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Alleblas J. Analyzing the Role of Values and Ideals in the Development of Energy Systems: How Values, Their Idealizations, and Technologies Shape Political Decision-Making. SCIENCE AND ENGINEERING ETHICS 2024; 30:8. [PMID: 38421561 PMCID: PMC10904412 DOI: 10.1007/s11948-024-00463-7] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Grants] [Track Full Text] [Subscribe] [Scholar Register] [Received: 05/20/2021] [Accepted: 11/30/2023] [Indexed: 03/02/2024]
Abstract
This study examines an important aspect of energy history and policy: the intertwinement of energy technologies with ideals. Ideals play an important role in energy visions and innovation pathways. Aspirations to realize technical, social, and political ideals indicate a long-term commitment in the design of energy systems, distinguishable from commitment to other abstract goals, such as values. This study offers an analytical scheme that could help to conceptualize these differences and their impact on energy policy. In the proposed model, two spheres of interaction are highlighted: a material sphere in which values and technologies co-evolve, and an imaginary sphere in which ideals interact with idealized technologies. Furthermore, the relation between these two spheres can be understood in different ways. This study examines three cases that are illustrative of the different roles of ideals in the development of energy technologies and visions: (1) the evolution of safety in nuclear reactor design; (2) visions of atomic power in France; (3) the political idealization of a tidal power scheme in the Severn Estuary. Finally, the developed model implies more general insights for the development of sociotechnical systems. Amongst others, it shows why certain projects and technologies remain a political, but not a techno-economic option.
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Affiliation(s)
- Joost Alleblas
- Department of Values, Technology and Innovation, Technical University Delft, Delft, The Netherlands.
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2
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Thermal design and analysis of a passive modular molten salt microreactor concept. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2022.112107] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/23/2022]
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3
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Kotb SA, Zaky MM, Elbaset AA, Morad M. Application of hybrid renewable energy for supplying the emergency power supply system in case of station blackout in nuclear power plant. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109222] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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4
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Reliability analysis of passive systems: An overview, status and research expectations. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2021.104057] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Li Y, Zhang D, Sun D, Zan Y, Xi Z, Zhuo W, Li P. Experimental investigation on steam contact condensation in emergency makeup tank. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111470] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Wang D, Jiang J, Liu Y. Relaxation of the requirements on loop height and heat transfer area of a passive heat removal system in integral SMR using a self-powered booster. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108539] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Su Q, Xu H, Lu D, Wu X, Yao X, Lu X, Zhang J, Niu W. Experimental study on capability and start-up characteristic of advanced secondary passive residual heat removal system. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103929] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Li Y, Song P, Feng T, Wang M, Zhang D, Tian W, Qiu S. Numerical study on improved design of passive residual heat removal system for China pressurizer reactor. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111087] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Wang M, Manera A, Petrov V, Memmott MJ, Qiu S, Su G. Passive decay heat removal system design for the integral inherent safety light water reactor (I2S-LWR). ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.106987] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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10
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Reliability assessment of passive systems using artificial neural network based response surface methodology. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107487] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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11
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Tripathi M, Singh LK, Singh S. Dynamic reliability framework for a Nuclear Power Plant using dynamic flowgraph methodology. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107467] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Li Y, He C, Qiu J, Tan S, Hou X, Li L, Xiao Q. Numerical study on transient response characteristics of natural circulation in coupled loops under ocean condition. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2020.103248] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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Olatubosun SA. Numerical approach for estimating the conditions for natural circulation in a simple nuclear passive system. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107350] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Na MW, Shin D, Park JH, Lee JI, Kim SJ. Indefinite sustainability of passive residual heat removal system of small modular reactor using dry air cooling tower. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2019.11.003] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Lyu X, Peng M, Xia G. Analysis of start-up and long-term operation characteristics of passive residual heat removal system. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.02.033] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Hou Y, Wang M, Zhang J, Qiu S, Su G, Tian W. Comparative analysis of auxiliary feedwater system and passive safety system under typical accident scenarios for integrated pressurized water reactor (IPWR). PROGRESS IN NUCLEAR ENERGY 2019. [DOI: 10.1016/j.pnucene.2019.03.020] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Olatubosun SA, Zhang Z. Screening of critical parameters influencing thermal-hydraulic reliability of simple passive system. J NUCL SCI TECHNOL 2019. [DOI: 10.1080/00223131.2019.1612794] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Affiliation(s)
