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Journal articles on the topic 'Light water reactors Thermal properties'

Author: Grafiati

Published: 4 June 2021

Last updated: 17 February 2022

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1

Song, Carol. "IRRADIATION EFFECTS ON ZR-2.5NB IN POWER REACTORS." CNL Nuclear Review 5, no. 1 (2016): 17–36. http://dx.doi.org/10.12943/cnr.2016.00010.

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Zirconium alloys are widely used as structural materials in nuclear applications because of their attractive properties such as a low absorption cross-section for thermal neutrons, excellent corrosion resistance in water, and good mechanical properties at reactor operating temperatures. Zr-2.5Nb is one of the most commonly used zirconium alloys and has been used for pressure tube materials in CANDU (Canada Deuterium Uranium) and RBMK (Reaktor Bolshoy Moshchnosti Kanalnyy, “High Power Channel-type Reactor”) reactors for over 40 years. In a recent report from the Electric Power Research Institut

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2

Latta, Ryan, Shripad T. Revankar, and Alvin A. Solomon. "Modeling and Measurement of Thermal Properties of Ceramic Composite Fuel for Light Water Reactors." Heat Transfer Engineering 29, no. 4 (2008): 357–65. http://dx.doi.org/10.1080/01457630701825390.

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3

Degueldre, Claude. "Zirconia Inert Matrix for Plutonium Utilisation and Minor Actinides Disposition in Thermal Reactors." Advances in Science and Technology 45 (October 2006): 1907–14. http://dx.doi.org/10.4028/www.scientific.net/ast.45.1907.

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The toxicity of the UO2 spent fuel is dominated by plutonium and minor actinides (MA): Np, Am and Cm, after decay of the short live fission products. Zirconia ceramics containing Pu and MA in the form of an Inert Matrix Fuel (IMF) could be used to burn these actinides in Light Water Reactors. Optimisation of the fuel designs dictated by properties such as thermal, mechanical, chemical and physical must be performed with attention for their behaviour under irradiation. Zirconia must be stabilised by yttria to form a solid solution such as AnzYyPuxZr1-yO2-y where minor actinide oxides are also s

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4

Nakata, Alexandre Ezzidi, Masanori Naitoh, and Chris Allison. "NEED OF A NEXT GENERATION SEVERE ACCIDENT CODE." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 21, no. 3 (2019): 119. http://dx.doi.org/10.17146/tdm.2019.21.3.5630.

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Two international severe accident benchmark problems have been performed recently by using several existing parametric severe accident codes: The Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF) and the Benchmark of the In-Vessel Melt Retention (IVMR) Analysis of a VVER-1000 Nuclear Power Plant (NPP). The BSAF project was organized by the Nuclear Power Engineering Center (NUPEC) of the Institute of Applied Energy (IAE) in Japan for the three Boiling Water Reactors (BWRs) of the Fukushima NPP. The IVMR Project was organized by the Joint Research Center (JRC) o

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5

Kulikov, G. G., A. N. Shmelev, and V. A. Apse. "Improving Nuclear Safety of Fast Reactors by Slowing Down Fission Chain Reaction." International Journal of Nuclear Energy 2014 (October 16, 2014): 1–18. http://dx.doi.org/10.1155/2014/373726.

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Light materials with small atomic mass (light or heavy water, graphite, and so on) are usually used as a neutron reflector and moderator. The present paper proposes using a new, heavy element as neutron moderator and reflector, namely, “radiogenic lead” with dominant content of isotope 208Pb. Radiogenic lead is a stable natural lead. This isotope is characterized by extremely low micro cross-section of radiative neutron capture (~0.23 mb) for thermal neutrons, which is smaller than graphite and deuterium cross-sections. The reflector-converter for a fast reactor core is the structure capable o

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6

Aly, Ahmed, Agustin Abarca, Maria Avramova, and Kostadin Ivanov. "EXTENDING CTF MODELING CAPABILITIES TO SFRs AND VALIDATION AGAINST SHRT TESTS." EPJ Web of Conferences 247 (2021): 10034. http://dx.doi.org/10.1051/epjconf/202124710034.

