Relevant bibliographies by topics / Burrup

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Academic literature on the topic 'Burrup'

Author: Grafiati
Published: 4 June 2021
Last updated: 31 July 2024

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Journal articles on the topic "Burrup"

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Johnson, Michael S., Sean Stankowski, Peter G. Kendrick, Zoë R. Hamilton, and Roy J. Teale. "Diversity, complementary distributions and taxonomy of Rhagada land snails (Gastropoda : Camaenidae) on the Burrup Peninsula, Western Australia." Invertebrate Systematics 30, no. 4 (2016): 323. http://dx.doi.org/10.1071/is15046.

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Phylogenetic diversity of Rhagada land snails is high on the Burrup Peninsula, Western Australia, with four distinct clades, representing three of the four major clades of the Pilbara region. Detailed sampling indicated little geographic overlap of the four clades, conforming to the general rarity of congeneric sympatry in Australian camaenids. The diversity on the Burrup Peninsula includes three previously unclassified morphotypes. One of these lies within the broad endemic clade of the adjacent Dampier Archipelago, and is provisionally assigned to the island species R. perprima, based on phylogenetic evidence. The two other undescribed morphotypes constitute an endemic clade that is the sister group of the broader Dampier Archipelago clade. All COI p-distances within clades are less than 6%, whereas nearly all distances between clades exceed 10%, the gap corresponding to differences among species of Rhagada generally. One morphotype in the Burrup Peninsula endemic clade has a low spire and a distinctive keel, and is restricted to a single rockpile. Detailed local sampling revealed gradation between this form and the more widely distributed globose morphotype. On the basis of genetic similarity and morphological continuity, we describe the morphologically variable endemic Burrup Peninsula clade as Rhagada ngurrana, sp. nov., which has a distribution spanning only 9 km.
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Lukatela, Tom, and Holly Thomas. "Transition to tolling third-party gas at Karratha Gas Plant: an attractive investment which unlocks infrastructure utilisation." APPEA Journal 63, no. 2 (2023): S125—S128. http://dx.doi.org/10.1071/aj22257.

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In December 2020, the North West Shelf (NWS) Project participants executed fully-termed third-party Gas Processing Agreements with Woodside Burrup Pty Ltd (Woodside Burrup), for gas from the Pluto fields, and with subsidiaries of Mitsui & Co Ltd and Beach Energy Limited (Mitsui and Beach), for the Waitsia Gas Project Stage 2. These agreements underpinned final investment decisions in the infrastructure projects, business processes, and digital tools, necessary to process third-party gas from the Pluto-Karratha Gas Plant (KGP) Interconnector, and the Burrup Extension Pipeline (BEP). Tolling operations commenced at the NWS Project in March 2022 with the processing of gas delivered from Pluto through the Interconnector. The first Liquefied Natural Gas (LNG) cargo produced from gas through the Interconnector was loaded in April 2022. KGP is also expected to commence processing Waitsia gas via the BEP from 2023. Woodside CEO Meg O’Neill stated: ‘The start-up of the Pluto-KGP Interconnector provides access to spare capacity at Karratha Gas Plant to process gas owned by other resource owners, both onshore and offshore Western Australia. The commencement of Pluto gas flowing through the Interconnector is the first example of this… The commercial agreements underpinning third-party gas processing at the North West Shelf reflect the commitment of Woodside and the North West Shelf Project to maximising value from the significant infrastructure on the Burrup Peninsula’. The development of the necessary infrastructure, business/operational processes, and digital tools is a forward looking investment which unlocks an efficient market in third-party gas processing market at KGP.
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Vinnicombe, Patricia. "Salvage Archaeology of the Burrup Peninsula." Australian Archaeology 25, no. 1 (1987): 53–79. http://dx.doi.org/10.1080/03122417.1987.12093125.

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Gregory, Jenny. "Stand Up for the Burrup: Saving the Largest Aboriginal Rock Art Precinct in Australia." Public History Review 16 (December 27, 2009): 92–116. http://dx.doi.org/10.5130/phrj.v16i0.1234.

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The Dampier Rock Art Precinct contains the largest and most ancient collection of Aboriginal rock art in Australia. The cultural landscape created by generations of Aboriginal people includes images of long-extinct fauna and demonstrates the response of peoples to a changing climate over thousands of years as well as the continuity of lived experience. 
 
 Despite Australian national heritage listing in 2007, this cultural landscape continues to be threatened by industrial development. Rock art on the eastern side of the archipelago, on the Burrup Peninsula, was relocated following the discovery of adjacent off-shore gas reserves so that a major gas plant could be constructed. Work has now begun on the construction of a second major gas plant nearby. 
 
 This article describes the rock art of the Dampier Archipelago and the troubled history of European-Aboriginal contact history, before examining the impact of industry on the region and its environment. The destruction of Aboriginal rock art to meet the needs of industry is an example of continuing indifference to Aboriginal culture. While the complex struggle to protect the cultural landscape of the Burrup, in particular, involving Indigenous people, archaeologists, historians, state and federal politicians, government bureaucrats and multi-national companies, eventually led to national heritage listing, it is not clear that the battle to save the Burrup has been won.
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O'Neill, Caitlin, Michael S. Johnson, Zoë R. Hamilton, and Roy J. Teale. "Molecular phylogenetics of the land snail genus Quistrachia (Gastropoda : Camaenidae) in northern Western Australia." Invertebrate Systematics 28, no. 3 (2014): 244. http://dx.doi.org/10.1071/is13045.

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Recent collecting in the remote Pilbara region of Western Australia has revealed substantial increases in the apparent distributions of species of the genus Quistrachia, and the discovery of new forms, raising questions about the morphological taxonomy. To resolve these questions, we examined mtDNA sequences in all known species of Quistrachia, the unidentified new forms and other members of the subfamily Sinumeloninae. Phylogenetic analysis confirmed the monophyly of Quistrachia, including one of the new forms. The two other new forms represent new genera within the Sinumeloninae. Monophyly of each species was confirmed, with the exception of Q. legendrei, in which populations from the Dampier Archipelago and those from the adjacent Burrup Peninsula are in separate clades. Based on phylogeny and levels of divergence within other species in the genus, the Burrup populations appear to be conspecific with Q. turneri. This is supported by anatomical comparisons, but not by shell morphology, which may well reflect the evolutionary plasticity of shell form. Given the patchiness of searches for land snails in the largely inaccessible Pilbara region, additional species almost certainly remain to be discovered. Our study shows the value of including molecular analyses in determining the taxonomic status of new forms.
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Casement, William. "Art and Race: The Strange Case of Eddie Burrup." Society 53, no. 4 (2016): 422–24. http://dx.doi.org/10.1007/s12115-016-0037-1.

