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Title: Simulation of reflooding on two parallel heated channel by TRACE

Abstract

In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the nuclear fuel is not adequately removed because of the decrease of the coolant mass flow rate in the reactor core. This fact leads to an increase of the fuel temperature that can cause damage to the core and leakage of the radioactive fission products. In order to reflood the core and to discontinue the increase of temperature, an Emergency Core Cooling System (ECCS) delivers water under this kind of conditions. This study is an investigation of how the power distribution between two channels can affect the process of reflooding when the emergency water is injected from the top of the channels. The peak cladding temperature (PCT) on LOCA transient for different axial level is determined as well. A thermal-hydraulic system code TRACE has been used. A TRACE model of the two heated channels has been developed, and three hypothetical cases with different power distributions have been studied. Later, a comparison between a simulated and experimental data has been shown as well.

Authors:
 [1]
  1. Department of Nuclear Engineering, Chalmers University of Technology, Gothenburg (Sweden)
Publication Date:
OSTI Identifier:
22608564
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1754; Journal Issue: 1; Conference: ICME 2015: 11. international conference on mechanical engineering, Dhaka (Bangladesh), 18-20 Dec 2015; Other Information: (c) 2016 Author(s); Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COOLANTS; ECCS; FISSION; FISSION PRODUCTS; FLOW RATE; HEAT; LOSS OF COOLANT; LOSSES; MASS; POWER DISTRIBUTION; REACTOR CORES; SIMULATION; THERMAL HYDRAULICS; TRANSIENTS; WATER

Citation Formats

Zakir, Md. Ghulam. Simulation of reflooding on two parallel heated channel by TRACE. United States: N. p., 2016. Web. doi:10.1063/1.4958436.
Zakir, Md. Ghulam. Simulation of reflooding on two parallel heated channel by TRACE. United States. doi:10.1063/1.4958436.
Zakir, Md. Ghulam. Tue . "Simulation of reflooding on two parallel heated channel by TRACE". United States. doi:10.1063/1.4958436.
@article{osti_22608564,
title = {Simulation of reflooding on two parallel heated channel by TRACE},
author = {Zakir, Md. Ghulam},
abstractNote = {In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the nuclear fuel is not adequately removed because of the decrease of the coolant mass flow rate in the reactor core. This fact leads to an increase of the fuel temperature that can cause damage to the core and leakage of the radioactive fission products. In order to reflood the core and to discontinue the increase of temperature, an Emergency Core Cooling System (ECCS) delivers water under this kind of conditions. This study is an investigation of how the power distribution between two channels can affect the process of reflooding when the emergency water is injected from the top of the channels. The peak cladding temperature (PCT) on LOCA transient for different axial level is determined as well. A thermal-hydraulic system code TRACE has been used. A TRACE model of the two heated channels has been developed, and three hypothetical cases with different power distributions have been studied. Later, a comparison between a simulated and experimental data has been shown as well.},
doi = {10.1063/1.4958436},
journal = {AIP Conference Proceedings},
number = 1,
volume = 1754,
place = {United States},
year = {Tue Jul 12 00:00:00 EDT 2016},
month = {Tue Jul 12 00:00:00 EDT 2016}
}