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The utilization of liquid metals as coolants for fast reactors brings several economical and practical advantages that lead to a sustainable future for nuclear energy. Molten sodium is used as a coolant in Sodium Fast Reactors (SFRs). Sodium is relatively cheaper than other metal coolants. It requires lower pumping power, causes less neutron moderation and it is non-corrosive to the fuel cladding. The SFR hexagonal subassemblies are relatively smaller than Light Water Reactors (LWRs) subassemblies. The differences in the geometrical design of SFRs compared to LWRs lead to different physical be

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7

Ghasabian, M., F. Mofidnakhaei, and S. Talebi. "Effect of gap design pressure on the LWR fuel rods lifetime." Kerntechnik 86, no. 3 (2021): 202–9. http://dx.doi.org/10.1515/kern-2021-0004.

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Abstract The fuel burn-up rate has been raised in recent years to improve the efficiency of nuclear LWRs (light water reactors). Therefore, surveying and estimating changes in fuel properties and structural materials during radiation exposure is of paramount importance. In the present study, the researchers focused on analyzing the role of LWR fuel rod initial gap pressure (initial gas pressure when a fuel rod is fabricated) on the rod’s thermal and mechanical performance. FRAPCON-4.0 steady-state fuel performance code was used to simulate the effect of initial gap pressure on the behavior of

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8

Vänskä, Emilia, and Tapani Vuorinen. "Effect of cellulase-assisted refining on the thermal degradation of bleached high-density paper." Holzforschung 69, no. 6 (2015): 703–12. http://dx.doi.org/10.1515/hf-2014-0194.

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Abstract Pulp was treated with cellulase, and the chemical, physical, and optical properties of the refined pulps in paper sheets were measured in terms of the degree of polymerization of cellulose, tensile strength, elongation, burst strength, light scattering, and brightness. The sheets were thermally treated for 20 and 60 min at 225°C in the presence of 1% and 75% (v/v) water vapor. The cellulase treatment intensified the fibrillation of fibers and reduced the specific energy consumption during refining. It was demonstrated based on the water retention value that the refining modified the w

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9

Li, Xiuping, Yuchun Zhai, Peihua Ma, and Rongxiang Zhao. "Preparation and Photocatalysis of Nano-Zn/Ce Composite Oxides." Australian Journal of Chemistry 67, no. 4 (2014): 657. http://dx.doi.org/10.1071/ch13448.

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Metal oxide photocatalysts often lead to partial or complete mineralization of organic pollutants. On irradiation with UV-visible light, metal oxides catalyze redox reactions in the presence of air and O2 and water. Using ascorbic acid as a new combustion agent, ZnO was rapidly synthesized. Nano-Zn/CeO2 composites were prepared by a heterogeneous-precipitation method using (NH4)2CO3 as precipitation agent. X-ray diffraction, field-emission scanning electron microscopy, transmission electron microscopy, Fourier-transform infrared spectrometry, ultraviolet spectrophotometry, and differential the

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10

Yu, Tao, Hong Mei Wang, and Xin Tan. "New Reactor Fabricated Using Light Leakage Fiber for Azo Dye Degradation." Advanced Materials Research 716 (July 2013): 235–39. http://dx.doi.org/10.4028/www.scientific.net/amr.716.235.

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Lanthanum-doped anatase TiO2coatings, which are composed of assemble crystalline of 50 nm diameter particles, when the percentage of dopant is 0.5 wt%, have been successfully fabricated by solgel dip-coating process on light leakage silica fiber (LSF) which length is 15cm and diameter is 125μm. This was achieved by adjustment of the lanthanum-doped solgel parameters such as molar ratio of precursors in lanthanum-doped TiO2-sols, the ratio of titanium tetrabutoxide to polyvinyl alcohol, dip-coating velocity, drying duration in air, thermal treatment and number of cyclical time of the process. T

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11

Shaginyan, Ruben, Valery Kolesov, and Evgeny Ivanov. "A MESOSCOPIC OXIDE FUEL CLUSTERING AND ITS GLOBAL PERFORMANCE." EPJ Web of Conferences 247 (2021): 15012. http://dx.doi.org/10.1051/epjconf/202124715012.

