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1

Cabet, C., J. Jang, J. Konys, and P. F. Tortorelli. "Environmental Degradation of Materials in Advanced Reactors." MRS Bulletin 34, no. 1 (January 2009): 35–39. http://dx.doi.org/10.1557/mrs2009.10.

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AbstractAdvanced fission-based reactors challenge our ability to fully understand environment–materials reactions in terms of fundamental stability and kinetics, including the influences of composition, microstructure, and system design, and to predict associated long-term performance. This article briefly describes corrosion reactions and the processes by which such are managed for several elevated-temperature environments associated with advanced reactor concepts: helium, molten Pb–Bi, fluorides, and supercritical water. For most of the subject environments, corrosion resistance critically depends on the ability to form and maintain protective surface layers. Effects of corrosion on mechanical behavior can be from thermally and chemically induced changes in microstructures or from environmental effects on cracking susceptibility. In most cases, the simultaneous effects of chemical reactivity and radiation have not been fully addressed, nor has much attention been paid to newly emerging alloy compositions or the effects of substantially increased operating temperatures.
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2

Allen, T., H. Burlet, R. K. Nanstad, M. Samaras, and S. Ukai. "Advanced Structural Materials and Cladding." MRS Bulletin 34, no. 1 (January 2009): 20–27. http://dx.doi.org/10.1557/mrs2009.8.

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AbstractAdvanced nuclear energy systems, both fission- and fusion-based, aim to operate at higher temperatures and greater radiation exposure levels than experienced in current light water reactors. Additionally, they are envisioned to operate in coolants such as helium and sodium that allow for higher operating temperatures. Because of these unique environments, different requirements and challenges are presented for both structural materials and fuel cladding. For core and cladding applications in intermediate-temperature reactors (400–650°C), the primary candidates are 9–12Cr ferritic–martensitic steels (where the numbers represent the weight percentage of Cr in the material, i.e., 9–12 wt%) and advanced austenitic steels, adapted to maximize high-temperature strength without compromising lower temperature toughness. For very high temperature reactors (>650°C), strength and oxidation resistance are more critical. In such conditions, high-temperature metals as well as ceramics and ceramic composites are candidates. For all advanced systems operating at high pressures, performance of the pressure boundary materials (i.e., those components responsible for containing the high-pressure liquids or gases that cool the reactor) is critical to reactor safety. For some reactors, pressure vessels are anticipated to be significantly larger and thicker than those used in light water reactors. The properties through the entire thickness of these components, including the effects of radiation damage as a function of damage rate, are important. For all of these advanced systems, optimizing the microstructures of candidate materials will allow for improved radiation and high-temperature performance in nuclear applications, and advanced modeling tools provide a basis for developing optimized microstructures.
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3

Albagnac, G. "Biomass Retention in Advanced Anaerobic Reactors." Water Science and Technology 22, no. 1-2 (January 1, 1990): 17–24. http://dx.doi.org/10.2166/wst.1990.0132.

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Recognition of the advantages of anaerobic wastewater treatment induced the development of high rate processes, i.e. reactors designed to allow an efficient treatment of even diluted streams. The performance of these advanced reactors is mainly dependent on the retention within the reactor of high bacterial concentrations. The prevailing mechanism is either the formation of bacterial aggregates with good settling characteristics, the development of methanogenic biolayers at the surface of inert carriers or both. During the past decade information on the biology of methanogenic ecosystems became available at an increasing rate. From a practical point of view it can be stated that the biological conversion of organic compounds to methane is reasonably well understood. However the current knowledge on the aggregation and adhesion of methanogenic consortia remains very limited. In most cases reactor start-up procedures are rather long and appear to be more empirical than rational. This paper is a brief presentation on the current knowledge of methanogenic aggregates and biofilms. The fundamental aspects of bacterial adhesion and the modelling of anaerobic biofilms growth are presented elsewhere.
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4

Sozzi, A., and F. Taghipour. "The importance of hydrodynamics in UV advanced oxidation reactors." Water Science and Technology 55, no. 12 (June 1, 2007): 53–58. http://dx.doi.org/10.2166/wst.2007.378.

