[go: up one dir, main page]
More Web Proxy on the site http://driver.im/

Zhao et al., 2016 - Google Patents

CFD analysis of the primary cooling system for the small modular natural circulation lead cooled fast reactor SNRLFR‐100

Zhao et al., 2016

View PDF @Full View
Document ID
1215853340416372421
Author
Zhao P
Shi K
Li S
Feng J
Chen H
Publication year
Publication venue
Science and Technology of Nuclear Installations

External Links

Snippet

Small modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast reactor (LFR) is one of the most promising advanced reactors which are able to meet the safety economic goals of Gen‐IV nuclear energy systems. A small modular natural …
Continue reading at onlinelibrary.wiley.com (PDF) (other versions)

Classifications

    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y02E30/40—Other aspects relating to nuclear fission
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y02E30/34—Fast breeder reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24—Promoting flow of the coolant
    • G21C15/243—Promoting flow of the coolant for liquids
    • G21C15/247—Promoting flow of the coolant for liquids for liquid metals
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactors
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator; Metal cooled reactors; Fast breeders
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactors
    • G21C1/04—Thermal reactors; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E60/00—Enabling technologies or technologies with a potential or indirect contribution to GHG emissions mitigation
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E10/00—Energy generation through renewable energy sources
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel

Similar Documents

Publication Publication Date Title
Zhang et al. Review of conceptual design and fundamental research of molten salt reactors in China
Allison et al. Role of RELAP/SCDAPSIM in nuclear safety
Kim et al. Design Concept of Advanced Sodium‐Cooled Fast Reactor and Related R&D in Korea
Chen et al. Preliminary design of a medium‐power modular lead‐cooled fast reactor with the application of optimization methods
Zhao et al. CFD analysis of the primary cooling system for the small modular natural circulation lead cooled fast reactor SNRLFR‐100
Faghihi et al. Neutronics and sub-channel thermal-hydraulics analysis of the Iranian VVER-1000 fuel bundle
Zheng et al. Study on the DLOFC and PLOFC accidents of the 200 MWe pebble-bed modular high temperature gas-cooled reactor with TINTE and SPECTRA codes
Khan et al. Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor
Shin et al. Natural circulation with DOWTHERM RP and its MARS code implementation for molten salt‐cooled reactors
Uitslag-Doolaard et al. Multiscale modelling of the phénix dissymmetric test benchmark
Alkaabi et al. Benchmarking COMSOL Multiphysics Single‐Subchannel Thermal‐Hydraulic Analysis of a TRIGA Reactor with RELAP5 Results and Experimental Data
Wang et al. Multiscale thermal hydraulic study under the inadvertent safety injection system operation scenario of typical pressurized water reactor
Wang et al. Thermal hydraulics analysis of the advanced high temperature reactor
Wang et al. Sub‐channel analysis for Pb‐Bi‐cooled direct contact boiling water fast reactor
Bassi et al. Reliability Assessment of 2400 MWth Gas‐Cooled Fast Reactor Natural Circulation Decay Heat Removal in Pressurized Situations
Hu et al. Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor
Bhowmik Nanofluid operation and valve engineering of super for small unit passive enclosed reactor
Sun et al. Transient Study on the HTR‐PM with TINTE‐vPower Coupling Code Package
Larsen et al. Thermal design and analysis of a passive modular molten salt microreactor concept
Valinčius et al. Modelling of Severe Accident and In‐Vessel Melt Retention Possibilities in BWR Type Reactor
Zhou et al. Phenomena identification and ranking table of station blackout accidents for China sodium cooled fast reactor
Chenu Single-and two-phase flow modeling for coupled neutronics/thermal-hydraulics transient analysis of Advanced Sodium-Cooled Fast Reactors
Lyu et al. Benchmark Analysis on Loss‐of‐Flow‐without‐Scram Test of FFTF Using Refined SAC‐3D Models
Chang et al. Model development for analysis of the Korea advanced liquid metal reactor
Krumwiede et al. Design of the Mark-1 pebble-bed, fluoride-salt-cooled, high-temperature reactor commercial power plant