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Transient fuel behavior in a Light Water-cooled Reactor core depends on nuclear properties (Doppler broadening, moderation ratio, and, sometimes, neutron gas temperature etc.) and on variations of thermal-physics parameters (temperature distributions, fuel elongation and moderator density). Usually, in a rough reactor analysis one ignores the very details of temperature distributions largely staying in a frame of so-called adiabatic assumptions (when temperature and density distribution are changing in sync keeping given spatial shapes). In majority of practical applications the radially distr

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12

Yu, Tao, Xin Tan, Peng Chen, and Hong Mei Wang. "Lanthanum-Doped Titania Film Coated on Light Leakage Fiber Photo-Degradation Methyl Orange." Advanced Materials Research 512-515 (May 2012): 1651–55. http://dx.doi.org/10.4028/www.scientific.net/amr.512-515.1651.

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Lanthanum-doped anatase TiO2coatings, which are composed of assemble crystalline of 50 nm diameter particles, when the percentage of dopant is 0.5 wt%, have been successfully fabricated by sol–gel dip-coating process on light leakage silica fiber (LSF) which length is 15cm and diameter is 125μm. This was achieved by adjustment of the lanthanum-doped sol–gel parameters such as molar ratio of precursors in lanthanum-doped TiO2-sols, the ratio of titanium tetrabutoxide to polyvinyl alcohol, dip-coating velocity, drying duration in air, thermal treatment and number of cyclical time of the process.

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13

Clara, Cedric, Marc Durandeau, Gerard Quenault, and Tuyet-Hang Nguyen. "Laboratory Studies for Light-Oil Air Injection Projects: Potential Application in Handil Field." SPE Reservoir Evaluation & Engineering 3, no. 03 (2000): 239–48. http://dx.doi.org/10.2118/64272-pa.

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Summary Air injection into light-oil reservoirs is now a proven field technique. Because of the unlimited availability and the nil access cost of the injectant, the application potential of this improved recovery process is promising when associated with the lack of available hydrocarbon gas sources for injection. One of the keys of a successful air injection project is the evaluation of the process by carrying out representative laboratory studies. Therefore, an original laboratory strategy was proposed to assess the recovery potential by air injection into light-oil reservoirs, and to help t

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14

Alshoaibi, Adil. "Effective optical nanoparticles and nanocomposites based on a carbon nanotubes-organic—inorganic nanohybrid for industrial pollutant removal." Materials Express 10, no. 6 (2020): 856–65. http://dx.doi.org/10.1166/mex.2020.1733.

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Improving the optical properties of zinc oxide to meet the practical requirements of photocatalytic reactions and solar cells is an ongoing challenge. To address this challenge, different nanostructures of ZnO were prepared from an organic—inorganic-CNTs nanohybrid. The nanohybrid was formed through intercalation of the long chain fatty acid C17H35COOH and carbon nanotubes into Zn–Al nanolayered structures. X-ray diffraction revealed an increase in the interlayer spacing of the Zn–Al layered double hydroxides from 0.75 nm to 2.1 nm after admixing with the CNTs and organic fatty acid. Thermal a

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15

Domine, F., M. Albert, T. Huthwelker, et al. "Snow physics as relevant to snow photochemistry." Atmospheric Chemistry and Physics 8, no. 2 (2008): 171–208. http://dx.doi.org/10.5194/acp-8-171-2008.

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Abstract. Snow on the ground is a complex multiphase photochemical reactor that dramatically modifies the chemical composition of the overlying atmosphere. A quantitative description of the emissions of reactive gases by snow requires knowledge of snow physical properties. This overview details our current understanding of how those physical properties relevant to snow photochemistry vary during snow metamorphism. Properties discussed are density, specific surface area, thermal conductivity, permeability, gas diffusivity and optical properties. Inasmuch as possible, equations to parameterize t

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16

Domine, F., M. Albert, T. Huthwelker, et al. "Snow physics as relevant to snow photochemistry." Atmospheric Chemistry and Physics Discussions 7, no. 3 (2007): 5941–6036. http://dx.doi.org/10.5194/acpd-7-5941-2007.

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Abstract. Snow on the ground is a complex multiphase photochemical reactor that dramatically modifies the chemical composition of the overlying atmosphere. A quantitative description of the emissions of reactive gases by snow requires the knowledge of snow physical properties. This overview details our current understanding of how those physical properties relevant to snow photochemistry vary during snow metamorphism. Properties discussed are density, specific surface area, optical properties, thermal conductivity, permeability and gas diffusivity. Inasmuch as possible, equations to parameteri

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17

Bhowmik, Pradip K., Tae S. Jo, Jung J. Koh, et al. "Poly(Pyridinium Salt)s Containing 2,7-Diamino-9,9′-Dioctylfluorene Moieties with Various Organic Counterions Exhibiting Both Lyotropic Liquid-Crystalline and Light-Emitting Properties." Molecules 26, no. 6 (2021): 1560. http://dx.doi.org/10.3390/molecules26061560.