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The flow field of UV reactors was characterised experimentally using particle image velocimetry (PIV) and modelled with computational fluid dynamics (CFD). The reactor flow was integrated with the radiation fluence rate and photolysis kinetics to calculate the overall conversion of photo-reactant components in annular UV reactors with an inlet parallel and perpendicular to the reactor axis. The results indicated that the fluid flow distribution within the reactor volume affects photo-reactor performance.
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5

Golay, Michael W., and Neil E. Todreas. "Advanced Light-Water Reactors." Scientific American 262, no. 4 (April 1990): 82–89. http://dx.doi.org/10.1038/scientificamerican0490-82.

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6

Golay, M. W. "Advanced Fission Power Reactors." Annual Review of Nuclear and Particle Science 43, no. 1 (December 1993): 297–332. http://dx.doi.org/10.1146/annurev.ns.43.120193.001501.

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7

KATO, Yasuyoshi, Masaya OHTSUKA, Koji FUJIMURA, Hideaki HEKI, Kouji HIRAIWA, Masanori ARITOMI, Yoshiaki MAKIHARA, et al. "Development of Advanced Small Reactors." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 43, no. 11 (2001): 1054–99. http://dx.doi.org/10.3327/jaesj.43.1054.

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8

Riznic, Jovica, Carsten Schroer, and Yassin Hassan. "Material challenges for advanced reactors." Nuclear Engineering and Design 280 (December 2014): 651. http://dx.doi.org/10.1016/j.nucengdes.2014.06.002.

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9

Carmack, W. J., D. L. Porter, Y. I. Chang, S. L. Hayes, M. K. Meyer, D. E. Burkes, C. B. Lee, T. Mizuno, F. Delage, and J. Somers. "Metallic fuels for advanced reactors." Journal of Nuclear Materials 392, no. 2 (July 2009): 139–50. http://dx.doi.org/10.1016/j.jnucmat.2009.03.007.

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10

Dutton, R., E. O. Moeck, N. J. Spinks, C. E. Coleman, B. A. Cheadle, A. D. Lane, A. I. Miller, R. A. Judd, and L. R. Lupton. "Advanced technologies for CANDU reactors." Nuclear Engineering and Design 144, no. 2 (October 1993): 269–81. http://dx.doi.org/10.1016/0029-5493(93)90143-w.

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11

Was, Gary S., and Todd R. Allen. "Corrosion in Advanced Nuclear Reactors." Electrochemical Society Interface 30, no. 2 (June 1, 2021): 57–62. http://dx.doi.org/10.1149/2.f10212if.

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12

Duffey, R. B., I. L. Pioro, and S. Kuran. "ICONE15-10276 ADVANCED CONCEPTS FOR PRESSURE-CHANNEL REACTORS : MODULARITY, PERFORMANCE AND SAFETY." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_135.

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13

Cheng, X., Y. H. Yang, Y. Ouyang, and H. X. Miao. "Role of Passive Safety Systems in Chinese Nuclear Power Development." Science and Technology of Nuclear Installations 2009 (2009): 1–7. http://dx.doi.org/10.1155/2009/573026.

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Passive safety systems have been widely applied to advanced water-cooled reactors, to enhance the safety of nuclear power plants. The ambitious program of the nuclear power development in China requires reactor concepts with high safety level. For the near-term and medium-term, the Chinese government decided for advanced pressurized water reactors with an extensive usage of passive safety systems. This paper describes some important criteria and the development program of the Chinese large-scale pressurized water reactors. An overview on representative research activities and results achieved so far on passive safety systems in various institutions is presented.
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14

Petti, D., D. Crawford, and N. Chauvin. "Fuels for Advanced Nuclear Energy Systems." MRS Bulletin 34, no. 1 (January 2009): 40–45. http://dx.doi.org/10.1557/mrs2009.11.

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AbstractFuels for advanced nuclear reactors differ from conventional light water reactor fuels and also vary widely because of the specific architectures and intended missions of the reactor systems proposed to deploy them. Functional requirements of all fuel designs for advanced nuclear energy systems include (1) retention of fission products and fuel nuclides, (2) dimensional stability, and (3) maintenance of a geometry that can be cooled. In all cases, anticipated fuel performance is the limiting factor in reactor system design, and cumulative effects of increased utilization and increased exposure to inservice environments degrade fuel performance. In this article, the current status of each fuel system is reviewed, and technical challenges confronting the implementation of each fuel in the context of the entire advanced reactor fuel cycle (fabrication, reactor performance, recycle) are discussed.
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15

Takeda, Toshikazu, Massimo Salvatores, Giuseppe Palmiotti, Kazumi Aoto, and Katsuhisa Yamaguchi. "Fast Reactors and Advanced Light Water Reactors for Sustainable Development." Science and Technology of Nuclear Installations 2012 (2012): 1–2. http://dx.doi.org/10.1155/2012/373891.

