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Journal articles on the topic 'Boiling water reactors'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 August 2024

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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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11

Sarott, Flurin-A. "Water Chemistry in Boiling Water Reactors – A Leibstadt-Specific Overview." CHIMIA International Journal for Chemistry 59, no. 12 (2005): 923–28. http://dx.doi.org/10.2533/000942905777675336.

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12

Hazzan, M. J., M. S. Stocknoff, David W. Barcomb, and Timothy Irving. "Radiation Levels During Shutdown in Boiling Water Reactors." Nuclear Technology 69, no. 3 (1985): 249–56. http://dx.doi.org/10.13182/nt85-a33608.

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13

Wachter, O., and G. Brümmer. "Experiences with austenitic steels in boiling water reactors." Nuclear Engineering and Design 168, no. 1-3 (1997): 35–52. http://dx.doi.org/10.1016/s0029-5493(96)01308-8.

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14

Jones, Robin L., Joe D. Gilman, and J. Lawrence Nelson. "Controlling stress corrosion cracking in boiling water reactors." Nuclear Engineering and Design 143, no. 1 (1993): 111–23. http://dx.doi.org/10.1016/0029-5493(93)90279-i.

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15

Postnikov, N. S. "Investigation of chaotic oscillations in boiling-water reactors." Atomic Energy 107, no. 5 (2009): 291–301. http://dx.doi.org/10.1007/s10512-010-9228-9.

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16

Kurskii, A. S., V. M. Eshcherkin, V. V. Kalygin, M. N. Svyatkin, and I. I. Semidotskii. "Boiling water vessel reactors for nuclear district heating." Atomic Energy 111, no. 5 (2012): 370–76. http://dx.doi.org/10.1007/s10512-012-9506-9.

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17

Tellez, Alberto Quezada, Francisco A. Godínez, Guillermo Fernández-Anaya, Marco A. Polo-Labarrios, and Sergio Quezada García. "Multifractal detrended fluctuation analysis of boiling water reactors." Nuclear Engineering and Design 421 (May 2024): 113106. http://dx.doi.org/10.1016/j.nucengdes.2024.113106.

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18

Sharaievskii, G. "Problems in Validation of the Chornobyl Accident Initiating Event." Nuclear and Radiation Safety, no. 1(69) (February 17, 2016): 20–27. http://dx.doi.org/10.32918/nrs.2016.1(69).03.

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The paper presents validation of known calculation dependencies used in RELAP-5 and other advanced computer codes to predict thermohydraulic anomalies from the standpoint of analyzing effect of initial coolant boiling in the Chornobyl accident on its further progression. The authors show current unsatisfactory efficiency of state-of-the-art computer codes in definition of the initial boiling point for the coolant in water-cooled nuclear reactors. The calculation methodology for improving accuracy in the predicting of dangerous thermal anomaly in reactor channels is under consideration.

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19

Huang, Hai, Chenxi Cao, Yue Wang, Youwei Yang, Jianning Lv, and Jing Xu. "Model-Based Analysis for Ethylene Carbonate Hydrogenation Operation in Industrial-Type Tubular Reactors." Processes 10, no. 4 (2022): 688. http://dx.doi.org/10.3390/pr10040688.

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Hydrogenation of ethylene carbonate (EC) to co-produce methanol (MeOH) and ethylene glycol (EG) offers an atomically economic route for CO2 utilization. Herein, aided with bench and pilot plant data, we established engineering a kinetics model and multiscale reactor models for heterogeneous EC hydrogenation using representative industrial-type reactors. Model-based analysis indicates that single-stage adiabatic reactors, despite a moderate temperature rise of 12 K, suffer from a narrow operational window delimited by EC condensation at lower temperatures and intense secondary EG hydrogenation

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20

Muñoz-Cobo, J. L., S. Chiva, and A. Escrivá. "Influence of subcooled boiling on out-of-phase oscillations in boiling water reactors." Nuclear Engineering and Design 235, no. 10-12 (2005): 1267–82. http://dx.doi.org/10.1016/j.nucengdes.2005.01.018.

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21

Lin, Chaung, Feng-Ling Jeng, Chi-Szu Lee, and Raghu Raghavan. "Hierarchical Fuzzy Logic Water-Level Control in Advanced Boiling Water Reactors." Nuclear Technology 118, no. 3 (1997): 254–63. http://dx.doi.org/10.13182/nt97-a35366.

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22

Khedr, Ahmed, Martina Adorni, and Francesco d’Auria. "The effect of code user and boundary conditions on RELAP calculations of MTR research reactor transient scenarios." Nuclear Technology and Radiation Protection 20, no. 1 (2005): 16–22. http://dx.doi.org/10.2298/ntrp0501016k.

