ORNL-4191 - the Molten Salt Energy Technologies Web Site

FUEL. CEL1.S
420 Ar 59/,6 in PlrCH
5?8 in. HEX
x 13fl 3 in LONG
BLANKET CELLS
252 AT 53/8 DlAM
(-15 in TOTAL)
REF LEC rofi
GRAPHITE
(-6 in TOTAL1
c
72
14 ft 3in OD
10 ft 0 ill. DlAM CORE
Fig. 5.8. 250 Mw (Electrical) Reactor - Plan. 420 53i-i". cells.
Table 5.1 do not take into account the cost of replacing
the graphite moderator at intervals determined
by radiation damage to the graphite. The
frequency of replacement and the contribution to
the power cost are greater at the higher power
densities, and this effect essentially offsets the
difference in initial cost.
Plan and elevation views of the reactor are
shown in Figs. 5.8 and 5.9. The design pararneteis
are given in Table 5.2.
There are 420 two-pass fuel flow channels in
the reactor core graphite. As shown in Fig. 5.10,
each of these channels is formed from two graphite
extrusions. The outer, and longer, of the pieces
is hexagonally shaped, 5?8 in. across the flats,
and has a 2 "/, ,-in. -diam hole in the center. The
total length of the extrusion is about 141i ft. The
inner piece is a cylinder, 2 in. OD x 1'/2 in. 111,
and fits inside the hole of the hexagonal extrusion.
The fuel salt enters the reactor through the inlet
plenum at the bottom of the core and flows upward
through the annulus between the inner and outer
graphite extrusions to the top of the reactor, where
it turns and flows through six V2- by 1 ?,-in. slots