Relevant bibliographies by topics / Heavy liquid metal fast reactor

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Heavy liquid metal fast reactor'

Author: Grafiati
Published: 22 February 2023

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Journal articles on the topic "Heavy liquid metal fast reactor"

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Dragunova, Anastasiya V., Mikhail S. Morkin, and Vladimir V. Perevezentsev. "Features of methods for monitoring the fuel cladding tightness in lead-cooled fast breeder reactors." Nuclear Energy and Technology 7, no. 4 (2021): 319–25. http://dx.doi.org/10.3897/nucet.7.78372.

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To timely detect failed fuel elements, a reactor plant should be equipped with a fuel cladding tightness monitoring system (FCTMS). In reactors using a heavy liquid-metal coolant (HLMC), the most efficient way to monitor the fuel cladding tightness is by detecting gaseous fission products (GFP). The article describes the basic principles of constructing a FCTMS in liquid-metal-cooled reactors based on the detection of fission products and delayed neutrons. It is noted that in a reactor plant using a HLMC the fuel cladding tightness is the most efficiently monitored by detecting GFPs. The autho
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Shmelev, A. N., G. G. Kulikov, V. A. Apse, E. G. Kulikov, and V. V. Artisyuk. "Radiogenic Lead with Dominant Content of208Pb: New Coolant and Neutron Moderator for Innovative Nuclear Facilities." Science and Technology of Nuclear Installations 2011 (2011): 1–12. http://dx.doi.org/10.1155/2011/252903.

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As a rule materials of small atomic weight (light and heavy water, graphite, and so on) are used as neutron moderators and reflectors. A new very heavy atomic weight moderator is proposed—radiogenic lead consisting mainly of isotope208Pb. It is characterized by extremely low neutron radiative capture cross-section (0.23 mbarn for thermal neutrons, i.e., less than that for graphite and deuterium) and highest albedo of thermal neutrons. It is evaluated that the use of radiogenic lead makes it possible to slow down the chain fission reaction on prompt neutrons in a fast reactor. This can increase
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Neuhausen, Jörg. "Radionuclide Chemistry in Nuclear Facilities Based on Heavy Liquid Metal Coolants: Past, Present and Future." CHIMIA International Journal for Chemistry 74, no. 12 (2020): 976–83. http://dx.doi.org/10.2533/chimia.2020.976.

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Heavy liquid metals such as lead and lead bismuth eutectic (LBE) are considered as spallation target material for next-generation neutron sources and as coolant of fast spectrum nuclear reactors that are developed to facilitate more efficient use of nuclear fuel as well as transmutation of long-lived nuclear waste. During the operation of such facilities, the heavy liquid metal will be activated by nuclear reactions. Additionally, fission product radionuclides may be introduced into the liquid metal from leaking fuel pins or by fission of the target nuclei in spallation. The chemical behaviour
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Samui, Pradeep, and Renu Agarwal. "Thermodynamic Assessment and Solubility of Ni in LBE Coolants." Thermo 2, no. 4 (2022): 371–82. http://dx.doi.org/10.3390/thermo2040025.

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Lead–Bismuth Eutectic (LBE) is a heavy metal liquid alloy used as a coolant for compact high temperature reactors (CHTRs), fast breeder reactor (FBRs) and as a spallation target for ADS. In spite of many advantages due to its thermophysical properties, corrosion towards structural materials remains one of the major issues of LBE. In absence of any oxygen impurity, corrosion in LBE is driven by dissolution processes and the solubility of the main elements of the structural material alloys. Using the CALPHAD method, Thermo-Calc software, a thermodynamic database was developed to assess the inter
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Kotov, Vladimir M. "Thermal Energetic Reactor with High Reproduction of Fission Materials." Science and Technology of Nuclear Installations 2012 (2012): 1–5. http://dx.doi.org/10.1155/2012/534541.

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Existing thermal reactors are energy production scale limited because of low portion of raw uranium usage. Fast reactors are limited by reprocessing need of huge mass of raw uranium at the initial stage of development. The possibility of development of thermal reactors with high fission materials reproduction, which solves the problem, is discussed here. Neutron losses are decreased, uranium-thorium fuel with artificial fission materials equilibrium regime is used, additional in-core and out-core neutron sources are used for supplying of high fission materials reproduction. Liquid salt reactor
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Huang, Xi, Peng Chen, Yuan Yin, et al. "Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors." Nuclear Engineering and Design 361 (May 2020): 110567. http://dx.doi.org/10.1016/j.nucengdes.2020.110567.

