Primary system design of sodium-cooled fast reactors

Journal Article · Mon Oct 01 04:00:00 EDT 1973 · J. Brit. Nucl. Energy Soc., v. 12, no. 4, pp. 357-365

OSTI ID:4396167

Campbell, R H

Three alternative designs for pool type primary circuits and the loop type of circuit are described. The choice of refueling schemes is discussed. The relative merits of pool and loop circuits are compared, taking into consideration engineering aspects and other important features such as maintainability, ease of inspection, and safety characteristics. The development potential is also considered. It is concluded that there is no clear argument in favor of either system. The pool type appears marginally better for the first generation of large plant and loops will probably be more suitble for later larger plants. (UK)

• Research Organization: Nuclear Power Group Ltd., Risley, Eng.
• NSA Number: NSA-29-011903
• OSTI ID: 4396167
• Journal Information: J. Brit. Nucl. Energy Soc., v. 12, no. 4, pp. 357-365, Journal Name: J. Brit. Nucl. Energy Soc., v. 12, no. 4, pp. 357-365; ISSN JBNSA
• Country of Publication: United Kingdom
• Language: English

Related Subjects

*FBR TYPE REACTORS
*LMFBR TYPE REACTORS-- PRIMARY COOLANT CIRCUITS
*PRIMARY COOLANT CIRCUITS-- DESIGN
INSPECTION
N77500* --Reactors--Power Reactors
Breeding
NUCLEAR POWER PLANTS
REACTOR FUELING
REACTOR MAINTENANCE
REACTOR SAFETY