.ThermoSysPro.NuclearCore

Library to model a nuclear core

Information

Copyright © EDF 2002 - 2024

ThermoSysPro Version 4.1

Contents

NameDescription
 Xenonxenon as fission product
 FuelThermalPowerGrid model that describes the dynamic of the conduction of heat generated by fission in a fuel rod.
 ReactivityFeedbacksThis module calculates the neutronic feedback reactions due to the control rods, the Doppler effect, the moderator, the boron and the xenon for a punctual neutronic flux. The emergency shutdown (SCRAM) of the reactor is not considered in this module.
 ResidualPowerCalculation of the residual power given by the decay of the fission products in the core of the nuclear reactor; maximum 6 groups of radio-isotopes are considered.
 NeutronKineticsThis module contains a model of the neutronic flux with six groups of delayed neutrons. Starting from the total reactivity, which is an input in the module and it is given by the sum of all the possible feedback effects (Doppler, moderator, control bars, boron and xenon), this module calculates the fission power of the reactor. The total power is the sum of the neutronic power and the residual power (which is an input of the module).

Generated at 2025-10-08T18:21:08Z by OpenModelicaOpenModelica 1.25.4 using GenerateDoc.mos