These are just my notes on the textbook "Nuclear Systems" Volume 1, by Todreas and Kazimi. The textbook seems to be a classic on "Thermal Hydraulic Fundamentals" of nuclear power reactors.
This chapter attempts to give a friendly, high-level comparison of the different kinds of nuclear power reactors out there. It gives some reference as to their similarities and differences, and general performance and safety characteristics.
Neutron Energy Range | Energy Range Name |
---|---|
0 - 0.025 eV | Cold Neutrons |
0.025 eV | Thermal Neutrons |
1 - 20 MeV | Fast Neutrons |
Note: Thermal Neutrons have probably bounced around a bit and are at room temperature. Note: Fast Neutrons are of particular interest, as they are what TerraPower is designing for.
- LWR - light water reactor (category)
- HWR - heavy water reactor (category)
- PWR - pressurized water reactor
- BWR - boiling water reactor
- PHWR - pressurized heavy water reactor
- SGHWR - steam-generating heavy water reactor
- AGR - advanced gas reactor
- HTGR - high-temperature gas reactor
- SFR - sodium-cooled fast reactor
- SFBR - sodium-cooled fast breeder reactor
- core
- moderator
- coolant
- generator
- control rod
- fuel pin
- fuel pellet
Core Energergy Production Parameters
variable | units | description |
---|---|---|
q'''(r) | W / cm^3 | volumetric energy generation rate |
q''(s) | kW / m^3 | surface heat flux |
q'(z) | kW / m | linear power / linear heat generation rate |
q dot | kW | energy generation rate per pin |
Q dot | MW | core power |
Q''' Qdot_th / V_core | kW / L | core power density |
Q^m Qdot_th/M_IHM | kW / kg_IHM | core-specific power |
Obviously, the q dot through q''' above are related by spatial integrals.
- IHX - Intermediate Heat eXchange
- IHM - Initial Heavy Metal
- CHF - Critical Heat Flux
- DNB - Departure from Nucleate Boiling