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Gleeson, Deirdre B., Matthias Leopold, Benjamin Smith, and John L. Black. "Rock-art microbiome: influences on long term preservation of historic and culturally important engravings." Microbiology Australia 39, no. 1 (2018): 33. http://dx.doi.org/10.1071/ma18009.

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The Burrup Peninsula in north-west Western Australia is home to one of the most substantial collections of rock engravings, or petroglyphs, in the world. These petroglyphs are carved through the dark coloured patina, commonly referred to as rock varnish, into the weathering rind of the local parent rock. Rock varnish is essentially a thin layer of manganese (Mn) and iron (Fe) oxides and hydroxides with embedded clay minerals, the formation of which is relatively poorly understood. It is generally considered to be a hostile environment for microorganisms due to extreme environmental conditions including low nutrient availability, lack of water, exposure to extreme ultraviolet radiation and intense seasonal and diurnal temperature fluctuations. However, despite these environmental extremes, microorganisms have been found on and in rock varnish and have been reported as playing a significant role in the formation of rock varnish. Given this, it is likely that any change in local environmental conditions will influence the types and activities of microorganisms found in and on rock varnish and associated rock art. This article focuses on the major influences on the microbiome of culturally important rock art in the Burrup Peninsula and the implications of any environmental change on the rock art itself.
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González Zarandona, José Antonio. "The Destruction of Heritage: Rock Art in the Burrup Peninsula." International Journal of the Humanities: Annual Review 9, no. 1 (2011): 325–42. http://dx.doi.org/10.18848/1447-9508/cgp/v09i01/43116.

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Zarandona, José. "The Destruction of Heritage: Rock Art in the Burrup Peninsula." Journal of Urban Culture Research 4, no. 1 (2012): 64–81. http://dx.doi.org/10.58837/chula.jucr.4.1.5.

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Mulvaney, Ken. "Burrup Peninsula: Cultural Landscape and Industrial Hub, a 21st Century Conundrum." Landscape Research 40, no. 6 (2015): 759–72. http://dx.doi.org/10.1080/01426397.2015.1057804.

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Dissertations / Theses on the topic "Burrup"

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Rosensvärd, Markus, and David Danneker. "Flexural strength of zirconia after grinding, using diamond burrs, silicon carbide burr and water-cooling." Thesis, Malmö universitet, Odontologiska fakulteten (OD), 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:mau:diva-19863.

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SyfteSyftet med föreliggande studie är att undersöka om slipning av zirkonia med silikatkarbid, diamant, vattenkylning, höghastighetsturbin och låghastighetshandstycke påverkar böjhållfastheten hos zirkonia.Material och metodFemtio provkroppar av yttriumoxidstabiliserad tetragonal zirkonia framställdes med CAD/CAM. Provkropparna delades in i 5 grupper med 10 i varje; polerad med låghastighetshandstycke (P), vattenkylning med finkornig diamantfräs (HDW), höghastighetsturbinshandstycke utan vattenkylning med finkornig diamantfräs (HDD), låghastighetshandstycke med finkornig diamantfräs (LD) och låghastighetshandstycke med kiselkarbidfräs (LC). Efter slipningen polerades alla provkropparna med låghastighetshandstycke och polertrissa. Artificiell åldring genomfördes med cyklisk dynamisk förbelastning och termocykling. Provkropparna testades med ett biaxialt böjhållfasthetstest i en universaltestmaskin. Resultaten analyserades med hjälp av en One-way ANOVA, Tukey’s test. Signifikansnivån sattes till α = 0,05.ResultatResultatet visade ingen signifikant skillnad mellan de olika grupperna. MPa medelvärde för varje grupp och standardavvikelser; P 1061(±82), HDW 1023(±92), HDD 1002(±127), LD 812(±228) and LS 984(±83).SlutsatsInom begränsningarna för föreliggande studie kan slutsatsen dras att böjhållfastheten hos zirkonia inte signifikant påverkas efter användning av följande slipningsprocesser:Höghastighetstubin med fin diamant och vattenkylning eller med höghastighetsturbin med fin diamant och utan vattenkylning eller med låghastighetshandstycke med fin diamant eller kiselkarbidfräs när zirkoniaytan är polerad.<br>AimThe purpose of this study is to investigate whether grinding zirconia with silicon carbide, diamond, water cooling, high speed turbine and low speed handpiece affects the flexural strength of zirconia.Material and methodFifty specimens of yttrium oxide stabilized tetragonal zirconia were produced using CAD/CAM. The specimens were divided into 5 groups with 10 in each; polished with low speed handpiece (P), high speed turbine with water cooling using a fine diamond burr (HW), high speed turbine without cooling using a fine diamond burr (H), low speed handpiece with a fine diamond burr (LD) and low speed handpiece with silicon carbide burr (LC). After grinding all specimens were polished with a slow speed handpiece and a polishing wheel. Artificial aging was performed using cyclic dynamic loading and thermocycling. The specimens were then tested in a biaxial flexural strength test using a universal testing machine. The results were analysed using One-way ANOVA, Tukey’s test. Level of significance was set at α = 0.05.ResultsThe results showed no significant differences between the groups. MPa means for each group and SD; P 1061(±82), HDW 1023(±92), HDD 1002(±127), LD 812(±228) and LS 984(±83).ConclusionWithin the limitations of this study it can be concluded that flexural strength of zirconia is not significantly affected using the following grinding processes: High-speed turbine with fine diamond and water cooling or with fine diamond without water cooling, low-speed handpiece with fine diamond or with silicon carbide burr when the zirconia has been polished.
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Stewart, Christopher L. "Antineutrino-based safeguards for ultra-high burnup fast reactors." Diss., Georgia Institute of Technology, 2016. http://hdl.handle.net/1853/55024.