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A series of poly(pyridinium salt)s-fluorene main-chain ionic polymers with various organic counterions were synthesized by using ring-transmutation polymerization and metathesis reactions. Their chemical structures were characterized by Fourier Transform Infrared (FTIR), proton (1H), and fluorine 19 (19F) nuclear magnetic resonance (NMR) spectrometers. These polymers showed a number-average molecular weight (Mns) between 96.5 and 107.8 kg/mol and polydispersity index (PDI) in the range of 1.12–1.88. They exhibited fully-grown lyotropic phases in polar protic and aprotic solvents at different c

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18

Nakatsuka, Toru, Yoshiaki Oka, and Seiichi Koshizuka. "Startup Thermal Considerations for Supercritical-Pressure Light Water-Cooled Reactors." Nuclear Technology 134, no. 3 (2001): 221–30. http://dx.doi.org/10.13182/nt01-a3197.

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19

M, El-sheikh. "Steady State Thermal Hydraulic Model for PWR Light Water Reactors." Journal of Nuclear Technology in Applied Science 6, no. 2 (2018): 107–14. http://dx.doi.org/10.21608/jntas.2018.10201.

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20

Bethmont, M., Y. Meyzaud, and P. Soulat. "Properties of cast austenitic materials for light water reactors." International Journal of Pressure Vessels and Piping 65, no. 3 (1996): 221–29. http://dx.doi.org/10.1016/0308-0161(94)00133-4.

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21

Han, Gee Y., and Thomas P. Stanley. "Thermal-hydraulic transient analysis of light water reactors using moving boundaries." Annals of Nuclear Energy 26, no. 4 (1999): 301–26. http://dx.doi.org/10.1016/s0306-4549(98)00049-8.

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22

Eliseev, Vladimir A., Dmitry A. Klinov, Noël Camarcat, et al. "On the possibility to improve mixed uranium-plutonium fuel in fast reactors." Nuclear Energy and Technology 6, no. 2 (2020): 131–35. http://dx.doi.org/10.3897/nucet.6.51587.

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Accumulation of plutonium extracted from the spent nuclear fuel (SNF) of light water reactors is one of the central problems in nuclear power. To reduce out-of-the-reactor Pu inventory, leading nuclear power countries (France, Japan) use plutonium in light water power reactors in the form of MOX fuel, with half of Pu fissioning in this fuel. The rest of Pu cannot be reused easily and efficiently in light water reactors because of the high content of even isotopes. Plutonium for which there are no potential consumers is accumulated. Unlike thermal reactors, fast reactors take plutonium of any i

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23

Kataoka, Isao. "Review of thermal-hydraulic researches in severe accidents in light water reactors." Journal of Nuclear Science and Technology 50, no. 1 (2013): 1–14. http://dx.doi.org/10.1080/00223131.2013.750797.

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24

Schreiber, Ulrich, and Christian Neubauer. "The Polyphasic Rise of Chlorophyll Fluorescence upon Onset of Strong Continuous Illumination: II. Partial Control by the Photosystem II Donor Side and Possible Ways of Interpretation." Zeitschrift für Naturforschung C 42, no. 11-12 (1987): 1255–64. http://dx.doi.org/10.1515/znc-1987-11-1218.

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The fluorescence rise kinetics in saturating light display two well separated components with largely different properties. The rapid rise from F0 to a first intermediate level, I1 is photochemically controlled, while the following phases leading to a secondary intermediate level, I2 and to a peak level, P, are limited by thermal reactions. Treatments which primarily affect components at the photosystem II donor side are shown to increase quenching at I1 and/or to suppress the secondary fluorescence rise to I2. Preillumination by single turnover saturating flashes causes I1- quenching oscillat

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25

Rubiyanti, Tri, Wahyu Hidayat, Indra Gumay Febryano, and Samsul Bakri. "Characterization of Rubberwood (Hevea brasiliensis) Pellets Torrefied with Counter-Flow Multi Baffle (COMB) Reactor." Jurnal Sylva Lestari 7, no. 3 (2019): 321. http://dx.doi.org/10.23960/jsl37321-331.

