ACR Workshop -Core Design & Reactor Physics- - NRC

More documents

Recommendations

Info

ACR-700 Reactivity Mechanisms Plan View Pg 8
Safety Parameters in ACR-700 and CANDU 6 Total Delayed Neutron Fraction ( ß ) Prompt Neutron Lifetime ( millisecond) Full-Core Coolant Void Reactivity Power Coefficient SDS1 SDS2 ACR-700 0.0056 0.33 - 3 mk -0.07 ( mk per % power) 20 Absorber Rods 6 Poison Nozzles (reflector region) CANDU 6 0.0058 0.92 + 15 mk (Approx.) ~ 0 28 Absorber Rods 6 Poison Nozzles (core region) Pg 9
Page 1 and 2: ACR Workshop -Core Design & Reactor
Page 3 and 4: Fuel Temperature effect Reactivity
Page 5 and 6: ACR-700 Reactor Control & Safety Sy
Page 7: End-View of ACR-700 Pg 7
Page 11 and 12: Coolant CANDU 6 (D 2 O ) ACR (H 2
Page 13 and 14: Effects of CANFLEX SEU Fuel in ACR
Page 15 and 16: Effect of Coolant Void in ACR ACR
Page 17 and 18: Comparison of CANDU 6 and ACR Latti
Page 19 and 20: Effect of Trip Time & CVR on LOCA T
Page 21 and 22: Relative Power 1.1 1 0.9 0.8 0.7 0.
Page 23 and 24: Thermal Flux ( 10E14 ) 4 3.5 3 2.5
Page 25 and 26: Thermal Flux Profile upon LOCA at t
Page 27 and 28: Thermal Flux Profile upon LOCA at t
Page 29 and 30: Thermal Flux Ratios in ACR-700 upon
Page 31: Pg 31

ACR Workshop -Core Design & Reactor Physics- - NRC

Create successful ePaper yourself

Delete template?

Save as template?