[go: up one dir, main page]

Lee et al., 2024 - Google Patents

i-SMR Core Design Option Study with Gadolinium Nitride Coating Burnable Absorber

Lee et al., 2024

View PDF
Document ID
18102381815111402009
Author
Lee W
Cho S
Hong S
Publication year
Publication venue
Transactions of the Korean Nuclear Society Autumn Meeting Changwon, Korea

External Links

Snippet

Soluble boron-free (SBF) operation enhances reactor safety by reducing liquid radioactive waste, eliminating corrosion issues caused by boric acid in the primary coolant system, and providing inherent safety through a more negative moderator temperature coefficient (MTC) …
Continue reading at www.kns.org (PDF) (other versions)

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/38Fuel
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/40Other aspects relating to nuclear fission
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/34Fast breeder reactors
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/39Control of nuclear reactions
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E60/00Enabling technologies or technologies with a potential or indirect contribution to GHG emissions mitigation
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21YINDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
    • G21Y2004/00SOLUTION
    • G21Y2004/10Compositions

Similar Documents

Publication Publication Date Title
Kodochigov et al. Neutronic features of the GT-MHR reactor
Lu et al. Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost
WO1995015564A1 (en) A bwr fuel assembly
CN101206930B (en) Method for cycle using multi-stack combined nuclear fuel
Awan et al. Neutronic design study of a small modular IPWR loaded with accident tolerant-fully ceramic micro-encapsulated (AT-FCM) fuel
Handwerk et al. Optimized core design of a supercritical carbon dioxide-cooled fast reactor
Mitachi et al. Three-region core design for 200-MW (electric) molten-salt reactor with thorium-uranium fuel
WO1993016477A1 (en) Nonproliferative light water nuclear reactor with economic use of thorium
Chang et al. Thorium-based fuel cycles in the modular high temperature reactor
Lee et al. i-SMR Core Design Option Study with Gadolinium Nitride Coating Burnable Absorber
WO2001082306A2 (en) Method of incineration of minor actinides in nuclear reactors
US20090268861A1 (en) Plutonium/Zirconium Hydride/Thorium Fuel Matrix
Odeh et al. Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50)
Kloosterman et al. Plutonium recycling in pressurized water reactors: influence of the moderator-to-fuel ratio
Leer et al. Fast modular reactor nuclear design parameters of fuel cycle and power distributions
Mohamed Design of a PWR for long cycle and direct recycling of spent fuel
Kim et al. Comparison of Core Design Parameters for BANDI-60 Using UO2 and U-Mo Fuels
Goto et al. Development of Security and Safety Fuel for Pu-Burner HTGR: Part 2—Design Study of Fuel and Reactor Core
Kloosterman Multiple recycling of plutonium in advanced PWRs
Hino et al. Application of the resource-renewable boiling water reactor for TRU management and long-term energy supply
Nguyen et al. High-performance multi-batch fuel managements for the advanced soluble-boron-free ATOM core
Ye et al. Neutronics Study and Conceptual Design for Small Sodium-Cooled-Fast-Reactor With Annular Fuel
Fetterman Advanced first core design for the Westinghouse AP1000
Märkl et al. Advanced core and fuel design for light water reactors
Zhu et al. Neutronic design and fuel cycle analysis of a fluoride salt-cooled High Temperature Reactor (FHR)