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Indonesia has the largest rubberwood (Hevea brasiliensis) plantation area in the world. Rubberwood is mainly planted for latex production and as latex production declines with age, rubberwood is generally felled. The logging waste and industrial waste of rubberwood-based products could be utilized as raw materials to produce biomass pellets. The quality of biomass pellets can be increased through torrefaction, a thermal process in the temperature range of 200-300°C under an inert atmosphere. This study aimed to evaluate the effect of torrefaction on the characteristics of rubberwood pellets. T

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26

Degueldre, Claude, and Jean-Marie Paratte. "Basic Properties of a Zirconia-Based Fuel Material for Light Water Reactors." Nuclear Technology 123, no. 1 (1998): 21–29. http://dx.doi.org/10.13182/nt98-a2876.

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27

Zhou, Wenzhong, Rong Liu, and Shripad T. Revankar. "Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors." Annals of Nuclear Energy 81 (July 2015): 240–48. http://dx.doi.org/10.1016/j.anucene.2015.02.044.

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28

Forsberg, C. W., D. Curtis, and D. Stack. "Light Water Reactors with Crushed Rock Thermal Storage for Industrial Heat and High-Value Electricity." Nuclear Technology 198, no. 1 (2017): 70–78. http://dx.doi.org/10.1080/00295450.2017.1294426.

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29

Xin, Ling, Jiwei Hu, Yiqiu Xiang, et al. "Carbon-Based Nanocomposites as Fenton-Like Catalysts in Wastewater Treatment Applications: A Review." Materials 14, no. 10 (2021): 2643. http://dx.doi.org/10.3390/ma14102643.

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Advanced oxidation (e.g., fenton-like reagent oxidation and ozone oxidation) is a highly important technology that uses strong oxidizing free radicals to degrade organic pollutants and mineralize them. The fenton-like reactions have the characteristics of low cost, simple operation, thorough reaction and no secondary pollution. Fenton-like reagents refer to a strong oxidation system composed of transition metal ions (e.g., Fe3+, Mn2+ and Ag+) and oxidants (hydrogen peroxide, potassium persulfate, sodium persulfate, etc). Graphene and carbon nanotube possess a distinctive mechanical strength, f

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30

Aggarwal, Hamender Kumar, Rahul Chhibber, Navneet Arora, and Rajeev Mehta. "Experimental Analysis of Thermal Fatigue in Bimetallic Welds." Materials Science Forum 880 (November 2016): 124–27. http://dx.doi.org/10.4028/www.scientific.net/msf.880.124.

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The bimetallic weld joints are widely utilized in the pressurized water reactors, boiling water reactors, heat exchangers in process industries, heat transport piping system utilized in nuclear plants, etc. The present study is aimed at analyzing the bimetallic weld strength degradation due to thermal fatigue. For generating thermal fatigue like conditions, an experimental test rig has been developed. The bimetallic weld between low alloy steel SA 516 grade 70 and stainless steel 304 L was prepared. The experimental results show that, heating time, notch radius and number of cycles have the ef

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31

Jaiswal, Vaibhav, Luiz Leal, and Alexander I. Kolesnikov. "Analysis of the time-of-flight neutron scattering cross-section data for light water measured at the SEQUOIA spectrometer, Spallation Neutron Source (SNS)." EPJ Web of Conferences 239 (2020): 14007. http://dx.doi.org/10.1051/epjconf/202023914007.

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Thermal neutron scattering cross-section data for light water available in the major nuclear data libraries observes significant differences especially at reactor operating temperatures. During the past few years there has been a renewed interest in reviewing the existing thermal scattering models and generating more accurate and reliable thermal scattering cross sections using existing experimental data and in some cases based on Molecular Dynamics (MD) simulations. There is a need for performing new time-of-flight experiments at high temperatures and pressures, to have a better understanding

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32

Safavi, A., M. H. Esteki, S. M. Mirvakili, and M. Khaki. "Validation of a new neutronics/thermal hydraulics coupling code for steady state analysis of light water reactors." Kerntechnik 85, no. 5 (2020): 351–58. http://dx.doi.org/10.3139/124.190087.

