Gajewski et al., 1971 - Google Patents

FFTF: COMPANION TEST AND DEVELOPMENT FACILITY FOR THE LMFBR PROGRAM.

Gajewski et al., 1971

View PDF
Document ID
17681202609906513870
Author
Gajewski W
Esselman W
Wolfe B
Taylor J
Publication year

External Links

Snippet

The steadily growing demand for electrical power, coupled with con-stantly increasing costs of fossil fuel, and ever more rigorous anti-pollution requirements, all combine to make nuclear power plants increasingly attractive. In fact, the consensus of those in the power …
Continue reading at www.osti.gov (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
    • 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
    • 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
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • 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
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • 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
    • G21C19/02—Details of handling arrangements
    • 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
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/032—Joints between tubes and vessel walls, e.g. taking into account thermal stresses
    • G21C13/036—Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall

Similar Documents

Publication Publication Date Title
Triplett et al. PRISM: a competitive small modular sodium-cooled reactor
Carelli et al. The design and safety features of the IRIS reactor
Yoo et al. Overall system description and safety characteristics of prototype Gen IV sodium cooled fast reactor in Korea
US4508677A (en) Modular nuclear reactor for a land-based power plant and method for the fabrication, installation and operation thereof
Guidez et al. New reactor safety measures for the european sodium fast reactor—part i: Conceptual design
Koch et al. Construction design of EBR-II: an integrated unmoderated nuclear power plant
Kwant et al. PRISM—liquid metal cooled reactor plant design and performance
JP6381839B1 (en) Reactor shutdown device, reactor shutdown method, and core design method
Gajewski et al. FFTF: COMPANION TEST AND DEVELOPMENT FACILITY FOR THE LMFBR PROGRAM.
Gaudet et al. Conceptual plant layout of the Canadian generation IV supercritical water-cooled reactor
Salerno et al. PRISM concept, modular LMR reactors
Filin et al. Design features of BREST reactors and experimental work to advance the concept of BREST reactors
Yetisir et al. Reactor core and plant design concepts of the Canadian supercritical water-cooled reactor
Wimunc et al. Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW
Marguet Pressurized Water Reactors of the Twenty-First Century
Pluta et al. PRISM: An Innovative Inherently Safe Modular Sodium Cooled Breeder Reactor
Pfeffer et al. Integrated Fast Reactor: PRISM
Alekseev et al. RBEC lead-bismuth cooled fast reactor: Review of conceptual decisions
JP2024514017A (en) Refueling a nuclear reactor
Beeley et al. Operating experience with the sodium reactor experiment and its application to the hallam nuclear power facility
Pal Singh et al. Inherent safety concepts in nuclear power reactors
Ragheb INHERENTLY SAFE REACTORS DESIGNS
Gyorey et al. Prism: Power Reactor-Inherently Safe Module, Nuclear Power for the Next Century
Meyer FRG activities in the framework of IWGATWR
Brynsvold et al. Conceptual Design for 75 MWe Mixed Spectrum Superheating Reactor Power Plant