(2) The modeling of conduction-limited fuel vaporization and condensation causes the energetics to be highly sensitive to variations in the droplet size (i.e., in the parametric values) for the sizes of interest in HCDA analysis. Furthermore, if conditions of saturation are assumed to be maintained, calculations that do not permit vapor-liquid slip appear to be conservative.
#Pcalc 208 leasing code
Scoping studies of the importance of including these phenomena performed with the parametric two-field, two-component coupled neutronic/thermodynamic/hydrodynamic code FX2-TWOPOOL indicate for the prompt burst portion of an HCDA that: (1) Vapor-liquid slip plays a more » relatively insignificant role in establishing energetics, implying that analyses that do not model vapor-liquid slip may be adequate.
The main contributions such codes are expected to make are the inclusion of detailed modeling of the relative motion of liquid and vapor (slip), the inclusion of modeling of nonequilibrium/nonsaturation thermodynamics, and the use of more detailed neutronics methods. The main objective of the development of multifield, multicomponent thermohydrodynamic computer codes is the detailed study of hypothetical core disruptive accidents (HCDAs) in liquid-metal fast breeder reactors. A structure field with nine density and five energy components a liquid field with eight density and six energy components and a vapor field with six density and on energy component are coupled by exchange functions representing a modified-dispersed flow regime with a zero-dimensional intra-cell structure model.Īuthors: Bohl, W R Luck, L B Publication Date: Fri Jun 01 00:00: Research Org.: Los Alamos National Lab., NM (USA) Sponsoring Org.: USNRC OSTI Identifier: 6851447 Report Number(s): LA-11415-MS ON: DE90014435 TRN: 90-028868 DOE Contract Number: W-7405-ENG-36 Resource Type: Technical Report Country of Publication: United States Language: English Subject: 22 GENERAL STUDIES OF NUCLEAR REACTORS 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE LMFBR TYPE REACTORS REACTOR CORE DISRUPTION S CODES BOUNDARY CONDITIONS COMPUTER PROGRAM DOCUMENTATION CORIUM DATA PROCESSING EQUATIONS OF STATE FLOW MODELS FLUID FLOW FLUID MECHANICS HEAT TRANSFER HYDRAULICS LIQUIDS PHASE TRANSFORMATIONS PROGRAMMING STRUCTURAL MODELS VAPORS ACCIDENTS BREEDER REACTORS COMPUTER CODES ENERGY TRANSFER EPITHERMAL REACTORS EQUATIONS FAST REACTORS FBR TYPE REACTORS FLUIDS GASES LIQUID METAL COOLED REACTORS MATHEMATICAL MODELS MECHANICS PROCESSING REACTOR ACCIDENTS REACTORS 220900* - Nuclear Reactor Technology- Reactor Safety 210500 - Power Reactors, Breeding 990200 - Mathematics & = , The fluid-dynamics calculation solves multicomponent, multiphase, multifield equations for mass, momentum, and energy conservation in (r,z) or (x,y) geometry. The neutronics and the fluid dynamics are coupled via temperature- and background-dependent cross sections and the reactor power distribution.
Reactor neutronic behavior is predicted by solving space (r,z), energy, and time-dependent neutron conservation equations (discrete ordinates transport or diffusion). The modeling philosophy is based on the use of general, but approximate, physics to represent interactions of accident phenomena and regimes rather than a detailed representation of specialized situations. SIMMER-2 (Version 12) is a computer program to predict the coupled neutronic and fluid-dynamics behavior of liquid-metal fast reactors during core-disruptive accident transients.
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