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1 VUJE, Inc., Trnava 2 SUT Bratislava. IM and Th Alternatives of VVER-440 Fuel Cycle. P. Da řílek 1 , J. Breza 1 , V. Nečas 2 , Peter Čerba 2 , Miriam Sačková 2 darilek@vuje.sk AER Working Group F Meeting „Spent Fuel Transmutations“
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1 VUJE, Inc., Trnava 2 SUT Bratislava IM and Th Alternatives of VVER-440 Fuel Cycle P. Dařílek1, J. Breza1, V. Nečas2, Peter Čerba2, Miriam Sačková2darilek@vuje.sk AER Working Group F Meeting „Spent Fuel Transmutations“ Konferenční centrum AV ČR – zámek Liblice, Czech Republic April14-17, 2009 VUJE , Inc., Okružná 5, 918 64 Trnava
Content IM: LWR-DEPUTY benchmark Th: • homogeneous assembly – templates • heterogeneous assembly • heterogeneous assembly - Radkowski VUJE , Inc., Okružná 5, 918 64 Trnava
IM – LWR-DEPUTY benchmark UOX pin IMF pin Mapping of fuel assembly VUJE , Inc., Okružná 5, 918 64 Trnava
IM – LWR-DEPUTY benchmark Basic VVER-440 core data 1/2 VUJE , Inc., Okružná 5, 918 64 Trnava
IM – LWR-DEPUTY benchmark Basic VVER-440 core data 2/2 VUJE , Inc., Okružná 5, 918 64 Trnava
IM – LWR-DEPUTY benchmark Fuel composition VUJE , Inc., Okružná 5, 918 64 Trnava
Th – homogeneous assembly - templates UThOX VUJE , Inc., Okružná 5, 918 64 Trnava
Th – homogeneous assembly - templates PuThOX VUJE , Inc., Okružná 5, 918 64 Trnava
Th – homogeneous assembly - templates 1. Reactor net electric output (MW)The reactor net electric output is taken account of on-site power demand which is to change depending on reactor concepts. 2. Average load factor (%)It is defined as planned (theoretical) value of the reactor design. For example, if the operation cycle length is scheduled 12 months in full power and annual refuelling or inspection interval 2 months, the average load factor will be 85.71% (=12/14). 3. Operation cycle length (EFPD)Operation cycle length should be given by the unit of equivalent full power day, because the fuel and core specifications are designed to keep sufficient reactivity for such operation. 4. No. of refuelling batchesIn some cases, the ratio of the refuelling is changeable depending on the operation cycle or regions of the core, so the number doesn’t have to be integer. Additional explanation 1/2 VUJE , Inc., Okružná 5, 918 64 Trnava
Th – homogeneous assembly - templates 5. Fuel residence time (EFPD)Fuel residence time = Operation cycle length (EFPD) x No. of refuelling batches In the case of fast reactors, the values should be given for core, axial blanket and radial blanket respectively. 6. Specific power density (MW/t)It’s defined as thermal output (MW) divided by heavy metal weight (t). As for 4, 5, 6 and 7 in fast reactor designs, the values should be given for the regions of core, axial blanket and radial blanket respectively. 7. Average discharge burnup (MWd/t)Usually, Average discharge burnup = Specific power density (MW/t) x Fuel residence time (EFPD) In the case of fast reactors, the values should be given for core, axial blanket and radial blanket respectively. 8. Refueling data Initial core design will be done in detailed design phase usually. So, please give the data, if any. But in early design phase, we can use the fuel loading and discharge data for equilibrium cycle as the data of initial core in fuel cycle analysis. For example, we can regard “fresh fuel loading for equilibrium cycle x No. of refuelling batch” as initial full core loading. Although in detail design phase, refueling scheme from initial core to equilibrium core is to be surveyed, in GAINS we may use equilibrium cycle refueling data for simplification. Additional explanation 2/2 VUJE , Inc., Okružná 5, 918 64 Trnava
Th – heterogeneous assembly UOX ThPuOX or ThUOX UOX + ThPuOX or ThUOX VUJE , Inc., Okružná 5, 918 64 Trnava
Th – heterogeneous assembly Pu concentrations Pu238-242 in: UOX ThPuOX ThUOX g/tTK Burnup [MWd/tTK] VUJE , Inc., Okružná 5, 918 64 Trnava
Th – heterogeneous assembly MA (Np, Am, Cm, Cf) in: UOX ThPuOX ThUOX g/tTK Burnup [MWd/tTK] MA concentrations VUJE , Inc., Okružná 5, 918 64 Trnava
Th – heterogeneous assembly - Radkowski VUJE , Inc., Okružná 5, 918 64 Trnava