Effectiveness of radial flow on rewetting of AHWR fuel cluster
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M. Kumar
Abstract
Rewetting of a hot surface is the process of establishing direct liquid contact with a large portion of the surface whose initial temperature exceeds that required to maintain film boiling for prescribed surface and flow conditions. The Advanced Heavy water Reactor (AHWR) is a natural circulation vertical pressure tube type boiling light water cooled and heavy water moderated reactor. In case of a loss of coolant accident, the clad surface temperature goes up very high and comes down due to coolant injection from the Emergency Core Coolant System (ECCS). The rewetting takes place in Boiling Water Reactors (BWR) due to top flooding and Pressurised Water Reactors (PWR) due to bottom flooding. But in AHWR, the emergency coolant enters into the reactor core in radial direction and after this, cross flow phenomenon takes place from one fuel pin ring to next. The study is being carried out on the effect of cross flow on rewetting of AHWR fuel bundle. This paper will discuss the modeling of the experimental setup having pressure tube, fuel cluster, steam generator, accumulator etc and study the effect of radial flow on rewetting of fuel pins. An analysis of the model, considering with and without cross flow, has been carried out and shows that the pick fuel temperature is sensitive to cross flow. The thermal hydraulic safety analysis code Relap5/3.2 is being used for modeling of experimental setup for rewetting study.
Kurzfassung
Der fortgeschrittene Schwerwasserreaktor (AHWR) ist ein Leichtwasser gekühlter, Schwerwasser moderierter Reaktor mit Naturumlauf. Im Falle eines Kühlmittelverlustunfalls steigt die Temperatur der Brennstoffhülle sehr hoch an und sinkt wieder nach einer Kühlmittelinjektion vom Notfallkühlsystem (ECCS). Die Wiederbenetzung findet bei Siedewasserreaktoren (BWR) durch fluten von oben statt, bei Druckwasserreaktoren (PWR) durch fluten von unten. Beim AHWR dagegen dringt das Notfallkühlmittel in radialer Richtung in den Reaktorkern ein. Danach kommt es zu Querströmungsphänomenen von einem Brennstab zum anderen. In der vorliegenden Studie wurde die Wirkung der Querströmung auf die Wiederbenetzung des AHWR-Brennelementbündels untersucht. Ein Experiment zur Untersuchung der Physik des Wiederbenetzungsverhaltens der Brennelementbündel des AHWR wurde konzipiert. Dabei wird die Modellierung der experimentellen Anordnung Druckröhren, Brennelementbündel, Dampferzeuger, Akkumulator, etc. diskutiert und die Wirkungsweise der radialen Strömung auf die Wiederbenetzung der Brennstäbe untersucht. Eine Analyse des Modells wurde sowohl mit wie auch ohne Querströmung durchgeführt und zeigt, dass die Temperatur der Brennelemente empfindlich auf Querströmungen reagiert. Der thermohydraulische Sicherheitsanalyse-Code Relap5/3.2 wurde für die Modellierung der experimentellen Anordnung und die Untersuchung der Wiederbenetzung verwendet.
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© 2014, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Analysis of processes in RBMK-1500 fuel rods during the operation, short and intermediate term storage
- Can mechanical stresses noticeably influence the diffusion of hydrogen in zircaloy?
- Out-of-pile modelling of nuclear fuel elements for MTR type reactors – Part 1
- Experimental study of PHWR debris bed under boil-off condition
- Effectiveness of radial flow on rewetting of AHWR fuel cluster
- Radiotracers in performance evaluation of nuclear grade resins Amberlite IRN-78 and Purolite NRW-8000
- The production of 238–242Pu(n,γ)239–243Pu fissionable fluids in a fusion-fission hybrid reactor
- Theoretical study of deuteron induced reactions on 6,7Li, 9Be and 19F targets
- Upgrading of neutron radiography/tomography facility at research reactor
- Assessment of the radiological health damage costs of the Yeniköy and Kemerköy lignite-fired power plants in Muğla
