Nothing Special   »   [go: up one dir, main page]

Kovacs et al., 2014 - Google Patents

The Nuclear Power Plant with WWER440 Reactors

Kovacs et al., 2014

Document ID
3039352314923936950
Author
Kovacs Z
Kovacs Z
Publication year
Publication venue
Probabilistic Safety Assessment of WWER440 Reactors: Prediction, Quantification and Management of the Risk

External Links

Snippet

The Nuclear Power Plant with WWER440 Reactors | SpringerLink Skip to main content Advertisement SpringerLink Account Menu Find a journal Publish with us Track your research Search Cart Book cover Probabilistic Safety Assessment of WWER440 Reactors pp 7–84Cite …
Continue reading at link.springer.com (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
    • Y02E30/32—Pressurized water 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
    • Y02E60/00—Enabling technologies or technologies with a potential or indirect contribution to GHG emissions mitigation
    • 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
    • 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

Similar Documents

Publication Publication Date Title
Chetal et al. The design of the prototype fast breeder reactor
Hannerz Towards intrinsically safe light-water reactors
Choi Small modular reactors (SMRs): The case of the Republic of Korea
Cisneros et al. Technical Description of the “Mark 1” Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant
Bereznai Nuclear power plant systems and operation
Kovacs Probabilistic Safety Assessment of WWER440 Reactors
Gaudet et al. Conceptual plant layout of the Canadian generation IV supercritical water-cooled reactor
Kovacs et al. The Nuclear Power Plant with WWER440 Reactors
Yetisir et al. Reactor core and plant design concepts of the Canadian supercritical water-cooled reactor
Misak History, specific design features, and evolution of VVER reactors
Shenoy et al. Steam cycle modular helium reactor
Bao et al. Simulation of BWR Mark I Station Black-Out accident using GOTHIC: an initial demonstration
Forsberg Passive emergency cooling systems for boiling water reactors (PECOS-BWR)
Pluta et al. PRISM: An Innovative Inherently Safe Modular Sodium Cooled Breeder Reactor
Bruschi et al. Safety: Evolving Technologies for Tomorrow’s Power Reactors
Schreiber Pressurized Water Reactors (PWRs)
Yan et al. Passive safety systems of advanced nuclear power plant: AP1000
Matsuura et al. Features of BWR plant
Saario APR1400 reactor design elements and advanced features
Zhao et al. Discussion on design of new-style innovative small modular reactor
Erlenwein et al. Assessment of Safety-Relevant Aspects of Kraftwerk Union’s 200-MW (thermal) Nuclear District Heating Plant Concept
Jayanti et al. Preliminary analysis of a small, inherently safe boiling water reactor
Xueqing et al. Advanced passive PWR AC-600: Development orientation of nuclear power reactors in China for the next century
Kunitomi et al. Safety characteristics of GTHTR and safety demonstration test program using HTTR
Built Nam Zin Cho⋅ Han Gon Kim Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon, Korea nzcho@ kaist. ac. kr