ORNL-2106 - the Molten Salt Energy Technologies Web Site

ANP PROJECT PROGRESS REPORT
Member
NO.+
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
TABLE 1.2.2. AVERAGE HEAT-GENERATION RATES IN MEMBERS OF ART NORTH HEAD
Description
Pressure shell
(below sodium expansion tank)
Liner
Fuel-expansiorrtank baffle
Fue I-exponsion-tank woll
Upper deck
(regions with sodium on both sides)
Upper deck
(regions with fuel on both sides)
Sw irl-c hamber boff le
Sw irl-c hamber wol I
Lower deck
(regions with fuel below and sodium above)
Lower deck
(regions with fuel on both sides)
Copper-boron tiles
F il Ier block
Beryllium support struts
Filler block
Copper-boron tile
Flat section of lower support ring
Strut part of loww support ring
Lower support ring
*See Fig. 1.1.5, Chap. 1.1, this report, for location of member.
The power-source distribution of the radioactive
nuclides is found by multiplying their equilibrium
concentration by their decay constant Ai and their
average energy per disintegration.
The total power and the power density in the
gas space of the fuel expansion tank as a function
of the volume of the gas and the helium flow rate
are given in Fig, 1.2.3. For these calculations,
A, was taken to be 5.82 x sec, which
corresponds to a fuel flow rate of 22 gpm through
the purging pumps. If the purging device is
36
Heat Generation
(w/cm3)
4
6 w/cm3 + 16 w/cm2 on expansiondank
surface due to
beto roys
15
12
25 w/cm2*t + 6 w/cm3, where
t = thickness of tiles (cm)
3
10
1
30
15
3
assumed to be 100% efficient, this means that the
reactivity effect of the xenon is reduced to about
0.1% at equilibrium.’ The sweeping constant,
A,, is dependent on the helium flow rate and the
gas volume, and thus it is different for each point
on the curves. In converting the STP values
of the helium flow rate, the temperature of the
gas was assumed to be 12OO0F, and the pressure
in the expansion chamber and off-gas line was
1 e 5
18J. L. Meem, The Xenon Problem in the ART,
ORNL CF-54-5-1 (May 3, 1954).
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