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    Technical note Variable moderation high performance light water reactor (VMHWR)

    , Article Annals of Nuclear Energy ; Volume 58 , 2013 , Pages 1-5 ; 03064549 (ISSN) Jahanfarnia, G ; Tashakor, S ; Salehi, A. A ; Abbaspour Tehrani Fard, A ; Sharif University of Technology
    2013
    Abstract
    A new flow model of high performance light water reactor (HPLWR) is discussed in the present study. HPLWR involves a negative density reactivity coefficient with high time delay. This factor decreases the stability of such reactors when transient and abnormal accidents happen. A new design for enhancing safety and efficiency in such reactors is presented. In the new design, the fluid passing through the moderator channels and the assembly gaps (known as a moderator) flows in channels detached from coolants. It is possible to control the moderator mass flux. Increasing or decreasing the moderator mass flux will modify the moderation capacity, which results in a change in the reactor power.... 

    Full-core reactor physics analysis for accident tolerant cladding in a VVER-1000 reactor

    , Article Annals of Nuclear Energy ; Volume 155 , 2021 ; 03064549 (ISSN) Safarzadeh, O ; Qarani tamai, M ; Sharif University of Technology
    Elsevier Ltd  2021
    Abstract
    Advanced accident tolerant cladding materials have brought up the potential to delay the deleterious consequences of loos of coolant accidents related to slowing down hydrogen formation from reaction of zirconium with steam in order to minimize the additional heat generation and improve fuel and cladding retention of fission products. The performance improvement offered by these advanced materials may expand the operating envelope of existing light water reactors. This paper examines the neutronic performance of the VVER-1000 light water reactor for the application of accident tolerant cladding in order to realize the endurance of severe accident conditions. This study includes a detailed... 

    Calculation and analysis of thermal-hydraulics fluctuations in pressurized water reactors

    , Article Annals of Nuclear Energy ; Volume 76 , 2015 , Pages 75-84 ; 03064549 (ISSN) Malmir, H ; Vosoughi, N ; Sharif University of Technology
    Elsevier Ltd  2015
    Abstract
    Analysis of thermal-hydraulics fluctuations in pressurized water reactors (e.g., local and global temperature or density fluctuations, as well as primary and charging pumps fluctuations) has various applications in calculation or measurement of the core dynamical parameters (temperature or density reactivity coefficients) in addition to thermal-hydraulics surveillance and diagnostics. In this paper, the thermal-hydraulics fluctuations in PWRs are investigated. At first, the single-phase thermal-hydraulics noise equations (in the frequency domain) are originally derived, without any simplifying assumptions. The fluctuations of all the coolant parameters, as well as the radial distribution of...