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Journal articles on the topic 'La calandria'

Author: Grafiati
Published: 14 December 2024

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1

David, R. "Heat transfer at the step of a CANDU calandria during a severe accident." Kerntechnik 86, no. 5 (October 1, 2021): 338–42. http://dx.doi.org/10.1515/kern-2021-0022.

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Abstract During the in-vessel stage of a severe accident in a CANDU 6 reactor, decay heat from a collapsed core would be rejected through the calandria walls into the surrounding water. At the step in the calandria wall, the subshell and annular plate meet at a right angle pointing into the calandria. The geometry at this joint could concentrate the exiting heat flux, potentially leading to calandria failure. Finite element analysis is used to study the heat transfer near the welded joint. Different weld profiles, boundary conditions, and decay heat characteristics are considered, and the local concentration of exiting heat flux is calculated.
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2

Lumsden, R. H., B. V. Luloff, N. Zahn, and N. Simpson. "Development Of NRU Reflector Wall Inspection System." AECL Nuclear Review 2, no. 1 (June 1, 2013): 17–26. http://dx.doi.org/10.12943/anr.2013.00002.

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In 2009 May, the National Research Universal (NRU) calandria leaked. During the next year, the calandria was inspected with six new Non-Destructive Evaluation (NDE) techniques to determine the extent of the corrosion, repaired, and finally the repair was inspected with four additional new NDE techniques before the reactor was returned to service. The calandria is surrounded by a light-water reflector vessel fabricated from the same material as the calandria vessel. Concerns that the same corrosion mechanism had damaged the reflector vessel led to the development of a system to inspect the full circumference of the reflector wall for corrosion damage. The inspection region could only be accessed through 64 mm diameter ports, was 10 m below the port, and had to be inspected from the corroded surface. The ultrasonic technique was designed to produce a closely spaced wall thickness (WT) grid over an area of approximately 5 m2 on the corroded surface using a very small probe holder. This paper describes the Reflector Wall Inspection (RWI) development project and the system that resulted.
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3

Shukla, Kaustubh. "Calandria - A Manufacturing Challenge." Advanced Materials Research 794 (September 2013): 159–62. http://dx.doi.org/10.4028/www.scientific.net/amr.794.159.

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Accelerating the pace of Nuclear Power Plants construction is critical to the Growth of Indian Economy. It calls for timely and First Time Right manufacturing of various Reactor Equipment. This paper captures the experience of Godrej Precision Engineering Division in successful realization of Calandria, in record time, with First Time Right Quality adhering to very demanding and stringent requirements.
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4

Guidotti, Angela. "Il doppio gioco della Calandria." MLN 104, no. 1 (January 1989): 98. http://dx.doi.org/10.2307/2904993.

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5

Bacchiega, Julia. "Calandria, S. (2021). Matar a la madre: Infanticidios, honor y género en la provincia de Buenos Aires (1886-1921). Ciudad Autónoma de Buenos Aires: Biblos; Málaga: Universidad de Málaga. (Ciudadanía e Inclusión)." Trabajos y comunicaciones, no. 56 (July 22, 2022): e175. http://dx.doi.org/10.24215/23468971e175.

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6

Park, Sooyong, Kwang-Il Ahn, and YongMann Song. "Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant." Science and Technology of Nuclear Installations 2015 (2015): 1–6. http://dx.doi.org/10.1155/2015/462941.

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This paper illustrates the application of a severe accident analysis computer program to the uncertainty analysis of molten corium-concrete interaction (MCCI) phenomena in cases of severe accidents in CANDU6 type plant. The potential hazard of MCCI is a failure of the reactor building owing to the possibility of a calandria vault floor melt-through even though the containment filtered vent system is operated. Meanwhile, the MCCI still has large uncertainties in several phenomena such as a melt spreading area and the extent of water ingression into a continuous debris layer. The purpose of this study is to evaluate the MCCI in the calandria vault floor via an uncertainty analysis using the ISAAC program for the CANDU6.
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7

Ells, C. E., C. E. Coleman, and C. K. Chow. "Properties of a Candu Calandria Tube." Canadian Metallurgical Quarterly 24, no. 3 (July 1985): 215–23. http://dx.doi.org/10.1179/cmq.1985.24.3.215.

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8

D'Amico, Jack. "Drama and the Court in "La Calandria"." Theatre Journal 43, no. 1 (March 1991): 93. http://dx.doi.org/10.2307/3207952.