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Sorokin, A., Ju Kuzina, and A. Orlov. "EXPERIMENTAL MODELING OF HYDRODYNAMICS AND HEAT TRANSFER IN REACTORS WITH HEAVY LIQUID METAL COOLANTS." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2019, no. 1 (2019): 21–51. http://dx.doi.org/10.55176/2414-1038-2019-1-21-51.

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The similarity analysis and the following criteria as well asymptotic solutions must be fully applied at planning and carry out the experimental study and generalizing its results. As academician S.S. Kutateladze notes "The external simplicity of the foundations of this analysis and the everincreasing multi-parametric nature of the problems for physical and mathematical modeling lead to many misunderstandings and direct mistakes”. Liquid metals form a special class of coolants characterized by a significant volumetric heat capacity and high thermal conductivity, which have the coefficient of k
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Petrović, Đorđe, Matteo Zanetti, Guy Scheveneels, Andrei Rineiski, Xue-Nong Chen, and William D’Haeseleer. "On physics of a hypothetical core disruptive accident in Multipurpose hYbrid Research Reactor for High-tech Applications – MYRRHA." EPJ Nuclear Sciences & Technologies 9 (2023): 4. http://dx.doi.org/10.1051/epjn/2022047.

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The sensitivity of the reactivity of a fast reactor core to changes in its geometry and/or fuel relocation calls for particular attention with regard to criticality events. A category of these events, the so-called Core Disruptive Accidents (CDAs), are intensively studied in the safety assessment of Sodium-cooled Fast Reactors (SFRs), and more recently also in the case of other systems. Differences between SFRs and Heavy Liquid Metal Fast Reactors (HLMFRs) are significant and therefore warrant an understanding of phenomena and the development of models specific to HLMFRs. This paper provides a
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Beznosov, Aleksandr V., Pavel A. Bokov, Aleksandr V. Lvov, Tatyana A. Bokova, Nikita S. Volkov, and Aleksandr R. Marov. "Experimental studies into the performance of the lead coolant axial pump wet ends to justify main circulation pumps for the HMLC reactor plant circuits." Nuclear Energy and Technology 6, no. 3 (2020): 143–47. http://dx.doi.org/10.3897/nucet.6.57736.

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The paper presents the results of the studies to justify the design solutions for the main circulation pumps of the heavy liquid-metal cooled reactor plant circuits. A substantial difference has been shown in the performance of pumps for the heavy liquid-metal coolant transfer. The studies have confirmed the qualitative difference in the cavitation performance of coolants, the state of the gases and vapors they contain, the influence of supply and discharge devices, and the effects of the impeller blade section performance and geometry and the hub-tip ratio on the pump performance. The studies
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Tarantino, Mariano, Massimo Angiolini, Serena Bassini, et al. "Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA." Energies 14, no. 16 (2021): 5157. http://dx.doi.org/10.3390/en14165157.

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The next generation of nuclear energy systems, also known as Generation IV reactors, are being developed to meet the highest targets of safety and reliability, sustainability, economics, proliferation resistance, and physical protection, with improved performances compared with the currently licensed plants or those presently being built. Among the proposed technologies, lead-cooled fast reactors (LFRs) have been identified by nuclear industries in both Western and developing countries as being among the optimal Generation IV candidates. Since 2000, ENEA, the Italian National Agency for New Te
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Dissertations / Theses on the topic "Heavy liquid metal fast reactor"

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Kane, Stephen James. "Two-phase flow of water and steam in a liquid metal fast breeder reactor pipe." Thesis, University of Southampton, 1994. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.261438.

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Lázaro, Chueca Aurelio. "Development, assessment and application of computational tools for design safety analysis of liquid metal cooled fast breeder reactors." Doctoral thesis, Universitat Politècnica de València, 2014. http://hdl.handle.net/10251/39353.

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El Generation IV International Forum (GIF) [1] es un programa internacional dedicado a apoyar, coordinar y dirigir las iniciativas de investigación y desarrollo encaminados a implementar las soluciones tecnológicas que caracterizarán a la siguiente generación de reactores nucleares. Estos reactores se caracterizaran por una gestión más eficiente del combustible nuclear, un incremento en las exigencias de seguridad y una alta competitividad económica. Con tales objetivos, GIF propuso una serie de diseños potencialmente capaces de alcanzarlos. Estos diseños son tecnológicamente muy distintos a
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Kumar, Mithlesh. "Magnetic flux distorsion in two-phase liquid metal flow." Phd thesis, Toulouse, INPT, 2016. http://oatao.univ-toulouse.fr/15854/1/Kumar_1.pdf.

