9. Delayed Neutron Emission Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002
10.
11.
12.
13. Delayed Energy Released Anti-neutrino Decay Chains Energy = Mass Defect c 2 Delayed Fission Energy Released
14. Energy Released in Fission Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002
15.
16.
17. The Neutron Cycle in a Thermal Reactor Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002
18.
19.
20.
21.
22. Quantification of the Thermal Cycle Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002
23.
24.
25. Core Design Estimates Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002 Increasing But, there is no U-233 in Nature, one must “make” it.
26.
27. Quantification of the Thermal Cycle Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002
28.
29. Core Design Estimates Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002 HETEROGENEOUS CORE Fuel Moderator Neutron moderation fast thermal More Heterogeneous: f decreases More heterogeneous: p increases There´s an optimum for k∞ max