Article ID Journal Published Year Pages File Type
297967 Nuclear Engineering and Design 2011 12 Pages PDF
Abstract

In fast reactor safety post accident heat removal assessment assumes importance to ensure integrity of the structural components. It is essential to demonstrate the passive built-in heat removal capabilities of the reactor in the event of a core disruptive accident. This paper details the commissioning aspect of Post Accident Thermal Hydraulics (PATH) experimental facility that is a scaled 1:4 water model of Prototype Fast Breeder Reactor (PFBR) India, to investigate heat removal by the natural convection with water as working fluid. This paper presents experimental temperature mapping and numerical methodology to evolve transient response of the system. Preliminary commissioning results for a case of 12 kW heat source is highlighted.

► We have commissioned and tested 1:4 FBR water model for natural convection studies. ► Study is focused on PAHR after severe accident. ► Accurate online temperature measurements are made to study transient behavior. ► Commissioning results for a case of 12 kW are highlighted.

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Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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