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

Han et al., 2024 - Google Patents

Application of automatic few-group structure optimization based on perturbation theory to VHTR cores

Han et al., 2024

View HTML
Document ID
5048027311186823138
Author
Han T
Lee H
Publication year
Publication venue
Nuclear Engineering and Technology

External Links

Snippet

A new automatic group structure optimization method based on the perturbation theory was proposed for the few-group structure in two-step nuclear design procedure for VHTR. It applies the sensitivity coefficient of the perturbation theory which includes not only the effect …
Continue reading at www.sciencedirect.com (HTML) (other versions)

Classifications

    • 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
    • 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
    • Y02E30/38Fuel
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326Bundles 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • GPHYSICS
    • G06COMPUTING; CALCULATING; COUNTING
    • G06FELECTRICAL DIGITAL DATA PROCESSING
    • G06F17/00Digital computing or data processing equipment or methods, specially adapted for specific functions
    • G06F17/20Handling natural language data
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control
    • G21D2003/002Core design; Core simulations
    • 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
    • Y02E10/00Energy generation through renewable energy sources
    • Y02E10/50Photovoltaic [PV] energy
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21YINDEXING 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
    • G21Y2004/00SOLUTION
    • G21Y2004/10Compositions
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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

Similar Documents

Publication Publication Date Title
Fridman et al. On the use of the Serpent Monte Carlo code for few-group cross section generation
Davidson et al. Nuclide depletion capabilities in the Shift Monte Carlo code
Lindley et al. Current status of the reactor physics code WIMS and recent developments
Bostelmann et al. SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis
Nguyen et al. Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis
Mao et al. A new Tone's method in APOLLO3® and its application to fast and thermal reactor calculations
Permana Basic design analysis of a heavy water-cooled thorium breeder reactor
Yu et al. A reduced-boron OPR1000 core based on the BigT burnable absorber
Aghaie et al. Coupled neutronic thermal–hydraulic transient analysis of accidents in PWRs
Mercatali et al. SCALE modeling of selected neutronics test problems within the OECD UAM LWR’s benchmark
Chen et al. Accident source term and radiological consequences of a small modular reactor
Faucher et al. Multi-physics transient simulations with TRIPOLI-4®
Lkouz et al. Revolutionizing LWR SMR reactors: exploring the potential of (Th-233U-235U) O2 fuel through a parametric study
Tomatis et al. Quantification of history effects in PWR modelling
Rivas et al. Propagating neutronic uncertainties for FFTF LOFWOS Test# 13
Kelly et al. Verification of a depletion method in SCALE for the Advanced High-Temperature Reactor
Han et al. Application of automatic few-group structure optimization based on perturbation theory to VHTR cores
Rivas et al. Nuclear data uncertainty propagation applied to the versatile test reactor conceptual design
Choi et al. Development and Demonstration of a Risk-Informed Approach to the Regulatory Required Fuel Reload Safety Analysis
Szames et al. A review of history parameters in PWR core analysis
Thilagam et al. Simulations for worth determination of CPSARs in VVER-1000 reactor using EXCEL and TRIHEX-FA code system
Böröczki et al. On the Effect of Scalar Flux Weighting of Linearly Anisotropic Scattering Matrices in Higher-Order Transport Calculations
Akie et al. Simple formula to evaluate helium production amount in fast reactor MA-containing MOX fuel and its accuracy
Khan et al. Neutronics analyses of natural uranium fueled, light water cooled, heavy water moderated and graphite reflected nuclear reactors
Fallah et al. Optimization of neutron energy-group structure in thermal lattices using ultrafine bilinear adjoint function