Biossorção de tório com emprego de Sargassum filipendula

Com o aumento do rigor para descarte de efluentes contaminado com metais pesados, as pesquisas têm se intensificado na busca de métodos de remoção, que tragam bons resultados de captação dos metais, aliado a um baixo custo. O uso de biomassas como bactérias, fungos e algas marinhas como material adsorvente, tem se apresentado como uma alternativa, principalmente para soluções com baixo teor de metais. Neste trabalho, a alga marinha Sargassum filipendula foi avaliada na sua capacidade de remoção do metal tório de uma solução sintética e do efluente dos laboratórios de análises ambientais do IRD. A cinética desta biossorção foi estudada em regime de batelada e o equilíbrio foi alcançado com 180 min de reação. Dois modelos cinéticos foram utilizados nesta avaliação, um de primeira ordem e um modelo de pseudo segunda ordem, tendo o modelo de segunda ordem apresentado um melhor ajuste dos dados. Na avaliação da capacidade máxima de captação do tório pela biomassa marinha em regime de batelada, foi construída a isoterma que apresentou um perfil crescente na captação alcançando um máximo de 2,59 mol/g. Os modelos de Langmuir e Freundlich foram utilizados para ajustar os dados da isoterma, tendo apresentado maior correlação com os dados o modelo de Langmuir, resultando num valor de captação máxima calculado pelo modelo de 2,92 mol/g. A capacidade de remoção do metal tório da alga Sargassum filipendula também foi avaliada em regime contínuo. Um estudo de altura crítica de leito foi realizado preenchendo-se uma coluna com diferentes massas de alga correspondendo a diferentes alturas de leito. A concentração de tório residual foi quantificada na solução de saída e a menor concentração na saída foi alcançada com 40 cm de leito ou 96 g de biomassa. Após este estudo um sistema contínuo com duas colunas, com 96 g de biomassa cada, e uma bomba peristáltica foi utilizado para o tratamento do efluente real do IRD, contendo não apenas o metal tório, mas outros metais como urânio, cálcio, cromo, ferro, chumbo, etc. Cento e cinco litros de efluente foram tratados numa concentração de 6 mg/L, a concentração do efluente de saída foi de 3,75 mg/L. A caracterização do efluente quanto aos metais presentes foi realizada em ICP-MS, os resultados demonstraram que não houve competição pelos sítios ligantes da biomassa entre o tório e os demais metais. Além disso, alguns metais como cálcio, ferro e magnésio, tiveram um aumento na concentração de saída indicando a presença do mecanismo de troca iônica na biossorção do tório por Sargassum filipendula

Metallogenic Provinces of the Southwestern United States and Northern Mexico

Some of the metallogenic provinces of the southwestern United States and northern Mexico are defined by the geographic distribution of trace elements in the primary sulfide minerals chalcopyrite and sphalerite. The elements investigated include antimony, arsenic, bismuth, cadmium, cobalt, gallium, germanium, indium, manganese, molybdenum, nickel, silver, tellurium, thallium, and tin. Of these elements, cobalt, gallium, germanium, indium, nickel, silver, and tin exhibit the best defined geographic distribution.

The data indicate that chalcopyrite is the preferred host for tin and perhaps molybdenum; sphalerite is the preferred host for cadmium, gallium, germanium, indium, and manganese; galena is the preferred host for antimony, bismuth, silver, tellurium, and thallium; and pyrite is the preferred host for cobalt, nickel, and perhaps arsenic. With respect to the two minerals chalcopyrite and sphalerite, antimony, arsenic, molybdenum, nickel, silver, and tin prefer chalcopyrite; and bismuth, cadmium, cobalt, gallium, germanium, indium, manganese, and thallium prefer sphalerite. This distribution probably is the result of the interaction of several factors, among which are these: the various radii of the elements, the association due to chemical similarities of the major and trace elements, and the degree of ionic versus covalent and metallic character of the metal-sulfur bonds in chalcopyrite and sphalerite. The type of deposit, according to a temperature classification, appears to be of minor importance in determining the trace element content of chalcopyrite and sphalerite.

