Published November 2012 | Version v1
Journal article

Thermal-hydraulic modeling and analysis of a tank in pool reactor for normal operation and loss of flow transient

  • 1. Atomic Energy Authority, Nuclear Research Center, Reactors Department, 13759 Cairo (Egypt)

Description

A transient thermal-hydraulic model entitled Tank in Pool Reactor Thermal-Hydraulic Analysis (TPRTHA) has been developed to simulate the steady-state operation and loss of flow transient for a tank in pool type research reactor. The model solves the momentum equation, energy equation and general conduction equation in cylindrical coordinates in order to predict the coolant velocity, coolant temperature and fuel rod temperature distribution respectively. The analytical solution is utilized for steady-state calculation while the finite difference technique with implicit scheme is adopted for transient calculation. The model divides the active core into a specified axial regions and the fuel rod into a specified radial zones, then a nodal calculation is performed for both average and hottest rods with a chopped cosine shaped heat generation flux. The model also predicts the heat flux leading to onset of nucleate boiling and the critical heat flux as well as the flow inversion phenomenon. The model is used to simulate a 2 MW reactor with downward flow direction and different types of fuel bundles of different powers and different flow rates. The best-estimate thermal-hydraulic safety margins are determined and the model results are analyzed and discussed.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.pnucene.2012.07.005

Additional details

Identifiers

DOI
10.1016/j.pnucene.2012.07.005;
PII
S0149197012000984;

Publishing Information

Journal Title
Progress in Nuclear Energy
Journal Volume
61
Journal Page Range
p. 78-87
ISSN
0149-1970

Optional Information

Notes
Copyright © 2012 Elsevier Ltd. All rights reserved.