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9

Villarreal Albitres, William, and Obidio Rubio Mercedes. "Simulación computacional de flujo de dos-fases de un evaporador Roberts." REVISTA TECNOLOGÍA & DESARROLLO 11, no. 1 (March 7, 2015): 7–14. http://dx.doi.org/10.18050/td.v11i1.81.

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El presente trabajo de investigación fue llevada a cabo con el objetivo de determinar el comportamiento de los campos de velocidades, temperaturas y presiones del jugo de caña, como fluido de estudio, de un sistema de dos-fase de un evaporador Roberts. Para simular computacionalmente el movimiento de la partícula del fluido en un medio ambiente de dos-fases se usó el código CFX-ANSYS, el cual calcula el campo del flujo por el Método del Volumen Finito. Asimismo, se registraron las condiciones del flujo tanto de jugo como de vapor a la entrada y salida de un evaporador Roberts de 785 m2  de Industrial Pucalá en Chiclayo. Para validar el perfil del campo de temperatura simulados computacionalmente se tomaron datos experimentales del jugo hirviendo, colocando bulbos de temperatura sobre la calandria del evaporador. Resultados obtenidos de la simulación computacional de los campos de velocidad, temperatura y presión del jugo de caña de un evaporador Roberts mostraron que la velocidad del jugo cae dramáticamente en el fondo y calandria del evaporador. Recirculación de jugo abundante ocurre entre la línea de salida de jugo evaporado y el tubo central de recirculado. Así mismo, las temperaturas del fluido que hierve son más altas en la parte media de la altura de la calandria, y su presión decrece uniformemente desde el fondo al cuerpo del evaporador. Los valores de la temperatura del jugo simulados computacionalmente y medidos experimentalmente mostraron estar en buena concordancia, validando al modelo desarrollado.
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10

Campbell, Susanna K., Alcides L. Morales-Perez, John F. Malloy, Oliver C. Muellerklein, Jin A. Kim, Karan J. Odom, and Kevin E. Omland. "Documentation of female song in a newly recognized species, the Puerto Rican Oriole (<em>Icterus portoricensis</em>)." Journal of Caribbean Ornithology 29 (October 24, 2016): 28–36. http://dx.doi.org/10.55431/jco.2016.29.28-36.

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Abstract: Evolutionary biologists often assume that male competition for females is the root of the evolution of elaborate coloration and song. However, recent findings show that in the ancestral history of songbirds, it is likely that song occurred in both males and females. Surprisingly, no data exist on female song for many species of birds. We investigated whether the Puerto Rican Oriole (Icterus portoricensis), a tropical songbird, exhibits both male and female song. For this project we marked individuals with sex-specific color bands and confirmed sex using genetic sexing. We repeatedly recorded both male and female orioles singing. Furthermore, female Puerto Rican Oriole song appears to be similar to male song, with no obvious differences in structure. Our study provides further evidence of the ubiquity of female song in tropical songbirds. Finally, our findings provide support that female song is ancestral in the Caribbean oriole clade, and that song dimorphism in temperate breeding species is a result of a loss of female song. Keywords: female song, female vocalizations, Icterus portoricensis, Puerto Rican Oriole, tropical songbirds Resumen: Biólogos evolutivos a menudo asumen que la competencia masculina para las mujeres es la raíz de la evolución de la coloración y canción. Sin embargo, recientes hallazgos muestran que los machos y las hembras ancestrales de todos los pájaros cantores probablemente cantaban; pero existen pocos datos sobre el canto de las hembras de muchas especies de aves. Nosotros investigamos el actuada canta de los hembras y los machos el pájaro, la Calandria Puertorriqueña (Icterus portoricensis). Para este proyecto, marcamos individuos de diferentes sexos con bandas de color específicas y confirmamos el sexo usando métodos genéticos. Adicionalmente; grabamos las canciones de ambos sexos de las Calandrias Puertorriqueñas. Somos los primeros en documentar canción de ambos sexos en esta especie. Por otra parte, la canción de la Calandria Puertorriqueña aparece ser similar a la canción de los machos, sin diferencias evidentes en la estructura de la canción. Nuestro estudio ofrece evidencia adicional de la omnipresencia de la canción femenina en las aves canoras tropicales. Por último, nuestros resultados respaldan la idea de que la canción femenina es ancestral en la clade de las calandrias caribes, y que el dimorfismo en la canción de especies de aves templadas es un resultado de la pérdida de la canción femenina. Palabras clave: aves canoras tropicales, Calandria Puertorriqueña, canto de hembras, Icterus portoricensis, vocalizaciones de hembras Résumé: Les biologistes évolutionnistes supposent souvent que la compétition entre mâles pour les femelles est à l’origine de l'évolution vers une coloration et un chant élaborés. Toutefois, des résultats récents montrent que, dans l'histoire ancestrale des oiseaux chanteurs, il est probable que le chant ait été présent à la fois par chez les mâles et chez les femelles. Étonnamment, aucune donnée n'existe sur le chant des femelles pour de nombreuses espèces d'oiseaux. Nous avons étudié si l'Oriole de Porto Rico (Icterus portoricensis), un oiseau chanteur tropical, présentait à la fois un chant mâle et un chant femelle. Pour ce projet, nous avons marqué les individus avec des bagues de couleurs différentes selon le sexe et confirmé le sexe par des analyses génétiques. Nous avons enregistré à plusieurs reprises des mâles et des femelles en train de chanter. En outre, le chant des femelles d't semble être similaire à celui des mâles, sans différence évidente dans la structure. Notre étude fournit une preuve supplémentaire de l'omniprésence du chant des femelles chez les oiseaux chanteurs tropicaux. Enfin, nos résultats soutiennent l'hypothèse affirmant que le chant des femelles est ancestral dans le clade des orioles des Caraïbes, et que le dimorphisme du chant chez les espèces nichant dans les régions tempérées est le résultat d'une disparition de chant chez les femelles. Mots clés: chant des femelles, Icterus portoricensis, oiseaux chanteurs tropicaux, Oriole de Porto Rico, vocalisation des femelles
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11