A preliminary investigation of large single crystals of sphalerite and chalcopyrite indicates that the distribution within a single crystal of some elements such as cadmium in sphalerite and indium and silver in chalcopyrite is relatively uniform, whereas the distribution of some other elements such as cobalt and manganese in sphalerite is somewhat less uniform and the distribution of tin in sphalerite is extremely erratic. The variations in trace element content probably are due largely to variations in the composition of the fluids during the growth of the crystals, but the erratic behavior of tin in sphalerite perhaps is related to the presence of numerous cavities and inclusions in the crystal studied.

Maps of the geographic distribution of trace elements in chalcopyrite and sphalerite exhibit three main belts of greater than average trace element content, which are called the Eastern, Central, and Western belts. These belts are consistent in trend and position with a beltlike distribution of copper, gold, lead, zinc, silver, and tungsten deposits and with most of the major tectonic features. However, there appear to be no definite time relationships, for as many as four metallogenic epochs, from Precambrian to late Tertiary, are represented by ore deposits within the Central belt.

The evidence suggests that the beltlike features have a deep seated origin, perhaps in the sub-crust or outer parts of the mantle, and that the deposits within each belt might be genetically related through a beltlike compositional heterogeneity in the source regions of the ores. Hence, the belts are regarded as metallogenic provinces.

The geochronology of the plutonic and metamorphic rocks of New Zealand

Extensive Rubidium-Strontium age determinations on both mineral and total rock samples of the crystalline rocks of New Zealand, which almost solely crop out in the South Island, indicate widespread plutonic and metamorphic activity occurred during two periods, one about 100-118 million years ago and the other about 340-370 million years ago. The former results date the Rangitata Orogeny as Cretaceous. They associate extensive plutonic activity with this orogeny which uplifted and metamorphosed the rocks of the New Zealand Geosyncline, although no field association between the metamorphosed geosynclinal rocks and plutonic rocks has been found. The Cretaceous plutonic rocks occur to the west in the Foreland Province in Fiordland, Nelson, and Westland, geographically separated from the Geosynclinal Province. Because of this synchronous timing of plutonic and high pressure metamorphic activity in spatially separated belts, the Rangitata Orogeny in New Zealand is very similar to late Mesozoic orogenic activity in many other areas of the circum-Pacific margin (Miyashiro, 1961).

The 340-370 million year rocks, both plutonic and metamorphic, have been found only in that part of the Foreland Province north of the Alpine Fault. There, they are concentrated along the west coast over a distance of 500 km, and appear scattered inland from the coast. Probably this activity marks the outstanding Phanerozoic stratigraphic gap in New Zealand which occurred after the Lower Devonian.

A few crystalline rocks in the Foreland Province north of the Alpine Fault with measured ages intermediate between 340 and 120 million years have been found. Of these, those with more than one mineral examined give discordant results. All of these rocks are tentatively regarded as 340-370 million year old rocks that have been variously disturbed during the Rangitata Orogeny, 100-120 million years ago.

In addition to these two periods, plutonic activity, dominantly basic and ultrabasic, but including the development of some rocks of intermediate and acidic composition, occurred along the margin of the Geosynclinal Province at its border with the Foreland Province during Permian times about 245 million years ago, and this activity possibly extended into the Mesozoic.

Evidence from rubidium-strontium analyses of minerals and a total rock, and from uranium, thorium, and lead analyses of uniform euhedral zircons from a meta-igneous portion of the Charleston Gneiss, previously mapped as Precambrian, indicate that this rock is a 350-370 million year old plutonic rock metamorphosed 100 million yea rs ago during the Rangitata Orogeny. No crystalline rocks with primary Precambrian ages have been found in New Zealand. However, Pb²⁰⁷/Pb₂₀₆ ages of 1360 million years and 1370 million years have been determined for rounded detrital zircons separated from each of two hornfels samples of one of New Zealand's olde st sedimentary units, the Greenland Series. These two samples were metamorphosed 345- 370 million years ago. They occur along the west coast, north of the Alpine Fault, at Waitaha River and Moeraki River, separated by 135 km. The Precambrian measured ages are most likely minimum ages for the oldest source area which provided the detrital zircons because the uranium, thorium and lead data are highly discordant. These results are of fundamental importance for the tectonic picture of the Southwest Pacific margin and demonstrate the existence of relatively old continental crust of some lateral extent in the neighborhood of New Zealand.

