Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model

Authors

  • Ahmad Gharib Amirkabir University of Technology (Tehran Polytechnic), Department of Energy Engineering and Physics, Tehran, Iran
  • Dariush Rezaei Amirkabir University of Technology (Tehran Polytechnic), Department of Energy Engineering and Physics, Tehran, Iran
  • Reza Akbari Amirkabir University of Technology (Tehran Polytechnic), Department of Energy Engineering and Physics, Tehran, Iran
Abstract:

Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very fast model for predicting thermal hydraulics behavior of pressurized water reactor core has been developed. For verifying the results of this model, we used RELAP5 code as US nuclear regulatory approved thermal hydraulics code. The results of developed single heated channel model have been checked with RELAP5 results for WWER-1000. This comparison shows the capability of single heated channel model for predicting thermal hydraulics behavior of reactor core. 

Upgrade to premium to download articles

Sign up to access the full text

Already have an account?login

similar resources

Core Loading Design for Bushehr Pressurized Water Reactor

The modified out-in fuel management strategy was applied to the core loading design for the first four cycles of the Bushehr (Iran-1) KWU designed Pressurized Water Reactor (PWR). The minimum peak-to-average power density was chosen as the objective function of the optimization process. Lattice homogenization and group constants generation were performed by using the LEOPARD computer code. For ...

full text

Pressurized Water Reactor Modelling with Modelica

In order to optimize and validate the design and the operation of its nuclear power plants facilities, EDF (Electricité de France) uses a proprietary tool called LEDA to perform static and dynamic simulation at the system level. EDF wishes to replace LEDA by state-of-the-art off-the-shelf tools, mainly to reduce maintenance cost while keeping up with the latest trend in modeling and simulation ...

full text

The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents

The effect of variation in thermal conductivity of light water reactor fuel elements on core response during loss-of-coolant accident scenarios is examined. Initially, a simplified numerical analysis is utilized to determine the time scales associated with dissipation of stored energy from the fuel into the coolant once the fission reaction is stopped. The analysis is then followed by full reac...

full text

Neural Network Controller for the Pressurized Water Reactor Power Control

Although there have been some severe nuclear accidents such as Three Mile Island (USA), Chernobyl (Ukraine) and Fukushima (Japan), nuclear fission energy is still a source of clean energy that can substitute fossil fuels in a centralized way and in a great amount with commercial availability and economic competitiveness. Since the pressurized water reactor (PWR) is the most widely used nuclear ...

full text

Actinide Burning in a Standard Pressurized Water Reactor

This study investigates actinide burning in a standard lattice PWR. It assumes that after the first loading of depleted uranium, plutonium and minor actinides, only the fission products are removed and only depleted uranium and the plutonium/minor actinide mixture are added. The relative concentrations of plutonium and minor actinide feed are always maintained the same as PWR discharge fuel aft...

full text

My Resources

Save resource for easier access later

Save to my library Already added to my library

{@ msg_add @}


Journal title

volume 3  issue 3

pages  192- 198

publication date 2017-08-01

By following a journal you will be notified via email when a new issue of this journal is published.

Hosted on Doprax cloud platform doprax.com

copyright © 2015-2023