Relevant bibliographies by topics / In-vessel melt retention

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  1. Journal articles

Academic literature on the topic 'In-vessel melt retention'

Author: Grafiati
Published: 24 June 2021
Last updated: 1 February 2022

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Journal articles on the topic "In-vessel melt retention"

1

Almyashev, V. I., V. S. Granovsky, V. B. Khabensky, et al. "Oxidation effects during corium melt in-vessel retention." Nuclear Engineering and Design 305 (August 2016): 389–99. http://dx.doi.org/10.1016/j.nucengdes.2016.05.024.

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2

Kang, Kyoung-Ho, Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, and Soon-Heung Chang. "Simulant Melt Experiments on In-Vessel Retention Through External Reactor Vessel Cooling." Nuclear Technology 155, no. 3 (2006): 324–39. http://dx.doi.org/10.13182/nt06-a3765.

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3

Theofanous, T. G., C. Liu, S. Additon, S. Angelini, O. Kymäläinen, and T. Salmassi. "In-vessel coolability and retention of a core melt." Nuclear Engineering and Design 169, no. 1-3 (1997): 1–48. http://dx.doi.org/10.1016/s0029-5493(97)00009-5.

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4

Asmolov, V., N. N. Ponomarev-Stepnoy, V. Strizhov, and B. R. Sehgal. "Challenges left in the area of in-vessel melt retention." Nuclear Engineering and Design 209, no. 1-3 (2001): 87–96. http://dx.doi.org/10.1016/s0029-5493(01)00391-0.

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5

Jiang, Nan, Tenglong Cong, and Minjun Peng. "Margin evaluation of in-vessel melt retention for small IPWR." Progress in Nuclear Energy 110 (January 2019): 224–35. http://dx.doi.org/10.1016/j.pnucene.2018.10.003.

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6

Abendroth, M., H. G. Willschütz, and E. Altstadt. "Fracture mechanical evaluation of an in-vessel melt retention scenario." Annals of Nuclear Energy 35, no. 4 (2008): 627–35. http://dx.doi.org/10.1016/j.anucene.2007.08.007.

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7

Zvonarev, Yu A., A. M. Volchek, V. L. Kobzar, and M. A. Budaev. "ASTEC application for in-vessel melt retention modelling in VVER plants." Nuclear Engineering and Design 272 (June 2014): 224–36. http://dx.doi.org/10.1016/j.nucengdes.2013.06.044.

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8

Gencheva, R., A. Stefanova, P. Groudev, B. Chatterjee, and D. Mukhopadhyay. "Study of in-vessel melt retention for VVER-1000/v320 reactor." Nuclear Engineering and Design 298 (March 2016): 208–17. http://dx.doi.org/10.1016/j.nucengdes.2015.12.031.

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9

Valinčius, Mindaugas, Tadas Kaliatka, Algirdas Kaliatka, and Eugenijus Ušpuras. "Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor." Science and Technology of Nuclear Installations 2018 (August 1, 2018): 1–14. http://dx.doi.org/10.1155/2018/7162387.

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Abstract:
One of the severe accident management strategies for nuclear reactors is the melted corium retention inside the reactor pressure vessel. The work presented in this article investigates the application of in-vessel retention (IVR) severe accident management strategy in a BWR reactor. The investigations were performed assuming a scenario with the large break LOCA without injection of cooling water. A computer code RELAP/SCDAPSIM MOD 3.4 was used for the numerical simulation of the accident. Using a model of the entire reactor, a full accident sequence from the large break to core uncover and heat-up as well as corium relocation to the lower head is presented. The ex-vessel cooling was modelled in order to evaluate the applicability of RELAP/SCDAPSIM code for predicting the heat fluxes and reactor pressure vessel wall temperatures. The results of different ex-vessel heat transfer modes were compared and it was concluded that the implemented heat transfer correlations of COUPLE module in RELAP/SCDAPSIM should be applied for IVR analysis. To investigate the influence of debris separation into oxidic and metallic layers in the molten pool on the heat transfer through the wall of the lower head the analytical study was conducted. The results of this study showed that the focusing effect is significant and under some extreme conditions local heat flux from reactor vessel could exceed the critical heat flux. It was recommended that the existing RELAP/SCDAPSIM models of the processes in the debris should be updated in order to consider more complex phenomena and at least oxide and metal phase separation, allowing evaluating local distribution of the heat fluxes.
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10

Granovsky, V. S., V. B. Khabensky, E. V. Krushinov, et al. "Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retention." Nuclear Engineering and Design 278 (October 2014): 310–16. http://dx.doi.org/10.1016/j.nucengdes.2014.07.034.

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