Defects in U3+: CaF2 single crystals grown under different conditions by the temperature gradient technique

Defects in as-grown U3+ : CaF2 crystals grown with or without PbF2 as an oxygen scavenger were studied using Raman spectra, thermoluminescence glow curves, and additional absorption (AA) spectra induced by heating and gamma-irradiation. The effects of heating and irradiation on as-grown U3+: CaF2 crystals are similar, accompanied by the elimination of H-type centers and production of F-type centers. U3+ is demonstrated to act as an electron donor in the CaF2 lattice, which is oxidized to the tetravalent form by thermal activation or gamma-irradiation. In the absence of PbF(2)as an oxygen scavenger, the as-grown U3+:CaF2 crystals contain many more lattice defects in terms of both quantity and type, due to the presence of O2- impurities. Some of these defects can recombine with each other in the process of heating and gamma-irradiation. (c) 2005 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Aplicación del método de series de Uranio al grafismo rupestre de estilo paleolítico: el caso de la cavidad de Covalanas (Ramales de la Victoria, Cantabria)

[EN] Se ensaya la aplicación del procedimiento analítico de series de Uranio para el conocimiento de la seriación artística de obras parietales de estilo paleolítico. El resultado obtenido muestra la validez del método y abre nuevas vías para la obtención de fechas absolutas "ante quem" y "post quem" que sirvan para enmarcar momentos de ejecución de obras rupestres.

¿Del estilo paleolítico a la cronología contemporánea?: Una (revisión) nueva versión del arte parietal de la cueva de El Becerral (La Gándara, Cantabria)

Homenaje a Ignacio Barandiarán Maestu / coord. por Javier Fernández Eraso, Juan Santos Yanguas

Avaliação do impacto radiológico atmosférico de uma unidade de mineração e beneficiamento de urânio

Este trabalho teve como objetivo avaliar o impacto radiológico atmosférico da Unidade de Concentrado de Urânio URA, Caetité, BA, através da modelagem da dispersão de radionuclídeos e a estimativa da dose efetiva anual (em mSv.ano-1). Para tal, utilizou-se o programa MILDOS-AREA que foi desenvolvido pelo Argonne National Laboratory (ANL) em conjunto com a U.S. Nuclear Regulatory Commission (USNRC), para avaliar impacto radiológico ambiental atmosférico nas instalações de mineração e beneficiamento de urânio. O incremento de dose efetiva anual para três grupos críticos hipotéticos e oito grupos populacionais reais foi estimado com base na medida de fluxos de radônio e na estimativa das concentrações de radionuclídeos em particulados no ar dos principais termos fontes da URA (cava da mina, depósito de estéril e britador). Paralelamente, as medidas de concentração de radônio e taxa de kerma no ar, reportadas nos relatórios dos programas de monitoração ambiental pré-operacional (PMAPO) e operacional (PMAO) da URA, foram avaliadas. Os valores de dose efetiva anual estimados para os grupos críticos hipotéticos variaram de 1,78E-02 a 2,10E-02 mSv.ano-1, enquanto que para os grupos populacionais, variaram de 7,49E-05 a 1,56E-02 mSv.ano-1. A maior contribuição para o incremento da dose foi devida a inalação do radônio, sendo responsável por quase a totalidade da dose efetiva anual estimada. A média da concentração de atividade de radônio no entorno da URA foi 137,21 Bq m-3 e não sendo observada diferenças significativas entre as concentrações de radônio reportadas nos programas de monitoramento ambiental pré-operacional (valores de background) e operacional. Os valores médios de taxa de kerma no ar no entorno da URA foram de 0,136 μGy h-1. No entanto, em todos os pontos de monitoramento, os valores reportados no programa operacional foram inferiores aos valores reportados no programa pré-operacional (background), o que sugere problemas de medidas ou de coleta de dados durante a realização deste programa. O operador da URA utilizou para avaliação de impacto radiológico atmosférico, resultados apresentados em seus relatórios finais de análise de segurança (RFAS), um modelo próprio de simulação de dispersão, denominado Impacto Ambiental Radiológico (IAR7). Uma comparação entre o MILDOS-AREA e o IAR7, utilizando os mesmos parâmetros de entrada reportados no RFAS sugere que o IAR7 subestimou as concentrações de radônio no ar para os grupos críticos hipotéticos. Os resultados de simulação com o MILDOS-AREA mostram que as doses efetivas estimadas para os grupos críticos hipotéticos são inferiores a 0,3 mSv.ano-1 que é a restrição de dose estabelecida pela Comissão Nacional de Energia Nuclear. Recomenda-se que o código MILDOS-AREA seja utilizado no Brasil, para fins de licenciamento e controle, tendo em vista que o mesmo é um código validado e já utilizado em outros países para avaliar impacto radiológico ambiental atmosférico em instalações de mineração e beneficiamento de urânio