Kim, Hyoung, Se-Myong Chang, and Young Son. "Unsteady Simulation of a Full-Scale CANDU-6 Moderator with OpenFOAM." Energies 12, no. 2 (January 21, 2019): 330. http://dx.doi.org/10.3390/en12020330.

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Three-dimensional moderator flow in the calandria tank of CANDU-6 pressurized heavy water reactor (PHWR) is computed with Open Field Operation and Manipulation (OpenFOAM), an open-source computational fluid dynamics (CFD) code. In this study, numerical analysis is performed on the real geometry model including 380 fuel rods in the calandria tank with the heat-source distribution to remove uncertainty of the previous analysis models simplified by the porous media approach. Realizable k-ε turbulence model is applied, and the buoyancy due to temperature variation is considered by Boussinesq approximation for the incompressible single-phase Navier-Stokes equations. The calculation results show that the flow is highly unsteady in the moderator. The computational flow visualization shows a circulation of flow driven by buoyancy and asymmetric oscillation at the pseudo-steady state. There is no region where the local temperature rises continuously due to slow circulating flow and its convection heat transfer.
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12

Brown, M. J., and D. G. Bailey. "FISSION-PRODUCT RELEASES FROM A PHWR TERMINAL DEBRIS BED." CNL Nuclear Review 5, no. 1 (June 2016): 95–105. http://dx.doi.org/10.12943/cnr.2015.00056.

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During an unmitigated severe accident in a pressurized heavy water reactor (PHWR) with horizontal fuel channels, the core may disassemble and relocate to the bottom of the calandria vessel. The resulting heterogeneous in-vessel terminal debris bed (TDB) would likely be quenched by any remaining moderator, and some of the decay heat would be conducted through the calandria vessel shell to the surrounding reactor vault or shield tank water. As the moderator boiled off, the solid debris bed would transform into a more homogeneous molten corium pool located between top and bottom crusts. Until recently, the severe accident code MAAP-CANDU assumed that unreleased volatile and semi-volatile fission products remained in the TDB until after calandria vessel failure, due to low diffusivity through the top crust and the lack of gases or steam to flush released fission products from the debris. However, national and international experimental results indicate this assumption is unlikely; instead, high- and medium-volatility fission products would be released from a molten debris pool, and their volatility and transport should be taken into account in TDB modelling. The resulting change in the distribution of fission products within the reactor and containment, and the associated decay heat, can have significant effects upon the progression of the accident and fission-product releases to the environment. This article describes a postulated PHWR severe accident progression to generate a TDB and the effects of fission-product releases from the terminal debris, using the simple release model in the MAAP-CANDU severe accident code. It also provides insights from various experimental programs related to fission-product releases from core debris, and their applicability to the MAAP-CANDU TDB model.
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13

Kundurpi, P. S., and A. P. Muzumdar. "Response of calandria vessel to impulse pressure loading." Nuclear Engineering and Design 130, no. 2 (September 1991): 171–78. http://dx.doi.org/10.1016/0029-5493(91)90125-2.