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A Generation IV Sodium cooled Fast Reactor (SFR) is being researched and developed at CEA, Cadarache France under the project named ASTRID. Monitoring gas presence in SFR is important with respect to its safe operation. In accordance with the principles of diversity, techniques based on different measurement principles have been proposed. This thesis concerns the detection and characterization of void using magnetic flux perturbation principle. An Eddy Current Flow Meter (ECFM) device is used for this purpose. From the technological point of view, the objective is to evaluate the feasibility o
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NASCIMENTO, JAMIL A. do. "Avaliacao neutronica de reator carregado com combustivel metalico e refrigerado por chumbo." reponame:Repositório Institucional do IPEN, 2000. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10789.

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Made available in DSpace on 2014-10-09T12:44:01Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:07:25Z (GMT). No. of bitstreams: 1 06864.pdf: 11106654 bytes, checksum: 851c7803db872d59fc1f49dc465fa8af (MD5)<br>Tese (Doutoramento)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Books on the topic "Heavy liquid metal fast reactor"

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Amorosi, A. Summary of Japan's fast reactor program as seen by OAAI visit, October 12-16, 1989. Available from Overseas Advisory Associates, 1989.

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Japan) International Workshop on Ceramic Breeder Blanket Interactions (11th 2003 Mito-shi. Proceedings of the Eleventh International Workshop on Ceramic Breeder Blanket Interactions, December 15-17, 2003, Tokyo, Japan. Japan Atomic Energy Research Institute, 2004.

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Agency, International Atomic Energy. Structural Materials for Heavy Liquid Metal Cooled Fast Reactors. International Atomic Energy Agency, 2021.

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Cochran, Thomas B. The Liquid Metal Fast Breeder Reactor. Routledge, 2015. http://dx.doi.org/10.4324/9781315671642.

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United States. Congress. Office of Technology Assessment., ed. Technical options for the advanced liquid metal reactor. The Office, 1994.

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Cochran, Thomas B. Liquid Metal Fast Breeder Reactor: An Environmental and Economic Critique. Taylor & Francis Group, 2017.

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Cochran, Thomas B. Liquid Metal Fast Breeder Reactor: An Environmental and Economic Critique. Taylor & Francis Group, 2015.

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Liquid Metal Fast Breeder Reactor: An Environmental and Economic Critique. Taylor & Francis Group, 2015.

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Cochran, Thomas B. Liquid Metal Fast Breeder Reactor: An Environmental and Economic Critique. Taylor & Francis Group, 2015.

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L, King T., U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation., and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., eds. Preapplication safety evaluation report for the sodium advanced fast reactor (SAFR) liquid-metal reactor. Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1991.

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Book chapters on the topic "Heavy liquid metal fast reactor"

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Karasev, B. G., I. R. Kirillov, and A. P. Ogorodnikov. "3500 m3/h MHD Pump for Fast Breeder Reactor." In Liquid Metal Magnetohydrodynamics. Springer Netherlands, 1989. http://dx.doi.org/10.1007/978-94-009-0999-1_41.

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Iizawa, K., K. Chatani, K. Ito, S. Suzuki, M. Akutsu, and K. Kinjo. "Transport of Radioactive Corrosion Products in Primary Systems of a Sodium Cooled Fast Reactor." In Liquid Metal Systems. Springer US, 1995. http://dx.doi.org/10.1007/978-1-4615-1977-5_2.

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Sherwood, G. "Liquid Metal Fast Breeder Reactor (LMFBR) Risk Assessment." In Uncertainty in Risk Assessment, Risk Management, and Decision Making. Springer US, 1987. http://dx.doi.org/10.1007/978-1-4684-5317-1_32.

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Lawrence, L. A. J., D. Pullen, I. C. Smith, and S. Orme. "Failsafe Operation of a PES in a Liquid Metal Fast Breeder Reactor Refuelling System." In Safety and Reliability of Programmable Electronic Systems. Springer Netherlands, 1986. http://dx.doi.org/10.1007/978-94-009-4317-9_9.

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Karmakar, Shubhajit, Swarnendu Sen, and Sanjib Kumar Acharyya. "Optimization of Primary Loop Pump Power of a Loop-type Liquid Metal Fast Breeder Reactor with Annular Fuel Using Genetic Algorithm." In Advances in Intelligent Systems and Computing. Springer India, 2014. http://dx.doi.org/10.1007/978-81-322-2217-0_29.

