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