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

Heidet et al., 2012 - Google Patents

Feasibility of lead cooled breed and burn reactors

Heidet et al., 2012

View PDF
Document ID
10761888161931900724
Author
Heidet F
Greenspan E
Publication year
Publication venue
Progress in Nuclear Energy

External Links

Snippet

The objective of the present work is to assess the feasibility and achievable performance of a large Breed-and-Burn (B&B) reactor core that is cooled with heavy-liquid-metal (HLM), such as lead or lead-bismuth eutectic (LBE), relative to a sodium-cooled B&B core. With the …
Continue reading at www.academia.edu (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
    • Y02E30/40Other 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
    • Y02E30/38Fuel
    • 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
    • Y02E30/34Fast breeder reactors
    • 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
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactors
    • G21C1/02Fast fission reactors, i.e. reactors not using a moderator; Metal cooled reactors; Fast breeders
    • 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
    • G21Y2002/00PROBLEM
    • G21Y2002/201Inadequate efficiency
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • 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
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control

Similar Documents

Publication Publication Date Title
Bortot et al. Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator
Gorton et al. Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR
Sobolev et al. Design of a fuel element for a lead-cooled fast reactor
Permana Basic design analysis of a heavy water-cooled thorium breeder reactor
Rineiski et al. ESFR-SMART core safety measures and their preliminary assessment
Wu et al. Neutronics analysis of the dual-cooled waste transmutation blanket for the FDS
Chen et al. Comparative studies of CERCER and CERMET fuels for EFIT from the viewpoint of core performance and safety
Heidet et al. Feasibility of lead cooled breed and burn reactors
Blanchet et al. Control rod depletion in sodium-cooled fast reactor: models and impact on reactivity control
Irwanto et al. Burnup characteristics of a peu à peu fuel loading scheme in a 110MWt simplified pebble bed reactor
Hino et al. Core design and analysis of axially heterogeneous boiling water reactor for burning transuranium elements
Faghihi et al. Shut-down margin study for the next generation VVER-1000 reactor including 13× 13 hexagonal annular assemblies
Weaver et al. A once-through fuel cycle for fast reactors
Chaudri et al. Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR
Heidet et al. Superprism-sized breed-and-burn sodium-cooled core performance
Okawa et al. Design study on Pb-208 cooled CANDLE burning reactors toward practical application for future nuclear energy source
Ponomarev et al. Superphénix benchmark Part II: transient results
Hartanto et al. An optimization study on the excess reactivity in a linear breed-and-burn fast reactor (B&BR)
Zhang et al. SFR with once-through depleted uranium breed & burn blanket
Hoang et al. Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling
Akie et al. Core design study on rock-like oxide fuel light water reactor and improvements of core characteristics
Okawa et al. Design study on power flattening to sodium cooled large-scale CANDLE burning core with using thorium fuel
Maráczy et al. HPLWR equilibrium core design with the KARATE code system
Yu et al. A study on the burn-up characteristics of inert matrix fuels
Permana et al. Breeding and void reactivity analysis on heavy metal closed-cycle water cooled thorium reactor