Study of Reactivity Effect on Reactor Power by Using the Neutronic- Thermohydrolic Coupling

The study deals with reactivity insertion linear and non linear and/or Ramp reactivity expressed as a polynomial in time in the presence of two Feedback mechanisms, using the neutronic-thermohydraulic coupling in order to predict the neutron behavior as a function of time in terms of reactor power....

Full description

Bibliographic Details
Main Author: Baghdad Science Journal
Format: Article
Language:Arabic
Published: College of Science for Women, University of Baghdad 2012-09-01
Series:Baghdad Science Journal
Online Access:http://bsj.uobaghdad.edu.iq/index.php/BSJ/article/view/1384
id doaj-9c7b25ea08f8440589ec05e1c73ce947
record_format Article
spelling doaj-9c7b25ea08f8440589ec05e1c73ce9472020-11-25T01:11:22ZaraCollege of Science for Women, University of BaghdadBaghdad Science Journal2078-86652411-79862012-09-019310.21123/bsj.9.3.459-465Study of Reactivity Effect on Reactor Power by Using the Neutronic- Thermohydrolic CouplingBaghdad Science JournalThe study deals with reactivity insertion linear and non linear and/or Ramp reactivity expressed as a polynomial in time in the presence of two Feedback mechanisms, using the neutronic-thermohydraulic coupling in order to predict the neutron behavior as a function of time in terms of reactor power. Also, a comparative study has been achieved in the case of the presence of the feedback mechanisms. Insertion of Ramp reactivities in terms of polynomial in time to study the behavior of power and reactivity as a function of time in the presence of two feedback mechanisms (fuel and coolant) has been carried out and the results are displayed as plots, and showed this results corresponding with international results. The present study shows that the simulation of neutron time behavior is a vital tool to predict the behavior of reactivity and/or power as a function of time in case of insertion of negative or positive and/or Ramp reactivities in power reactor core for the case including feedback mechanism. Also, the simulation may be considered a unique technique to predict unexpected incident and/or accident that may occur in reactor power core in case of the availability of accurated input data.http://bsj.uobaghdad.edu.iq/index.php/BSJ/article/view/1384
collection DOAJ
language Arabic
format Article
sources DOAJ
author Baghdad Science Journal
spellingShingle Baghdad Science Journal
Study of Reactivity Effect on Reactor Power by Using the Neutronic- Thermohydrolic Coupling
Baghdad Science Journal
author_facet Baghdad Science Journal
author_sort Baghdad Science Journal
title Study of Reactivity Effect on Reactor Power by Using the Neutronic- Thermohydrolic Coupling
title_short Study of Reactivity Effect on Reactor Power by Using the Neutronic- Thermohydrolic Coupling
title_full Study of Reactivity Effect on Reactor Power by Using the Neutronic- Thermohydrolic Coupling
title_fullStr Study of Reactivity Effect on Reactor Power by Using the Neutronic- Thermohydrolic Coupling
title_full_unstemmed Study of Reactivity Effect on Reactor Power by Using the Neutronic- Thermohydrolic Coupling
title_sort study of reactivity effect on reactor power by using the neutronic- thermohydrolic coupling
publisher College of Science for Women, University of Baghdad
series Baghdad Science Journal
issn 2078-8665
2411-7986
publishDate 2012-09-01
description The study deals with reactivity insertion linear and non linear and/or Ramp reactivity expressed as a polynomial in time in the presence of two Feedback mechanisms, using the neutronic-thermohydraulic coupling in order to predict the neutron behavior as a function of time in terms of reactor power. Also, a comparative study has been achieved in the case of the presence of the feedback mechanisms. Insertion of Ramp reactivities in terms of polynomial in time to study the behavior of power and reactivity as a function of time in the presence of two feedback mechanisms (fuel and coolant) has been carried out and the results are displayed as plots, and showed this results corresponding with international results. The present study shows that the simulation of neutron time behavior is a vital tool to predict the behavior of reactivity and/or power as a function of time in case of insertion of negative or positive and/or Ramp reactivities in power reactor core for the case including feedback mechanism. Also, the simulation may be considered a unique technique to predict unexpected incident and/or accident that may occur in reactor power core in case of the availability of accurated input data.
url http://bsj.uobaghdad.edu.iq/index.php/BSJ/article/view/1384
work_keys_str_mv AT baghdadsciencejournal studyofreactivityeffectonreactorpowerbyusingtheneutronicthermohydroliccoupling
_version_ 1725171443146162176