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The safety evaluation of nuclear power and re search reactors is a very important step before their construction and during their operation. This evaluation based on the best estimate calculations requires qualified codes qualified users, and qualified nodalizations. The effect of code users on the RELAP5 results during the analysis of loss of flow transient in MTR research reactors is presented in this pa per. To clarify this effect, two nodalizations for research reactor different in the simulation of the open water surface boundary conditions of the reactor pool have been used. Very differe

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23

Loberg, John, Michael Österlund, Jan Blomgren, and Klaes-Håkan Bejmer. "Neutron Detection–Based Void Monitoring in Boiling Water Reactors." Nuclear Science and Engineering 164, no. 1 (2010): 69–79. http://dx.doi.org/10.13182/nse09-17.

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24

Sun, Bill K. H., Robert Colley, David G. Cain, and John W. Hallam. "Development of a Postscram Analyzer for Boiling Water Reactors." Nuclear Technology 76, no. 3 (1987): 352–59. http://dx.doi.org/10.13182/nt87-a33920.

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25

MATHIEU, CHARLES E. "THE APPLICATION OF BOILING WATER REACTORS TO SHIP PROPULSION." Journal of the American Society for Naval Engineers 72, no. 3 (2009): 503–8. http://dx.doi.org/10.1111/j.1559-3584.1960.tb02394.x.

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26

Liu, Maolong, Nejdet Erkan, Yuki Ishiwatari, and Koji Okamoto. "Passive depressurization accident management strategy for boiling water reactors." Nuclear Engineering and Design 284 (April 2015): 176–84. http://dx.doi.org/10.1016/j.nucengdes.2014.12.020.

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27

Olvera-Guerrero, Omar Alejandro, Alfonso Prieto-Guerrero, and Gilberto Espinosa-Paredes. "A non-linear stability monitor for boiling water reactors." Annals of Nuclear Energy 135 (January 2020): 106983. http://dx.doi.org/10.1016/j.anucene.2019.106983.

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28

John, T. M., and Om Pal Singh. "The Interpretation of Neutron Noise in Boiling Water Reactors." Nuclear Science and Engineering 89, no. 4 (1985): 322–29. http://dx.doi.org/10.13182/nse85-a18624.

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29

Lin, Chien C. "The Radiolytic Gas Production Rate in Boiling Water Reactors." Nuclear Science and Engineering 99, no. 4 (1988): 390–93. http://dx.doi.org/10.13182/nse88-a23567.

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30

Merkulov, Viktor, Nikolay Didenko, Djamilia Skripnuk, and Sergey Kulik. "Analysis of small modular reactor technologies and socio-economic aspects of their application in the Russian Arctic in the era of digital transformation." E3S Web of Conferences 402 (2023): 10011. http://dx.doi.org/10.1051/e3sconf/202340210011.

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Small modular reactor technologies and social, economic, and technological aspects of their application in the Russian Arctic are considered in the article. An overview of the key factors influencing an implementation of small modular reactor plants in remote regions with a decentralized power grid is presented. The main directions of small modular reactor design activities of the key Russian centers of atomic research and development are given. An overview of current Russian small modular reactor technologies including pressurized water reactors, boiling water reactors, reactors installed on

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31

Zhao, Jiyun, Pradip Saha, and Mujid S. Kazimi. "Core-Wide (In-Phase) Stability of Supercritical Water-Cooled Reactors—II: Comparison with Boiling Water Reactors." Nuclear Technology 161, no. 2 (2008): 124–39. http://dx.doi.org/10.13182/nt08-a3918.

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32

Pivovarov, V. "BOILING WATER REACTOR WITH TIGHT LATTICE OF FUEL RODS - DIRECT-CIRCUIT WATER-COOLED FAST REACTOR." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2019, no. 2 (2019): 107–16. http://dx.doi.org/10.55176/2414-1038-2019-2-107-116.

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The original concept of the boiling water reactor core with the reduced moderation of neutrons is proposed, in which a negative void reactivity effect is provided not by increase leakage of neutrons in the axial direction, but by an another physical principle. Instead of the traditional core flattening, a special heterogeneous arrangement is proposed, in which, along with tight lattice fuel assemblies (fuel rod diameter is 13.5 mm, the distance between the fuel rods is 1.3 mm) containing uranium-plutonium (MOX) fuel, there are fuel assemblies with uranium-thorium fuel (UO2+ThO2) with a small (

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33

D’Auria, F., N. Aksan, and H. Glaeser. "Physical Phenomena in Nuclear Thermal Hydraulics and Current Status." Tecnica Italiana-Italian Journal of Engineering Science 65, no. 1 (2021): 1–11. http://dx.doi.org/10.18280/ti-ijes.650101.