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Since the first observation of antineutrinos from beta decay of the fission products inside a nuclear reactor in 1956, the design and operating experience of antineutrino detectors near reactors has increased to the point where monitoring the reactor's power level and progression through its burnup cycle has become possible. With the expected increase in world nuclear energy capacity, including the dissemination of reactor technologies to non-nuclear states, the need for safeguards measures which are able to provide continuous, near-real-time information about the state of the core, including its isotopic composition, in a tamper- and spoof-resistant manner is evident. Near-field (~20 m from the core) antineutrino detectors are able to fulfill this demand without perturbing normal reactor operation, without requiring instrumentation which penetrates the reactor vessel, and without displacing other plant structures. Two sodium-cooled long-life fast reactors that are characteristic of next-generation reactors which are attractive for installation in non-nuclear states, one large and one small power rating, have been modeled throughout their reference burnup cycles using MCC-3 and DIF3D/REBUS. Various diversions of fissile material from the core designed to obtain weapons-usable material for the purpose of nuclear proliferation were studied as perturbed core states. The difference in detector event rates between the reference and perturbed states was used to determine the probability that a particular diversionary activity would be apparent before the material could be converted into a weapon. These data indicate which types of diversion antineutrino safeguards are particularly strong against and how the technology might be implemented in current and future international policies concerning nuclear proliferation.
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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 extracted prior to disposal. Using CASMO-4, a standard Westinghouse 4-loop pressurized water reactor model was created and simulated with a three batch fuel cycle. U-235 enrichment was adjusted to achieve fuel burnups of 30, 50, 70 and 100 MWD per kg of initial uranium. These burnups demanded reload enrichments of 3.15%, 4.63%, 6.26% and 9.01% U-235 w/o respectively. The resultant spent fuel transuranic isotopic compositions were then provided as input into ORIGEN to study the decay behavior of the spent fuel. It was found that when burnup increased from 30 MWD/kg to 100 MWD/kg, the activity more than doubled due to the decreased Pu-241 content and the increased Np-239 presence. More importantly, the activity per MWD significantly decreased despite absolute increases in unit mass. The net result is that the half-life of high burnup fuels is greatly increased in comparison to low burnup fuels for the first decade of life. Beginning from day 14 after shutdown and until 10 years later, the 100 MWD/kg fuel has a half-life of 129 days while the 30 MWD/kg spent fuel has a half life of 5 days. Previous work has suggested that different trends dominate decay behavior from years 10 to 100 years following discharge.<br>by Drew A. Reese.<br>S.B.
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Kersting, Alyssa (Alyssa Rae). "Fluence-limited burnup as a function of fast reactor core parameters." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76938.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 39).<br>The limiting factor in current designs for fast reactors is not only the reactivity, but also the maximum permissible fast-neutron fluence in the cladding, especially for reduced uranium enrichment cores using high-albedo MgO reflectors. The intent of this thesis was to determine the best design parameters - fuel type, fuel compound, fuel arrangement, and coolant - while observing these limitations. The ERANOS code was used to determine the flux values for each design option. A curve was fitted to the fluxes taken at beginning of life, middle of life, and end of life. This curve was then integrated progressively until the clad fluence limit of 4 x 1023 fast neutrons/cm 2 was reached. The different design options were compared with emphasis on minimizing enrichment and maximizing burnup. Sodium was chosen as a coolant because of its extensive experience based compared to the other options, as well as its heat transfer properties. Inverted fuel was found to be better neutronically, in both clad lifetime and burnup than conventional pin-type fuel, but the requirement of fuel venting may discourage use of this option. Uranium carbide was found to be superior to nitride, oxide or metal fuel in its clad lifetime, especially if pin cell fuel is used. If inverted fuel is used, uranium oxide is also a valid choice from a burnup and cost perspective, especially should re-cladding not be feasible or desired, since the reactivity and clad fluence lifetimes of oxide fuel are similar to each other.<br>by Alyssa Kersting.<br>S.B.
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Xu, Zhiwen 1975. "Design strategies for optimizing high burnup fuel in pressurized water reactors." Thesis, Massachusetts Institute of Technology, 2003. http://hdl.handle.net/1721.1/16603.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003.<br>Includes bibliographical references (p. 254-264).<br>This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.<br>This work is focused on the strategy for utilizing high-burnup fuel in pressurized water reactors (PWR) with special emphasis on the full array of neutronic considerations. The historical increase in batch-averaged discharge fuel burnup, from ~30 MWd/kg in the 1970s to ~50 MWd/kg today, was achieved mainly by increasing the reload fuel enrichment to allow longer fuel cycles: from an average of 12 months to about 18 months. This also reduced operating costs by improving the plant capacity factor. Recently, because of limited spent fuel storage capacity, increased core power output and the search for increased proliferation resistance, achieving burnup in the 70 to 100 MWd/kg range has attracted considerable attention. However the implications of this initiative have not been fully explored; hence this work defines the practical issues for high-burnup PWR fuels based on neutronic, thermal hydraulic and economic considerations as well as spent fuel characteristics. In order to evaluate the various high burnup fuel design options, an improved MCNP-ORIGEN depletion program called MCODE was developed. A standard burnup predictor-corrector algorithm is implemented, which distinguishes MCODE from other MCNP-ORIGEN linkage codes. Using MCODE, the effect of lattice design (moderation effect) on core design and spent fuel characteristics is explored. Characterized by the hydrogen-to-heavy-metal ratio (H/HM), the neutron spectrum effect in UO2/H2O lattices is investigated for a wide range of moderation, from fast spectra to over-thermalized spectra. It is shown that either wetter or very dry lattices are preferable in terms of achievable burnup potential to those having an epithermal spectrum. Wet lattices are the preferred high burnup approach due to improved proliferation resistance. The constraint of negative moderator temperature coefficient (MTC) requires that H/HM values (now at 3.4) remain below ~6.0 for PWR lattices. Alternative fuel choices, including the conventional solid pellets, central-voided annular pellets, Internally- & eXternally-cooled Annular Fuel (IXAF), and different fuel forms are analyzed to achieve a wetter lattice. Although a wetter lattice has higher burnup potential than the reference PWR lattice, the requirement of a fixed target cycle energy production necessitates higher initial fuel enrichments to compensate for the loss of fuel mass in a wetter lattice. Practical issues and constraints for the high burnup fuel include neutronic reactivity control, heat transfer margin, and fission gas release. Overall the IXAF design appears to be the most promising approach to realization of high burnup fuel. High-burnup spent fuel characteristics are compared to the reference spent fuel of 33 MWd/kg, representative of most of the spent fuel inventory. Although an increase of decay power and radioactivity per unit mass of initial heavy metal is immediately observed, the heat load (integration of decay power over time) per unit electricity generation decreases as the fuel discharge burnup increases. The magnitude of changes depends on the time after discharge. For the same electricity production, not only the mass and volume of the spent fuel are reduced, but also, to a lesser extent, the total heat load of the spent fuel. Since the heat load in the first several hundred years roughly determines the capital cost of the repository, a high burnup strategy coupled with adequate cooling time, may provide a cost-reduction approach to the repository. High burnup is beneficial to enhancing the proliferation resistance. The plutonium vector in the high-burnup spent fuel is degraded, hence less attractive for weapons. For example, the ratio of Pu-238 to Pu-239 increases with burnup to the 2.5 power. However, the economic benefits are uncertain. Under the current economic conditions, the PWR fuel burnup appears to have a shallow optimum discharge burnup between 50 and 80 MWd/kg. The actual minimum is influenced by the financing costs as well as the cost of refueling shutdowns. Since the fuel cycle back-end benefits will accrue to the federal government, the current economic framework, such as the waste fee based on the electricity produced rather than volume or actinide content, does not create an incentive for utilities to increase burnup. Different schemes exist for fuel management of high burnup PWR cores. For the conventional core design, a generalized enrichment-burnup correlation (applicable between 3 w/o and 20 w/o) was produced based on CASMO/SIMULATE PWR core calculations. Among retrofit cores, increasing the number of fuel batches is preferred over increasing the cycle length due to nuclear fuel cycle economic imperatives. For future core designs, a higher power-density core is a very attractive option to cut down the busbar cost. The IXAF concept possesses key design characteristics that provide the necessary thermal margins at high core power densities. In this regard, the IXAF fuel deserves further investigation to fully exploit its high burnup capability.<br>by Zhiwen Xu.<br>Ph.D.
