Design of 2300 MW(e) twin high temperature gas-cooled reactors for the Philadelphia Electric Company
Journal Article
·
· Nucl. Eng. Des., v. 26, no. 1, pp. 27-37
The basic design features of a 2300 MW(e) twin high temperature gas- cooled reactor (HTGR) power plant are described. The reactor core consists of vertical columns of hexagonal graphite fuelmoderator elements and graphite reflector blocks which are grouped into a cylindrical array and supported by a graphite core support structure. Reactivity control is accomplished by means of 146 control rods. The distribution of helium coolant flow through the core is controlled by variable orifice valves. Each of the six primary coolant loops is equipped with a helium circulator. The main steam/water section of each steam generator consists of a single helical tube bundle arranged in an annulus around the center duct. A core auxiliary cooling system is provided to furnish an independent means of removing reactor afterheat. The inherent safety characteristics and the design safety features of the large HTGR are discussed. Station arrangement, steam cycle and twin turbine generators, plant performance and control, containment and fuel handling, and environmental controls, are described. (auth)
- Research Organization:
- Philadelphia Electric Co.
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-29-026065
- OSTI ID:
- 4343369
- Journal Information:
- Nucl. Eng. Des., v. 26, no. 1, pp. 27-37, Journal Name: Nucl. Eng. Des., v. 26, no. 1, pp. 27-37; ISSN NEDEA
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
Medium-size high-temperature gas-cooled reactor
Gas turbine HTGR for economical dry cooling or high-efficiency combined cycle
Hypothetical accident scenario analyses for a 250-MW(T) modular high temperature gas-cooled reactor
Conference
·
Fri Aug 01 00:00:00 EDT 1980
·
OSTI ID:5081853
Gas turbine HTGR for economical dry cooling or high-efficiency combined cycle
Conference
·
Wed Oct 01 00:00:00 EDT 1975
·
OSTI ID:4129558
Hypothetical accident scenario analyses for a 250-MW(T) modular high temperature gas-cooled reactor
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5537814