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HT 2005T8: Chain Reaction1 Chain Reaction Multiplication Criticality Conditions.

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Presentation on theme: "HT 2005T8: Chain Reaction1 Chain Reaction Multiplication Criticality Conditions."— Presentation transcript:

1 HT 2005T8: Chain Reaction1 Chain Reaction Multiplication Criticality Conditions

2 HT 2005T8: Chain Reaction2 Overview Chain Reaction Conversion and Breeding Doubling Time Neutron Cycle in a Thermal Reactor Multiplication Factor k Simplified Fuel Cycle Fuel at Discharge

3 HT 2005T8: Chain Reaction3 Chain Reaction ν β γ γ β ν n

4 HT 2005T8: Chain Reaction4 Uranium Fuel 238 U 4.5 10 9 yr 235 U 0.7 10 9 yr 234 U 247000 yr Application U nat 99.27%0.72%0.006%CANDU (D 2 O) UE98-95%2-5%0.006%LWR (H 2 O) DU (UD)99.8%0.2%0.006% Fast Reactor (FR, FBR) Armour for tanks Armour-piercing

5 HT 2005T8: Chain Reaction5 Conversion or Breeding

6 HT 2005T8: Chain Reaction6 Conversion

7 HT 2005T8: Chain Reaction7 Conversion

8 HT 2005T8: Chain Reaction8 Neutron Cycle in Reactor n/fission N1N1 N2N2 Leakage Fast fission Resonance abs. Non-fuel abs. Leakage Non-fissile abs. Fission Slowing down Energy E 2 MeV 1 eV 200 MeV/fission ν ≈ 2.5

9 HT 2005T8: Chain Reaction9 Fast Fission

10 HT 2005T8: Chain Reaction10 Simple Criticality Calculations

11 HT 2005T8: Chain Reaction11 Fuel Cycle (Thermal) Fuel Factory Thermal Reactor DU Fissile Materials Actinides (MA) Fiss. Pr. (FP) Spent Fuel

12 HT 2005T8: Chain Reaction12 Fuel Cycle (Fast) Fuel Factory Fast Reactor FP+MA Spent Fuel DU

13 HT 2005T8: Chain Reaction13 Neutron Economy

14 HT 2005T8: Chain Reaction14 Breeding Factor 1 neutron absorbed in fuel η neutrons produced B neutrons captured in fertile Non-fuel capture and losses C+L 1 neutron to maintain chain reaction

15 HT 2005T8: Chain Reaction15 η Factor η Isotope (100%) Thermal (0.025eV) Fast (>0.5 MeV) 235 U2.072.35 233 U2.292.40 239 Pu2.152.90

16 HT 2005T8: Chain Reaction16 Fission Neutrons 239 Pu 235 U 233 U E = 1

17 HT 2005T8: Chain Reaction17 Conversion Factor If B < 1 it is called conversion factor, C. Number of 239 Pu created per 1 neutron absorbed Reactor System Initial Fuel Conversion Cycle Conversion Ration BWR 235 U (2-4%) 238 U → 239 Pu0.6 PWR 235 U (2-4%) 238 U → 239 Pu0.6 PHWR (CANDU)U nat 238 U → 239 Pu0.8 HTGR 235 U (5%) 232 Th → 233 U0.8 LMFBR 239 Pu (10-20%) 238 U → 239 Pu1.0 – 1.6

18 HT 2005T8: Chain Reaction18 Neutron Cycle in Reactor n/fission N1N1 N2N2 Leakage Fast fission Resonance abs. Non-fuel abs. Leakage Non-fissile abs. Fission Slowing down Energy E 2 MeV 1 eV 200 MeV/fission ν ≈ 2.5

19 HT 2005T8: Chain Reaction19 Chain Reaction in U nat ?

20 HT 2005T8: Chain Reaction20 Doubling Time T d for a breeder reactor is the amount of time required for the original fissile loading to double

21 HT 2005T8: Chain Reaction21 Doubling Time for FR

22 HT 2005T8: Chain Reaction22 Multiplication Factor

23 HT 2005T8: Chain Reaction23 Chain Reaction by Fast N. 235 U

24 HT 2005T8: Chain Reaction24 Time to Fission 1 kg 235 U

25 HT 2005T8: Chain Reaction25 Energy Comparison

26 HT 2005T8: Chain Reaction26 Distribution of FP Mass

27 HT 2005T8: Chain Reaction27

28 HT 2005T8: Chain Reaction28 Long-Lived Radio Isotopes

29 HT 2005T8: Chain Reaction29 Half-Lives of L.L. Isotopes

30 HT 2005T8: Chain Reaction30 The END


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