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Liu, Wenfeng Ph D. Massachusetts Institute of Technology. "Assessment of high-burnup LWR fuel response to reactivity-initiated accidents." Thesis, Massachusetts Institute of Technology, 2007. http://hdl.handle.net/1721.1/44786.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007.<br>Includes bibliographical references (p. 263-273).<br>The economic advantages of longer fuel cycle, improved fuel utilization and reduced spent fuel storage have been driving the nuclear industry to pursue higher discharge burnup of Light Water Reactor (LWR) fuel. A design basis accident, the Reactivity Initiated Accident (RIA), became a concern for further increase of burnup as simulated RIA tests revealed lower enthalpy threshold for fuel failure associated with fuel dispersal, which may compromise the core coolability and/or cause radiological release should this happened in LWRs. Valuable information on the behavior of high burnup fuel during RIA are provided by the simulation tests. However atypical design and operating conditions in simulated tests limited the application of experimental data directly to evaluate the failure potential of LWR fuels. To better interpret the experimental results and improve the capability of the fuel performance codes to predict high burnup fuel behavior, this thesis developed mechanistic models of high burnup fuel during an RIA and implemented models in a transient fuel performance code FRAPTRAN 1.3. Fission gas release (FGR) and swelling were systematically modeled to quantify gaseous loading effects. The grain boundary fission gas inventory is simulated prior to the transient using a diffusion model in FRAPCON 3.3 code. The restructuring of high burnup fuel in rim region is described in terms of porosity, pore size distribution, fission gas concentration, and pore overpressure. The model assumes the fragmentation of fuel upon the separation of grain boundary or when a threshold temperature is exceeded in the rim region. The fission gas in fragmented fuel is assumed to release instantaneously to the free volume when the fuel expansion and swelling creates sufficient pellet-clad gap.<br>(cont.) The relaxation of rim pore at rapid temperature increase and the thermal expansion of fission gas in fragmented fuel are considered as additional loads on the cladding besides the contact force due to fuel thermal expansion. An analytical approximation is made to calculate the clad radial displacement subjected to fission gas expansion accounting for the constraint of the cladding on the fission gas which would otherwise be neglected in a rigid pellet model FRACAS-I in the FRAPTRAN code. In comparison to the measured FGR from CABRI, NSRR and BIGR test facilities, this mechanistic model can reasonably predict fission gas release fraction for most of the test cases covering a burnup range of 26-64 MWd/kgU and enthalpy deposit of 37-200 cal/g. It reveals the effects of burnup and enthalpy deposit on the fission gas release: burnup is an important parameter affecting fission gas inventory and fuel micro-structure evolution during base irradiation; enthalpy deposit is directly connected to the availability of fission gas release via the grain boundary separation by the intergranular bubble over-pressurization. Analysis of the fission gas radial profile is made with the aid of the neutronic code MCODE to validate the fission gas release from the rim of UO2 fuel. The analysis indicates fission gas release is partly from the rim region and the majority of fission gas release is from grain boundaries for burnup up to 50 MWd/kgU. Fission gas induced hoop strain is predicted to be less than 0.3% in the early phase of RIA with peak fuel enthalpy less than 145 cal/g. Given the fact that the concerned failure mode is the PCMI failure at low energy deposit, the pellet thermal expansion is still considered as effective in analyzing the PCMI failure. However at high level of enthalpy deposit, when clad yield strength is decreased at escalated temperature due to film boiling, the fission gas either released into the plenum or retained in the fuel pellet might strain more the cladding.<br>(cont.) This is observed in the large deformation of the cladding in some test cases in NSRR and BIGR due to pressure load. A new set of heat transfer correlations were selected and implemented in the FRAPTRAN code to model the cladding-coolant heat transfer of high burnup fuel at room temperature and atmospheric pressure condition. This new set of correlations addressed the effects of subcooling and oxiation on the heat transfer characteristics at pool boiling conditions. They reflect the increase of rewetting temperature and increase of Critical Heat Flux (CHF) due to subcooling. They account for oxidation effects on the transition and film boiling regime and heat conduction through thick oxide as the oxidation is considered as a prominent feature of surface condition change of high burnup fuel. In addition to high burnup fuels tested in NSRR, several fresh fuel tests with different degree of subcooling and a few separate-effects RIA tests are also included to validate the applicabilty of this set of correlations. For fuel enthalpy up to 190 cal/g and oxidation up to 25 micron, the predicted peak cladding temperature (PCT) and duration of DNB achieves generally good agreement with the experimental data. The analysis of high burnup fuel heat transfer reveals that the surface oxidation could cause an early rewetting of high burnup fuel or suppression of DNB. Surface oxidation can delay the heat conducting to the surface while keeping the surface heat transfer in the effective nucleate boiling regime. It also raises the miniumum stable film boiling temperature by lowering the interface temperature during liquid-solid contact resulting from vapor breaking down. Also modeled was Pellet-Cladding Mechanical Interaction (PCMI) failure of irradiated and hydrided cladding. The hydride rim accumulated at outer clad is assumed to cause the crack initiation. The fracture toughness of irradiated and hydrided cladding is obtained by fitting experimental data at different temperature range.<br>(cont.) The model sets forth a simple criterion for failure associated with crack growth based on the J integral approach. The simplification is that for the thin clad, failure is assumed to occur at the onset of crack tip growth. In comparison to CABRI and NSRR test results and other failure models, the model shows a good capability to separate the failure cases from non-failure cases. These models have been applied to LWR conditions to determine the failure potential of high burnup fuel. It shows that, at high burnup (and therefore high hydride levels in the cladding), the failure enthalpy is smaller than at low burnup. The pulse width is an important parameter in the burnup up to 50 MWd/kg, but starts to become less important for higher burnup with highly corroded cladding.<br>by Wenfeng Liu.<br>Ph.D.
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Long, Yun 1972. "Modeling the performance of high burnup thoria and urania PWR fuel." Thesis, Massachusetts Institute of Technology, 2002. http://hdl.handle.net/1721.1/30000.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2002.<br>Includes bibliographical references (p. 157-171).<br>Fuel performance models have been developed to assess the performance of ThO₂-UO₂ fuels that can be operated to a high burnup up to 80-100MWd/kgHM in current and future Light Water Reactors (LWRs). Among the various issues raised in high burnup fuel applications, the pellet rim effect, fission gas release (FGR), and response to reactivity initiated accidents (RIA) were of special interest in this work. These phenomena were modeled by modifying the NRC licensing codes FRAPCON-3 for normal operation and FRAP-T6 for transient conditions. These models were verified and compared to the results of previous thorium fuel studies and high burnup uranium fuel evaluations. The buildup of plutonium in the outer rim of LWR UO2 pellets has been observed to create a region of high fuel burnup, fission gas buildup and high porosity at the fuel rim. The power distribution of the thoria and urania fuel was calculated using a neutronics code MOCUP. Due to the lower build-up of Pu-239 (less U-238 in ThO₂-UO₂ fuel) and flatter distribution of U-233 (less resonance capture in Th-232), thoria fuel experiences a much flatter power distribution and thus has a less severe rim effect than UO₂ fuel. To model this effect properly, a new model, THUPS (Thoria-Urania Power Shape), was developed, benchmarked with MOCUP and adapted into FRAPCON-3. Additionally a porosity model for the rim region was introduced at high burnup to account for the larger fuel swelling and degradation of the thermal conductivity. The mechanisms of fission gas release in ThO₂-UO₂ fuel have been found similar to those of U0₂ fuel. Therefore, the general formulations of the existing fission gas release models in FRAPCON-3 were retained.<br>(cont.) However, the gas diffusion coefficient in thoria was adjusted to a lower level to account for the smaller observed gas release fraction in the thoria-based fuel. To model accelerated fission gas release at high burnup properly, a new athermal fission gas release model was developed. Other modifications include the thoria fuel properties, fission gas production rate, and the corrosion model to treat advanced cladding materials. The modified version of FRAPCON-3 was calibrated using the measured fission gas release data from the Light Water Breeder Reactor (LWBR) program. Using the new model to calculate the gas release in typical PWR hot pins gives data that indicate that the ThO₂-UO₂ fuel will have considerably lower fission gas release beyond a burnup of 50 MWd/kgHM. Investigation of the fuel response to an RIA included: (1) reviewing industry simulation tests to understand the mechanisms involved, (2) modifying FRAP-T6 code to simulate the RIA tests and investigate the key contributors to fuel failure (thermal expansion, gaseous swelling, cladding burst stress), and (3) assessing thoria and urania performance during RIA event in typical LWR situations. ThO₂-UO₂ fuel has been found to have better performance than U0₂ fuel under RIA event conditions due to its lower thermal expansion and a flatter power distribution in the fuel pellet (less power and less fission gas in the rim region). Overall, thoria has been found to have better performance than urania in both normal and off-normal conditions. However, calculations using the modified FRAPCON-3 ...<br>by Yun Long.<br>Ph.D.
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Wright, Amy G. "Drivers of burrow symbiont distribution in a softsediment system: host abundance or burrow trophic environment?" Bachelor's thesis, University of Cape Town, 2013. http://hdl.handle.net/11427/7634.