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16

Markov, S. I., V. S. Dub, A. G. Lebedev, E. A. Kuleshova, A. G. Balikoev, E. V. Makarycheva, D. S. Tolstykh, A. S. Frolov, and E. V. Krikun. "Advanced reactor vessel steels for reactors with supercritical coolant parameters." Russian Metallurgy (Metally) 2016, no. 9 (September 2016): 803–11. http://dx.doi.org/10.1134/s003602951609010x.

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17

Hishinuma, Akimichi. "Development of Advanced Materials for Reactors." Materia Japan 34, no. 3 (1995): 328–31. http://dx.doi.org/10.2320/materia.34.328.

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18

Robinson, Arthur L., and Gary S. Was. "Materials hurdles for advanced nuclear reactors." MRS Bulletin 40, no. 7 (July 2015): 554–55. http://dx.doi.org/10.1557/mrs.2015.146.

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19

Tang, Yu, Christopher Grandy, and Ralph Seidensticker. "Seismic Isolation for Advanced Fast Reactors." Nuclear Technology 173, no. 2 (February 2011): 135–52. http://dx.doi.org/10.13182/nt11-a11543.

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20

King, Thomas L. "NRC review of U.S. advanced reactors." Energy 16, no. 1-2 (January 1991): 353–58. http://dx.doi.org/10.1016/0360-5442(91)90114-2.

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21

Delene, J. G. "Updated Comparison of Economics of Fusion Reactors With Advanced Fission Reactors." Fusion Technology 19, no. 3P2A (May 1991): 807–12. http://dx.doi.org/10.13182/fst91-a29443.

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22

Erickson, Anna, and Christopher Stewart. "Monitoring of nuclear reactors with antineutrinos: comparison of advanced reactor systems." Journal of Physics: Conference Series 1216 (April 2019): 012018. http://dx.doi.org/10.1088/1742-6596/1216/1/012018.

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23

Xiong, Wen Bin, Hou Ming Zhang, Bo Ping Zhang, Hu Wei Li, Gang Wang, and Jie Zhu. "Features and Application Analysis of Advanced Small Nuclear Power Reactors." Advanced Materials Research 986-987 (July 2014): 315–21. http://dx.doi.org/10.4028/www.scientific.net/amr.986-987.315.

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In recent years, advanced small nuclear power reactors, namely small modular reactors (SMRs), gained widespread attention. In areas where energy can’t be provided by large scale reactors and the nuclear power plants with large scale reactors can’t compete with the non-nuclear power plant technology, SMRs, as a versatile distributed integrated energy source, which result in expanding peaceful applications of nuclear energy, have enormous potential. This article describes the characteristics and analyzes prospects and challenges of SMRs.
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24

Lacamp, Bruno, Flemming Hansen, Philippe Penillard, and Frank Rogalla. "Wastewater Nutrient Removal with Advanced Biofilm Reactors." Water Science and Technology 27, no. 5-6 (March 1, 1993): 263–76. http://dx.doi.org/10.2166/wst.1993.0506.

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25

Ryhiner, G., K. Sørensen, B. Birou, and H. Gros. "Biofilm reactors configuration for advanced nutrient removal." Water Science and Technology 29, no. 10-11 (October 1, 1994): 111–17. http://dx.doi.org/10.2166/wst.1994.0752.

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Characterization of a new biofilm reactors configuration was carried out on a pilot plant performing nitrification, pre- and post-denitrification. Thereby, degradation rate limitations - whether there are related to mass transfer resistances, kinetic or stoichiometry - were determined for the different stages. The experimental results showed that under certain conditions moderate aeration of the predenitrification stage enhances both denitrification and organic carbon removal due to an acceleration of diffusion rates. Post-denitrification was limited by the addition of C-source exclusively, whereas nitrification was inhibited by elevated organic loadings as well as low temperatures. The described system offers a certain flexibility concerning BOD removal in the predenitrification stage because of the potentiality of aeration, as well as the possibility of recirculating nitrate very economically enabled by the small head losses in the systems. Furthermore, combination of pre- and post-denitrification with biofilm systems leads to economic and safe processes for advanced elimination of nutrients such as nitrogen and phosphorus.
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26

Nayak, A. K., and R. K. Sinha. "Role of passive systems in advanced reactors." Progress in Nuclear Energy 49, no. 6 (August 2007): 486–98. http://dx.doi.org/10.1016/j.pnucene.2007.07.007.