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116 nuclear Thermal-Hydraulic Phenomena T-HP are identified in the present paper, following documents issued during the last three decades by the Committee on the Safety of Nuclear Installations of Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA/CSNI) and by the International Atomic Energy Agency (IAEA). The derived T-HP list includes consideration of experiments performed in Separate Effect Test (SET) and Integral Effect Test (IET) facilities relevant to reactor coolant system and containment of Water Cooled Nuclear Reactors (WCNR). We consider a d

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34

Macdonald, Digby D., George R. Engelhardt, and Andrei Petrov. "A Critical Review of Radiolysis Issues in Water-Cooled Fission and Fusion Reactors: Part I, Assessment of Radiolysis Models." Corrosion and Materials Degradation 3, no. 3 (2022): 470–536. http://dx.doi.org/10.3390/cmd3030028.

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A critical review is presented on modeling of the radiolysis of the coolant water in nuclear power reactors with emphasis on ITER. The review is presented in two parts: In Part I, we assess previous work in terms of compliance with important chemical principles and conclude that no model proposed to date is completely satisfactory, in this regard. Thus, some reactions that have been proposed in various radiolysis models are not elementary in nature and can be decomposed into two or more elementary reactions, some of which are already included in the models. These reactions must be removed in f

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35

Morreale, A. C., M. J. Brown, and S. M. Petoukhov. "PRELIMINARY METHODOLOGY FOR THE ANALYSIS OF THE NATIONAL RESEARCH UNIVERSAL REACTOR USING INTEGRATED SEVERE ACCIDENT MODELLING CODES." AECL Nuclear Review 4, no. 1 (2015): 53–65. http://dx.doi.org/10.12943/anr.2014.00035.

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The National Research Universal (NRU) Reactor is a multi-purpose research reactor located at Atomic Energy of Canada Limited (AECL) Chalk River Laboratories. The severe accident case for the NRU has been explored through deterministic and probabilistic safety analysis (PSA) including multi-level PSAs that detail the progression and consequences of a severe accident in the NRU. These previous calculations lack the interconnected and comprehensive features of a full severe accident modelling code that is now the standard for severe accident analysis of power reactors. It was of interest within A

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36

Takagi, Junichi, and Kenkichi Ishigure. "Thermal Decomposition of Hydrogen Peroxide and Its Effect on Reactor Water Monitoring of Boiling Water Reactors." Nuclear Science and Engineering 89, no. 2 (1985): 177–86. http://dx.doi.org/10.13182/nse85-a18191.

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37

FORD, F. Peter. "Quantitative Prediction of Environmentally Assisted Cracking in Boiling Water Reactors." Proceedings of the Asian Pacific Conference on Fracture and Strength and International Conference on Advanced Technology in Experimental Mechanics 1.01.203 (2001): 27–39. http://dx.doi.org/10.1299/jsmeatemapcfs.1.01.203.0_27.

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38

Espinosa-Paredes, Gilberto, Alfonso Prieto-Guerrero, Alejandro Núñez-Carrera, and Rodolfo Amador-García. "Wavelet-Based Method for Instability Analysis in Boiling Water Reactors." Nuclear Technology 151, no. 3 (2005): 250–60. http://dx.doi.org/10.13182/nt05-a3647.

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39

Farawila, Yousef M., and Douglas W. Pruitt. "Critical Power Response to Power Oscillations in Boiling Water Reactors." Nuclear Science and Engineering 143, no. 3 (2003): 211–25. http://dx.doi.org/10.13182/nse03-a2331.

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40

Forsberg, Charles W. "Passive Emergency Cooling Systems for Boiling Water Reactors (PECOS-BWR)." Nuclear Technology 76, no. 1 (1987): 185–92. http://dx.doi.org/10.13182/nt87-a33909.

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41

Tiftikci, Ali, and Mehmet Türkmen. "Monte Carlo model of annular flow in boiling water reactors." Progress in Nuclear Energy 123 (May 2020): 103307. http://dx.doi.org/10.1016/j.pnucene.2020.103307.

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42

Vook, R. W., T. V. Rao, T. Swirbel, J. Bucci, and W. Meyer. "Thin films for radiation control in boiling water nuclear reactors." Proceedings, annual meeting, Electron Microscopy Society of America 44 (August 1986): 520–21. http://dx.doi.org/10.1017/s0424820100144115.

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Boiling water nuclear reactors (BWR's) experience radioactive film buildup on the inner walls of their out-of-core stainless steel (S.S.) cooling water pipes. These films consist of various oxides of Fe, Cr, and Ni, and contain small amounts of radioactive Co-60. As a result the pipes must be decontaminated or replaced periodically. Efforts are currently being made to passivate these S.S. surfaces so as to reduce the rate of radiation buildup. In the present work, the effects of various protective metallic thin film coatings on the morphology of the radioactive oxide film grown in a simulated

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43

Burte, D. P., and S. G. Vaidya. "Parametrization for optimization of reload patterns for boiling water reactors." Annals of Nuclear Energy 20, no. 4 (1993): 237–49. http://dx.doi.org/10.1016/0306-4549(93)90079-5.