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14

Prasad, Sumit V., A. K. Nayak, and M. K. Samal. "Development of correlation for natural convection heat transfer for large horizontal calandria vessel for in-calandria retention of corium in PHWRs." Nuclear Engineering and Design 360 (April 2020): 110517. http://dx.doi.org/10.1016/j.nucengdes.2020.110517.

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15

Prasad, Sumit Vishnu, Arun Kumar Nayak, Primal Pramod Kulkarni, Pallippattu Krishnan Vijayan, and Keshav K. Vaze. "Study on heat removal capability of calandria vault water from molten corium in calandria vessel during severe accident of a PHWR." Nuclear Engineering and Design 284 (April 2015): 130–42. http://dx.doi.org/10.1016/j.nucengdes.2014.12.014.

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16

Tanner, Lawrence H., Megan T. Wilckens, Morgan A. Nivison, and Katherine M. Johnson. "Biomass and Soil Carbon Stocks in Wet Montane Forest, Monteverde Region, Costa Rica: Assessments and Challenges for Quantifying Accumulation Rates." International Journal of Forestry Research 2016 (2016): 1–8. http://dx.doi.org/10.1155/2016/5812043.

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We measured carbon stocks at two forest reserves in the cloud forest region of Monteverde, comparing cleared land, experimental secondary forest plots, and mature forest at each location to assess the effectiveness of reforestation in sequestering biomass and soil carbon. The biomass carbon stock measured in the mature forest at the Monteverde Institute is similar to other measurements of mature tropical montane forest biomass carbon in Costa Rica. Local historical records and the distribution of large trees suggest a mature forest age of greater than 80 years. The forest at La Calandria lacks historical documentation, and dendrochronological dating is not applicable. However, based on the differences in tree size, above-ground biomass carbon, and soil carbon between the Monteverde Institute and La Calandria sites, we estimate an age difference of at least 30 years of the mature forests. Experimental secondary forest plots at both sites have accumulated biomass at lower than expected rates, suggesting local limiting factors, such as nutrient limitation. We find that soil carbon content is primarily a function of time and that altitudinal differences between the study sites do not play a role.
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17

Rapela, C. W., and R. J. Pankhurst. "Monzonite suites: the innermost Cordilleran plutonism of Patagonia." Earth and Environmental Science Transactions of the Royal Society of Edinburgh 87, no. 1-2 (1996): 193–203. http://dx.doi.org/10.1017/s026359330000660x.

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ABSTRACT:In Patagonia a Triassic-Early Jurassic Cordilleran interior magmatic belt preceded the widespread eruption of Middle Jurassic syn-extensional rhyolites. Two plutons (La Calandria and La Leona) represent the easternmost plutonic rocks of this belt, > 750 km east of the present oceanic trench. They define a high-K calc-alkaline monzonite series in contrast with the main Andinotype arc magmatism of the Pacific margin: they are enriched in large ion lithophile elements (K, Rb, Ba, Sr and Th), LREE and P2O5and depleted in HREE and Y, with low FeO*/MgO ratio. The range of observed compositions (56-76% SiO2) resulted from high-level fractionation of plagioclase, hornbleńde, biotite, K-feldspar and accessories (sphene, apatite and zircon).Initial87Sr/86Sr ratios, average εNdtand mean depleted-mantle Nd model ages of the two plutons are 0·70487, -0·5 and 1050 Ma for La Calandria and 0·70509, -1·4 and 1125 Ma for La Leona, respectively. They are thus isotopically more primitive than the Middle Jurassic rhyolites, previously attributed to partial melting of Mesoproterozoic mafic lower crust. The preferred model for the origin of the monzonites is remelting of an amphibole- + garnet-bearing, plagioclase-poor, high-K mafic source (?underplating). This occurred in a distal sector of a dying oblique subduction regime, immediately preceding the extensional silicic volcanism.
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18

Hejzlar, Pavel, Neil E. Todreas, and Michael J. Driscoll. "Large Passive Pressure Tube Light Water Reactor with Voided Calandria." Nuclear Technology 113, no. 2 (February 1996): 134–44. http://dx.doi.org/10.13182/nt96-a35183.