Interações do lantânio e cério com microalgas dos gêneros Monoraphidium e Scenedesmus

Os elementos de terras raras, representados em sua maioria pelos lantanídeos, ocorrem principalmente como constituintes-traço da maioria dos minerais de rochas comuns (monazita, apatita) e também estão presentes em alguns minérios. Tais elementos foram largamente usados por décadas como fertilizantes na China. Na área das inovações tecnológicas, a demanda por esses metais vem crescendo por conta das suas aplicações em diversos campos. Consequentemente, grandes quantidades desses elementos são acumulados em ambientes aquáticos atingindo o fitoplâncton. Assim, as microalgas que são organismos ecologicamente importantes na cadeia alimentar têm sido frequentemente usadas em estudos ambientais para avaliar a toxicidade relativa de várias descargas químicas e são largamente estudadas na detecção dos primeiros impactos no ecossistema. Somado a isso, são biomassas que possuem boa capacidade de biossorção de metais devido à presença de ligantes na sua estrutura que promovem a captação deles quando em solução. Dessa forma, as interações entre as microalgas verdes Monoraphidium e Scenedesmus e os íons La3+ e Ce3+ foram investigadas neste trabalho. Para isso, foram avaliados o efeito tóxico e a bioacumulação do La3+ pelas duas microalgas verdes. Adicionalmente, estudos em batelada da biossorção do La3+ e Ce3+ em soluções contendo os elementos isoladamente ou em combinação foram realizados. No estudo de toxicidade e de bioacumulação o meio de cultivo utilizado foi o ASM-1, com e sem presença de La3+ (10 mg.L-1 a 100 mg.L-1), onde o efeito tóxico do metal foi monitorado por análises micro e macroscópica das células e também pela quantificação do crescimento celular baseada em medidas da massa seca. A bioacumulação do metal foi avaliada da mesma forma para ambas as microalgas. Os resultados obtidos mostraram que o efeito tóxico do metal foi presente em concentrações iônicas de 50 e 100 mg.L-1 e que houve uma bioconcentração do La3+ em ambas espécies de microalgas, principalmente quando a concentração inicial do La3+ foi de 10 e 25 mg.L-1, mostrando que houve uma relação direta entre a bioconcentração e a toxicidade do La3+. O gênero Monoraphidium bioconcentrou mais metal que o gênero Scenedesmus. Os resultados da biossorção dos metais em solução monoelementar mostraram que as microalgas apresentaram grande capacidade de captação do La3+ (20,7 mmol.g-1 para Monoraphidium sp. e 17,8 mmol.g-1 para Scenedesmus sp.) e do Ce3+ (25,7 mmol.g-1 para Monoraphidium sp. e 11,5 mmol.g-1 para Scenedesmus sp.). Os resultados obtidos revelaram que os dados melhor se ajustaram ao modelo de Freundlich, na maioria dos casos. Em sistema binário, notou-se que houve uma menor captação de cada um individualmente, evidenciando uma competição entre eles pelos mesmos sítios ligantes e que ambas apresentaram maior afinidade pelo Ce3+

Near-complete transuranic waste incineration in a thorium fuelled pressurised water reactor

