – 25 – 100\%, Pebble bed reactor, Rankine},
	file = {ScienceDirect Full Text PDF:/home/zoe/snap/zotero-snap/common/Zotero/storage/IJG99TUZ/Brits et al. - 2018 - A control approach investigation of the Xe-100 pla.pdf:application/pdf;ScienceDirect Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/J8RCNDM3/S0029549317305630.html:text/html},
}

@online{espi_metals_graphite-pyrolytic_2019,
	title = {Graphite-Pyrolytic Grade},
	url = {https://www.espimetals.com/index.php/technical-data/74-graphite-pyrolytic-grade},
	author = {{ESPI Metals}},
	urldate = {2019-09-24},
	date = {2019},
	file = {Graphite-Pyrolytic Grade:/home/zoe/snap/zotero-snap/common/Zotero/storage/885GA2G6/74-graphite-pyrolytic-grade.html:text/html},
}

@article{ramana_checkered_2016,
	title = {The checkered operational history of high-temperature gas-cooled reactors},
	volume = {72},
	issn = {0096-3402},
	url = {https://doi.org/10.1080/00963402.2016.1170395},
	doi = {10.1080/00963402.2016.1170395},
	abstract = {The high-temperature gas-cooled reactor ({HTGR}) has long been considered a promising nuclear technology, and several countries are either considering the construction of new {HTGRs} or pursuing research into the field. In the past, both Germany and the United States spent large amounts of money to design and construct {HTGRs}, four of which fed electricity into the grid. Examining the performances of these {HTGRs} offers a useful guide to what one can expect from future {HTGRs}, if and when more are constructed, and reasons to reject that option altogether.},
	pages = {171--179},
	number = {3},
	journaltitle = {Bulletin of the Atomic Scientists},
	shortjournal = {Bulletin of the Atomic Scientists},
	author = {Ramana, M. V.},
	urldate = {2019-09-20},
	date = {2016-05-03},
	keywords = {nuclear power, advanced reactors, commercial viability, high-temperature gas-cooled reactor, {HTGR}, pebble-bed reactor, {GAS} cooled {reactorsNUCLEAR} {reactorsNUCLEAR} {energyHIGH} temperature {physicsINTERNATIONAL} relations},
	file = {EBSCO Full Text:/home/zoe/snap/zotero-snap/common/Zotero/storage/FHYVXK6Y/Ramana - 2016 - The checkered operational history of high-temperat.pdf:application/pdf;Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/4GY46CDI/00963402.2016.html:text/html;Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/CBURZJ4T/00963402.2016.html:text/html},
}

@article{zhang_economic_2007,
	title = {Economic potential of modular reactor nuclear power plants based on the Chinese {HTR}-{PM} project},
	volume = {237},
	issn = {0029-5493},
	url = {http://www.sciencedirect.com/science/article/pii/S002954930700283X},
	doi = {10.1016/j.nucengdes.2007.04.001},
	abstract = {Modular reactors with improved safety features have been developed after the Three-Mile Island accident. Economics of small modular reactors compared to large light water reactors whose power output is 10 times higher is the major issue for these kind of reactors to be introduced into the market. Based on the Chinese high temperature gas-cooled reactor pebble-bed module ({HTR}-{PM}) project, this paper analyzes economical potentials of modular reactor nuclear power plants. The reactor plant equipments are divided into 6 categories such as {RPV} and reactor internals, other {NSSS} components and so on. The economic impact of these equipments is analyzed. It is found that the major difference between an {HTR}-{PM} plant and a {PWR} is the capital costs of the {RPV} and the reactor internals. The fact, however, that {RPV} and reactor internals costs account for only 2\% of the total plant costs in {PWR} plants demonstrates the limited influence of this difference. On the premise of multiple {NSSS} modules forming a nuclear power plant with a plant capacity equivalent to a typical {PWR} plant, an upper value and a target value of the total plant capital costs are estimated. A comparison is made for two design proposals of the Chinese {HTR}-{PM} project. It is estimated that the specific costs of a ready-to-build 2×250MWth modular plant will be only 5\% higher than the specific costs of one 458MWth plant. When considering the technical uncertainties of the latter, a 2×250MWth modular plant seems to be more attractive. Finally, four main points are listed for {MHTGRs} to achieve economic viability.},
	pages = {2265--2274},
	number = {23},
	journaltitle = {Nuclear Engineering and Design},
	shortjournal = {Nuclear Engineering and Design},
	author = {Zhang, Zuoyi and Sun, Yuliang},
	urldate = {2020-02-12},
	date = {2007-12-01},
	langid = {english},
	file = {ScienceDirect Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/3D969CFK/S002954930700283X.html:text/html;ScienceDirect Full Text PDF:/home/zoe/snap/zotero-snap/common/Zotero/storage/XSDP52QA/Zhang and Sun - 2007 - Economic potential of modular reactor nuclear powe.pdf:application/pdf},
}