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19

Harvel, Glenn D., Richard C. Scrannage, and Daniel M. Hobbs. "Scoping assessment of design characteristics for an enhanced calandria tube." Nuclear Engineering and Design 241, no. 8 (August 2011): 2688–97. http://dx.doi.org/10.1016/j.nucengdes.2011.05.038.

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20

Kansal, Anuj Kumar, G. L. Kumawat, M. T. Kamble, Naresh Kumar Maheshwari, and Jyeshtharaj B. Joshi. "Poison injection in AHWR calandria: Flow pattern and mixing characteristics." International Journal of Heat and Mass Transfer 105 (February 2017): 359–75. http://dx.doi.org/10.1016/j.ijheatmasstransfer.2016.09.109.

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21

Joshi, Sanjay P., and Alok Goyal. "Dynamic response analysis of tube array in partially filled calandria." Earthquake Engineering & Structural Dynamics 28, no. 3 (March 1999): 287–309. http://dx.doi.org/10.1002/(sici)1096-9845(199903)28:3<287::aid-eqe817>3.0.co;2-y.

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22

Tae, Ryong Kime, and Man Sohn Seok. "ICONE11-36042 COMPUTATION AND MEASUREMENT OF CALANDRIA TUG SAG IN PHWR." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2003 (2003): 50. http://dx.doi.org/10.1299/jsmeicone.2003.50.

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23

Mohta, Keshav, Suneel K. Gupta, Soupramanien Cathirvolu, Swaminathan Jaganathan, and J. Chattopadhyay. "High temperature deformation behavior of Indian PHWR Calandria material SS 304L." Nuclear Engineering and Design 368 (November 2020): 110801. http://dx.doi.org/10.1016/j.nucengdes.2020.110801.

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24

Teyssedou, A., R. Necciari, M. Reggio, F. Mehdi Zadeh, and S. Étienne. "Moderator Flow Simulation Around Calandria Tubes of Candu-6 Nuclear Reactors." Engineering Applications of Computational Fluid Mechanics 8, no. 1 (January 2014): 178–92. http://dx.doi.org/10.1080/19942060.2014.11015506.

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25

Kim, Tae Ryong, and Seok Man Sohn. "Computation and measurement of calandria tube sag in pressurized heavy water reactor." Nuclear Engineering and Design 230, no. 1-3 (May 2004): 339–48. http://dx.doi.org/10.1016/j.nucengdes.2003.11.036.

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26

Behdadi, Azin, Farshad Talebi, and John Luxat. "Critical heat flux for downward-facing pool boiling on CANDU calandria vessel." Annals of Nuclear Energy 110 (December 2017): 768–78. http://dx.doi.org/10.1016/j.anucene.2017.07.008.

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27

Joshi, Sanjay P. "Dynamic response analysis of tube array in calandria to rotational vault motion." Nuclear Engineering and Design 205, no. 3 (April 2001): 313–22. http://dx.doi.org/10.1016/s0029-5493(00)00391-5.

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28

David, Robert. "Calculation of Heat Fluxes Exiting a CANDU Calandria During In-Vessel Retention." Nuclear Technology 205, no. 11 (May 1, 2019): 1488–94. http://dx.doi.org/10.1080/00295450.2019.1597581.

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29

Mohta, Keshav, Suneel K. Gupta, Onkar S. Gokhale, Deb Mukhopadhyay, and J. Chattopadhyay. "An analysis method to assess in-Calandria corium retention time in PHWRs." Procedia Structural Integrity 60 (2024): 36–43. http://dx.doi.org/10.1016/j.prostr.2024.05.029.

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30

Hu, Bai Song, Fan Zhang, Xin Liang Wang, Hui Peng Sun, and Xiao Ping Shi. "Experimental Study on the Liquid Distributor of Horizontal Tube Falling Film Evaporator." Advanced Materials Research 550-553 (July 2012): 2897–902. http://dx.doi.org/10.4028/www.scientific.net/amr.550-553.2897.