The production of long-lived transuranic (TRU) waste is a major disadvantage of fission-based nuclear power. Incineration, and virtual elimination, of waste stockpiles is possible in a thorium (Th) fuelled critical or subcritical fast reactor. Fuel cycles producing a net decrease in TRUs are possible in conventional pressurised water reactors (PWRs). However, minor actinides (MAs) have a detrimental effect on reactivity and stability, ultimately limiting the quality and quantity of waste that can be incinerated. In this paper, we propose using a thorium-retained-actinides fuel cycle in PWRs, where the reactor is fuelled with a mixture of thorium and TRU waste, and after discharge all actinides are reprocessed and returned to the reactor. To investigate the feasibility and performance of this fuel cycle an assembly-level analysis for a one-batch reloading strategy was completed over 125 years of operation using WIMS 9. This one-batch analysis was performed for simplicity, but allowed an indicative assessment of the performance of a four-batch fuel management strategy. The build-up of 233U in the reactor allowed continued reactive and stable operation, until all significant actinide populations had reached pseudo-equilibrium in the reactor. It was therefore possible to achieve near-complete transuranic waste incineration, even for fuels with significant MA content. The average incineration rate was initially around 330 kg per GW th year and tended towards 250 kg per GW th year over several decades: a performance comparable to that achieved in a fast reactor. Using multiple batch fuel management, competitive or improved end-of-cycle burn-up appears achievable. The void coefficient (VC), moderator temperature coefficient (MTC) and Doppler coefficient remained negative. The quantity of soluble boron required for a fixed fuel cycle length was comparable to that for enriched uranium fuel, and acceptable amounts can be added without causing a positive VC or MTC. This analysis is limited by the consideration of a single fuel assembly, and it will be necessary to perform a full core coupled neutronic-thermal-hydraulic analysis to determine if the design in its current form is feasible. In particular, the potential for positive VCs if the core is highly or locally voided is a cause for concern. However, these results provide a compelling case for further work on concept feasibility and fuel management, which is in progress. © 2011 Elsevier Ltd. All rights reserved.

A novel method for rapid comparative quantitative analysis of nuclear fuel cycles

One of the greatest obstacles facing the nuclear industry is that of sustainability, both in terms of the finite reserves of uranium ore and the production of highly radiotoxic spent fuel which presents proliferation and environmental hazards. Alternative nuclear technologies have been suggested as a means of delivering enhanced sustainability with proposals including fast reactors, the use of thorium fuel and tiered fuel cycles. The debate as to which is the most appropriate technology continues, with each fuel system and reactor type delivering specific advantages and disadvantages which can be difficult to compare fairly. This paper demonstrates a framework of performance metrics which, coupled with a first-order lumped reactor model to determine nuclide population balances, can be used to quantify the aforementioned pros and cons for a range of different fuel and reactor combinations. The framework includes metrics such as fuel efficiency, spent fuel toxicity and proliferation resistance, and relative cycle performance is analysed through parallel coordinate plots, yielding a quantitative comparison of disparate cycles. © 2011 Elsevier Ltd. All rights reserved.

Open cycle thorium–uranium-fuelled nuclear energy systems

The potential for countries that currently have a nominal nuclear energy infrastructure to adopt thorium–uranium-fuelled nuclear energy systems, using a once-through ‘open’ nuclear fuel cycle, has been suggested by the International Atomic Energy Agency. This review paper highlights generation II, III and III+ nuclear energy technologies that could potentially adopt an open thorium–uranium fuel cycle and qualitatively highlights the main differences between the open thorium–uranium and open uranium fuel cycles.

Recycle of transuranium elements in light water reactors for reduction of geological storage requirements

This paper presents results of a feasibility study aimed at developing a zero-transuranic-discharge fuel cycle based on the U-Th-TRU ternary cycle. The design objective is to find a fuel composition (mixture of thorium, enriched uranium, and recycled transuranic components) and fuel management strategy resulting in an equilibrium charge-discharge mass flow. In such a fuel cycle scheme, the quantity and isotopic vector of the transuranium (TRU) component is identical at the charge and discharge time points, thus allowing the whole amount of the TRU at the end of the fuel irradiation period to be separated and reloaded into the following cycle. The TRU reprocessing activity losses are the only waste stream that will require permanent geological storage, virtually eliminating the long-term radiological waste of the commercial nuclear fuel cycle. A detailed three-dimensional full pressurized water reactor (PWR) core model was used to analyze the proposed fuel composition and management strategy. The results demonstrate the neutronic feasibility of the fuel cycle with zero-TRU discharge. The amount of TRU and enriched uranium loaded reach equilibrium after about four TRU recycles. The reactivity coefficients were found to be within a range typical for a reference PWR core. The soluble boron worth is reduced by a factor of ∼2 from a typical PWR value. Nevertheless, the results indicate the feasibility of an 18-month fuel cycle design with an acceptable beginning-of-cycle soluble boron concentration even without application of burnable poisons.

