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

Zedler et al., 2020 - Google Patents

Experimental study of the influence of cross-overflow on the decay heat removal from spent fuel pools

Zedler et al., 2020

View PDF
Document ID
4998506168989541462
Author
Zedler P
Schuster C
Lippmann W
Hurtado A
Publication year
Publication venue
Experimental and Computational Multiphase Flow

External Links

Snippet

In the case of failure of cooling systems or structures in spent fuel pools (SFP), the decay heat removal must be guaranteed to prevent a fission product release. The heat, generated by the fuel assemblies (FA), causes a water level decrease, when heat removal systems fail …
Continue reading at www.academia.edu (PDF) (other versions)

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • 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
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control

Similar Documents

Publication Publication Date Title
Henry et al. Natural and mixed convection in the cylindrical pool of TRIGA reactor
EP1775732A1 (en) A method of estimating dryout properties in a nuclear light water reactor
Chatzidakis et al. Evaluation of RELAP5/MOD3 behavior against loss of flow experimental results from two research reactor facilities
Zedler et al. Experimental study of the influence of cross-overflow on the decay heat removal from spent fuel pools
Lisowski et al. Experimental observations of natural circulation flow in the NSTF
Rohde et al. Investigating the ESBWR stability with experimental and numerical tools: a comparative study
Andreani et al. Gas mixing caused by interacting heat sources. Part ii: Modelling
Feng et al. Dynamic response of the HTR-10 under the control rod withdrawal test without scram
Farahani et al. Sensitivity analysis for thermo-hydraulics model of a Westinghouse type PWR: verification of the simulation results
Gutowska Study on depressurized loss of coolant accident and its mitigation method framework at very high temperature gas cooled reactor
Sung et al. COBRA-TF Evaluation and application for PWR steamline break DNB analysis
Zhukov et al. Emergency cooling down of fast-neutron reactors by natural convection (a review)
D'Auria The BWR stability issue
Lisowski et al. Experimental observations of natural circulation flow in the nstf at steady-state conditions
Talley et al. Razorback–A reactor transient analysis code for large rapid reactivity additions in a natural circulation research reactor
Saraswat et al. Validation and Verification of ASYST Code for Predicting Condensation Phenomena in Nuclear Reactor Safety Systems
Hong et al. Validation of GAMMA+ code for SFR application using FFTF loss-of-flow-without-scram test results
Brillant et al. Rod bundle cooling by a spray system in spent fuel pool accident conditions
Unver Analysis of the Thermal-Hydraulic Response of the Reactor Cavity Cooling System During Accident Scenarios Using the RELAP5/SCDAPSIM System Code
Frisani Analysis of the reactor cavity cooling system for very high temperature gas-cooled reactors using computational fluid dynamics tools
Chahi et al. Thermal-hydraulic investigations to the flow of model gases at a PWR fuel assembly dummy and overflow of air above the top of the dummy
Pehlivan Investigation of the Reactor Cavity Cooling System Experimental Facility with RELAP5/SCDAPSIM System Code
Zhao LEU-HEU Mixed Core Conversion Thermal-hydraulic Analysis and Coolant System Upgrade Assessment for the MIT Research Reactor
Chatzidakis et al. An algorithmic approach for RELAP5/MOD3 reactivity insertion analysis in research reactors
Paramonov et al. The Flow Field in a Reactor Core and its Effect on Rod Vibration and Wear