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Smith, Craig F. "Heavy Liquid Metal (HLM) Cooled Fast Small Modular Reactors." In Encyclopedia of Nuclear Energy. Elsevier, 2021. http://dx.doi.org/10.1016/b978-0-12-819725-7.00189-6.

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Kloman, Erasmus H. "The Liquid Metal Fast Breeder Reactor." In Cases in Accountability: the Work of the Gao. Routledge, 2019. http://dx.doi.org/10.4324/9780429050664-3.

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"Chapter 10. Liquid metal cooled fast neutron reactors." In Nuclear Reactor Systems. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-1985-0-013.

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"Chapter 10. Liquid metal cooled fast neutron reactors." In Nuclear Reactor Systems. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-1985-0.c013.

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"APPENDIXES." In The Liquid Metal Fast Breeder Reactor. Routledge, 2015. http://dx.doi.org/10.4324/9781315671642-25.

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Conference papers on the topic "Heavy liquid metal fast reactor"

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Enuma, Yasuhiro, Tomoyasu Mizuno, Takatsugu Mihara, Mamoru Konomura, Makoto Mito, and Mikio Tanji. "HLMC Fast Reactor With Complete Natural Circulation." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22223.

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To seek for a promising concept of a heavy liquid metal coolant (HLMC) fast reactor plant, Japan Nuclear Cycle Development Institute (JNC) and the electric utilities conducted conceptual design study on various types of plant concepts and compared these concepts based on technical feasibility and economical perspective. The Pb-Bi cooled complete natural circulation reactor concept may attain high safety level and construction cost goal (¥200,000/kWe).
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Bokov, P. A., A. V. Beznosov, A. V. Lvov, M. V. Iarmonov, and T. A. Bokova. "The Study of Cavitation Characteristics of a Heavy Liquid-Metal Coolant." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15263.

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Adequate design solution and maintenance of circuits with fast reactors cooled by lead and lead-bismuth coolants require taking into account the peculiarities of hydrodynamics of these coolant flows. The design pressure of saturated vapors of lead and its alloys at temperatures of 400–550 °C is 10 −18−10 −10 atm, which is significantly less than that of sodium or water. Processes of traditional cavitation cannot occur in a flow of heavy liquid-metal coolants because of their specific character. The main circulation pumps of reactor circuits are one of their basic elements. In fact, the flow-ty
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Takahashi, Minoru, Masayuki Igashira, Toru Obara, et al. "Studies on Materials for Heavy-Liquid-Metal-Cooled Reactors in Japan." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22166.

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Recent studies on materials for the development of lead-bismuth (Pb-Bi)-cooled fast reactors (FR) and accelerator-driven sub-critical systems (ADS) in Japan are reported. The measurement of the neutron cross section of Bi to produce 210Po, the removal experiment of Po contamination and steel corrosion test in Pb-Bi flow were performed in Tokyo Institute of Technology. A target material corrosion test was performed in the project of Transmutation Experimental Facility for ADS in Japan Atomic Energy Research Institute (JAERI). Steel corrosion test was started in Mitsui Engineering &amp; Shipbuil
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Antonenkov, M. A., P. A. Bokov, D. V. Kuznetsov, T. A. Bokova, and A. V. Besnosov. "Peculiarities of Friction and Depreciation of Contact Surfaces in High-Temperature Lead and Lead-Bismuth Coolants of Reactor Loops." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29175.

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The increasing interest to reactors of heavy nuclear fission by fast neutrons initiates the research substantiating the operational integrity of mechanisms with contact surfaces in a medium of high-temperature heavy liquid-metal coolants.
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Bokov, P. A., V. S. Baranova, M. S. Kustov, M. A. Antonenkov, A. G. Meluzov, and A. V. Besnosov. "Peculiarities of Hydrodynamics of Lead and Lead-Bismuth Coolant Flows of Reactor Loops." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29173.

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Adequate design engineering and maintenance of circuits with fast neutron reactors cooled with lead and lead-bismuth coolants require considering the peculiarities of hydrodynamics of these coolant flows. It is traditionally reputed that the hydrodynamic characteristics of heavy liquid-metal melts are analogous to the characteristics of water and primary sodium, which is practically valid for the conditions of part of the equipment and channels of a reactor circuit. The main peculiarities of heavy liquid-metal coolants compared to water and primary sodium, which affect the flow characteristics
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Sekimoto, Hiroshi, Shinichi Makino, Kunihiko Nakamura, Yoshio Kamishima, and Takashi Kawakita. "Small LBE-Cooled Fast Reactor for Expanding Market." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22049.

