Sökning: "BFBT benchmark"

Hittade 2 avhandlingar innehållade orden BFBT benchmark.

  1. 1. Uncertainty and Sensitivity Analysis Applied to the Validation of BWR Bundle Thermal-Hydraulic Calculations

    Författare :Augusto Hernandéz Solís; Chalmers tekniska högskola; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Latin Hypercube sampling; uncertainty and sensitivity analysis; Thermal‐hydraulic codes; simple random sampling; reactor safety analysis; BFBT benchmark;

    Sammanfattning : In recent years, more realistic safety analyses of nuclear reactors have been based on best estimate (BE) computercodes. The need to validate and refine BE codes that are used in the predictions of relevant reactor safetyparameters, led to the organization of international benchmarks based on high quality experimental data. LÄS MER

  3. 2. Uncertainty and sensitivity analysis applied to LWR neutronic and thermal-hydraulic calculations

    Författare :Augusto Hernandéz Solís; Chalmers tekniska högskola; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; sensitivity analysis; Nuclear best estimate codes; uncertainty analysis;

    Sammanfattning : The deterministic modeling of LWRs begins with the computation of energy‐collapsed and homogenizedmacroscopic cross‐sections by means of a lattice code. Once these parameters are functionalized as a functionof the reactor state variables and discretized in space, they are used as input variables by core simulators inorder to calculate the spatial distribution of the neutron flux and thus, the spatial distribution of the power. LÄS MER