Essays about: "BWR"

Showing result 1 - 5 of 36 essays containing the word BWR.

  1. 1. Development of a Nordic BWR plant model in APROS and design of a power controller using the control rods

    University essay from KTH/Fysik

    Author : Jonathan Al-Ani; [2021]
    Keywords : APROS; Dynamic process simulation; System code; Nuclear reactor; nuclear power; BWR; Boiling Water Reactor; closed cycle; steam cycle; one-dimensional flow; Westinghouse; control rods; APROS; Dynamisk processimulering; Beräkningsmodell; Kärnkraft; BWR; Kokvattenreaktor; ångcykel; en-dimensionell flödesmodell; Westinghouse; kontrollstavar;

    Abstract : In this master thesis an input-model of a Nordic BWR power plant has been developed in APROS. The plant model contains key systems and major thermohydraulic components of the steam cycle, including I&C systems (i.e. power, pressure, level and flow controls). READ MORE

  2. 2. Validation of the Westinghouse BWR nodal core simulator POLCA8 against Serpent2 reference results

    University essay from KTH/Fysik

    Author : Mathilde Gaillard; [2021]
    Keywords : Nodal Core Analysis; Monte Carlo Methods; CBH Effects; Nodal kärnanalys; Monte Carlo-metoder; CBH-effekter;

    Abstract : When a new nodal core simulator is developed, like all other simulators, it must go through an extensive verification and validation effort where, in the first stage, it will be tested against appropriate reference tools in various theoretical benchmark problems. The series of tests consist of comparing several geometries, from the simplest to the most complex, by simulating them with the nodal core simulator developed and with some higher order solver representing the reference solution, in this case on the Serpent2 Monte Carlo transport code. READ MORE

  3. 3. CFD Annular Flow Modelling Based on a Three-Field Approach

    University essay from Luleå tekniska universitet/Institutionen för teknikvetenskap och matematik

    Author : Erik Skoog; [2020]
    Keywords : CFD; BWR; annular flow; deposition;

    Abstract : This master thesis aim to model the annular flow that occurs in the final section between the fuel rods inside Boiling Water Reactors, by approximating the geometry to a cylindrical pipe. Simulations were performed in the software ANSYS Fluent, as a step in the development of replacing the 1D correlations currently used in the nuclear industry with CFD models in 3D. READ MORE

  4. 4. Compilation and evaluation of validations of computer codes for spent nuclear fuel – a review

    University essay from Lunds universitet/Kärnfysik; Lunds universitet/Fysiska institutionen

    Author : Staffan Fors; [2019]
    Keywords : Nuclear fuel; Kärnbränsle; Slutförvar; Fissionsprodukter; Physics and Astronomy;

    Abstract : This report describes a systematic review regarding validations of calculations by measurements of isotopic compositions, or decay heat, on spent nuclear fuel, SNF. 15 relevant or otherwise interesting studies, were found. Two reports were chosen among the found studies and analyzed. READ MORE

  5. 5. Application of sub-channel thermal-hydraulic analysis to core calculations with POLCA8 and VIPRE-W

    University essay from Uppsala universitet/Tillämpad kärnfysik

    Author : Larisa Castellanos Alvarez; [2019]
    Keywords : nuclear physics; westinghouse; POLCA; Vipre; BWR;

    Abstract : This report investigates the steps of a one-way coupling between two simulation codes developed by Wesinghouse Electric Sweden AB. The Westinghouse POLCA8 is a three dimensional steady-state diffusion theory code used for simulating the neutronic, thermal and hydraulic behavior of a reactor core. READ MORE