[go: up one dir, main page]

Calleja et al., 2014 - Google Patents

Coupling of COBAYA3/SUBCHANFLOW inside the NURESIM platform and validation using selected benchmarks

Calleja et al., 2014

View PDF
Document ID
12534987798206896302
Author
Calleja M
Sanchez V
Jimenez J
Imke U
Stieglitz R
Macián R
Publication year
Publication venue
Annals of Nuclear Energy

External Links

Snippet

Current generation of codes applied to Light Water Reactors (LWR) are based on 3D neutronic nodal methods coupled with one or two phase flow thermal–hydraulic system or subchannel codes. Multi-scale and multi-physics problems reveal significant challenges …
Continue reading at www.academia.edu (PDF) (other versions)

Classifications

    • G—PHYSICS
    • G06—COMPUTING; CALCULATING; COUNTING
    • G06F—ELECTRICAL DIGITAL DATA PROCESSING
    • G06F17/00—Digital computing or data processing equipment or methods, specially adapted for specific functions
    • G06F17/50—Computer-aided design
    • G06F17/5009—Computer-aided design using simulation
    • G06F17/5018—Computer-aided design using simulation using finite difference methods or finite element methods
    • 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
    • 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
    • G21C3/326—Bundles 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
    • 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
    • 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
    • Y02E30/39—Control of nuclear reactions
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • G21D2003/002—Core design; Core simulations
    • 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
    • G21Y2004/00—SOLUTION
    • G21Y2004/30—Improving a design
    • G—PHYSICS
    • G06—COMPUTING; CALCULATING; COUNTING
    • G06F—ELECTRICAL DIGITAL DATA PROCESSING
    • G06F2217/00—Indexing scheme relating to computer aided design [CAD]
    • G06F2217/16—Numerical modeling
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction

Similar Documents

Publication Publication Date Title
Blandford et al. Kairos power thermal hydraulics research and development
Kotlyar et al. Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore system
Kozmenkov et al. Validation and verification of the coupled neutron kinetic/thermal hydraulic system code DYN3D/ATHLET
Keresztúri et al. Development and validation of the three-dimensional dynamic code—KIKO3D
Elsawi et al. Benchmarking of the WIMS9/PARCS/TRACE code system for neutronic calculations of the Westinghouse AP1000™ reactor
Khan et al. Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor
Pawlowski DESIGN OF A HIGH FIDELITY CORE SIMULATOR FOR ANALYSIS OF PELLET CLAD INTERACTION.
Kliem et al. The reactor dynamics code DYN3D
Noori-Kalkhoran et al. Full scope thermal-neutronic analysis of LOFA in a WWER-1000 reactor core by coupling PARCS v2. 7 and COBRA-EN
Aghaie et al. Coupled neutronic thermal–hydraulic transient analysis of accidents in PWRs
Spasov et al. Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
Calleja et al. Coupling of COBAYA3/SUBCHANFLOW inside the NURESIM platform and validation using selected benchmarks
Duerigen et al. The reactor dynamics code DYN3D and its trigonal-geometry nodal diffusion model
Hursin et al. Impact of improved neutronic methodology on the cladding response during a PWR reactivity initiated accident
Lian et al. Development of a three-dimensional method for thermal-hydraulics/neutronics coupling analysis and its application on CFETR helium-cooled solid breeder blanket
Calleja et al. Investigations of boron transport in a PWR core with COBAYA3/SUBCHANFLOW inside the NURESIM platform
Lindley et al. Modelling and simulation activities in support of the UK nuclear R&D programme on digital reactor design
Venter et al. Integrated design approach of the pebble BeD modular reactor using models
Aldridge Scaling study of the depressurized conduction cooldown event in the high temperature test facility using RELAP5-3D/ATHENA
Feltus et al. Three-dimensional coupled kinetics/thermal-hydraulic benchmark TRIGA experiments
Martínez-Quiroga et al. NIRK3D and 3DKIN: General Description and current status of the new 3D kinetics capabilities of RELAP5/SCDAPSIM/MOD4. 0
Salah et al. Analysis of the VVER1000 coolant trip benchmark using the coupled RELAP5/PARCS code
Tucker et al. The impact of fueling operations on full core uncertainty analysis in CANDU reactors
Jiménez et al. Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis
Mori Core design analysis of the supercritical water fast reactor