Arn 01-0-nuclear fission

Fission Reactions ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],Possible neutron Interactions with U-235

Fission Reactions ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],232 Th and 238 U are FERTILE nuclides

Characteristics of the Fission Reaction ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],Coulomb Repulsion >> Nuclear Forces

Fission Products ,[object Object],[object Object],[object Object],[object Object],Hahn and Strassman discovered fission Characterization of Promethium and production of Samarium. Very effective thermal neutron absorbers Discovery and Production of Technetium for medical applications Production of Xe-135, largest low energy neutron absorption X-section

Fission Products ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002

Fission Products ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]

Neutron Emission in Fission ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],DELAYED Neutrons are ESSENTIAL to control the Nuclear Reaction Average Number of PROMPT Neutrons DELAYED Neutron Fraction Average TOTAL Number of Neutrons

Delayed Neutron Emission Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002

Neutron Emission in Fission ,[object Object],[object Object],[object Object],[object Object],Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002

Prompt Energy Released ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],6.7 MeV 5.2 MeV

Energy from Fission Products ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002

Delayed Energy Released Anti-neutrino Decay Chains Energy = Mass Defect c 2 Delayed Fission Energy Released

Energy Released in Fission Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002

Energy Released in Fission ,[object Object]

Nuclear Fission Chain Reaction ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],Leakage 2 nd generation 3 rd generation 1 st generation Non-Fission Absorption

The Neutron Cycle in a Thermal Reactor Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002

Quantification of the Thermal Cycle ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]

Quantification of the Thermal Cycle ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]

Quantification of the Thermal Cycle ,[object Object],[object Object],[object Object],[object Object],Thermal Diffusion Coefficient Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002

Quantification of the Thermal Cycle ,[object Object],[object Object],[object Object],[object Object],[object Object],Fuel Absorption rate Non-Fuel Absorption rate  MUST be > 1 for a self sustaining chain reaction

Quantification of the Thermal Cycle Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002

Quantification of the Thermal Cycle ,[object Object],[object Object],[object Object],k ∞ depends only on the MATERIAL in the core

Core Design Estimates ,[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object],[object Object]

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.

Core Design Estimates ,[object Object],[object Object],[object Object],[object Object],Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002 Only Heavy Water as a Moderator can be used for an homogeneous natural uranium reactor

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

Core Design Estimates ,[object Object],[object Object],[object Object],Reflectors reduce Leakage Reflectors reduce Peak-to-average power Reflectors reduce Fast Neutron Flux outside the core  neutrons/cm 2 s center Source: J.K. Shultis and R.E. Faw, “Fundamentals of Nuclear Engineering”, Marcel Dekker, 2002

Arn 01-0-nuclear fission

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