Sökning: "Pool-type"

Hittade 3 uppsatser innehållade ordet Pool-type.

  1. 1. Load following with a passive reactor core using the SPARC design

    Uppsats för yrkesexamina på avancerad nivå, Uppsala universitet/Tillämpad kärnfysik

    Författare :Sebastian Svanström; [2016]
    Nyckelord :Nuclear physics; fast reactors; load following; metal cooled fast reactor; SFR; sodium cooled fast reactor; NPP; SPARC; ARC; battery core;

    Sammanfattning : This thesis is a follow up on "SPARC fast reactor design: Design of two passively metal-fuelled sodium-cooled pool-type small modular fast reactors with Autonomous Reactivity Control" by Tobias Lindström (2015). In this thesis the two reactors designed by Lindström in said thesis were evaluated. LÄS MER

  3. 2. SPARC fast reactor design : Design of two passively safe metal-fuelled sodium-cooled pool-type small modular fast reactors with Autonomous Reactivity Control

    Uppsats för yrkesexamina på avancerad nivå, Uppsala universitet/Tillämpad kärnfysik

    Författare :Tobias Lindström; [2015]
    Nyckelord :Fast Reactor; Reactor Design; Passive; ARC; Autonomous Reactivity Control; SPARC; Safe and Passive with Autonomous Reactivity Control; Generation IV; Sodium; Pool-type; Metal-fuel; Reactivity Sustaining;

    Sammanfattning : In this master thesis a small modular sodium-cooled metal-fuelled pool-type fast reactor design, called SPARC - Safe and Passive with Autonomous Reactivity control, has been designed. The long term reactivity changes in the SPARC are managed by implementation of the the Autonomous Reactivity Control (ARC) system, which is the novelty of the design. LÄS MER

  4. 3. Application of CFD to Safety and Thermal-Hydraulic Analysis of Lead-Cooled Systems

    Master-uppsats, KTH/Fysik

    Författare :Marti Jeltsov; [2011]
    Nyckelord :Coupled Codes; Verification Validation; CFD; System Thermal-Hydraulics; Lead Cooled sys-;

    Sammanfattning : Computational Fluid Dynamics (CFD) is increasingly being used in nuclear reactor safety analysis as a tool that enables safety related physical phenomena occurring in the reactor coolant system to be described in more detail and accuracy. Validation is a necessary step in improving predictive capability of a computationa code or coupled computational codes. LÄS MER