Primary loop heat exchanger for HTGR plant residual heat removal and auxiliary cooling system

Journal Article · Thu Oct 01 04:00:00 EDT 1981 · Am. Soc. Mech. Eng., (Pap.); (United States)

OSTI ID:5558031

Hurn, E J; Carosella, D P

Design studies have been under way on high-temperature process heat and steam applications utilizing a high-temperature gas-cooled reactor plant. Plant designs have incorporated safety-class core auxiliary cooling systems (CACSs). These systems differ from comparable light water reactor systems in that they are additional to, and separate from, the reactor main coolant loops. The CACS, therefore, provides an independent means of cooling the reactor core and is designed to maintain the prestressed concrete reactor vessel, core, and component temperatures within safe limits. Each CACS primary loop includes an auxiliary helium circulator, shutoff valve, and water-cooled core auxiliary heat exchanger (CAHE). This paper addresses the design criteria, design configuration, performance, and safety aspects of the CAHE design. 1 ref.

• Research Organization: Gen At Co, San Diego, Calif
• OSTI ID: 5558031
• Journal Information: Am. Soc. Mech. Eng., (Pap.); (United States), Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Vol. 81-JPGC-NE-10; ISSN ASMSA
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AFTER-HEAT REMOVAL
COOLING SYSTEMS
ENERGY SYSTEMS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT EXCHANGERS
HTGR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
REMOVAL
RHR SYSTEMS
SAFETY
THERMAL POWER PLANTS