Design and development of a steam turbine driven circulator for high temperature gas-cooled reactors

Journal Article · Tue Jan 01 04:00:00 EST 1974 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/0029-5493(74)90050-8· OSTI ID:4343328

Cavallaro, L.; Yampolsky, J.

Design optimization of high temperature gas-cooled power reactors with integration of the entire primary coolant system in a prestressed concrete reactor pressure vessel (PCRV) leads to stringent power, size, and environmental requirements for the primary coolant circulation equipment. To meet these requirements, the series steam turbine helium circulator (SSTHC) was conceived and developed by Gulf General Atomic. The SSTHC consists of a single stage axial- flow helium compressor driven by a single stage steam turbine. The compressor and the drive turbine are integrally attached to a single vertical shaft and overhung from a central bearlng and seal housing. The drive turbines are in series with the lower-producing main steam turbine. The design points of the compressor, drive turbine and auxiliary Pelton wheel drive, as well as the design requirements for the bearings and seal system are presented. A general outline of the SSTHC development program carried out at Gulf General Atomic is given. The following areas are included in the development program: aerodynamics, compressor noise, primary coolant shutoff valve, water bearings and rotor dynamics, seals, blade vibration, and disk catcher. Further, a comprehensive series of transient tests on a circulator have been carried out.

• Research Organization: Gulf General Atomic Co., San Diego, CA
• Sponsoring Organization: USDOE
• NSA Number: NSA-29-026073
• OSTI ID: 4343328
• Journal Information: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: 1 Vol. 26; ISSN 0029-5493
• Publisher: Elsevier
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

*COMPRESSORS-- SPECIFICATIONS
*HTGR TYPE REACTORS-- COMPRESSORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HELIUM
PRIMARY COOLANT CIRCUITS
STEAM TURBINES