Physics and engineering aspects of the Oak Ridge experimental power reactor Page: 2 of 5
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and neutron, chii ged ' ir iicle and eliv;ical ",put tering
occur drrinig the he. lh Char rI i ti tcrpeZsi-
tot'o of thi partisi-. iutradl zm with the wall i';
assumed to be O.. "T. > or 5 percent of the avvragm
ion taCperaturc. 'flit fraction of the sn,' tered
particles recuning to the p1ls15 and their contain-
ment t ime in the plasm arc given by f and -tc,
!50 pb.50 MW -.O.T5
0.)r T.P. LOSSES
o* t00 - p 0.50
a BEAM OFF
50 - P/S 0.25
0.0 2.0 4.0 6.0 8.0 10.0
-I- - - - -
I - s <0.01
I I I
The chemical sputtering yield" is assumed to be
constant (0.03), the charged particle sputtering
yields are energy dependent' and in the same ratios
as those givcu by liehrischs for Nb. The absolute
values are normalized to that taken for deuterons
(0.04j. For the long burning cases shown in Figure 2,
PF 800 NW, :. 2.7, and Pn/S = 1 l-W/m' . This case
results in P = 160 K1, or 160 W of heat loss which
must be removed by cooling the first wall.
Slanlot and Shield System
'h phil uphy u";d to develop the reference
blanket csirin was that its features wust be consistent
with eytrapu1.ition to a fusion reactor. This restraint
coupled with the requirements of useful heat produc-
tion, comp:.tability with remote assembly, and the need
to dcn.onstrate tritium breeding in at least one module
resulted in the design shown in Figure 3.
JA~i.~JO -' -
--- - -- Coot,
.1 . PRIMARY
--_-- -- - - figure
2G60' 300 466 -0 6GO 760
Theic are 60 blanket segments which, when clamped
together and.Feal-welded; comprise the plasma vacuum
enclosure. 'Ihrrse segments are wedge shaped and are
95 centirmetr'rs wide on the outer circumference and
about 40 centimeters wide on the inner circuitference.
The si c of th~e segments allows them to be loaded be-
tween the toroidal field coils thus permittin;; removal
of any or, all segments for maintenance without inter-
ferring r;ith the coils. Totally remote techniques
would beused in the assembly and disassembly
All structure is 316 stainless steel, and aie
;)rinciple neutron absorber material is liquid r~etal.
For the experimental breeding modules, lithium is
used. For the non-breeding modules either sodium or
potassium is used. The blanket is cooled by helium
at a pressure of 70 atmospheres. The helium inlet
temperature is 2600 C and the outlet temperature is
The blanket section (See Figure 3) is composed of
three basic regions inside of a stainless steel, wedge-
shaped, circcular structure. The first region, which
containes liquid metal is 25 centimeters thick. This
section absorbs about 52% of t:,e neutron and gammna-ray
energy produced. In the case of the breeding module,
it produces most of the tritium. The first two rows
of coolant tubes are in series so that the coolant
first passes near the inner wall to remove the leat
deposited there by plasma loss processes. The helium
then flows through the second row of tubes and into
the outlet header. The liquid metal conducts the heat
from the first wall structure to the coolant cubes.
The second region is 10 centimeters thick and is
composed of graphite. This reflector moderates and
scatters the fast neutrons so that a high fraction of
them return to the lithium. The slower neutrons are
captured by e in the breeding modules. This graphite
reflector is cooled by radiation from all faces to the
cooler portions of the blanket.
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McAlees, D.G.; Bettis, E.S.; Huxford, T.J. & Marcus, F.B. Physics and engineering aspects of the Oak Ridge experimental power reactor, article, January 1, 1975; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc865751/m1/2/: accessed April 24, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.