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27

Oka, Y., and S. Koshizuka. "Conceptual design study of advanced power reactors." Progress in Nuclear Energy 32, no. 1-2 (January 1998): 163–77. http://dx.doi.org/10.1016/s0149-1970(97)00014-0.

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28

Wood, Richard T., Belle R. Upadhyaya, and Dan C. Floyd. "An autonomous control framework for advanced reactors." Nuclear Engineering and Technology 49, no. 5 (August 2017): 896–904. http://dx.doi.org/10.1016/j.net.2017.07.001.

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29

Bochkarev, A. S., A. S. Korsun, V. S. Kharitonov, and P. N. Alekseev. "Inherent Safety Characteristics of Advanced Fast Reactors." Journal of Physics: Conference Series 781 (January 2017): 012001. http://dx.doi.org/10.1088/1742-6596/781/1/012001.

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30

M'Saad, M., J. Chebassier, and E. Miklovičová. "On the Advanced Control of Batch Reactors." IFAC Proceedings Volumes 30, no. 6 (May 1997): 1581–86. http://dx.doi.org/10.1016/s1474-6670(17)43586-5.

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31

Fullwood, R., R. Lofaro, and P. Samanta. "Reliability assurance for regulation of advanced reactors." IEEE Transactions on Nuclear Science 39, no. 5 (1992): 1357–62. http://dx.doi.org/10.1109/23.173205.

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32

Suk, Pavel. "ADVANCED HOMOGENIZATION METHODS FOR PRESSURIZED WATER REACTORS." Acta Polytechnica CTU Proceedings 19 (December 14, 2018): 14. http://dx.doi.org/10.14311/app.2018.19.0014.

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Macroscopic cross section generation is key part of core calculation. Commonly, the data are prepared independently without a knowledge of fuel loading pattern. The fuel assemblies are simulated in infinite lattice (with mirror boundary conditions). Rehomogenization method is based on combination of actual neutron flux in fuel assembly with macroscopic data from infinite lattice. Rehomogenization method was implemented into the macrocode Andrea and tested on a reference cases. Cases consist of fuel cases, cases with strong absorber, cases with absorption rods, or cases with reflector assemblies. Testing method is based on a comparisons of homogenized and rehomogenized macroscopic cross sections and later on a comparisons of relative power of each fuel assembly. Above that there is comparison of eigenvalue.
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33

Kupitz, J. "Role of advanced reactors for sustainable development." Progress in Nuclear Energy 29 (January 1995): 11–18. http://dx.doi.org/10.1016/0149-1970(95)00021-b.

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34

Dean, Richard A. "Advanced fission reactors for central station power." Journal of Fusion Energy 10, no. 3 (September 1991): 215–20. http://dx.doi.org/10.1007/bf01885457.

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35

Klueh, R. L. "Ferritic/martensitic steels for advanced nuclear reactors." Transactions of the Indian Institute of Metals 62, no. 2 (April 2009): 81–87. http://dx.doi.org/10.1007/s12666-009-0011-3.

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36

Birkhofer, A. "Advanced power reactors with improved safety characteristics." Applied Radiation and Isotopes 46, no. 6-7 (June 1995): 701–6. http://dx.doi.org/10.1016/0969-8043(95)00135-2.

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37

Böning, Klaus, and Peter Von Der Hardt. "Physics and safety of advanced research reactors." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 260, no. 1 (October 1987): 239–46. http://dx.doi.org/10.1016/0168-9002(87)90408-6.

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38

Chiang, Ren-Tai. "Safety Features of Advanced and Economic Simplified Boiling Water Reactors." Indonesian Journal of Physics and Nuclear Applications 3, no. 1 (May 6, 2018): 1–6. http://dx.doi.org/10.24246/ijpna.v3i1.1-6.