@article{reutler_advantages_1984,
	title = {Advantages of going modular in {HTRs}},
	volume = {78},
	issn = {0029-5493},
	url = {http://www.sciencedirect.com/science/article/pii/002954938490298X},
	doi = {10.1016/0029-5493(84)90298-X},
	abstract = {A multitude of problems that are encountered in large {HTR} power plans, constructively as well as concerning plant safety, can be related to the mere physical size of a large reactor core. In limiting the thermal power of an {HTR}-module to approximately 200 {MW} an inherent limitation of the fuel element temperature below critical values can be guaranteed for all possible core heat up accidents. Consequently, a significant failure rate of coated particles can be excluded and, hence, out of physical reasons, no intolerable fission product release from the core will ever have to be considered. The {HTR}-module is so qualified and very well suited for all possible plant sides which have to be taken into consideration for medium sized plants for the production of process steam and electricity. The cost investigations show considerable cost advantages for modular {HTRs}. For German conditions it was found that even a four-modular plant (800 {MW}/thermal) is competitive with a fossile-fueled plant of the same size, the specific plant costs were evaluated to be {DM} 4700/{kW} (electric). Moreover the investigations show that the increase of the power of the modular unit yields only small cost advantages, therefore in a modularized power plant it even would be possible to reduce the power of a modular unit below 200 {MW} without having to cope with severe economic penalties, if the distance from technological or safety limits is felt to be too small.},
	pages = {129--136},
	number = {2},
	journaltitle = {Nuclear Engineering and Design},
	shortjournal = {Nuclear Engineering and Design},
	author = {Reutler, H. and Lohnert, G. H.},
	urldate = {2020-02-12},
	date = {1984-04-01},
	langid = {english},
	file = {ScienceDirect Full Text PDF:/home/zoe/snap/zotero-snap/common/Zotero/storage/MG8SLPED/Reutler and Lohnert - 1984 - Advantages of going modular in HTRs.pdf:application/pdf;ScienceDirect Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/LQLHLR65/002954938490298X.html:text/html},
}

@report{helmreich_year_2017,
	title = {Year One Summary of X-energy Pebble Fuel Development at {ORNL}},
	url = {https://www.osti.gov/biblio/1376502},
	abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information},
	number = {{ORNL}/{TM}-2017/337},
	institution = {Oak Ridge National Lab. ({ORNL}), Oak Ridge, {TN} (United States)},
	author = {Helmreich, Grant W. and Hunn, John D. and {McMurray}, Jake W. and Hunt, Rodney D. and Jolly, Brian C. and Trammell, Michael P. and Brown, Daniel R. and Blamer, Brandon J. and Reif, Tyler J. and Kim, Howard T.},
	urldate = {2020-02-12},
	date = {2017-06-01},
	doi = {10.2172/1376502},
	file = {Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/8YZV72YC/1376502.html:text/html;Full Text PDF:/home/zoe/snap/zotero-snap/common/Zotero/storage/W3MCF5V4/Helmreich et al. - 2017 - Year One Summary of X-energy Pebble Fuel Developme.pdf:application/pdf},
}

@report{hussain_advances_2018,
	location = {Vienna, Austria},
	title = {Advances in Small Modular Reactor Technology Developments},
	url = {http://aris.iaea.org},
	abstract = {The driving forces in the development of {SMRs} are their specific characteristics. They can be deployed
incrementally to closely match increasing energy demand resulting in a moderate financial commitment for
countries or regions with smaller electricity grids. {SMRs} show the promise of significant cost reduction
through modularization and factory construction which should further improve the construction schedule and
reduce costs. In the area of wider applicability {SMR} designs and sizes are better suited for partial or
dedicated use in non-electrical applications such as providing heat for industrial processes, hydrogen
production or sea-water desalination. Process heat or cogeneration results in significantly improved thermal
efficiencies leading to a better return on investment. Some {SMR} designs may also serve niche markets, for
example to burn nuclear waste.
Booklets on the status of {SMR} technology developments have been published in 2012, 2014 and 2016. The
objective is to provide Member States with a concise overview of the latest status of {SMR} designs. This
booklet is reporting the advances in design and technology developments of {SMRs} of all the major
technology lines within the category of {SMRs}. It covers land based and marine based water-cooled reactors,
high temperature gas cooled reactors, liquid metal, sodium and gas-cooled fast neutron spectrum reactors and
molten salt reactors. The content on the specific {SMRs} is provided by the responsible institute or
organization and is reproduced, with permission, in this booklet.},
	institution = {Nuclear Power Technology Development Section, Division of Nuclear Power of the {IAEA} Department of Nuclear Energy},
	type = {A Supplement to: {IAEA} Advanced Reactors Information System ({ARIS})},
	author = {Hussain, M. and Reitsma, F. and Subki, M.H. and Kiuchi, H.},
	date = {2018-09},
	file = {IAEA - 2018 - Advances in Small Modular Reactor Technology Devel.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/L89AXQ6V/IAEA - 2018 - Advances in Small Modular Reactor Technology Devel.pdf:application/pdf},
}