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33

Kheradmand Saadi, M., and B. Bashiri. "Neutronic and thermal-hydraulic analysis of alternative ceramic fuels in the next-generation of light water reactors." Progress in Nuclear Energy 87 (March 2016): 89–96. http://dx.doi.org/10.1016/j.pnucene.2015.11.002.

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34

Safavi, Amir, Mohammad Hossein Esteki, Seyed Mohammad Mirvakili, and Mehdi Khaki Arani. "Application of a new neutronics/thermal-hydraulics coupled code for steady state analysis of light water reactors." Nuclear Engineering and Technology 52, no. 8 (2020): 1603–10. http://dx.doi.org/10.1016/j.net.2020.01.024.

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35

Al-Qasir, Iyad, Victor Gillette, and Abdallah Qteish. "Thermal neutron scattering kernels for uranium mono-nitride: A potential advanced tolerant fuel candidate for light water reactors." Annals of Nuclear Energy 127 (May 2019): 68–78. http://dx.doi.org/10.1016/j.anucene.2018.11.047.

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36

Alhummiany, H. "Novel Nanofluid Based on Water-Loaded Delafossite CuAlO2 Nanowires: Structural and Thermal Properties." Journal of Nanomaterials 2018 (2018): 1–6. http://dx.doi.org/10.1155/2018/4076960.

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Ultra-high cooling performance is a crucial requirement of many thermomechanical systems, such as microelectronic devices, engine cooling systems, nuclear power systems, chemical reactors, and refrigeration systems. Recent experimental results reveal the potential thermal properties of suspended nanometallics in conventional fluids. In this study, the facile synthesis of one-dimensional delafossite CuAlO2 nanowires by microwave hydrothermal treatment was presented. A novel type of nanofluid consisting of CuAlO2 nanowires suspended in distilled water at various volume fractions (0.0, 0.2, 0.4,

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Corbin, J. C., U. Lohmann, B. Sierau, A. Keller, H. Burtscher, and A. A. Mensah. "Black carbon surface oxidation and organic composition of beech-wood soot aerosols." Atmospheric Chemistry and Physics 15, no. 20 (2015): 11885–907. http://dx.doi.org/10.5194/acp-15-11885-2015.

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Abstract. Soot particles are the most strongly light-absorbing particles commonly found in the atmosphere. They are major contributors to the radiative budget of the Earth and to the toxicity of atmospheric pollution. Atmospheric aging of soot may change its health- and climate-relevant properties by oxidizing the primary black carbon (BC) or organic particulate matter (OM) which, together with ash, comprise soot. This atmospheric aging, which entails the condensation of secondary particulate matter as well as the oxidation of the primary OM and BC emissions, is currently poorly understood. In

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38

Mousa, Mohamed M. "Finite Element Investigation of Stationary Natural Convection of Light and HeavyWater in a Vessel Containing Heated Rods." Zeitschrift für Naturforschung A 67, no. 6-7 (2012): 421–28. http://dx.doi.org/10.5560/zna.2012-0040.

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This numerical study investigates the steady state natural convection of light and heavy water entering a vessel from the left and leaving on the right. The cavity consists of a matrix of cylindrical heated rods as in light and heavy water reactors. The aim of the study is to describe the effects of water inlet velocity on the flow and thermal fields in presence of such heated obstacle. The investigations are conducted for different values of rods temperatures. From the numerical results, it is evident that the flow pattern and temperature fields are significantly dependent on the water inlet

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Sharaevsky, І. G., N. М. Fіаlkо, А. V. Nоsоvskyi, L. B. Zimin, Т. S. Vlasenko, and G. І. Sharaevsky. "Problem issues of cores thermal-hydraulic calculation for prospective water-cooled reactors with supercritical parameters." Nuclear Power and the Environment 19, no. 4 (2020): 3–15. http://dx.doi.org/10.31717/2311-8253.20.4.1.

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The fundamental thermophysical features of the heat exchange process between the heated wall of a vertical channel and the light-water coolant of supercritical parameters concerning the conditions of heat-generating assemblies channels and cores of perspective energy nuclear reactors are considered. The available methods and recommendations for determining the limits of thermal load are analyzed. It is a guarantee the absence of the characteristic dangerous mode possibility of deteriorated heat exchange in these conditions and corresponding sharp rise in the channels wall temperature, which th

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40

Tsige-Tamirat, Haileyesus, and Luca Ammirabile. "Study on the Use of Hydride Fuel in High-Performance Light Water Reactor Concept." Science and Technology of Nuclear Installations 2015 (2015): 1–8. http://dx.doi.org/10.1155/2015/965274.

