Physics HL · Chapter 24: Nuclear Fission
24.3 Reactor Core Components and Control
Connect moderator, fuel, coolant, control rods, and shielding to the underlying neutron and heat-flow physics.
Estimated time: 46 minutes
Fuel and Enrichment
Most thermal reactors rely on uranium fuel with controlled enrichment of U-235. Higher enrichment generally improves neutron economy for sustained fission, but it also changes control requirements and proliferation risk profiles. Engineering design is therefore a tradeoff, not simply a race to maximize enrichment.
Moderator Role: Slow Neutrons, Improve Capture Probability
Fast neutrons born from fission are often too energetic for efficient capture by U-235 in thermal designs. A moderator such as water or graphite reduces neutron kinetic energy through repeated collisions, increasing the probability that neutrons induce further fission instead of escaping or being absorbed elsewhere.
Important
Removing the moderator from a thermal reactor usually reduces fission rate because neutrons remain too fast for efficient U-235 capture.
Control Rods and Coolant Loops
Control rods absorb neutrons and provide active reactivity control. Insertion depth determines how strongly neutron population is suppressed. Coolant systems remove thermal energy from the core and deliver it to steam-generation stages. A reactor can be neutron-stable but thermally unsafe if heat extraction fails, so neutronics and thermal hydraulics must be managed together.
Shielding and containment complete the system-level view. Thick concrete and engineered barriers limit radiation leakage in normal operation and reduce environmental release risk in accident scenarios. Distinguish clearly between reactor conditions that alter chain rate and structures that limit radiation exposure.
Simulation: Reactor Core Control Surface
Tune enrichment, moderator effectiveness, control-rod insertion, and coolant flow to inspect k-effective, thermal/electrical output, and safety margin trends.
k_eff
0.941
Thermal power
893.8 MW
Electrical output
295.7 MW
Core temperature
396.7 degC
Safety margin
100.0 %
Test Yourself
In a standard thermal reactor, what is the most likely immediate effect if moderator performance drops sharply while all else is unchanged?