@unpublished{harlan_ans_2017,
	location = {{DC} {ANS} Conference 2017},
	title = {{ANS} Xe 100 Overview 2017},
	url = {http://local.ans.org/dc/wp-content/uploads/2014/01/ANS_Xe-100-Overview_04052017.pdf},
	author = {Harlan, Bowers},
	urldate = {2020-02-12},
	date = {2017-04-04},
	file = {ANS_Xe-100-Overview_04052017.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/98BPL5ZA/ANS_Xe-100-Overview_04052017.pdf:application/pdf},
}

@online{agnihotri_intrinsically_2017,
	title = {An Intrinsically Safe Generation {IV} Reactor},
	url = {http://digitaleditions.nuclearplantjournal.com/SO17/24/},
	abstract = {The September-October 2017 digital version of Nuclear Plant Journal. Subscribe for free!},
	titleaddon = {Nuclear Plant Journal},
	author = {Agnihotri, Newal and Mulder, Eben},
	urldate = {2020-02-25},
	date = {2017-10},
	file = {Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/L9X2M3TK/24.html:text/html},
}

@article{hereward_measurement_1947,
	title = {Measurement of the Diffusion Length of Thermal Neutrons in Graphite},
	volume = {25a},
	issn = {1923-4287},
	url = {https://www.nrcresearchpress.com/doi/abs/10.1139/cjr47a-002},
	doi = {10.1139/cjr47a-002},
	abstract = {The theory and method of measuring the diffusion length of thermal neutrons in graphite are discussed in detail. The graphite pile was a rectangular parallelepiped, 185.8 cm. square and 153.6 cm. h..., non disponible},
	pages = {15--25},
	number = {1},
	journaltitle = {Canadian Journal of Research},
	shortjournal = {Can. J. Res.},
	author = {Hereward, H. G. and Paneth, H. R. and Laurence, G. C. and Sargent, B. W.},
	urldate = {2020-09-16},
	date = {1947-01-01},
	note = {Publisher: {NRC} Research Press},
	file = {NRC Research Press Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/F29SJCQU/cjr47a-002.html:text/html},
}

@unpublished{mulder_reactor_2020,
	location = {Urbana, {IL}},
	title = {Reactor Physics Overview of the Xe-100 {GEN} {IV} Reactor},
	rights = {© 2020 X Energy {LLC}, all rights reserved},
	abstract = {I intend to provide a short, high-level overview of X-energy and its offerings in terms of fuel and reactors. In the second part to my talk I would like to give a high-level technology overview. In particular the physics codes under development for designing pebble bed high temperature gas-cooled reactors will be discussed. The differences in the application of the physics between the Xe-100 and typical {LWRs} will be highlighted. Examples will be provided of analyses performed of the operational states and control measures to add insight into the Xe-100 design considerations.},
	type = {Invited Seminar},
	howpublished = {Invited Seminar},
	note = {{NPRE} 596 Graduate Seminar},
	author = {Mulder, Eben},
	date = {2020-09-01},
	file = {Mulder - Reactor Physics Overview of the Xe-100 GEN IV Reac.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/V888PQE9/Mulder - Reactor Physics Overview of the Xe-100 GEN IV Reac.pdf:application/pdf},
}

@inproceedings{scopatz_pyne:_2012,
	location = {San Diego, {CA}, {USA}},
	title = {{PyNE}: Python for Nuclear Engineering},
	volume = {107},
	url = {http://epubs.ans.org/?a=14978},
	series = {Reactor Physics: General—I},
	abstract = {{PyNE}, or 'Python for Nuclear Engineering' 1 , is a nascent
free and open source C++/Cython/Python package for perform-
ing common nuclear engineering tasks. This is intended as a
base level tool kit - akin to {SciPy} or Biopython - for common
algorithms in the nuclear science and engineering domain.
The remainer of this paper is composed of a discussion of the
difficulties which prevented {PyNE} from being written earlier,
a listing of the first cut capabilities, and a description of why
{PyNE} has thus far been successful and what future features are
currently planned.},
	eventtitle = {American Nuclear Society Winter Conference},
	pages = {985--987},
	booktitle = {Transactions of the American Nuclear Society},
	publisher = {American Nuclear Society},
	author = {Scopatz, Anthony and Romano, Paul K. and Wilson, Paul P. H. and Huff, Kathryn D.},
	date = {2012-11-11},
	file = {trans_v107_n1_pp985-987.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/TQ9E3XGC/trans_v107_n1_pp985-987.pdf:application/pdf},
}

@online{leppanenjaakko_serpent_2015,
	title = {Serpent – a Continuous-energy Monte {CarloReactor} Physics Burnup Calculation Code},
	url = {http://montecarlo.vtt.fi/download/Serpent_manual.pdf},
	author = {Leppänen,Jaakko},
	urldate = {2021-02-21},
	date = {2015-06-18},
	file = {Serpent_manual.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/KBSMK8Q6/Serpent_manual.pdf:application/pdf},
}