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Hydride fuels have features which could make their use attractive in future advanced power reactors. The potential benefit of use of hydride fuel in HPLWR without introducing significant modification in the current core design concept of the high-performance light water reactor (HPLWR) has been evaluated. Neutronics and thermal hydraulic analyses were performed for a single assembly model of HPLWR with oxide and hydride fuels. The hydride assembly shows higher moderation with softer neutron spectrum and slightly more uniform axial power distribution. It achieves a cycle length of 18 months wit

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41

Sharayevsky, I. G., N. M. Fialko, A. V. Nosovskyi, L. B. Zimin, T. S. Vlasenko, and G. I. Sharayevsky. "Actual problems of the thermal hydraulic reliability ensuring of prospective nuclear reactors with supercritical parameters." Nuclear Power and the Environment 20 (2021): 27–38. http://dx.doi.org/10.31717/2311-8253.21.1.2.

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There is a significant lack of reliable information on the physical characteristics of thermohydraulic processes in emergency heat transfer modes when cooling the surface of fuel rods with light water coolant with supercritical thermodynamic parameters, in particular, on the physics of heat transfer processes and hydromechanics in the critical area. It is shown that in these conditions there is physical uncertainty about the causes of deteriorating heat transfer, which limits the possibility of creating effective calculation techniques for reliable determination of the upper limit of safe forc

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42

Jithendra Kumar, Repalle, B. V. S. Raghu Vamsi, T. Siva Krishna, D. Tarun, and M. Kamal Tej. "Evaluation of Coefficient of Thermal Expansion of Zirconium by Using Dilatometer & Ansys." Advanced Materials Research 1148 (June 2018): 128–35. http://dx.doi.org/10.4028/www.scientific.net/amr.1148.128.

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Zirconium alloys are solid solutions of zirconium or other metals. Zirconium has very low absorption cross-section of thermal neutrons. Zirconium has high corrosion resistance, ductility and hardness. Zirconium is mainly used as a good refractory metal. Zirconium can be manufactured by using standard fabrication techniques. In the present scenario zirconium alloys are used in water reactors for the cladding of fuel rods in nuclear reactors in nuclear technology. We use the composition of zirconium alloys as more than 94.5 weight percentage of zirconium and less than 2.45 weight percentage of c

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Leal, Luiz, Vaibhav Jaiswal, and Alexander I. Kolesnikov. "High-resolution neutron time-of-flight measurements for light water at the Spallation Neutron Source (SNS), Oak Ridge National Laboratory." EPJ Web of Conferences 239 (2020): 14005. http://dx.doi.org/10.1051/epjconf/202023914005.

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Series of light water inelastic neutron scattering experiments have been made at the Oak Ridge National Laboratory (ORNL), Spallation Neutron Source (SNS) covering temperatures ranging from 295 K to 600 K and pressures of 1 bar and 150 bar. The temperatures and pressures ranges correspond to that of pressurized light water reactors. The inelastic scattering measurements will help the development of light water thermal scattering kernels, also known as S (α,β) thermal scattering law (TSL), in a consistent fashion given the amount and the quality of the measured data. Light water thermal scatter

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Chang, H. T., and B. E. Rittmann. "Predicting bed dynamics in three-phase, fluidized-bed biofilm reactors." Water Science and Technology 29, no. 10-11 (1994): 231–41. http://dx.doi.org/10.2166/wst.1994.0766.

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This paper presents a unified model that inter-relates gas flow rate, liquid flow rate, and hold-ups of each of the liquid, gas, and solid phases in three-phase, fluidized-bed biofilm (TPFBB) process. It describes how carrier properties, biofilm properties, and gas and liquid flow velocities control the system dynamics, which ultimately will affect the density, thickness, and distribution of the biofilm. The paper describes the development of the mathematical model to correlate the effects of gas flow rate, liquid flow rate, solid concentration, and biofilm thickness and density. This knowledg

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Demchenko, Oksana, Volodymyr Shulgin, and Ruslan Petrash. "Experimental Study on Light Concrete Properties Using Bottom Ash of Thermal Power Stations." International Journal of Engineering & Technology 7, no. 3.2 (2018): 1. http://dx.doi.org/10.14419/ijet.v7i2.26.14366.