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A calandria liquid distributor device was designed for horizontal falling film evaporation. The guide plate was introduced in this, which is easy to manufacture and can effectively reduce splash phenomenon. This paper studies the liquid distribution from the relation between distributive unwell-distributed coefficient and liquid flux of distributor tube and distributor hole. The result showed that the distributive unwell-distributed coefficient of in liquid distributor was decreased along with accretion of liquid flux, as apposed to homogeneous perforated. The unwell-distributed hole coefficient of distributor tube No.0 was increased along with accretion of flux, as apposed to distributor tube No.1 and distributor tube No.2.
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Behdadi, Azin, Farshad Talebi, and John Luxat. "Critical heat flux for downward-facing pool boiling on CANDU calandria tube surface." Nuclear Engineering and Design 315 (April 2017): 104–16. http://dx.doi.org/10.1016/j.nucengdes.2017.02.017.

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32

Atkins, M. D., D. J. Rossouw, M. Boer, T. Kim, B. W. Rhee, and H. T. Kim. "Mixed convection around calandria tubes in a ¼ scale CANDU-6 moderator circulation tank." Nuclear Engineering and Design 316 (May 2017): 151–62. http://dx.doi.org/10.1016/j.nucengdes.2017.03.010.

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33

Kundurpi, P. S., and A. P. Muzumdar. "Structural response of calandria tube to a spontaneous rupture of the pressure tube." International Journal of Pressure Vessels and Piping 31, no. 4 (January 1988): 241–53. http://dx.doi.org/10.1016/0308-0161(88)90008-7.

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., Hardik P. Patel. "CFD ANALYSIS OF CALANDRIA BASED NUCLEAR REACTOR: PART-II. PARAMETRIC ANALYSIS OF MODERATOR." International Journal of Research in Engineering and Technology 03, no. 07 (July 25, 2014): 347–51. http://dx.doi.org/10.15623/ijret.2014.0307059.

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35

Klein, Geoffrey, Mark S. Luloff, Jordan E. Morelli, and Thomas W. Krause. "Evaluation of Concentric Tube Model for Pressure Tube to Calandria Tube Gap Measurement." IEEE Sensors Journal 19, no. 15 (August 1, 2019): 6233–39. http://dx.doi.org/10.1109/jsen.2019.2909493.

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36

Shoukri, M., and A. M. C. Chan. "On the thermal analysis of pressure tube/calandria tube contact in CANDU reactors." Nuclear Engineering and Design 104, no. 2 (October 1987): 197–206. http://dx.doi.org/10.1016/0029-5493(87)90299-8.

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37

Alfaro Moreno, Rosa María. "Is it Possible to Generate Development Starting from Communication?" Nordicom Review 33, Special-Issue (December 1, 2012): 91–103. http://dx.doi.org/10.2478/nor-2013-0028.

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Abstract Communication, both intra-sector and among sectors, can generate dialogues and reciprocity and render development a public matter, i.e. a matter that pertains to all, including the media sector. However, it is still the case that we are faced with scattered social forces, unclear about their role in promoting inclusive, equitable and plural development. Those forces sometimes lack in democratic convictions or in significant social bonds among similarly minded groups. This article condenses years of reflection on our work at the Association of Social Communicators “Calandria”, a Peruvian civil society institution created in 1983 as the point of departure to argue that citizens should be the protagonists of development in a relationship with other key players, from government, the business community and organized civil society.
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38

KULKARNI, P. P., S. V. PRASAD, A. K. NAYAK, and P. K. VIJAYAN. "THERMAL AND STRUCTURAL ANALYSIS OF CALANDRIA VESSEL OF A PHWR DURING A SEVERE ACCIDENT." Nuclear Engineering and Technology 45, no. 4 (August 2013): 469–76. http://dx.doi.org/10.5516/net.03.2012.052.

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., Hardik P. Patel. "CFD ANALYSIS OF CALANDRIA BASED NUCLEAR REACTOR: PART-I. MODELING & ANALYSIS OF MODERATOR." International Journal of Research in Engineering and Technology 03, no. 06 (June 25, 2014): 540–43. http://dx.doi.org/10.15623/ijret.2014.0306101.

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Hejzlar, Pavel, Michael J. Driscoll, and Neil E. Todreas. "Physics Characteristics of a Large, Passive, Pressure Tube Light Water Reactor with Voided Calandria." Nuclear Science and Engineering 121, no. 3 (December 1995): 448–60. http://dx.doi.org/10.13182/nse95-a24146.