@article{tulluri_analysis_nodate,
	title = {Analysis of random packing of uniform spheres using the Monte Carlo simulation method},
	pages = {107},
	author = {Tulluri, Sai S},
	langid = {english},
	file = {Tulluri - Analysis of random packing of uniform spheres usin.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/MYFV45D8/Tulluri - Analysis of random packing of uniform spheres usin.pdf:application/pdf},
}

@online{nanstad_milestone_2011,
	title = {Milestone Report-08-2011-Assessment of Thermal Annealing-{FINAL}.pdf},
	url = {https://www.energy.gov/sites/prod/files/Milestone%20Report-08-2011-Assessment%20of%20Thermal%20Annealing-FINAL.pdf},
	author = {Nanstad, R.K. and Server, W. L.},
	urldate = {2021-02-25},
	date = {2011-09},
	file = {Milestone Report-08-2011-Assessment of Thermal Annealing-FINAL.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/V5JGWY85/Milestone Report-08-2011-Assessment of Thermal Annealing-FINAL.pdf:application/pdf},
}

@report{chopra_degradation_2010,
	title = {Degradation of {LWR} Core Internal Materials due to Neutron Irradiation},
	url = {https://www.nrc.gov/docs/ML1027/ML102790482.pdf},
	institution = {Nuclear Regulatory Commission},
	author = {Chopra, O. K. and S. Rao, Appajosula},
	date = {2010-12},
}

@article{dudley_reactor_2006,
	title = {{THE} {REACTOR} {CORE} {NEUTRONIC} {MODEL} {FOR} {THE} {PBMR} {PLANT} {TRAINING} {SIMULATOR}},
	abstract = {The technical aspects of the {PBMR} Plant and Training Simulator with respect to the Reactor Core Neutronic model are described in this paper. The theory and solution techniques used in modelling and simulating the neutronic core are also described. The neutronic model derivation is discussed, as well as the model capabilities and model requirements. The model formulation utilizes the nuclear reactor software called Remark©. The derived model is called the {PBMR}-Remark Neutronic model. A preliminary test result is included for completeness.},
	pages = {13},
	journaltitle = {South Africa},
	author = {Dudley, Trevor and Tsaoi, Oliver and Mulder, Eben},
	date = {2006},
	langid = {english},
	file = {Dudley et al. - 2006 - THE REACTOR CORE NEUTRONIC MODEL FOR THE PBMR PLAN.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/4IKENMVP/Dudley et al. - 2006 - THE REACTOR CORE NEUTRONIC MODEL FOR THE PBMR PLAN.pdf:application/pdf},
}

@report{mulder_pebble_1999,
	title = {Pebble bed reactor with equalised core power distribution inherently safe and simple},
	url = {https://juser.fz-juelich.de/record/820874/},
	abstract = {Based an the physical properties of pebble bed reactors, a multitude of variations are possible in the layout of the fuel and fuelling schemes. These properties are being exploited in a conceptual design, offering an attractive layout in terms of the inter-related aspects of safety, economy and simplicity. Advantages of this layout are highlighted by means of a direct comparison to a similar reactor characterised by a conventional fuelling scheme. The proposed concept is characterised by the following: In the {OTTO} (\${\textbackslash}underline\{O\}\$nce \${\textbackslash}underline\{T\}\$hrough \${\textbackslash}underline\{T\}\$hen \${\textbackslash}underline\{O\}\$ut) fuelling scheme the fuel spheres pass through the core once only. Therefore the fuel recirculation subsystems may be negated in the design. The {PAP}2 (\${\textbackslash}underline\{P\}\$ower \${\textbackslash}underline\{A\}\$djusted by-\${\textbackslash}underline\{P\}\$oison) fuelling scheme involves adding of pebbles with burnable poison that will lead to a strong flattening of the axial core power density. These absorber spheres contain coated particles of B\$\_\{4\}\$C instead of fuel. In the radial direction flattening of the power density is achieved by increasing the loading of graphite spheres into the central fuelling channel (2-zone fuelling). The advantages of a relatively high power performance (250 {MW}\$\_\{th\}\$), a high heavy metal loading per fuel element (14g\$\_\{{HM}\}\$), and high burnup (120 {MWd}/Kg\$\_\{{HM}\}\$ can be directly translated into an economical advantage. Lowly enriched uranium is employed as fuel which provides a highly proliferation resistant solution when coupled to the high burnup and oncethrough only cycle. The control capability includes unlimited power variations within the operational range of 100-20-100\%. In the proposed concept the reactor is coupled to a power conversion unit which employs a direct cycle helium power turbine. - During a loss of coolant ({DLOFC} = Depressurised Loss Of Forced Coolant) event, the fuel element temperature is passively limited below 1600 °C, thus avoiding any radioactive release. Computationally the reactor is simulated by means of the {VSOP} (\${\textbackslash}underline\{V\}\$ery \${\textbackslash}underline\{S\}\$uperior \${\textbackslash}underline\{O\}\$ld \${\textbackslash}underline\{P\}\$rograms) staple of codes. For this purpose the following extensions to the code have been developed: A so-called onion-skin burnup model is introduced to calculate the burnup of the B\$\_\{4\}\$C kernels. Within the absorber spheres the burnup of the coated (B\$\_\{4\}\$C) particles are being followed in a nurnher of separate fiel zones. Based an experimental findings a fuel sphere flog scheine has been developed, which moves downward in parallel in the top area, while the bottorn area is re-organised in a funnel shape towards die de fuelling pipe in accordance with the angle of the conus and discharge rate. A 3-D geometric modeller, {FIRZIT} (i.e. in \${\textbackslash}phi\$-r-z-ordinates) has been exclusively developed for modelling the so-called noses, employed for housing the cold shut down system in a core with 3,5 m diarneter. This enables the modelling of various pebble flow schernes in azimuthal segments. [...] Mulder, E. J.},
	number = {{FZJ}-2016-06138},
	institution = {Forschungszentrum Jülich {GmbH} Zentralbibliothek, Verlag},
	author = {Mulder, E. J.},
	urldate = {2021-02-25},
	date = {1999},
	langid = {english},
	file = {Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/BNWJUVGD/820874.html:text/html},
}

