A Reliable Steam Generator That Will Allow the Elimination of the Secondary Sodium Circuit in an LMFBR

Journal Article · Fri Apr 15 04:00:00 EDT 2005 · Nuclear Technology

OSTI ID:20840260

Sherwood, D V; Chikazawa, Y

A particular weakness of the commercial liquid-metal fast breeder reactor is the design of the steam generator (SG). Any small leak in the SG allows the hot sodium (Na) to come into contact with the water/steam, and this results in a violent reaction and SG damage. A secondary circuit is normally used to prevent such reactions causing damage to the reactor core and primary vessel.NNC Ltd. has developed a copper (Cu)-bonded SG system, the objective of which is to provide three separate solid boundaries (two steel and one Cu) between the primary sodium coolant and the water/steam and hence eliminate the possibility of contact between Na and water/steam. The design uses a hot isostatic pressure method of construction to bond all three barriers to aid heat transfer. This highly reliable system allows the elimination of the secondary circuit, greatly reducing the cost of the reactor system and increasing availability.

• OSTI ID: 20840260
• Journal Information: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 1 Vol. 150; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AUGMENTATION
AVAILABILITY
CONSTRUCTION
CONTAINERS
COOLANTS
COPPER
COST
DAMAGE
DESIGN
HEAT TRANSFER
LMFBR TYPE REACTORS
REACTOR CORES
SODIUM
STEAM
STEAM GENERATORS
STEELS
WATER