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The Langebaan Lagoon sandflats are dominated by the burrowing activities of thalassinid shrimps. Their burrows are home to various burrow symbionts including a commensal shrimp (Betaeus jucundus), a six-legged crab (Spiroplax spiralis) and a scaleworm (Antinoe lactea). Little work has been conducted on these burrow symbionts, and the mechanisms influencing their abundance and distribution are unknown. To test whether host abundance or the burrow trophic environment (i.e. food availability) is the dominant force shaping patterns of burrow symbiont distribution, samples of host and symbiont abundances as well as chlorophyll-a and extracellular polymeric substance (EPS) measurements were taken from three sites in Langebaan Lagoon over spring and autumn. Clear signals emerged in contradiction of the hypothesis that burrow symbiont abundances peak in areas associated with high abundances of hosts. Host abundances peaked at Bottelary (10.18 counts/site ± 1.02 SE), a site where recreational activities and thalassinid shrimp bait collection are prohibited. In contrast, peak B. jucundus abundance (6.56 counts/site ± 0.37 SE) occurred at Oesterval during September – the muddy sediment of the site resulted in high sedimentary food retention and the September spring phytoplankton bloom resulted in peak chlorophylla (234.12 mg chl-a/g sediment ± 42.74 SE) and EPS (0.13 mg EPS/g sediment ± 0.008 SE) concentrations. Regression analyses confirmed that food availability was the best explanation of the patterns observed in B. jucundus distributions, over and above that of host distributions. S. spiralis and A. lactea did not show this pattern, the result of the low counts of these species in the collected samples or their reliance on food sources different to those depended on by B. jucundus. These results are of consequence in changing the way we think about symbiont distributions relative to that of the hosts, in that the two may not be linked directly, but rather influenced by larger scale trophic changes such as the availability of food within the burrow.
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Larson, Kyle Blake. "Nest habitat selection of burrowing owls in relation to soils, burrow availability, and burrow temperature." Pullman, Wash. : Washington State University, 2009. http://www.dissertations.wsu.edu/Thesis/Summer2009/K_Larson_072409.pdf.