@article{simnad_early_1991,
	title = {The early history of high-temperature helium gas-cooled nuclear power reactors},
	volume = {16},
	issn = {0360-5442},
	url = {https://www.sciencedirect.com/science/article/pii/036054429190084Y},
	doi = {10.1016/0360-5442(91)90084-Y},
	series = {High-temperature Helium Gas-cooled Nuclear reactors: Past Experience Current Status and Future Prospects},
	abstract = {The original concepts in the proposals for hightemperature helium gas-cooled power reactors by Farrington Daniels, during the decade 1944–1955, are summarized. The early research on the development of the helium gas-cooled power reactors is reviewed, and the operational experiences with the first generation of {HTGRs} are discussed.},
	pages = {25--32},
	number = {1},
	journaltitle = {Energy},
	shortjournal = {Energy},
	author = {Simnad, Massoud T.},
	urldate = {2021-02-25},
	date = {1991-01-01},
	langid = {english},
	file = {ScienceDirect Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/76NC8BEW/036054429190084Y.html:text/html},
}

@report{nasas_goddard_institute_for_space_studies_global_2021,
	location = {Greenbelt, {MD}},
	title = {Global Surface Temperature},
	url = {https://climate.nasa.gov/vital-signs/global-temperature},
	abstract = {Vital Signs of the Planet: Global Climate Change and Global Warming. Current news and data streams about global warming and climate change from {NASA}.},
	number = {February 25, 2021},
	institution = {{NASA} Global Climate Change},
	type = {{NASA} Global Climate Change},
	author = {{NASA's Goddard Institute for Space Studies}},
	urldate = {2021-02-25},
	date = {2021-02-25},
	file = {Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/UJGLUB45/global-temperature.html:text/html},
}

@online{noauthor_serpent_nodate,
	title = {Serpent - A Monte Carlo Reactor Physics Burnup Calculation Code},
	url = {http://montecarlo.vtt.fi/},
	urldate = {2021-04-01},
	file = {Serpent - A Monte Carlo Reactor Physics Burnup Calculation Code:/home/zoe/snap/zotero-snap/common/Zotero/storage/D5BM98ZW/montecarlo.vtt.fi.html:text/html},
}

@article{noauthor_results_1990,
	title = {Results of experiments at the {AVR} reactor},
	volume = {121},
	issn = {0029-5493},
	url = {https://www-sciencedirect-com.proxy2.library.illinois.edu/science/article/pii/002954939090099J},
	doi = {10.1016/0029-5493(90)90099-J},
	abstract = {The most important experiments at the {AVR} reactor and their results will be discussed. This choice illustrates the significance of the “{AVR} experiment…},
	pages = {143--153},
	number = {2},
	journaltitle = {Nuclear Engineering and Design},
	urldate = {2021-04-01},
	date = {1990-07-02},
	langid = {english},
	note = {Publisher: North-Holland},
	file = {Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/CHU875BW/002954939090099J.html:text/html},
}

@article{beck_high_nodate,
	title = {High Temperature Gas-cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant},
	pages = {78},
	author = {Beck, J M and Pincock, L F},
	langid = {english},
	file = {Beck and Pincock - High Temperature Gas-cooled Reactors Lessons Learn.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/DLETU3B8/Beck and Pincock - High Temperature Gas-cooled Reactors Lessons Learn.pdf:application/pdf},
}

@article{venter_pbmr_2005,
	title = {{PBMR} {REACTOR} {DESIGN} {AND} {DEVELOPMENT}},
	abstract = {The {PBMR} reactor is the first pebble bed reactor that will be utilised in a high temperature direct Brayton cycle. This leads to a number of unique challenges. The impact of these challenges on the structural design of the reactor and its subsystems are discussed. The reactor design and especially the design of the Core Structures are described. This design description covers the functional requirements, structural arrangement and features of these subsystems and their components. The design of the reactor results in components utilizing design codes and materials that are currently available.},
	pages = {15},
	author = {Venter, Pieter J and Mitchell, Mark N and Fortier, Fred},
	date = {2005},
	langid = {english},
	file = {Venter et al. - 2005 - PBMR REACTOR DESIGN AND DEVELOPMENT.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/XWK6AYBN/Venter et al. - 2005 - PBMR REACTOR DESIGN AND DEVELOPMENT.pdf:application/pdf},
}

