ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site
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0<br />
8 6 4<br />
7-<br />
4=H20 SPECTRUM<br />
2=D20 SPECTRUM<br />
-<br />
86<br />
NEUTRON ENERGY (MeV)<br />
3 2 40 08 06<br />
I 1<br />
I<br />
!<br />
3=C4RBON SPECTRUM<br />
4=FAST SPECTRUM (50% Na, 50% U-METAL, ~ o % * ~ ~ 80% U , 23aU)<br />
spectra, and comparing it with experimental de-<br />
terminations of <strong>the</strong> same quantities. The results<br />
indicate that <strong>the</strong> model is useful at least for pre-<br />
dicting relative damage rates in different spectra.<br />
A useful simplification arises from <strong>the</strong> observa-<br />
tion that <strong>the</strong> damage per unit time is closely pro-<br />
portional to <strong>the</strong> total neutron flux above some<br />
energy E,, where Eo has <strong>the</strong> same value for widely<br />
different reactor spectra. We have reconfirmed this<br />
observation, to our own satisfaction, by comparing<br />
<strong>the</strong> (calculated) damage per unit flux above energy<br />
E, as a function of E, for spectra appropriate to<br />
three different moderators (H20, DLO, and C) and<br />
for a “typical” fast reactor spectrum. The results,<br />
plotted in Fig. 6.5, show that <strong>the</strong> flux above about<br />
50 kev is a reliable indication of <strong>the</strong> relative dam-<br />
age rate in graphite for quite different spectra.<br />
Figure 6.6 shows <strong>the</strong> spectra for which <strong>the</strong>se re-<br />
sults were derived. The equivalence between<br />
MSBR and DFR experiments is simply found by<br />
equating <strong>the</strong> doses due to neutrons above 50 kev<br />
in <strong>the</strong> two reactors. We have not yet calculated<br />
<strong>the</strong> DFK spectrum explicitly, but we expect it to<br />
04 03 07 015<br />
1 - 1- ry -<br />
ORNI-OWG 61-44844<br />
O.(O 0.08<br />
I I<br />
4 2 3 4<br />
5<br />
LETHARGY U<br />
Fig. 6.6. Neutron Flux Per Unit Lethargy vs Lethargy. Normalized for equal dunioye in graphite.<br />
be similar to <strong>the</strong> “fast reactor” spectrum of Fig.<br />
6.6, in which 94% of <strong>the</strong> total flux lies above 50<br />
kev. Since <strong>the</strong> damage flux in <strong>the</strong> MSBR is essentially<br />
proportional to <strong>the</strong> local power density,<br />
we postulate that <strong>the</strong> useful life of <strong>the</strong> graphite is<br />
governed by <strong>the</strong> maximum power density ra<strong>the</strong>r than<br />
by <strong>the</strong> average, and thus depends on <strong>the</strong> degree of<br />
power flattening that can be achieved (see next<br />
section). In <strong>the</strong> hlSBR <strong>the</strong> average flux above 50<br />
kev is about 0.94 x 1014 neutrons cm-’ sec-’ at<br />
a power density of 20 w/cm3. From <strong>the</strong> DFR irradiations<br />
it has been concluded that a dose of<br />
5.1 x 10‘’ nvt (> 50 kev) can be tolerated. The<br />
lifetime of <strong>the</strong> graphite is <strong>the</strong>n easily computed;<br />
this useful life is shown in Table 6.1 for an assumed<br />
plant factor of 0.8 and for various combinations<br />
of average power density and peak-toaverage<br />
power-density ratio.<br />
It must be acknowledged that in applying <strong>the</strong><br />
results of DFK experiments to <strong>the</strong> MSBX, <strong>the</strong>re<br />
remain some uncertainties, including <strong>the</strong> possibility<br />
of an appreciable dependence of <strong>the</strong> d a ~<br />
age on <strong>the</strong> rate at which <strong>the</strong> dose is accumulated