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This paper presents the most optimal compositions of light concrete utilizing bottom ash for manufacturing the energy efficient wall products. Bottom ash usage as a filler instead of quartz sand acts as utilization of wastes which has a positive impact on ecology. It’s been experimentally investigated the influence of the amount of cement and water on strength, density, water consumption, and thermal conductivity of light concrete manufactured using the bottom ash from thermal electrical stations as a filler. Using the STATISTICA 12 software there were obtained the precise values of coefficien

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Eklund, Matthew D., and Tatjana Jevremovic. "AGENT-TH scheme: New thermal hydraulics (TH) code coupled with the AGENT neutronics code for light water reactors modeling and analysis." Progress in Nuclear Energy 92 (September 2016): 175–96. http://dx.doi.org/10.1016/j.pnucene.2016.07.003.

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Perovic, V., A. Perovic, G. C. Weatherly, and A. M. Brennenstuhl. "Microstructure and Microchemistry of Inconel 600 STEAM Generator Tubing." Microscopy and Microanalysis 6, S2 (2000): 356–57. http://dx.doi.org/10.1017/s1431927600034279.

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Inconel 600 is an austenitic Ni-Cr-Fe alloy which is extensively used for tubing in steam generators of pressurized light water reactors (PWR) and CANDU heavy water reactors, because of its excellent mechanical properties and corrosion resistance. However, there have been instances of intergranular stress corrosion cracking of tubes in operating steam generators. The chemistry and the structure of grain boundaries and grain boundary precipitation have emerged as factors of prime importance in understanding stress corrosion cracking and intergranular attack of nickel-base alloys (see e.g. ref.

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Marquez Damian, Jose Ignacio, Javier Dawidowski, Rolando Jose Granada, et al. "Experimental validation of the temperature behavior of the ENDF/B-VIII.0 thermal scattering kernel for light water." EPJ Web of Conferences 239 (2020): 14001. http://dx.doi.org/10.1051/epjconf/202023914001.

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The Neutron Physics Department at Centro Atómico Bariloche developed new models for the interaction of thermal neutrons with water which have been validated against experimental data, including new thermal scattering experiments, and were adopted for the release of ENDF/B-VIII.0. Although the older models are, in general, good for most applications, some discrepancies had appeared in the case of heavy water, and this motivated new measurements that validated the new model. In the case of light water, the new model predicts a reduction of the total cross section around 0.025 eV when the tempera

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Losa, Evžen, Michal Košťál, Tomáš Czakoj, et al. "NEUTRON FIELD MOCK-UP DEVELOPMENT FOR THE FLUORIDE SALT REACTORS NEUTRONIC RESEARCH." EPJ Web of Conferences 247 (2021): 08013. http://dx.doi.org/10.1051/epjconf/202124708013.

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Experimental work at the LR-0 reactor was carried out to determine the possibility of the mock-up neutron field creation for the fluoride salt-based reactors. Previous calculations and experiments have shown that the fast part of the molten salt reactor (MSR) spectrum is shaped by fluorine and even the Teflon material is suitable for neutronics in that energy range. Properly selected spectrum indices can describe the neutron field of the MSR in fast thermal and intermediate parts of the spectrum. Current research has focused on a deeper study of the possibility of using the filtered thermal an

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Kim, Kang Seog, Brian J. Ade, and Nicholas P. Luciano. "DEVELOPMENT OF THE MPACT 69-GROUP LIBRARY FOR MAGNOX REACTOR ANALYSIS USING CASL VERA." EPJ Web of Conferences 247 (2021): 10016. http://dx.doi.org/10.1051/epjconf/202124710016.

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The Consortium for Advanced Simulation of Light Water Reactors (CASL) has developed the CASL toolset, Virtual Environment for Reactor Analysis (VERA), for pressurized water reactor (PWR) analysis. Recently the CASL VERA was improved for Magnox reactor analysis, which required the development of a new cross section library and new geometrical and thermal feedback capabilities for graphite-moderated Magnox reactors. The MPACT neutronics module of the CASL core simulator is a 3D whole core transport code, which requires a new cross section library with a different energy group structure due to th

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