Transient performance during stopping the research reactor primary loop pump
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H. Akbarian Shourkaei
Abstract
In this work an attempt is made to achieve characteristics curves for the Tehran Research Reactor (TRR) during stopping. The TRR pump speed during the event is time dependent. This is done for the TRR first quadrant operating characteristics. The obtained results indicate that the time needed for the coolant flow rate to reach zero is greater than the time necessary for the pump to come to complete stoppage.
Kurzfassung
In diesem Beitrag werden die charakteristischen Kurven während des Abschaltvorgangs für den Teheraner Forschungsreaktor (TRR) bestimmt. Die Pumpengeschwindigkeit des TRR ist während dieses Vorgangs zeitabhängig. Die Bestimmung erfolgt für die Betriebscharakteristik des ersten Quadranten. Die erhaltenen Ergebnisse zeigen, dass die Zeitspanne, um die Strömungsgeschwindigkeit des Kühlmittels auf Null zu bringen, größer ist als die Zeit, die die Pumpe zum vollständigen Stillstand benötigt.
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© 2015, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Evaluation of advanced displacement cross-sections for the major EUROFER constituents based on an atomistic modelling approach
- Tarapur atomic power station: analysis of station blackout scenario
- Estimating steady state and transient characteristics of molten salt natural circulation loop using CFD
- Thermal hydraulic analysis of ETRR-2 using RELAP5 code
- Transient performance during stopping the research reactor primary loop pump
- Neutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo method
- A study on the criticality of modified neutron transport equation by using alternative scattering phase functions
- Production cross–section calculations of medical 32P, 117Sn, 153Sm and 186,188Re radionuclides used in bone pain palliation treatment
- Study on carbonated hydroxyapatite as a thermoluminescence dosimeter
- Social impact theory based modeling for security analysis in the nuclear fuel cycle
- Analysis of a homogenous and heterogeneous stylized half core of a CANDU reactor