- Samuel Abiodun Olatubosun
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin, China
- Nigeria Atomic Energy Commission, Abuja, Nigeria
| | - Zhijian Zhang
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin, China
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Al Zubaidi FN, Walton KL, Tompson RV, Ghosh TK, Loyalka SK. The Effect of Long-Term Oxidation on the Total Hemispherical Emissivity of Type 316L Stainless Steel. NUCL TECHNOL 2018. [DOI: 10.1080/00295450.2018.1542257] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
Affiliation(s)
- Faten N. Al Zubaidi
- Technology University, Department of Electromechanical Engineering, Baghdad, Iraq
- University of Missouri, Mechanical and Aerospace Engineering, Columbia, Missouri 65211
| | - Kyle L. Walton
- University of Missouri, Nuclear Science & Engineering Institute and Particulate Systems Research Center, Columbia, Missouri 65211
| | - Robert V. Tompson
- University of Missouri, Mechanical and Aerospace Engineering, Columbia, Missouri 65211
- University of Missouri, Nuclear Science & Engineering Institute and Particulate Systems Research Center, Columbia, Missouri 65211
| | - Tushar K. Ghosh
- University of Missouri, Nuclear Science & Engineering Institute and Particulate Systems Research Center, Columbia, Missouri 65211
- University of Missouri, Chemical Engineering, Columbia, Missouri 65211
| | - Sudarshan K. Loyalka
- University of Missouri, Mechanical and Aerospace Engineering, Columbia, Missouri 65211
- University of Missouri, Nuclear Science & Engineering Institute and Particulate Systems Research Center, Columbia, Missouri 65211
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Zhu H, Zhang S, Xia G, Peng M. Analysis of operating characteristics of IPWR under natural circulation. KERNTECHNIK 2018. [DOI: 10.3139/124.110942] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
AbstractMany integrated pressurized water reactor (IPWR) designs using natural circulation operation mainly to enhance their inherent safety. The operating characteristics of primary coolant are completely different without mechanical pumps. The designs and safety analysis of forced circulation reactors are widely researched, but the natural circulation characteristics of IPWR have not been well studied by literatures. The present work discussed the thermal-hydraulic characteristics of IPWR under natural circulation conditions by using the best estimate codes RELAP5. And the effect of system parameters on natural circulation characteristics of IPWR is also studied. The results show that, the primary coolant average temperature and steam pressure are two key parameters that affect the natural circulation stable operating load. The set value of primary coolant average temperature effects the core outlet temperature and the steam temperature, but the primary coolant flow is basically the same under different primary coolant average temperature but same load conditions. The smaller steam pressure is more conducive to produce superheated steam, but there is risk of two phase flow instability in OTSG secondary side. The rapid load change process under natural circulation indicating that the reactor has a good load tracking characteristics under natural circulation, but the rapid change of primary coolant temperature will cause oscillations in system parameters.
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Affiliation(s)
- H. Zhu
- 1Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin City 150001, China
| | - S. Zhang
- 2School of Energy and Power Engineering, Beijing University of Aeronautics and Astronautics, Beijing 100191, China
| | - G. Xia
- 1Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin City 150001, China
| | - M. Peng
- 1Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin City 150001, China
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Solanki R, Kulkarni HD, Singh S, Verma A, Varde P. Optimization of regression model using principal component regression method in passive system reliability assessment. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2017.11.012] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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22
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Sun D, Xi Z, Li Y, Zan Y, Xiong W, Li P, Zhuo W. Experimental investigation on natural circulation characteristics of emergency passive residual heat removal system in HPR1000. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2017.11.001] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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23
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24
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Heat transfer and flow characteristics of a cooling thimble in a molten salt reactor residual heat removal system. NUCLEAR ENGINEERING AND TECHNOLOGY 2017. [DOI: 10.1016/j.net.2017.07.026] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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25
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Experimental evaluation of safety performance of emergency passive residual heat removal system in HPR1000. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.04.003] [Citation(s) in RCA: 14] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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26
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Carlsson J, Wider HU. Safety Investigation of Liquid-Metal-Cooled Nuclear Systems with Heat Exchanger in the Risers of Simple Flow-Path Pool Design. NUCL TECHNOL 2017. [DOI: 10.13182/nt05-a3679] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Johan Carlsson
- European Commission-DG Joint Research Centre, Institute for Energy, NL-1755 LE Petten, Netherlands
| | - Hartmut U. Wider
- European Commission-DG Joint Research Centre, Institute for Energy, NL-1755 LE Petten, Netherlands
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Jeon IS, Han SH, Kang SH, Kang HG. Development of a feed-and-bleed operation strategy with hybrid-SIT under low pressure condition of PWR. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.02.003] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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28
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Yang Z, Shan J, Gou J. Preliminary assessment of a combined passive safety system for typical 3-loop PWR CPR1000. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2016.11.020] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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29
