Relevant bibliographies by topics / Boiling water reactors

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  1. Journal articles

Academic literature on the topic 'Boiling water reactors'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 August 2024

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Journal articles on the topic "Boiling water reactors"

1

Ganda, Francesco, Francisco J. Arias, Jasmina Vujic, and Ehud Greenspan. "Self-Sustaining Thorium Boiling Water Reactors." Sustainability 4, no. 10 (2012): 2472–97. http://dx.doi.org/10.3390/su4102472.

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2

Lin, Chien C. "Hydrogen Water Chemistry Technology in Boiling Water Reactors." Nuclear Technology 130, no. 1 (2000): 59–70. http://dx.doi.org/10.13182/nt00-a3077.

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3

Györke, Gábor, and Attila R. Imre. "Physical-chemical Background of the Potential Phase Transitions during Loss of Coolant Accidents in the Supercritical Water Loops of Various Generation IV Nuclear Reactor Types." Periodica Polytechnica Chemical Engineering 63, no. 2 (2019): 333–39. http://dx.doi.org/10.3311/ppch.12770.

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Loss of coolant accidents (LOCA) are a serious type of accidents for nuclear reactors, when the integrity of the liquid-loop breaks. While in traditional pressurized water reactors, pressure drop can cause flash boiling, in Supercritical-Water Cooled reactors, the pressure drop can be terminated by processes with fast phase transition (flash boiling or steam collapse) causing pressure surge or the expansion can go smoothly to the dry steam region. Modelling the pressure drop of big and small LOCAs as isentropic and isenthalpic processes and replacing the existing reactor designs with a simplif
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4

YAMAZAKI, Yukitaka, Katsumi YAMADA, Chikako IWAKI, Shinichi MOROOKA, Hideo SONEDA, and Tomohiro YAGII. "ICONE15-10464 DEVELOPMENT OF LOW PRESSURE LOSS STEAM SEPARATOR FOR BOILING WATER REACTORS." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_248.

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5

Dokhane, Abdelhamid. "Boiling water reactors as dynamic complex systems." International Journal of Nuclear Energy Science and Technology 4, no. 4 (2009): 275. http://dx.doi.org/10.1504/ijnest.2009.028588.

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6

Hampel, R., A. Traichel, S. Fleischer, and R. Kästner. "Water level in boiling water reactors — Measurement, modelling, diagnostic." Progress in Nuclear Energy 43, no. 1-4 (2003): 121–28. http://dx.doi.org/10.1016/s0149-1970(03)00018-0.

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7

Chen, Yen-Shu, Li-Ying Huang, and Ansheng Lin. "Water inventory calculation for the shutdown boiling water reactors." Nuclear Engineering and Design 408 (July 2023): 112315. http://dx.doi.org/10.1016/j.nucengdes.2023.112315.

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8

Giustini, Giovanni. "Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief Review." Inventions 5, no. 3 (2020): 47. http://dx.doi.org/10.3390/inventions5030047.

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The boiling process is utterly fundamental to the design and safety of water-cooled fission reactors. Both boiling water reactors and pressurised water reactors use boiling under high-pressure subcooled liquid flow conditions to achieve high surface heat fluxes required for their operation. Liquid water is an excellent coolant, which is why water-cooled reactors can have such small sizes and high-power densities, yet also have relatively low component temperatures. Steam is in contrast a very poor coolant. A good understanding of how liquid water coolant turns into steam is correspondingly vit
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9

Pruit, D. W., D. R. Tinkler, and Y. M. Farawila. "ICONE15-10489 An Enhanced Detect-and-Suppress Stability Protection Method for Boiling Water Reactors." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_260.

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10

Chiang, Ren-Tai. "Safety Features of Advanced and Economic Simplified Boiling Water Reactors." Indonesian Journal of Physics and Nuclear Applications 3, no. 1 (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 opera
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