PWR Operator Manual · Open the simulator
01 — Plant General Description
Document: PWR-GD-01
Plant: Pressurized Water Reactor (PWR)
Plant: SLS-100 (Single Loop Simulated, 100 MWe) Rating: ≈ 100 MWe / ≈ 300 MWt — a compact single-loop experimental PWR (one reactor coolant pump, one U-tube steam generator, one main steam line). Small and generously margined by design, and reactor trips are reserved for genuine limits. The steam dump is sized at 40 % of rated steam flow, the prototypical Westinghouse capacity: a 50 % loss of load is absorbed with no trip and no relief lift, and a larger rejection is ridden out by the reactor itself running back, with the PORV as the backstop.
Revision: 24
1.0 Purpose
This document describes the Reactor⚛️Dynamics PWR unit: design concept, major systems, operating modes, and deliberate simplifications. Operators should read this before free-play or procedure training.
2.0 Design concept
A Pressurized Water Reactor keeps primary coolant water under high pressure so it does not boil in the core. Heat is transferred through Steam Generators (SG) into a separate secondary loop that produces steam for the turbine-generator.
| Parameter | Nominal (hot full power) |
|---|---|
| Electrical output | ≈ 100 MWe |
| Primary pressure | 2235 psi (15.41 MPa) |
| Average coolant temperature (Tavg) | ≈ 580.3 °F (304.6 °C) — on its program, Tref 580.1 °F (304.5 °C) |
| Hot leg / cold leg | ≈ 609.8 / 550.9 °F (321.0 / 288.3 °C) (ΔT ≈ 58.9 °F / 32.7 °C at rated) |
| Pressurizer (PZR) level | ≈ 61.5 % |
| Steam Generator level | ≈ 65 % |
| Secondary steam pressure | ≈ 827 psi (5.70 MPa) |
| Subcooling margin | ≈ 42.7 °F (23.7 °C) — taken at the hot leg, the hottest water in the loop; the board reads about 44 °F |
Why high primary pressure? Subcooling margin (how far the coolant is from boiling) is the plant’s guarantee that the primary stays liquid. Lose pressure or overheat the coolant, and boiling (voids) begins — the lesson behind Three Mile Island.
3.0 Energy path (what the operator is controlling)
FISSION HEAT (core)
→ Primary coolant (hot leg → SG U-tubes → cold leg → RCP → core)
→ Steam Generator (secondary boils; loops never mix)
→ Main steam → Turbine-Generator → Grid (MWe)
→ Condenser → Feed pumps → SG
Pressurizer (PZR) sits on the hot leg: heaters raise pressure, spray lowers it, and the Power-Operated Relief Valve (PORV) with block valve protects / can mislead.
Negative feedbacks (Doppler and Moderator Temperature Coefficient) make the plant self-regulating: hotter fuel and hotter moderator reduce reactivity. Power tends to follow steam demand.
4.0 Major systems
4.1 Reactor core and reactivity control
| System | Function |
|---|---|
| Control bank | Operable rods — withdraw to add reactivity, insert to remove |
| Shutdown bank | Emergency-protection group carrying shutdown margin — operable, with Withdraw / Insert on the board (one click drives the full stroke at fast speed). Parked fully withdrawn at power; SCRAM drives it in and overrides any manual command. Not for routine trim — see 03 §3.3 |
| Boron (CVCS chemical shim) | Dissolved neutron absorber — borate lowers power, dilute raises power (slow) |
| Nuclear Instrumentation (NIS) | Source Range (SR), Intermediate Range (IR), Power Range (PR) |
Simplification: One control group + one shutdown group (no multi-bank overlap sequencing).
4.2 Reactor Coolant System (RCS) / primary
| System | Function |
|---|---|
| RCP | Forced circulation; spray effectiveness depends on RCP flow |
| Pressurizer | Pressure control (heaters / spray / PORV / spring safeties) |
| CVCS | Charging, letdown, boron adjust, inventory make-up |
| HPI/LPI | Merged emergency injection (high-head trickle, high volume at low pressure) |
| Accumulators | Passive injection when primary pressure falls low enough |
| RHR | Residual heat removal when cool and depressurized |
Simplification: Single lumped primary loop (one representative RCP/SG), uniform primary pressure (no leg ΔP model).