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The Advanced Boiling Water Reactor (ABWR) and the Economic Simplified Boiling Water Reactor (ESBWR) are two kinds of contemporary, advanced, commercially available nuclear power reactors. Reactor internal pumps in an ABWR improve performance while eliminating the large recirculation pumps in earlier BWRs. The utilization of natural circulation and passive safety systems in the ESBWR design simplifies nuclear reactor system designs, reduces cost, and provides a reliable stability solution for inherently safe operation. The conceptually reliable stability solution for inherently safe ESBWR operation is developed by establishing a sufficiently high natural circulation flow line, which has a core flow margin at least 5% higher than the stability boundary flow at 100% rated power of a conventional BWR, and then by designing a high flow natural circulation system to achieve this high natural circulation flow line. The performance analyses for the ESBWR Emergency Core Cooling System (ECCS) show that: (1) the core remains covered with a large margin and there is no core heat up in the ESBWR for any break size, (2) the long-term containment pressure increases gradually with time, in the order of hours, and the peak pressure is below the design value with a large margin, and (3) the margins depend on the containment volumes and water inventories. These safety design features ensure inherently safe ESBWR operation. Enhanced safety features based on lessons learned from the Fukushima nuclear accident are added in ABWR’s and ESBWR’s safety designs. The major enhancements are the further prevention of station blackout and loss of ultimate heat sink.
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39

Okafor, Obinna, Andreas Weilhard, Jesum A. Fernandes, Erno Karjalainen, Ruth Goodridge, and Victor Sans. "Advanced reactor engineering with 3D printing for the continuous-flow synthesis of silver nanoparticles." Reaction Chemistry & Engineering 2, no. 2 (2017): 129–36. http://dx.doi.org/10.1039/c6re00210b.

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3D printing has been employed to manufacture advanced reactor geometries based on miniaturised continuous-flow oscillatory baffled reactors (mCOBRs) and they have been applied for the fouling free continuous-flow synthesis of silver nanoparticles with optimal size control.
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40

Durán Moreno, A., B. A. Frontana-Uribe, and R. M. Ramírez Zamora. "Electro-Fenton as a feasible advanced treatment process to produce reclaimed water." Water Science and Technology 50, no. 2 (July 1, 2004): 83–90. http://dx.doi.org/10.2166/wst.2004.0095.

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The feasibility of the electro-Fenton process to generate simultaneously both of the Fenton's reagent species (Fe2+/H2O2), was assessed as a potentially more economical alternative to the classical Fenton's reaction to produce reclaimed water. An air-saturated combined wastewater (mixture of municipal and laboratory effluents) was treated in discontinuous and continuous reactors at pH = 3.5. The discontinuous reactor was a 2 L electrochemical laboratory cell fitted with concentric graphite and iron electrodes. The continuous reactor tests used a pilot treatment system comprising the aforementioned electrochemical cell, two clarifiers and one sand filter. Several tests were carried out at different conditions of reaction time (0-60 min) and electrical current values (0.2-1.0 A) in the discontinuous reactor. The best operating conditions were 60 min and 1 A without filtration of effluents. At these conditions, in discontinuous and continuous reactors with filtration, the COD, turbidity and color removal were 65-74.8%, 77-92.3% and 80-100%, respectively. Fecal and total coliforms, Escherichia coli, Shigella and Salmonella sp. were not detected at the end of the pilot treatment system. Electrogeneration of the Fenton's reagent is also economical; its cost is one-fifth the cost reported for Advanced Primary Treatment.
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41

Tahir, N. A., and D. H. H. Hoffmann. "Development of advanced fuel inertial fusion targets." Laser and Particle Beams 15, no. 4 (December 1997): 575–87. http://dx.doi.org/10.1017/s0263034600011150.

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This paper discusses the implications of using different fuels, including pure deuterium, deuterium–tritium, deuterium–helium3, and proton–boron11, on safety and environmental compatibility of the fusion reactor, as well as on the driver requirements. Due to present-day technology limitations, it seems likely that the first generation of the fusion reactors will be based on a deuterium–tritium cycle. Such a scheme, however, would pose serious problems, including neutron activation and tritium handling. We show that by developing low-level tritium inertial fusion targets, one may substantially reduce the daily use of tritium in the reactor that may ultimately lead to a reduction in the overall tritium inventory in the power plant. Such reduced tritium targets will still generate sufficient energy to run the power plant economically.
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42

Röske, I., K. Röske, and D. Uhlmann. "Gradients in the taxonomic composition of different microbial systems: comparison between biofilms for advanced waste treatment and lake sediments." Water Science and Technology 37, no. 4-5 (February 1, 1998): 159–66. http://dx.doi.org/10.2166/wst.1998.0608.