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A long-life safe simple small portable proliferation-resistant reactor is expected to solve many problems associating future energy and globally environmental problems. From discussions on mainly neutronics and safety points it has been shown that the heavy liquid metal cooled fast reactor is the best candidate to satisfy the above requirements. A lead-bismuth-eutectic (LBE) cooled fast reactor LSPR (LBE-Cooled Long-Life Safe Simple Small Portable Proliferation-Resistant Reactor) has been designed and continues to be improved. In the present paper a recent version of LSPR is presented. The tot
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Ma, Juan, and Mei Huang. "Seismic Analysis of Lead-Bismuth-Cooled Fast Reactor Vessel." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15899.

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This paper is aimed at analyzing the structural responses of a Generation IV heavy-liquid-metal-cooled reactor (lead-bismuth-cooled fast reactor) vessel in the event of earthquake. For a seismic design, the seismic time history response analyses are carried out for both a top support type and a bottom support type. It is found that the bottom support type exhibits the better performance. There is the gap between the reactor vessel and guard vessel being filled with [1] argon. It is indispensable to add bellows at vessel upper end for a bottom support type to achieve the connection and seal bet
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Song, Jian, Limin Liu, Simiao Tang, et al. "Implementation of Liquid Metal Properties in RELAP5 MOD3.2 for Safety Analysis of Sodium-Cooled Fast Reactors." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66009.

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Due to great deal of operation experience and technology accumulation, sodium cooled fast reactor (SFR) is the most promising among the six Generation IV reactors, which has advantages of breeding nuclear fuel, transmuting long-lived actinides and good safety characteristics. Thermal-hydraulic computer codes will have to be developed, verified, and validated to support the conceptual and final designs of new SFRs. However, work on developing thermal hydraulic analysis code for SFR is very limited in China, while the common software RELAP5 MOD3 is unable to analyze liquid metal systems. So the
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Makhov, Kirill, Aleksander V. Beznosov, Tatyana Bokova, Artem Shumilkov, Aleksei Chernysh, and Alexander Vladimirovich Knyazev. "Experimental Study of the Wall Boundary Layer “Heavy Liquid-Metal Coolant – Constructional Material” as Applied to Fast Reactors." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30269.

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The specific feature of heavy liquid-metal coolants (HLMC) is the possibility to form solid-phase impurity particles, which requires a deep study of characteristics of the wall boundary layer enriched with impurity particles. This is necessary for a fundamental understanding of the processes occurring on contact surfaces and triboprocesses to validate the use of materials for developing fast reactors with these coolants. The paper deals with results of experimental studies of structures and characteristics of the wall boundary layer. The use of the thermal shock technique enabled us to experim
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Sienicki, James J., and Plamen V. Petkov. "Passive Safety of the STAR-LM HLMC Natural Convection Reactor." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22290.

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The STAR-LM 300 to 400 MWt class modular, factory fabricated, fully transportable, proliferation resistant, autonomous, reactor system achieves passive safety by taking advantage of the intrinsic benefits of inert lead-bismuth eutectic heavy liquid metal coolant, 100+% natural circulation heat transport, a fast neutron spectrum core utilizing high thermal conductivity transuranic nitride fuel, redundant passive air cooling of the outside of the guard/containment vessel driven by natural circulation, and seismic isolation where required by site conditions. Postulated loss-of-heat sink without s
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Reports on the topic "Heavy liquid metal fast reactor"

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Homan, F. (Liquid metal reactor/fast breeder reactor research and development). Office of Scientific and Technical Information (OSTI), 1990. http://dx.doi.org/10.2172/7177367.

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Van Tuyle, G. J., G. C. Slovik, B. C. Chan, R. J. Kennett, H. S. Cheng, and P. G. Kroeger. Summary of advanced LMR (Liquid Metal Reactor) evaluations: PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor). Office of Scientific and Technical Information (OSTI), 1989. http://dx.doi.org/10.2172/5491968.

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John D. Bess. Evaluation of the Initial Isothermal Physics Measurements at the Fast Flux Test Facility, a Prototypic Liquid Metal Fast Breeder Reactor. Office of Scientific and Technical Information (OSTI), 2010. http://dx.doi.org/10.2172/983334.

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Denman, Matthew R., Katrina M. Groth, Jeffrey N. Cardoni, and Timothy A. Wheeler. Advance Liquid Metal Reactor Discrete Dynamic Event Tree/Bayesian Network Analysis and Incident Management Guidelines (Risk Management for Sodium Fast Reactors). Office of Scientific and Technical Information (OSTI), 2015. http://dx.doi.org/10.2172/1177842.

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