Essays about: "Boiling Water Reactor"

Showing result 1 - 5 of 14 essays containing the words Boiling Water Reactor.

  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. Development of the endurance test program and the assembly fixture for TRITON11™

    University essay from Lunds universitet/Produktutveckling

    Author : William Lundström; [2016]
    Keywords : Nuclear fuel; Boiling Water Reactor; fretting wear; test program; assembly fixture; Technology and Engineering;

    Abstract : The engineers at Westinghouse Electric Company have developed a new nuclear fuel design called TRITON11™, which will be used in Boiling Water Reactors (BWR). This project has been to develop a test program and an assembly fixture for TRITON11™. The test program can not be fully presented in this repport due to confidentiality. READ MORE

  4. 4. Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate

    University essay from Uppsala universitet/Tillämpad kärnfysik

    Author : Daniel Constanda; [2015]
    Keywords : nuclear power; bwr; boiling water reactor; BISON; POLCA; partial SCRAM modeling; control rod effect; transients;

    Abstract : This study aims to improve the modeling of partial SCRAM in the BISON plant model for the Forsmark 2 nuclear reactor after power uprate. Validation of the BISON model against tests performed from March to May in 2013 have shown that this is one of the areas in which there is room for improvement. READ MORE

  5. 5. Influence of In-vessel Pressure and Corium Melt Properties on Global Vessel Wall Failure of Nordic-type BWRs

    University essay from KTH/Kärnkraftsäkerhet

    Author : Andrei Goronovski; [2013]
    Keywords : Severe accident; Vessel failure; CRGT cooling; Thermo-Mechanical creep analysis;

    Abstract : The goal of the present study is to investigate the effect of different scenarios of core degradation in a Nordic-type BWR (boiling water reactor) on the reactor pressure vessel failure mode and timing. Specifically we consider the effects of (i) in-vessel pressure, (ii) melt properties. READ MORE