@online{noauthor_pebble_2017,
	title = {Pebble Bed Modular Reactor {SOC} Ltd},
	url = {http://www.pbmr.co.za/index2.asp?Content=129},
	urldate = {2021-04-01},
	date = {2017-05-16},
	file = {PBMR - Welcome:/home/zoe/snap/zotero-snap/common/Zotero/storage/MWTPCL5D/index2.html:text/html},
}

@report{lommers_ngnp_2012,
	title = {{NGNP} High Temperature Materials White Paper},
	url = {https://www.osti.gov/biblio/1055953-ngnp-high-temperature-materials-white-paper},
	abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information},
	number = {{INL}/{EXT}-09-17187},
	institution = {Idaho National Laboratory ({INL})},
	author = {Lommers, Lew and Honma, George},
	urldate = {2021-04-01},
	date = {2012-08-01},
	doi = {10.2172/1055953},
	file = {Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/7QL4IGSK/1055953-ngnp-high-temperature-materials-white-paper.html:text/html;Submitted Version:/home/zoe/snap/zotero-snap/common/Zotero/storage/A9KUU724/Lommers and Honma - 2012 - NGNP High Temperature Materials White Paper.pdf:application/pdf},
}

@online{inl_basis_2011,
	title = {Basis for {NGNP} Reactor Design Down-Selection},
	url = {https://inldigitallibrary.inl.gov/sites/sti/sti/5223031.pdf},
	author = {{INL}},
	urldate = {2021-04-01},
	date = {2011-11},
	file = {5223031.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/7KNXLPPK/5223031.pdf:application/pdf},
}

@online{noauthor_areva_nodate,
	title = {Areva modular reactor selected for {NGNP} development - World Nuclear News},
	url = {https://www.world-nuclear-news.org/NN-Areva_modular_reactor_selected_for_NGNP_development-1502124.html},
	urldate = {2021-04-01},
	file = {Areva modular reactor selected for NGNP development - World Nuclear News:/home/zoe/snap/zotero-snap/common/Zotero/storage/HUGYGEPE/NN-Areva_modular_reactor_selected_for_NGNP_development-1502124.html:text/html},
}

@online{cole_gentry_generate_2015,
	title = {generate random particle or pebble bed files for {HTGR} calc - Discussion forum for Serpent users},
	url = {https://ttuki.vtt.fi/serpent/viewtopic.php?f=3&t=2267&p=6161&hilit=growth+and+shake#p6161},
	abstract = {written by cgentry7},
	titleaddon = {Discussion Forum for Serpent Users},
	author = {{Cole Gentry}},
	urldate = {2021-05-13},
	date = {2015-09-29},
	file = {generate random particle or pebble bed files for HTGR calc - Discussion forum for Serpent users:/home/zoe/snap/zotero-snap/common/Zotero/storage/BP8T76SG/viewtopic.html:text/html},
}

@article{murata_new_1997,
	title = {New Sampling Method in Continuous Energy Monte Carlo Calculation for Pebble Bed Reactors},
	volume = {34},
	issn = {0022-3131},
	url = {https://doi.org/10.1080/18811248.1997.9733737},
	doi = {10.1080/18811248.1997.9733737},
	abstract = {A pebble bed reactor generally has double heterogeneity consisting of two kinds of spherical fuel element. In the core, there exist many fuel balls piled up randomly in a high packing fraction. And each fuel ball contains a lot of small fuel particles which are also distributed randomly. In this study, to realize precise neutron transport calculation of such reactors with the continuous energy Monte Carlo method, a new sampling method has been developed. The new method has been implemented in the general purpose Monte Carlo code {MCNP} to develop a modified version {MCNP}-{BALL}. This method was validated by calculating inventory of spherical fuel elements arranged successively by sampling during transport calculation and also by performing criticality calculations in ordered packing models. From the results, it was confirmed that the inventory of spherical fuel elements could be reproduced using {MCNP}-{BALL} within a sufficient accuracy of 0.2\%. And the comparison of criticality calculations in ordered packing models between {MCNP}-{BALL} and the reference method shows excellent agreement in neutron spectrum as well as multiplication factor. {MCNP}-{BALL} enables us to analyze pebble bed type cores such as {PROTEUS} precisely with the continuous energy Monte Carlo method.},
	pages = {734--744},
	number = {8},
	journaltitle = {Journal of Nuclear Science and Technology},
	author = {{MURATA}, Isao and {TAKAHASHI}, Akito and {MORI}, Takamasa and {NAKAGAWA}, Masayuki},
	urldate = {2021-05-29},
	date = {1997-08-01},
	note = {Publisher: Taylor \& Francis
\_eprint: https://doi.org/10.1080/18811248.1997.9733737},
	keywords = {computer codes, accuracy, errors, continuous energy Monte Carlo method, double heterogeneity, {HTGR} type reactors, nearest neighbor distribution, neutron transport, neutron transport calculation, packing simulation, pebble bed reactors, random distribution, spherical fuel element},
	file = {Full Text PDF:/home/zoe/snap/zotero-snap/common/Zotero/storage/SID3LYYK/MURATA et al. - 1997 - New Sampling Method in Continuous Energy Monte Car.pdf:application/pdf;Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/QEHMJFCY/18811248.1997.html:text/html},
}