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The application of in situ hybridization with group specific oligonucleotide probes detected by epifluorescence microscopy and confocal laser scanning microscopy was tested to identify spatial gradients in the distribution of bacteria in biofilms of plug flow reactors and in the bottom sediment layer of a drinking water reservoir. The two tubular biofilm reactors were fed with the effluent from a full scale biological wastewater treatment plant to which were added the chlorophenols whole degradation was being investigated. One was operated as a continuous-flow reactor and the other as a sequencing batch reactor. The vertical gradients in the microbial colonization of the sediment were analyzed by means of glass slides exposed to the sediment. In the biofilms of both reactors the beta-Proteobacteria dominated. The Cytophaga-Flavobacterium group and the Gram-positive bacteria were also abundant. Only small amounts of gamma-bacteria could be detected. This is contrary to findings using traditional cultivation methods. Unlike the biofilms in the reactor, the bacterial Aufwuchs on the glass slides in the sediment presented a surprising diversity of morphological types and size classes of bacteria.
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43

Kaballo, Hans-Peter, Yuangang Zhao, and Peter A. Wilderer. "Elimination of p-chlorophenol in biofilm reactors - a comparative study of continuous flow and sequenced batch operation." Water Science and Technology 31, no. 1 (January 1, 1995): 51–60. http://dx.doi.org/10.2166/wst.1995.0013.

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The chlorophenol elimination potential of two identically designed fixed bed biofilm reactors was compared. One of the reactors was operated continuously, and the other in sequenced batch mode. In the continuous flow biofilm reactor (CFBR) a stratification of biomass occurred, whereas biomass in the sequencing batch biofilm reactor (SBBR) developed uniformly due to the use of an advanced fill strategy. Recirculation was needed to overcome biosorption during filling and to achieve equal biomass distribution. Under shock loading, degradation in SBBR was better than in CFBR. However, even the CFBR showed a high flexibility, i.e. it performed better than expected. Sorption properties in both reactors seem to be responsible for the flexibility in terms of break through. Experimental studies and modelling of sorption properties are necessary to describe the response of biofilm reactors to unsteady state conditions.
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44

Mularski, Jakub, and Norbert Modliński. "Impact of Chemistry–Turbulence Interaction Modeling Approach on the CFD Simulations of Entrained Flow Coal Gasification." Energies 13, no. 23 (December 7, 2020): 6467. http://dx.doi.org/10.3390/en13236467.

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This paper examines the impact of different chemistry–turbulence interaction approaches on the accuracy of simulations of coal gasification in entrained flow reactors. Infinitely fast chemistry is compared with the eddy dissipation concept considering the influence of turbulence on chemical reactions. Additionally, ideal plug flow reactor study and perfectly stirred reactor study are carried out to estimate the accuracy of chosen simplified chemical kinetic schemes in comparison with two detailed mechanisms. The most accurate global approach and the detailed one are further implemented in the computational fluid dynamics (CFD) code. Special attention is paid to the water–gas shift reaction, which is found to have the key impact on the final gas composition. Three different reactors are examined: a pilot-scale Mitsubishi Heavy Industries reactor, a laboratory-scale reactor at Brigham Young University and a Conoco-Philips E-gas reactor. The aim of this research was to assess the impact of gas phase reaction model accuracy on simulations of the entrained flow gasification process. The investigation covers the following issues: impact of the choice of gas phase kinetic reactions mechanism as well as influence of the turbulence–chemistry interaction model. The advanced turbulence–chemistry models with the complex kinetic mechanisms showed the best agreement with the experimental data.
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45

Marcus, Gail H. "Heeding the Lessons of History." Mechanical Engineering 134, no. 07 (July 1, 2012): 28–33. http://dx.doi.org/10.1115/1.2012-jul-1.

