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Recycled Nuclear Fuel Cost Calculator

(last updated 12 Nov 2009)
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Calculates the material balance and cost of nuclear fuel (for light-water reactors) produced from enriched natural uranium (Unat), re-enriched depleted uranium (Udep), enriched uranium recycled from spent fuel (Urep), plutonium recycled from spent fuel (MOX), and uranium blended down from highly enriched uranium (HEU).

Enter a value into any one field of the Material Balance and click the "Calculate" button below. HELP new window
"t" = metric tonne. "HM" = heavy metal. "Puf" = fissile plutonium (Pu-239 and Pu-241). "wt-%" = weight-percent.
"RB" = Raw Blendstock. "FB" = Final Blendstock.

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Material Balance
 UnatUdepUrepMOXHEU
Source
Material
t U3O8
(= t Unat)
t U3O8
(= t Udep)
t UO3
(= t Urep)
kg Pu
(= kg Puf)
t UO2
(= t U)
kg UO3 HEU
(= kg U)
t U3O8 RB
(= t U)
Conver-
sion
t UF6 (nat) t UF6 (dep) t UF6 (rep)  t UF6 HEU

t UF6 RB
Re-Enrich-
ment
  SWU
t UF6 (nat-equiv.)
     
Enrich-
ment
SWU
t UF6 (enriched)
SWU
t UF6 (enriched)
SWU
t UF6
(rep,enriched to equiv.)
  SWU
t UF6 FB
Fuel
Fab.
t UO2
(= t U)
t UO2
(= t U)
t UO2
(= t U)
t MOX
(= t HM)
t UO2
(= t U)
Power
Plant
GWhe ( = GWae)

Cost Summary (in Thousand US$)
 UnatUdepUrepMOXHEU
Source Material
Conversion 
Re-Enrichment    
Enrichment 
Fuel Fabrication
Total


Cost Summary Chart

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    Cost Parameters    
 UnatUdepUrepMOXHEU
Source Material
$ / lb U3O8
$ / kg U$ / kg U$ / kg Pu
$ / kg U
$ / kg U HEU
$ / kg U RB
Conversion$ / kg U *)$ / kg U *)$ / kg U $ / kg U HEU
Re-Enrichment $ / SWU   
Enrichment$ / SWU *)$ / SWU  
Fuel Fabrication$ / kg U$ / kg U$ / kg HM$ / kg U

Assay Summary
 UnatUdepUrepMOXHEU
 [wt-% U-235][wt-% U-235][wt-% U-235][wt-% U-236][wt-% U-235][wt-% Puf][wt-% U-235][wt-% U-236]
Feed (re-enr.)
(enr.)
   (HEU)
(RB)
(FB)
(HEU)


Fuel
Tails (re-enr.)
(enr.)
   

    Process Parameters    
Source
Material
Unat Unat enrichment to initial enrichment (see Power Plant)
Unat tails assay: wt-% U-235
Udep Step 1: Udep re-enrichment to natural equivalent (0.711 wt-% U-235)
Udep feed assay: wt-% U-235   ·   tails assay: wt-% U-235
Udep supplied as: U3O8,   UF6
Step 2: further enrichment to initial enrichment (see Power Plant); tails assay: see Unat
Urep Urep reprocessed after 5 year storage of spent fuel after unload from reactor
Urep enrichment to initial enrichment equivalent (see Power Plant); tails assay: 0.2 wt-% U-235
MOX Puf equiv. of U-235: g Puf per g U-235
Puf conc. in total Pu: wt-% Puf
MOX U component assay: wt-% U-235
HEU HEU assay: wt-% U-235   ·   wt-% U-236

Blendstock sample:
DU = depleted uranium · Unat = natural uranium · SEU = slightly enriched uranium

Final Blendstock (FB) assay: wt-% U-235

If Final Blendstock is obtained by enrichment of Raw Blendstock:
Raw Blendstock (RB) assay: wt-% U-235   ·   Tails assay: wt-% U-235

Raw Blendstock (RB) supplied as: U3O8,   UF6

Factor for U-236 effect: excess wt-% U-235 per wt-% U-236
Conversion Losses: %
Fuel Fabrication Losses: %
Power Plant burnup · initial enrichment:

Efficiency: %


> See also:

 

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