Feasibility of Natural Circulation Heat Transport in the ENHS
Conference
·
OSTI ID:21062363
- Argonne National Laboratory, 9700 S. Cass Avenue Argonne, IL 60439 (United States)
An analysis has been carried out of natural circulation thermal hydraulics in both the primary and intermediate circuits of the Encapsulated Nuclear Heat Source (ENHS). It is established that natural circulation enhanced by gas injection into the primary coolant above the core, or the intermediate coolant above the heat exchange zone, is effective in transporting the nominal core power to the steam generators without the attainment of excessive system temperatures. Uncertainties in thermophysical properties and wall friction have a relatively small effect upon the calculated best estimate primary and intermediate coolant system temperature rises. (authors)
- Research Organization:
- The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
- OSTI ID:
- 21062363
- Country of Publication:
- United States
- Language:
- English
Similar Records
Feasibility of natural circulation heat transport in the ENHS.
Thermal-Hydraulic Analysis on the Encapsulated Nuclear Heat Source (ENHS)
Effect of Fuel Type on the Attainable Power of the Encapsulated Nuclear Heat Source Reactor
Conference
·
Wed Feb 13 23:00:00 EST 2002
·
OSTI ID:793885
Thermal-Hydraulic Analysis on the Encapsulated Nuclear Heat Source (ENHS)
Conference
·
Thu Jul 01 00:00:00 EDT 2004
·
OSTI ID:21160702
Effect of Fuel Type on the Attainable Power of the Encapsulated Nuclear Heat Source Reactor
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:21021056