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

Alawad, 2020 - Google Patents

Thermal–hydraulic phenomenology analysis and RELAP5/MOD3. 3 code assessment for ATLAS 1% upper head SBLOCA test

Alawad, 2020

View PDF
Document ID
3027586506943845300
Author
Alawad A
Publication year

External Links

Snippet

In 2002, vessel head wall thinning that was identified at the Davis Besse reactor in the US shaded the lights on the importance of SB-LOCA's in the upper head of RPV. The lower rates of coolant discharge through the break and primary circuit depressurization are the …
Continue reading at upcommons.upc.edu (PDF) (other versions)

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • 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
    • GPHYSICS
    • G06COMPUTING; CALCULATING; COUNTING
    • G06FELECTRICAL DIGITAL DATA PROCESSING
    • G06F17/00Digital computing or data processing equipment or methods, specially adapted for specific functions
    • G06F17/50Computer-aided design
    • G06F17/5009Computer-aided design using simulation
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24Promoting flow of the coolant
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control
    • G21D2003/002Core design; Core simulations
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/08Regulation of any parameters in the plant

Similar Documents

Publication Publication Date Title
Hainoun et al. International benchmark study of advanced thermal hydraulic safety analysis codes against measurements on IEA-R1 research reactor
Silde et al. Containment model library of the Apros process simulation software: an overview of development and validation work
Kliem et al. Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high-resolution measurement techniques and numerical modeling
Casamor et al. Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison
Umminger et al. Restart of natural circulation in a PWR–PKL test results and s-relap5 calculations
Lorduy-Alós et al. Appliance of scaling methodologies for designing counterpart experiments dominated by natural circulation phenomena
Xu Improvement of PWR (LOCA) safety analysis based on PKL experimental data
D'Auria et al. V&V&C in nuclear reactor thermal-hydraulics
Alawad Thermal–hydraulic phenomenology analysis and RELAP5/MOD3. 3 code assessment for ATLAS 1% upper head SBLOCA test
Jin et al. Development of a new spacer grid pressure drop model in rod bundle for the post-dryout two-phase flow regime during reflood transients
Grahn et al. Modelling of complex boron dilution transients in PWRs—Validation of CFD simulation with ANSYS CFX against the ROCOM E2. 3 experiment
Bestion et al. Recommendation on use of CFD codes for nuclear reactor safety analysis
Martínez Quiroga Scaling-up methodology: a systematical procedure for qualifying NPP nodalizations. Application to the OECD/NEA ROSA-2 and PKL-2 Counterpart test
Takeda ROSA/LSTF test and RELAP5 code analyses on PWR hot leg small-break LOCA with accident management measure based on core exit temperature and PKL counterpart test
Trewin et al. Evaluation of Uncertainties in Thermal-Hydraulic Analyses of PTS for the APAL European Project
Bertolotto Coupling a system code with computational fluid dynamics for the simulation of complex coolant reactivity effects
Quiroga Scaling-up methodology: a systematical procedure for qualifying NPP nodalizations. Application to the OECD/NEA ROSA-2 and PKL-2 Counterpart test
Blinkov et al. Investigation on the interphase drag and wall friction in vertically oriented upward and downward two-phase flows under accident conditions in light water reactors
Kozmenkov et al. Application of statistical uncertainty and sensitivity evaluations to a PWR LBLOCA analysis calculated with the code ATHLET. Part 1: uncertainty analysis
Allen et al. Fluoride-salt-cooled, high-temperature reactor (FHR) methods and experiments program white paper
Coscarelli et al. Qualification of TRACE V5. 0 Code against Fast Cooldown Transient in the PKL‐III Integral Test Facility
Lorenzo et al. Assessment of an isolation condenser of an integral reactor in view of uncertainties in engineering parameters
Bestion et al. Identification of Thermalhydraulic Phenomena for PWR Transient Analysis and Simulation
Liu et al. Improvement of ATHLET modelling capability for asymmetric natural circulation phenomenon using uncertainty and sensitivity measures
D’Auria Approach And Methods To Evaluate The Uncertainty In System Thermalhydraulic Calculations.