[go: up one dir, main page]

Forsberg et al., 2008 - Google Patents

Design options for the advanced high-temperature reactor

Forsberg et al., 2008

View PDF
Document ID
9784704263759521318
Author
Forsberg C
Peterson P
Kochendarfer R
et al.
Publication year
Publication venue
Proceedings of ICAPP

External Links

Snippet

The Advanced High-Temperature Reactor (AHTR) is a new reactor concept under development that uses a solid high-temperature fuel and a liquid fluoride salt coolant. Depending upon the specific salt coolant that is selected, the liquid melting point of the …
Continue reading at www.researchgate.net (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
    • 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
    • Y02E30/38—Fuel
    • 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
    • G21C1/07—Pebble-bed reactors; Reactors with granular fuel
    • 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
    • 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
    • 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
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326—Bundles 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
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21Y—INDEXING 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
    • G21Y2002/00—PROBLEM
    • G21Y2002/201—Inadequate efficiency

Similar Documents

Publication Publication Date Title
Yoo et al. Overall system description and safety characteristics of prototype Gen IV sodium cooled fast reactor in Korea
Sinha et al. Design and development of the AHWR—the Indian thorium fuelled innovative nuclear reactor
Triplett et al. PRISM: a competitive small modular sodium-cooled reactor
Carelli et al. The design and safety features of the IRIS reactor
Forsberg et al. Design options for the advanced high-temperature reactor
Dai Thorium molten salt reactor nuclear energy system
Greene et al. Pre-conceptual design of a fluoride-salt-cooled small modular advanced high temperature reactor (SmAHTR)
Wu et al. A novel concept for a molten salt reactor moderated by heavy water
Carre et al. Update of the French R&D strategy on gas-cooled reactors
Song Small modular reactors (SMRs): The case of China
Orlov et al. Heavy liquid metal cooled fast reactors: peculiarities and development status of the major projects
Forsberg Thermal-and fast-spectrum molten salt reactors for actinide burning and fuel production
Cisneros et al. Technical Description of the “Mark 1” Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant
US20240371535A1 (en) Nuclear Reactor with Liquid Coolant and Solid Fuel Assemblies, Integrating a System of Evacuation of the Nominal Power with Liquid Metal Bath and Material(s) (MCP) for the Evacuation of the Residual Power in the Event of an Accident
Pope et al. Experimental Breeder Reactor II
Todreas et al. Flexible conversion ratio fast reactors: Overview
Forsberg Goals, requirements, and design implications for the advanced high-temperature reactor
Saraf et al. Molten salt reactors and their development over the years-a review
Peterson et al. A flexible baseline design for the advanced high temperature reactor using metallic internals (AHTR-MI)
Forsberg The Advanced High-Temperature Reactor: High-Temperature Fuel, Molten Salt Coolant, and Liquid-Metal Reactor Plant
Koster et al. Pebble-bed modular reactor: a generation IV high-temperature gas-cooled reactor
Mikityuk et al. RBEC-M lead-bismuth cooled fast reactor: optimization of conceptual decisions
US20240304344A1 (en) Nuclear reactor with liquid heat transfer and solid fuel assemblies, integrating a nominal power evacuation system with a liquid metal bath and material(s) (mcp) for the evacuation of residual power in the event of an accident
Ragheb Fourth generation reactor concepts
Greenspan STAR: The Secure Transportable Autonomous Reactor System-Encapsulated Fission Heat Source