@report{tkkim_whole-core_nodate,
	title = {Whole-Core Depletion Studies in Support of Fuel Specification for the Next Generation Nuclear Plant ({NGNP}) Core},
	url = {https://publications.anl.gov/anlpubs/2004/11/51497.pdf},
	number = {July 30, 2004},
	institution = {Argonne National Laboratory},
	author = {{T.K.Kim} and {W.S. Yang} and {T.A. Taiwo} and {H.S. Khalil}},
}

@article{turkmen_effect_2012,
	title = {Effect of pebble packing on neutron spectrum and the isotopic composition of {HTGR} fuel},
	volume = {46},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S0306454912000953},
	doi = {10.1016/j.anucene.2012.03.016},
	abstract = {Fission products play an important role in the safety and fuel integrity of high-temperature gas-cooled reactor ({HTGR}) and they depend on temperature, burnup, neutron energy distribution, and fast fluence. Energy distribution of neutrons in a fuel region determines the isotopic distribution of the fission products to be produced. The local concentrations of these isotopes are considered to be functions of temperature and burnup as well as the amount transported from the kernel to the coating layers where they interact and may degrade layers. Thus, the integrity of the fuel particle may be lost and fission products can be released into the reactor coolant inventory. In this study, it is the main purpose to perform neutron energy spectrum shift in spherical {HTGR} fuels and to investigate its effect on fission products. Moreover, it is also intended to analyze the effect of unit cell geometries on criticality of the system. The calculations for group fluxes based on {ENDF}4 library with 27 neutron energy groups are accomplished by the {MCNP}5 neutron transport code. Burnup and criticality analyses are performed by using the {MONTEBURNS}2 code ({MCNP}5 coupled with {ORIGENS}). To simplify the neutron transport problem, instead of full core modeling, two fundamental unit cell arrangements, body-centered cubic ({BCC}) and hexagonal close-packed ({HCP}) lattices, are considered to be as reference geometry models. Unit cells are defined with proper boundary conditions and random packing for {TRISO} particles provided by the stochastic geometry card specified in {MCNP}5 for {HTGR} pebbles is used.},
	pages = {29--36},
	journaltitle = {Annals of Nuclear Energy},
	shortjournal = {Annals of Nuclear Energy},
	author = {Türkmen, Mehmet and Çolak, Üner},
	urldate = {2021-06-02},
	date = {2012-08-01},
	langid = {english},
	keywords = {Fission products, Neutron spectrum, {HTGR}, Spherical {HTGR} fuel},
	file = {ScienceDirect Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/U8DDJMAF/S0306454912000953.html:text/html},
}

@inproceedings{karriem_mcnp_2001,
	location = {Berlin, Heidelberg},
	title = {{MCNP} Modelling of {HTGR} Pebble-Type Fuel},
	isbn = {978-3-642-18211-2},
	doi = {10.1007/978-3-642-18211-2_134},
	abstract = {Criticality calculations for systems (reactor, critical assembly or storage tank) in which pebble-type fuel is used or stored, presents itself as an interesting problem. This is due to the heterogeneous nature of the fuel itself, as well as the heterogeneity that occurs in an arrangement of such pebbles. An example of this heterogeneity at the pebble level, is found in the {ASTRA} Critical Facility [1] where fuel pebbles are mixed with non-fuel (moderator and absorber) pebbles that are identical in size, but different in material composition.},
	pages = {841--846},
	booktitle = {Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications},
	publisher = {Springer},
	author = {Karriem, Z. and Stoker, C. and Reitsma, F.},
	editor = {Kling, Andreas and Baräo, Fernando J. C. and Nakagawa, Masayuki and Távora, Luis and Vaz, Pedro},
	date = {2001},
	langid = {english},
	keywords = {Critical Assembly, Fuel Region, Hexagonal Close Packing, Kernel Homogenise, Packing Arrangement},
	file = {Springer Full Text PDF:/home/zoe/snap/zotero-snap/common/Zotero/storage/S9VXIVMQ/Karriem et al. - 2001 - MCNP Modelling of HTGR Pebble-Type Fuel.pdf:application/pdf},
}