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This article focuses on learning from the successes and failures of the first-generation reactor development. Reactor designs have evolved over time to meet increasingly rigorous demands for safety and to take advantage of technological developments to improve their economics, but these changes have been piecemeal. Although light-water reactors are the most common reactor technology in use today, heavy-water reactors were actually developed earlier. The earliest demonstration of a heavy-water moderated and cooled reactor took place in May 1944 at Argonne. The reasons for the domination of water-cooled reactors, and particularly of light-water reactors, are complex. The article suggests that it is interesting to speculate on how the new initiative to develop more advanced designs may play out. There are already strong pressures to focus on the integral light-water design; based on well-understood light-water technology, the argument goes, such designs will be much easier to develop and license. In the longer term, however, some of the non-light water reactors could ultimately achieve greater levels of passive safety, efficient fuel utilization, economic performance, and proliferation resistance.
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46

Cappelli, M., B. Castillo-Toledo, L. G. D'Abbieri, and S. Di Gennaro. "ICONE23-1634 DESIGN OF ADVANCED CONTROLLERS FOR NUCLEAR REACTORS USING AN EVENT-TRIGGERED CONTROL TECHNIQUE." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–1—_ICONE23–1. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-1_308.

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47

Muddemann, Thorben, Rieke Neuber, Dennis Haupt, Tobias Graßl, Mohammad Issa, Fabian Bienen, Marius Enstrup, et al. "Improving the Treatment Efficiency and Lowering the Operating Costs of Electrochemical Advanced Oxidation Processes." Processes 9, no. 9 (August 24, 2021): 1482. http://dx.doi.org/10.3390/pr9091482.

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Electrochemical advanced oxidation processes (EAOP®) are promising technologies for the decentralized treatment of water and will be important elements in achieving a circular economy. To overcome the drawback of the high operational expenses of EAOP® systems, two novel reactors based on a next-generation boron-doped diamond (BDD) anode and a stainless steel cathode or a hydrogen-peroxide-generating gas diffusion electrode (GDE) are presented. This reactor design ensures the long-term stability of BDD anodes. The application potential of the novel reactors is evaluated with artificial wastewater containing phenol (COD of 2000 mg L−1); the reactors are compared to each other and to ozone and peroxone systems. The investigations show that the BDD anode can be optimized for a service life of up to 18 years, reducing the costs for EAOP® significantly. The process comparison shows a degradation efficiency for the BDD–GDE system of up to 135% in comparison to the BDD–stainless steel electrode combination, showing only 75%, 14%, and 8% of the energy consumption of the BDD–stainless steel, ozonation, and peroxonation systems, respectively. Treatment efficiencies of nearly 100% are achieved with both novel electrolysis reactors. Due to the current density adaptation and the GDE integration, which result in energy savings as well as the improvements that significantly extend the lifetime of the BDD electrode, less resources and raw materials are consumed for the power generation and electrode manufacturing processes.
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48

Hofman-Caris, C. H. M., D. J. H. Harmsen, B. A. Wols, L. J. J. M. Janssen, E. F. Beerendonk, A. H. Knol, and J. A. M. H. Hofman. "Prediction of advanced oxidation performance in UV/H2O2 reactor systems with LP-UV lamps." Water Supply 11, no. 4 (September 1, 2011): 460–67. http://dx.doi.org/10.2166/ws.2011.070.

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Advanced oxidation processes, like UV/H2O2 oxidation, are important barriers against organic micro pollutants in drinking water treatment. In order to guarantee safe drinking water, it is important to be able to predict the reactors' performance to adjust the operating conditions to the actual influent water characteristics (like UV transmission) and lamp performance. Therefore, a design tool was developed, which is based on a kinetic model that describes and predicts the direct photolysis and oxidation of organic compounds in pilot experiments, using Low Pressure (LP) UV-lamps. This model has been combined with computational fluid dynamics (CFD), in order to be able to accurately predict the results of pilot and full scale installations, and also to design reactor systems. The model was applied to three model compounds (atrazine, ibuprofen and NDMA) in two different pilot reactors, and it has been shown that reactor performance can be fairly predicted by applying this ‘UVPerox’ model. The model takes into account the water quality and power of the lamps, and the properties of the compounds involved.
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49

Shaat, Mohamed. "Safety and Economics of Advanced Light Water Reactors." International Conference on Chemical and Environmental Engineering 7, no. 7 (May 1, 2014): 1. http://dx.doi.org/10.21608/iccee.2014.35463.

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50

Popa-Simil, L. "Advanced Space Nuclear Reactors from Fiction to Reality." Physics Procedia 20 (2011): 270–92. http://dx.doi.org/10.1016/j.phpro.2011.08.025.

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