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Mohta, Keshav, Onkar S. Gokhale, Suneel K. Gupta, Deb Mukhopadhyay, and J. Chattopadhyay. "Structural integrity assessment of Calandria of 540 MWe PHWR for in-vessel corium retention." Nuclear Engineering and Design 367 (October 2020): 110791. http://dx.doi.org/10.1016/j.nucengdes.2020.110791.

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Yang, Jue, and Baoshan Jia. "Unstructured grid and unstructured grid porous methods for numerical analysis of TACR moderator calandria." Advances in Engineering Software 39, no. 5 (May 2008): 407–15. http://dx.doi.org/10.1016/j.advengsoft.2007.03.007.

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de Dios, Javier Berzal. "Conjuring the Concept of Rome: Alterity and Synecdoche in Peruzzi's Design for La Calandria." Sixteenth Century Journal 45, no. 1 (March 1, 2014): 25–50. http://dx.doi.org/10.1086/scj24247471.

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Kim, Hyoung Tae, Se-Myong Chang, Young Woo Son, and Taegee Min. "Multiphysical Simulations for the IAEA/ISCP Benchmark Model on the Contact of Pressure Tube and Calandria Tube in the Moderator System of CANDU-6 PHWR." Science and Technology of Nuclear Installations 2018 (November 1, 2018): 1–8. http://dx.doi.org/10.1155/2018/3096862.

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Abstract:
The LOCA (loss of coolant accident) is a kind of severe accident in the operation of PHWR (pressurized heavy water reactor) as well as other nuclear facilities, and possible cause of LOCA can be counted on the ballooning of pressure tube (PT) contacted to the outer calandria tube (CT) in the moderator system of CANDU-6 reactors. In the paper, we simulated the 150-kW experimental facility proposed by IAEA/ISCP, modeling the transient creeping behavior of pressurized tube heated with thermal radiation between the gaps of two concentric pipes. The outer boundary is simplified with a switched model that depends on the local temperature. With a multiphysical model supported by a commercial code, COMSOL multiphysics, the unsteady phenomena are simulated with models concerning various kinds of mechanics such as thermodynamics, nonlinear structural dynamics, and two-phase boiling heat transfer models.
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Lee, Gong-Hee, Young-Seok Bang, and Sweng-Woong Woo. "Performance Assessment of Turbulence Models for the Prediction of Moderator Thermal Flow Inside CANDU Calandria." Transactions of the Korean Society of Mechanical Engineers B 36, no. 3 (March 1, 2012): 363–69. http://dx.doi.org/10.3795/ksme-b.2012.36.3.363.

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Kulkarni, P. S. "Complex fluid flow and heat transfer analysis inside a calandria based reactor using CFD technique." Journal of Physics: Conference Series 822 (April 11, 2017): 012026. http://dx.doi.org/10.1088/1742-6596/822/1/012026.

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Mandal, Jadav C., and Chandrakant R. Sonawane. "Simulation of Moderator Flow and Temperature Inside Calandria of CANDU Reactor Using Artificial Compressibility Method." Heat Transfer Engineering 35, no. 14-15 (March 4, 2014): 1254–66. http://dx.doi.org/10.1080/01457632.2013.876802.

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Kim, Manwoong, Seon-Oh Yu, and Hho-Jung Kim. "Analyses on fluid flow and heat transfer inside Calandria vessel of CANDU-6 using CFD." Nuclear Engineering and Design 236, no. 11 (June 2006): 1155–64. http://dx.doi.org/10.1016/j.nucengdes.2005.10.018.

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Gerardi, C., and J. Buongiorno. "Pressure-tube and calandria-tube deformation following a single-channel blockage event in ACR-700." Nuclear Engineering and Design 237, no. 9 (May 2007): 943–54. http://dx.doi.org/10.1016/j.nucengdes.2006.06.007.

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Rossouw, D. J., M. D. Atkins, K. Beharie, T. Kim, B. W. Rhee, and H. T. Kim. "The thermal interaction of a buoyant plume from a calandria tube with an oblique jet." Nuclear Engineering and Design 310 (December 2016): 163–74. http://dx.doi.org/10.1016/j.nucengdes.2016.10.011.

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