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44

Wang, Haoyu, Andrew Longman, J. Thomas Gruenwald, James Tusar, and Richard Vilim. "Machine-Learning Analysis of Moisture Carryover in Boiling Water Reactors." Nuclear Technology 205, no. 8 (2019): 1003–20. http://dx.doi.org/10.1080/00295450.2019.1583957.

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45

Weeks, John R., Brijesh Vyas, and Hugh S. Isaacs. "Environmental factors influencing stress corrosion cracking in boiling water reactors." Corrosion Science 25, no. 8-9 (1985): 757–68. http://dx.doi.org/10.1016/0010-938x(85)90009-5.

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46

Sikorska, Daria, Julia Brzozowska, Agata Pawełkiewicz, Mateusz Psykała, Przemysław Błasiak, and Piotr Kolasiński. "Convective Heat Transfer in PWR, BWR, CANDU, SMR, and MSR Nuclear Reactors—A Review." Energies 17, no. 15 (2024): 3652. http://dx.doi.org/10.3390/en17153652.

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Nuclear reactors are very complex units in which many physical processes occur simultaneously. Efficient heat removal from the reactor core is the most important of these processes. Heat is removed from the reactor core via heat conduction, radiation, and convection. Thus, convective heat transfer and its conditions play a crucial role in the operation and safety of nuclear reactors. Convective heat transfer in nuclear reactors is a very complex process, which is dependent on many conditions and is usually described by different correlations which combine together the most important criteria n

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47

Paramanantham, SalaiSargunan S., Thanh-Hoang Phan, and Warn-Gyu Park. "Numerical analysis of bubble condensation behavior under high-pressure flow conditions." Proceedings of the Institution of Mechanical Engineers, Part C: Journal of Mechanical Engineering Science 234, no. 18 (2020): 3725–41. http://dx.doi.org/10.1177/0954406220916496.

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Heat transfer during subcooled flow boiling has a pivotal role in pressurized water reactors; it also occurs in boiling water reactors prior to the onset of saturated nucleate boiling. We examined the condensation behavior of vapor bubbles in the subcooled liquid phase using the fully compressible two-phase homogeneous mixture method, solved by an implicit dual-time preconditioned method. The continuous surface force method was applied to determine the surface tension between the phases in the simulation. To predict the empirical coefficient, we conducted a sensitivity study using Lee’s mass t

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48

Wang, Mei-Ya, and Tsung-Kuang Yeh. "Evaluation of Early Hydrogen Water Chemistry on Corrosion Mitigation in Boiling Water Reactors." Nuclear Science and Engineering 186, no. 2 (2017): 180–89. http://dx.doi.org/10.1080/00295639.2016.1273014.

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49

Yefimov, Olexander, Mykola Pylypenko, Larysa Tiutiunyk, Tetyana Harkusha, Tetyana Yesipenko, and Anastasiia Motovilnik. "Construction Materials of Active Zones of New Generation Nuclear Reactors." NTU "KhPI" Bulletin: Power and heat engineering processes and equipment, no. 1-2 (August 7, 2023): 43–46. http://dx.doi.org/10.20998/2078-774x.2023.01.07.

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The materials of the article consider the analysis of construction materials of active zones of new generation nuclear reactors. The analysis reflects general ideas about the development of reactor technologies: in the 1950s and 1960s, the first generation of reactors was created; in the early 1970s, the operation of industrial reactors began - reactors of the second generation: pressurized water reactors (WWER, PWR), boiling water reactors (RBMK, BWR), heavy water reactors (CANDU), as well as gas-cooled reactors (AGR). Further development of some types of reactors made it possible to create r

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50

Xue, He, and Tetsuo Shoji. "Quantitative Prediction of EAC Crack Growth Rate of Sensitized Type 304 Stainless Steel in Boiling Water Reactor Environments Based on EPFEM." Journal of Pressure Vessel Technology 129, no. 3 (2006): 460–67. http://dx.doi.org/10.1115/1.2748827.

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The quantitative prediction of environmentally assisted cracking (EAC) or stress corrosion cracking (SCC) is essential in order to predict service life and also the structural integrity and safety assessment of light water reactors. During the last 3 decades many of the research results obtained on the quantitative prediction of the EAC crack growth rate have been based on linear fracture mechanics. In order to investigate EAC behavior in the high strain zone of important structures in light water reactors, the approach taken in this paper is one in which quantitative calculations of the EAC c

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