@article{brown_stochastic_2005,
	title = {{STOCHASTIC} {GEOMETRY} {AND} {HTGR} {MODELING} {WITH} {MCNP}5},
	abstract = {The {MCNP}5 Monte Carlo code has been frequently used to model {HTGRs} with explicit geometric representation of fuel compacts or pebbles, including the microscopic fuel kernels within them. The random locations of fuel kernels within each fuel compact or pebble, and of pebbles within the core, however, present difficulties. A new, on-the-fly, stochastic geometry model for {MCNP}5 has been developed for modeling the random fuel kernels within the graphite matrix. This model is compared to both fixed lattices and multiple realizations of explicit random kernels. In addition, the effects of infinite vs. finite lattices on full-core geometries are investigated, including the effects of stochastic geometry modeling.},
	pages = {13},
	author = {Brown, Forrest B and Martin, William R and Ji, Wei and Conlin, Jeremy L and Lee, John C},
	date = {2005},
	langid = {english},
	file = {Brown et al. - 2005 - STOCHASTIC GEOMETRY AND HTGR MODELING WITH MCNP5.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/HSLAN2AW/Brown et al. - 2005 - STOCHASTIC GEOMETRY AND HTGR MODELING WITH MCNP5.pdf:application/pdf},
}

@report{hamilton_htgr_1976,
	title = {{HTGR} spent fuel composition and fuel element block flow},
	url = {https://www.osti.gov/biblio/7157851},
	abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information},
	number = {{GA}-A-13886(Vol.1)},
	institution = {General Atomic Co., San Diego, Calif. ({USA})},
	author = {Hamilton, C. J. and Holder, N. D. and Pierce, V. H. and Robertson, M. W.},
	urldate = {2021-06-03},
	date = {1976-07-01},
	doi = {10.2172/7157851},
	file = {Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/J6X7HL7I/7157851.html:text/html;Full Text PDF:/home/zoe/snap/zotero-snap/common/Zotero/storage/D3BMXEDI/Hamilton et al. - 1976 - HTGR spent fuel composition and fuel element block.pdf:application/pdf},
}

@article{van_rossum_python_nodate,
	title = {Python Reference Manual},
	pages = {196},
	author = {van Rossum, Guido and Drake, Fred L},
	langid = {english},
	file = {van Rossum and Drake - Python Reference Manual.pdf:/home/zoe/snap/zotero-snap/common/Zotero/storage/BWGHY4EB/van Rossum and Drake - Python Reference Manual.pdf:application/pdf},
}

@article{harris_array_2020,
	title = {Array programming with {NumPy}},
	volume = {585},
	rights = {2020 The Author(s)},
	issn = {1476-4687},
	url = {https://www.nature.com/articles/s41586-020-2649-2},
	doi = {10.1038/s41586-020-2649-2},
	abstract = {Array programming provides a powerful, compact and expressive syntax for accessing, manipulating and operating on data in vectors, matrices and higher-dimensional arrays. {NumPy} is the primary array programming library for the Python language. It has an essential role in research analysis pipelines in fields as diverse as physics, chemistry, astronomy, geoscience, biology, psychology, materials science, engineering, finance and economics. For example, in astronomy, {NumPy} was an important part of the software stack used in the discovery of gravitational waves1 and in the first imaging of a black hole2. Here we review how a few fundamental array concepts lead to a simple and powerful programming paradigm for organizing, exploring and analysing scientific data. {NumPy} is the foundation upon which the scientific Python ecosystem is constructed. It is so pervasive that several projects, targeting audiences with specialized needs, have developed their own {NumPy}-like interfaces and array objects. Owing to its central position in the ecosystem, {NumPy} increasingly acts as an interoperability layer between such array computation libraries and, together with its application programming interface ({API}), provides a flexible framework to support the next decade of scientific and industrial analysis.},
	pages = {357--362},
	number = {7825},
	journaltitle = {Nature},
	author = {Harris, Charles R. and Millman, K. Jarrod and van der Walt, Stéfan J. and Gommers, Ralf and Virtanen, Pauli and Cournapeau, David and Wieser, Eric and Taylor, Julian and Berg, Sebastian and Smith, Nathaniel J. and Kern, Robert and Picus, Matti and Hoyer, Stephan and van Kerkwijk, Marten H. and Brett, Matthew and Haldane, Allan and del Río, Jaime Fernández and Wiebe, Mark and Peterson, Pearu and Gérard-Marchant, Pierre and Sheppard, Kevin and Reddy, Tyler and Weckesser, Warren and Abbasi, Hameer and Gohlke, Christoph and Oliphant, Travis E.},
	urldate = {2021-07-14},
	date = {2020-09},
	langid = {english},
	note = {Bandiera\_abtest: a
Cc\_license\_type: cc\_by
Cg\_type: Nature Research Journals
Number: 7825
Primary\_atype: Reviews
Publisher: Nature Publishing Group
Subject\_term: Computational neuroscience;Computational science;Computer science;Software;Solar physics
Subject\_term\_id: computational-neuroscience;computational-science;computer-science;software;solar-physics},
	file = {Full Text PDF:/home/zoe/snap/zotero-snap/common/Zotero/storage/M8U3YY4S/Harris et al. - 2020 - Array programming with NumPy.pdf:application/pdf;Snapshot:/home/zoe/snap/zotero-snap/common/Zotero/storage/7IZRNIDW/s41586-020-2649-2.html:text/html},
}