A combined nonfertile and UO2 PWR fuel assembly for actinide waste minimization

A new combined Non Fertile and Uranium (CONFU) fuel assembly is proposed to limit the actinides that need long-term high-level waste storage from the pressurized water reactor (PWR) fuel cycle. In the CONFU assembly concept, ∼20% of the UO2 fuel pins are replaced with fertile free fuel hosting the transuranic elements (TRUs) generated in the previous cycle. This leads to a fuel cycle sustainable with respect to net TRU generation, and the amount and radiotoxicity of the nuclear waste can be significantly reduced in comparison with the conventional once-through UO2 fuel cycle. It is shown that under the constraints of acceptable power peaking limits, the CONFU assembly exhibits negative reactivity feedback coefficients comparable in values to those of the reference UO2 fuel. Feasibility of the PWR core operation and control with complete TRU recycle has been shown based on full-core three-dimensional neutronic simulation. However, gradual buildup of small amounts of Cm and Cf challenges fuel reprocessing and fabrication due to the high spontaneous fission rates of these nuclides and heat generation by some Pu, Am, and Cm isotopes. Feasibility of the processing steps becomes more attainable if the time between discharge and reprocessing is 20 yr or longer.

A survey of alternative once-through fast reactor core designs

Reprocessing of Light Water Reactor (LWR) spent fuel to recover plutonium or transuranics for use in Sodium cooled Fast Reactors (SFRs) is a distant prospect in the U.S.A. This has motivated our evaluation of potentially cost-effective operation of uranium startup fast reactors (USFRs) in a once-through mode. This review goes beyond findings reported earlier based on a UC fueled MgO reflected SFR to describe a broader parametric study of options. Cores were evaluated for a variety of fuel/coolant/reflector combinations: UC/UZr/UO 2/UN;Na/Pb; MgO/SS/Zr. The challenge is achieving high burnup while minimizing enrichment and respecting both cladding fluence/dpa and reactivity lifetime limits. These parametric studies show that while UC fuel is still the leading contender, UO 2 fuel and ZrH 1.7 moderated metallic fuel are also attractive if UC proves to be otherwise inadequate. Overall, these findings support the conclusion that a competitive fuel cycle cost and uranium utilization compared to LWRs is possible for SFRs operated on a once-through uranium fueled fuel cycle. In addition, eventual transition to TRU recycle mode is studied, as is a small test reactor to demonstrate key features.

Microheterogeneous Thoria-Urania Fuels for Pressurized Water Reactors

A thorium-based fuel cycle for light water reactors will reduce the plutonium generation rate and enhance the proliferation resistance of the spent fuel. However, priming the thorium cycle with ²³⁵U is necessary, and the ²³⁵U fraction in the uranium must be limited to below 20% to minimize proliferation concerns. Thus, a once-through thorium-uranium dioxide (ThO2-UO2) fuel cycle of no less than 25% uranium becomes necessary for normal pressurized water reactor (PWR) operating cycle lengths. Spatial separation of the uranium and thorium parts of the fuel can improve the achievable burnup of the thorium-uranium fuel designs through more effective breeding of ²³³U from the ²³²Th. Focus is on microheterogeneous fuel designs for PWRs, where the spatial separation of the uranium and thorium is on the order of a few millimetres to a few centimetres, including duplex pellet, axially microheterogeneous fuel, and a checkerboard of uranium and thorium pins. A special effort was made to understand the underlying reactor physics mechanisms responsible for enhancing the achievable burnup at spatial separation of the two fuels. The neutron spectral shift was identified as the primary reason for the enhancement of burnup capabilities. Mutual resonance shielding of uranium and thorium is also a factor; however, it is small in magnitude. It is shown that the microheterogeneous fuel can achieve higher burnups, by up to 15%, than the reference all-uranium fuel. However, denaturing of the ²³³U in the thorium portion of the fuel with small amounts of uranium significantly impairs this enhancement. The denaturing is also necessary to meet conventional PWR thermal limits by improving the power share of the thorium region at the beginning of fuel irradiation. Meeting thermal-hydraulic design requirements by some of the microheterogeneous fuels while still meeting or exceeding the burnup of the all-uranium case is shown to be potentially feasible. However, the large power imbalance between the uranium and thorium regions creates several design challenges, such as higher fission gas release and cladding temperature gradients. A reduction of plutonium generation by a factor of 3 in comparison with all-uranium PWR fuel using the same initial ²³⁵U content was estimated. In contrast to homogeneously mixed U-Th fuel, microheterogeneous fuel has a potential for economic performance comparable to the all-UO2 fuel provided that the microheterogeneous fuel incremental manufacturing costs are negligibly small.