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Thesis (M.S. in environmental science)--Washington State University, August 2009.<br>Title from PDF title page (viewed on Sept. 17, 2009). "School of Earth and Environmental Sciences." Includes bibliographical references (p. 35-42).
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Björkholm, Peter, and Anna Dyring. "A study of a high rate gamma-spectrometer system for burnup measurements." Thesis, Uppsala universitet, Institutionen för fysik och astronomi, 1990. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-260034.

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Books on the topic "Burrup"

1

Kate, Gregory, and National Trust of Australia (W.A.), eds. From the Barracks to the Burrup: The National Trust in Western Australia. National Trust, 2010.

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Guest, Krysti. The promise of comprehensive native title settlements: The Burrup, Mg-Ord and Wimmera agreements. Australian Institute of Aboriginal and Torres Strait Islander Studies, 2009.

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Vinnicombe, Patricia. Dampier archaeological project: Resource document, survey and salvage of Aboriginal sites, Burrup Peninsula, Western Australia. Western Australian Museum, 1987.

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Vinnicombe, Patricia. Dampier Archaeological Project: Resource of document, survey and salvage of aboriginal sites, Burrup Peninsula, Western Australia. Western Australian Museum, 1987.

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Briggs-Smith, Noeline. Burrul Wallaay. Northern Regional Library and Information Service, 2003.

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Wagner, J. C. Recommendations for addressing axial burnup in PWR burnup credit analyses. Division of Systems Analysis and Regulatory Effectiveness, U.S. Nuclear Regulatory Commission, 2003.

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Müzesi, Burdur Arkeoloji. Burdur Müzesi: Burdur Museum. Burdur Müze Müdürlüğü, 2017.

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Prčkov, Ǵorǵi. Burmut. Grafo Prom, 2008.

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Ireland, Crafts Council of, ed. Burren 5. Crafts Council of Ireland, 1988.

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Agency, International Atomic Energy, ed. Water reactor fuel extended burnup study. International Atomic Energy Agency, 1992.

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Book chapters on the topic "Burrup"

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Davidson, Iain, Tim Douglas, and Wilfred Hicks. "Burrup Peninsula." In Encyclopedia of Global Archaeology. Springer International Publishing, 2020. http://dx.doi.org/10.1007/978-3-030-30018-0_25.

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Davidson, Iain, Tim Douglas, and Wilfred Hicks. "Burrup Peninsula." In Encyclopedia of Global Archaeology. Springer New York, 2014. http://dx.doi.org/10.1007/978-1-4419-0465-2_25.

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Stevens, Amy, and Jo McDonald. "Local—National—Global: Defining Indigenous Values of Murujuga’s Cultural Landscape in the Frame of International Patrimony." In Deep-Time Images in the Age of Globalization. Springer International Publishing, 2024. http://dx.doi.org/10.1007/978-3-031-54638-9_15.

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AbstractMurujuga, as the Dampier Archipelago (including Burrup Peninsula) National Heritage Listed Place is known to its traditional custodians, is on the Pilbara coast of northern Western Australia. Murujuga’s scientific values are endorsed on Australia’s National Heritage List under a range of significance criteria. This chapter describes how an Australian local Aboriginal community’s contemporary connections and significance values have been framed through the lens of Outstanding Universal Value in a world heritage nomination—and the scaffolding required to translate local and national heritage values into the global purview. The World Heritage List (WHL) criteria distinguish between natural and cultural values: an anathema to Aboriginal custodians who see ngurra (country) as both a natural and cultural domain. We describe the disjunct between Aboriginal custodial connections to country and UNESCO’s framing of Outstanding Universal Values (OUV) for a world heritage nomination. The Ngarda-Ngarli are pursuing World Heritage by documenting outstanding universal cultural values under criteria i, iii, and v). For Aboriginal custodians this journey towards international recognition provides an opportunity to assert their local connection and control over this significant place, in the belief that global recognition will increase its protection. This chapter explores whether World Heritage recognition will help its traditional custodians to manage this extraordinary heritage estate, particularly in the face of the national economic value being placed on Industry in this same landscape.
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Weik, Martin H. "Burrus diode." In Computer Science and Communications Dictionary. Springer US, 2000. http://dx.doi.org/10.1007/1-4020-0613-6_1952.

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Gooch, Jan W. "Burlap." In Encyclopedic Dictionary of Polymers. Springer New York, 2011. http://dx.doi.org/10.1007/978-1-4419-6247-8_1683.

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Weik, Martin H. "Burrus light-emitting diode." In Computer Science and Communications Dictionary. Springer US, 2000. http://dx.doi.org/10.1007/1-4020-0613-6_1953.