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Butt HN, Ilyas M, Ahmad M, Aydogan F. Assessment of passive safety system of a Small Modular Reactor (SMR). ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2016.07.018] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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30
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Design and analysis of a new passive residual heat removal system. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.03.020] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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31
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Rao Y, Yu L, Li W, Zhang F. A choice of pure steam vertical in-tube condensation model for simulating a passive residual heat removal system. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2015.07.039] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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32
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Cadini F, Gioletta A, Zio E. Estimation of passive systems functional failure probabilities by the modified meta-IS algorithm. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2015.01.014] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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33
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Passive systems failure probability estimation by the meta-AK-IS 2 algorithm. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.06.025] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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34
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Xia G, Peng M, Du X. Calculation analysis on the natural circulation of a passive residual heat removal system for IPWR. ANN NUCL ENERGY 2014. [DOI: 10.1016/j.anucene.2014.02.018] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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35
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Papini D, Adamsson C, Andreani M, Prasser HM. Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.08.007] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Sun L, Sun L, Yan C, Fa D, Wang N. Conceptual design and analysis of a passive residual heat removal system for a 10 MW molten salt reactor experiment. PROGRESS IN NUCLEAR ENERGY 2014. [DOI: 10.1016/j.pnucene.2013.09.013] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Vinod V, Krishnakumar S, Punniyamoorthy R, Vijayakumar G, Chandramouli S, Padmakumar G, Nashine B, Rajan K. Experimental evaluation of safety grade decay heat removal in prototype fast breeder reactor. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.08.072] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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KUMAR MUKESH, NAYAK AK, JAIN V, VIJAYAN PK, VAZE KK. MANAGING A PROLONGED STATION BLACKOUT CONDITION IN AHWR BY PASSIVE MEANS. NUCLEAR ENGINEERING AND TECHNOLOGY 2013. [DOI: 10.5516/net.02.2012.086] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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40
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Gandhi MS, Joshi JB, Vijayan PK. Study of two phase thermal stratification in cylindrical vessels: CFD simulations and PIV measurements. Chem Eng Sci 2013. [DOI: 10.1016/j.ces.2013.04.051] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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The comparison of designed water-cooled and air-cooled passive residual heat removal system for 300MW nuclear power plant during the feed-water line break scenario. ANN NUCL ENERGY 2013. [DOI: 10.1016/j.anucene.2013.01.027] [Citation(s) in RCA: 17] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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42
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Wang M, Zhao H, Zhang Y, Su G, Tian W, Qiu S. Research on the designed emergency passive residual heat removal system during the station blackout scenario for CPR1000. ANN NUCL ENERGY 2012. [DOI: 10.1016/j.anucene.2012.03.004] [Citation(s) in RCA: 49] [Impact Index Per Article: 3.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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43
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OHNUKI A, AKIMOTO H. Model Development for Bubble Turbulent Diffusion and Bubble Diameter in Large Vertical Pipes. J NUCL SCI TECHNOL 2012. [DOI: 10.1080/18811248.2001.9715138] [Citation(s) in RCA: 10] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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44
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Design and transient analyses of emergency passive residual heat removal system of CPR1000. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2011.09.036] [Citation(s) in RCA: 26] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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45
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Zhang Y, Qiu S, Su G, Tian W. Design and transient analyses of emergency passive residual heat removal system of CPR1000. Part Ⅰ: Air cooling condition. PROGRESS IN NUCLEAR ENERGY 2011. [DOI: 10.1016/j.pnucene.2011.03.001] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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46
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Zio E, Pedroni N. How to effectively compute the reliability of a thermal–hydraulic nuclear passive system. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2010.10.029] [Citation(s) in RCA: 31] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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47
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Han SJ, Yang JE. A quantitative evaluation of reliability of passive systems within probabilistic safety assessment framework for VHTR. ANN NUCL ENERGY 2010. [DOI: 10.1016/j.anucene.2009.12.004] [Citation(s) in RCA: 17] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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48
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GU H, YAN C, SUN L. Experimental Study on the Fluid Stratification Mechanism in the Density Lock. J NUCL SCI TECHNOL 2009. [DOI: 10.1080/18811248.2009.9711601] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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49
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Zio E, Pedroni N. Estimation of the functional failure probability of a thermal–hydraulic passive system by Subset Simulation. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2008.11.005] [Citation(s) in RCA: 50] [Impact Index Per Article: 3.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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50
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