Title of article :
Thermal hydraulic challenges of Gas Cooled Fast Reactors with passive safety features Original Research Article
Author/Authors :
Michael A. Pope، نويسنده , , Jeong Ik Lee، نويسنده , , Pavel Hejzlar، نويسنده , , Michael J. Driscoll، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2009
Pages :
15
From page :
840
To page :
854
Abstract :
Transient response of a Gas Cooled Fast Reactor (GFR) coupled to a recompression supercritical CO2 (S-CO2) power conversion system (PCS) in a direct cycle to a Loss of Coolant Accident (LOCA) and a Loss of Generator Load Accident is analyzed using RELAP5-3D. A number of thermal hydraulic challenges for GFR design are pointed out as the designers strive to accommodate cooling of the high power density core of a fast reactor by a gas with its inherently low heat transfer capability, in particular under post-LOCA events when system pressure is lost and when reliance on passive decay heat removal (DHR) is emphasized. Although it is possible to design a S-CO2 cooled GFR that can survive LOCA by cooling the core through natural circulating loops between the core and elevated emergency cooling heat exchangers, it is not an attractive approach because of various bypass paths that can, depending on break location, degrade core cooling. Moreover, natural circulation gas loops can operate in deteriorated heat transfer regimes with substantial reduction of heat transfer coefficient: as low as 30% of forced convection values, and data and correlations in these regimes carry large uncertainties. Therefore, reliable battery powered blowers for post-LOCA decay heat removal that provide flow in well defined regimes with low uncertainty, and can be easily overdesigned to accommodate bypass flows were selected. The results confirm that a GFR with such a DHR system and negative coolant void worth can withstand LOCA with and without scram as well as loss of electrical load without exceeding core temperature and turbomachinery overspeed limits.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2009
Journal title :
Nuclear Engineering and Design Eslah
Record number :
895297
Link To Document :
بازگشت