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Sandner, Dieter. "Trigant Burrow." In Die Gruppe und das Unbewusste. Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-34819-8_20.

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Hockey, Thomas. "Burrau, Carl." In Biographical Encyclopedia of Astronomers. Springer New York, 2014. http://dx.doi.org/10.1007/978-1-4419-9917-7_222.

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Florence, Ronald, Steven N. Shore, Steven N. Shore, et al. "Burrau, Carl." In The Biographical Encyclopedia of Astronomers. Springer New York, 2007. http://dx.doi.org/10.1007/978-0-387-30400-7_222.

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Gooch, Jan W. "Jute (Burlap)." In Encyclopedic Dictionary of Polymers. Springer New York, 2011. http://dx.doi.org/10.1007/978-1-4419-6247-8_6612.

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Conference papers on the topic "Burrup"

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Weiwei, Wang, and Lu Lu. "Analysis on Impact of Fuel Thermal Conductivity Degradation (TCD) on Large Break Loss of Coolant Accidents of CAP1000." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66283.

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Under high burnup conditions, thermal conductivity of fuel pellet degrades, which is referred to as thermal conductivity degradation (TCD). TCD phenomenon influences fuel average temperature and fuel storage energy under steady state condition before loss of coolant accident (LOCA) and further influences peak cladding temperature (PCT) during large break LOCA process. In this study, sensitivity study on double ended guillotine break of cold leg in CAP1000 at different burnup conditions was performed, using large break LOCA analysis code WCOBRA/TRAC and PCTs under different conditions were obtained. The modified NFI (Nuclear Fuels Institute) TCD model was adopted to model fuel conductivity after degradation in analysis and decrease of peaking factors including FQ and FΔh after 30GWD/MTU was also considered. Sensitivity analysis showed that: after considering the influence of TCD and peaking factor burndown, the PCT limiting case did not occur in low burnup range again, but occurred at burup of about 29GWD/MTU. Compared to other burnup points, the first and second peak values of PCT at that burnup point were all at the highest level. Performing of this study could prefer reference for analysis and estimation of large break LOCA of passive nuclear power plants under high burnup conditions.
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Winston, P. L., and J. W. Sterbentz. "Gross Gamma Dose Rate Measurements for TRIGA Spent Nuclear Fuel Burnup Validation." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22138.

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Gross gamma-ray dose rates from six spent TRIGA fuel elements were measured and compared to calculated values as a means to validate the reported element burnups. A newly installed and functional gamma-ray detection subsystem of the In-Cell Examination System was used to perform the measurements and is described in some detail. The analytical methodology used to calculate the corresponding dose rates is presented along with the calculated values. Comparison of the measured and calculated dose rates for the TRIGA fuel elements indicates good agreement (less than a factor of 2 difference). The intent of the subsystem is to measure the gross gamma dose rate and correlate the measurement to a calculated dose rate based on the element s known burnup and other pertinent spent fuel information. Although validation of the TRIGA elements’ burnup is of primary concern in this paper, the measurement and calculational techniques can be used to either validate an element’s reported burnup or provide a burnup estimate for an element with an unknown burnup.
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Chang, Gray S., and Robert C. Pedersen. "Radial Power Profile of MOX and LEU Fuel Pellet Versus Burnup." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22483.

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One of challenge to burn the WG-Pu in Mixed Oxide (MOX) fuel in light water reactors (LWR) is to demonstrate that the differences between WG-MOX, RG-MOX, and LWR LEU fuel are minimal, and therefore, the commercial MOX and LEU fuel experience base is applicable. The MCWO-calculated Radial Power Profile of LEU, Weapons Grade-MOX and Reactor Grade-MOX fuel pellets at various burnups are similar toward the end of life (50 GWd/t). Therefore, the LEU fuel performance evaluation code — FRAPCON-3 with modifications, such as, the detailed fission power profiles versus burnup, can be used in the MOX fuel pellet performance analysis. MCWO also calculated the 240Pu/Pu ratio in WG-MOX versus burnup, which reaches an average of 31.25% at discharged burnup of 50 GWd/t. It meets the spent fuel standard for WG-Pu disposition in LWR.
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Niknam, Seyed Ali, Azziz Tiabi, Imed Zaghbani, Rene Kamguem, and Victor Songmene. "Milling Burr Size Estimation Using Acoustic Emission and Cutting Forces." In ASME 2011 International Mechanical Engineering Congress and Exposition. ASMEDC, 2011. http://dx.doi.org/10.1115/imece2011-63824.

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Burr formation is one of the main concerns usually faced by machining industries. Its presence leads to additional part edge finishing operations that are costly and time consuming. Burrs must be removed as they are source of dimensional errors, jamming and misalignment during assembly. In many cases burrs may injure workers during handling of machined part. Due to burr effect on machined part quality, manufacturing costs and productivity, more focus has been given to burr measurement/estimation methods. Large number of burr measurement methods has been introduced according to various criteria. The selection of appropriate burr size estimation method depends on number of factors such as desired level of quality and requested measuring accuracy. Traditional burr measurement methods are very time consuming and costly. This article aims to present empirical models using acoustic emission (AE) and cutting forces signals to predict entrance and exit burrs size in slot milling operation. These models can help estimating the burrs size without having to measure them. The machining tests were carried on Al 7075-T6 aluminum alloy using 3 levels of cutting speed, 3 levels of feed rate, 3 levels of cutting tool coating and 2 levels of depth of cut. Mathematical models were developed based on most sensitive AE parameters following statistical analysis, cutting forces and their interaction on predicting the entrance and exit burrs size. The proposed models correlate very well with the measured burrs size data.
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Matsumura, Takashi, Tsuyoshi Konno, Shouta Tobe, and Takafumi Komatsu. "Deburring of Micro-Scale Structures Machined in Milling." In ASME 2010 International Manufacturing Science and Engineering Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/msec2010-34149.

