Advanced PWR Thermal Loop Simulator

Nuclear Reactor System Overview

Interactive simulation mapping the reactor core, multi-loop heat exchange, adjustable coolant pump speeds, turbine generation, and cooling water dynamics.

System Telemetry

Core Temperature: 315 °C
Control Rods: 50%
Primary Pump Flow: 50%
Turbine Speed: 3,000 RPM
Power Generation: 1,000 MW

Operator Controls

Comprehensive Nuclear Plant Components

Detailed structural analysis of the pressurized water reactor (PWR) loop contained within the reinforced confinement shell.

1. Reactor Core & Control Rods

Houses enriched nuclear fuel assemblies. Neutron-absorbing control rods are lowered or raised dynamically to control fission rates and core reactivity.

2. Primary Loop & Circulation Pump

High-pressure water absorbs intense thermal energy from the core and is forced through the steam generator via heavy-duty coolant pumps.

3. Steam Generator (Heat Exchanger)

Isolates radioactive primary water from secondary loops while transferring thermal energy to vaporize secondary water into clean high-pressure steam.

4. Turbine, Generator & Condenser

Expansion of steam drives the turbine rotor linked to the electric generator. Exhaust steam is cooled back into liquid via external water sources.