Control rod material effect on safety parameters of research reactors
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M. Hassan
Abstract
Control rods provide adjustable manipulation of reactivity and prevent fission reaction from accelerating beyond control. In this paper, the Monte Carlo Code, MCNP6 was used to study the effect of using various control rod materials on the main safety parameters of a typical plate type material test research reactor. Three types of control rod materials were considered, Ag-In-Cd, B4C, and Hafnium. Parameters investigated are reactivity worth, excess reactivity and shutdown margin of absorber materials. The model was used to evaluate the effect of various materials on the flux and power shaping of the core. The resulting multiplication factor for this study was compared with previous work and found acceptable. It was found that boron carbide has the largest effect on safety parameters, as well as flux and power distribution.
Kurzfassung
Steuerstäbe ermöglichen es, die Reaktivität zu beeinflussen und zu verhindern, dass die Kernspaltungsreaktion außer Kontrolle beschleunigt wird. In diesem Beitrag wird eine Untersuchung vorgestellt, bei der mit Hilfe des Monte-Carlo-Codes MCNP6 der Einfluss verschiedener Steuerstabmaterialien auf die wichtigsten Sicherheitsparameter eines Forschungsreaktors mit plattenförmigen Brennelementen berechnet wurde. Dazu wurden Materialien Ag-In-Cd, B4C und Hafnium betrachtet. Berechnet wurden dazu die Parameter Reaktivität, Überschussreaktivität und Abschaltmarge dieser Absorbermaterialien. Das Modell wurde verwendet, um den Einfluss verschiedener Materialien auf den Fluss und die Leistungsformung des Kerns zu bewerten. Der resultierende Multiplikationsfaktor dieser Studie wurde mit früheren Arbeiten verglichen und als akzeptabel bewertet. Es wurde festgestellt, dass Borcarbid den größten Einfluss auf die Sicherheitsparameter sowie die Strömungs- und Leistungsverteilung hat.
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© 2019, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Revision of a CHF correlation for PWR under low pressure conditions with only dimensionless parameters as independent variables
- Experimental study on transient flow fluctuation characteristics in a 3 × 3 rod bundle under rolling condition
- The core shroud leakage analysis and study for Kuosheng nuclear power plant
- Coupling simulation of neutron kinetics core model with CFD of IPWR steam line break accident
- Numerical prediction of single-phase flow mixing characteristics in a 1/12th of the cross segment of a 54-rod bundle
- 10.3139/124.110984
- Control rod material effect on safety parameters of research reactors
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Revision of a CHF correlation for PWR under low pressure conditions with only dimensionless parameters as independent variables
- Experimental study on transient flow fluctuation characteristics in a 3 × 3 rod bundle under rolling condition
- The core shroud leakage analysis and study for Kuosheng nuclear power plant
- Coupling simulation of neutron kinetics core model with CFD of IPWR steam line break accident
- Numerical prediction of single-phase flow mixing characteristics in a 1/12th of the cross segment of a 54-rod bundle
- 10.3139/124.110984
- Control rod material effect on safety parameters of research reactors