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Recently micro cutting has been applied to manufacturing of micro devices. Burr formation is a troublesome problem in micro cutting. From the point of view of the required accuracy, burr removal in the micro manufacturing cannot be performed by the manual operations or the additional cuttings. The paper presents a deburring process to remove the burrs on the micro-scale structured surfaces, which are machined in micro milling. In order to remove the burrs on the pillars in the structures, the study examines burr removal milling, polishing and water jet finishing. Burr removal milling leaves the cutter traces with adhesion of the chips on the pillars. Polishing finishes the surfaces with removing the burrs on the top of the pillars. A supporting device is used for protecting the edge shapes of the pillars in polishing. Then, the burrs on the side of the pillars can be removed in water jet finishing. A water jet machine driven by a low pressure pump is developed to remove the burrs without losing their shapes. The process sequence of polishing and water jet finishing is effective in removing the burrs in micro milling. The presented process is discussed to manufacture the micro-scale structures in mechanical manner based on the axiomatic design.
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Niknam, Seyed Ali, and Victor Songmene. "Experimental Investigation and Modeling of Milling Burrs." In ASME 2013 International Manufacturing Science and Engineering Conference collocated with the 41st North American Manufacturing Research Conference. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/msec2013-1176.

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The burr formation is one of the most common and undesirable phenomenon occurring in machining operations which reduces assembly and machined part quality. Therefore, it is desired to eliminate the burrs or reduce the effort required to remove them. This paper presents the results of an experimental study and describe the influence of cutting parameters on slot milling burrs, namely top burrs and exit burrs. Statistical methods are also used to determine the controllability of each burr. A computational model is then proposed to predict the exit up milling side burr thickness based on cutting parameters and material properties such as yield strength and specific cutting force coefficient that are the only unknown variables in the model. The proposed computational model is validated using experimental results obtained during slot milling of 2024-T351 and 6061-T6 aluminium alloys.
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DEBARD, Benoit. "Experimental analysis of burr formation during Ti6Al4V drilling." In Material Forming. Materials Research Forum LLC, 2024. http://dx.doi.org/10.21741/9781644903131-228.

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Abstract. To improve the assembly process of aeronautical structures by the mean of One-Way Assembly strategies (no deburring of metallic parts before the installation of final fasteners), it is mandatory to monitor the burr size of drilled holes. Indeed, burrs can have a significant effect on the fatigue life of structures. It was shown that cracks are initiated from exit burrs. This paper presents an experimental analysis of the burr geometry through cutting forces and thermal imaging measurements. The effect of the tool wear on burr geometry is also analyzed to identify phenomena occurring during burr formation.
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Penalva, Jaime E., Francisco Feria, and Luis E. Herranz. "Modeling of Cladding Thermal Evolution Along Cask Storage." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30758.

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One of the safety requirements in dry storage of spent fuel is to ensure the cladding integrity. In this regard, the understanding of the cladding mechanical performance along the storage period is indispensable, both to analyse the failure probability and to characterize the state of the cladding so that fuel management is conducted with accurate knowledge of the material conditions. The main interest is focused on cladding degrading mechanisms as creep and hydrogen related (e.g. hydrides embrittlement), which are strongly influenced by temperature. Therefore, cladding thermal characterization along dry storage is an important element to predict fuel rod mechanical performance. Cladding temperature decay models found in the literature are fuel burnup independent and they cannot be applied to storage periods longer than some decades. The goal of this work is to develop a simplified model of cladding temperature as a function of burnup that spans up to 300 years of cask storage. To do so, a methodology is established based on FLUENT steady state calculations fed by heat decay data found in the literature for different burnups (33–63 MWd/kgU). From the results, a temperature correlation as a function of burnup and out-of-reactor time has been derived. It shows an average relative error less than 2% with respect FLUENT calculations. Finally, significance of having an accurate thermal characterization of the fuel rod has been highlighted by comparing fuel rod thermo-mechanics based on the derived correlation and the one resulting from using a correlation developed by EPRI.
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Lancaster, Dale, and Charles Rombough. "Burnup Credit for PWR Spent Fuel Pools with High Enriched/High Burnup Fuel." In Nuclear Criticality Safety Division Topical Meeting (NCSD 2022). American Nuclear Society, 2022. http://dx.doi.org/10.13182/t126-37470.

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Karriem, Veronica, William Marshall, and Robert Lefebvre. "Coupling SCALE with DAKOTA for Axial Burnup Profiles Assessment in Burnup Credit [Slides]." In 2023 ANS Winter Conference and Expo, Washington, DC (United States), 12-15 Nov 2023. US DOE, 2023. http://dx.doi.org/10.2172/2352251.

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Reports on the topic "Burrup"

1

Wagner, J. C. Review of Axial Burnup Distribtion Considerations for Burnup Credit Calculations. Office of Scientific and Technical Information (OSTI), 2000. http://dx.doi.org/10.2172/885581.

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Wagner, J. C., and M. D. DeHart. Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations. Office of Scientific and Technical Information (OSTI), 2000. http://dx.doi.org/10.2172/763169.

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Wagner, J. C. Recommendations for Addressing Axial Burnup in the PWR Burnup Credit Analyses. Office of Scientific and Technical Information (OSTI), 2002. http://dx.doi.org/10.2172/885754.

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Barner, J., M. Cunningham, M. Freshley, and D. Lanning. High Burnup Effects Program. Office of Scientific and Technical Information (OSTI), 1990. http://dx.doi.org/10.2172/5876135.

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J.M. Scaglione. PWR AXIAL BURNUP PROFILE ANALYSIS. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/862026.

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A. Alsaed. PWR AXIAL BURNUP PROFILE ANALYSIS. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/862027.

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J.M. Acaglione. PWR AXIAL BURNUP PROFILE ANALYSIS. Office of Scientific and Technical Information (OSTI), 2003. http://dx.doi.org/10.2172/862144.

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Diamond, D. J., L. Neymotin, and P. Kohut. Power excursion analysis for high burnup cores. Office of Scientific and Technical Information (OSTI), 1996. http://dx.doi.org/10.2172/207613.

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A. Alsaed. ISOTOPIC MODEL FOR COMMERCIAL SNF BURNUP CREDIT. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/862028.

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A.H. Wells. ISOTOPIC MODEL FOR COMMERCIAL SNF BURNUP CREDIT. Office of Scientific and Technical Information (OSTI), 2004. http://dx.doi.org/10.2172/862151.

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