ACR Workshop -Core Design & Reactor Physics- - NRC
ACR Workshop -Core Design & Reactor Physics- - NRC
ACR Workshop -Core Design & Reactor Physics- - NRC
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Safety Parameters in <strong>ACR</strong>-700 and CANDU 6<br />
Total Delayed Neutron<br />
Fraction ( ß )<br />
Prompt Neutron Lifetime<br />
( millisecond)<br />
Full-<strong>Core</strong> Coolant Void<br />
Reactivity<br />
Power Coefficient<br />
SDS1<br />
SDS2<br />
<strong>ACR</strong>-700<br />
0.0056<br />
0.33<br />
- 3 mk<br />
-0.07<br />
( mk per % power)<br />
20 Absorber<br />
Rods<br />
6 Poison Nozzles<br />
(reflector region)<br />
CANDU 6<br />
0.0058<br />
0.92<br />
+ 15 mk<br />
(Approx.)<br />
~ 0<br />
28 Absorber<br />
Rods<br />
6 Poison Nozzles<br />
(core region)<br />
Pg 9
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