4.3 Secondary / Balance of Plant (BOP)
| System | Function |
|---|---|
| Steam Generator | Heat sink and steam source |
| Main feed / feed pump | Maintains SG level (manual or three-element AUTO) |
| AFW | Auxiliary Feedwater when main feed is lost |
| MSIV | Isolates SG from turbine — and from a steam line break downstream of it (PWR-E19) |
| Turbine-generator | Electrical output; load modes Follow / Manual / Disconnected |
| Steam dump | Bypasses steam to the condenser. Two modes: a continuous AUTO mode holding secondary pressure at the dump setpoint — the mechanism behind heatup, cooldown and hot standby holding its own temperature — and a fast-open mode armed by a load rejection. Sized at 40 % of rated steam flow |
| Condenser | Vacuum must be healthy or turbine trips |
4.4 Protection and safety automation
| Layer | Role |
|---|---|
| RPS (Reactor Protection) | SCRAM on trip setpoints (reads instruments) |
| ESF arms (HPI, AFW, RHR) | AUTO or MANUAL; manual action disarms AUTO until re-armed |
| Alarms | Annunciate before / with trips; read instruments only |
| Interlocks | e.g. rod withdrawal blocked by a rod stop (high flux, or ΔT margin) |
5.0 Plant MODES (Mode 1, At Power through Mode 6, Refueling)
This trainer uses commercial PWR MODE numbers. In prose, say Mode 1, At Power, Mode 2, Startup, … Mode 6, Refueling.
| MODE | Spoken name | Name | Definition (trainer) | Free Play / notes |
|---|---|---|---|---|
| 1 | Mode 1, At Power | Power Operation | Critical, thermal power > 5 %, RCS hot | hot_full_power, 50_percent, 5_percent [sim] |
| 2 | Mode 2, Startup | Startup | Critical, power ≤ 5 %, RCS hot | After approach to criticality [sim] |
| 3 | Mode 3, Hot Standby | Hot Standby | Subcritical, RCS hot (Tavg ≥ 350.6 °F (177 °C)) | hot_zero_power [sim] |
| 4 | Mode 4, Hot Shutdown | Hot Shutdown | Subcritical, Tavg between 199.4 °F (93 °C) and 350.6 °F (177 °C) | Heatup / cooldown transit [sim] |
| 5 | Mode 5, Cold Shutdown | Cold Shutdown | Subcritical, RCS cold (Tavg ≤ 199.4 °F (93 °C)) | cold_shutdown [sim] — 122 °F (50 °C), 363 psi (2.50 MPa), RHR in service. |
| 6 | Mode 6, Refueling | Refueling | Head detensioned / refueling | Out of scope |
Modes 3/4/5 are decided by TEMPERATURE alone, not by pressure. A subcritical plant at 392 °F (200 °C) and 500 psi (3.45 MPa) is Mode 3 here even though it is nowhere near normal operating pressure — the boundaries above are the whole definition.
5_percentis a Mode 1 initial condition: it is authored at ~6 % power, deliberately just above the 5 % boundary.
Full commercial paths (see 05_MODE_TRANSITIONS.md) — both run on integrated physics, end to end on the board:
- Mode 5, Cold Shutdown → Mode 1, At Power — procedure PWR-T20, starting from the
cold_shutdowninitial condition (09 §11.0). - Mode 1, At Power → Mode 5, Cold Shutdown — procedure PWR-T21, down to a cold, depressurized plant on RHR.
NOTE: the heatup runs on real plant rates — ride the long legs at time acceleration; on the cooldown side the depressurisation rate remains deliberately compressed. See 12 §14.
Sim-only everyday path: Mode 3, Hot Standby ↔ Mode 1, At Power (PWR-T03 / PWR-T04).
Post-trip with the plant still hot is still Mode 3, Hot Standby by temperature class (subcritical, hot), even though crews often say “hot shutdown.”
6.0 Turbine load modes (not plant MODES)
Independent of plant MODE, the generator has three load modes:
| Load mode | Behavior |
|---|---|
| Follow | Turbine load tracks reactor power (lag ~45 s) |
| Manual | Operator sets the MWe target. This is the lineup Free Play hands you at hot_full_power and 50_percent, and what the rest of these manuals assume |
| Disconnected | 0 MWe, generator off line. Reached by a planned offline (breaker opens, no trip latches) or by a turbine trip — two different events that share one lamp; read TURB TRIP to tell them apart (03 §12.1). A SCRAM forces this |
Manual is the default you actually get, not Follow. Follow is the engine's own fallback and is what 5_percent starts in; the startup lineup overrides it to Manual at both main at-power initial conditions, and hot_shutdown spawns off line.
Coupled feedwater is a fallback, not the level control. Feed is briefly tied to the load target, but the three-element feed controller (STEAM GEN FEED → AUTO) is engaged by default in Free Play and takes the steam generator level as soon as it acts — measured, the coupling drops out within about three minutes of a full-power start. Treat three-element AUTO as the level backbone (PWR-N12); coupled feed is what remains when it is off.
Rule of thumb: The turbine leads, up and down: set LOAD, then move the rods to hold AVG COOLANT TEMPERATURE on program (Westinghouse Technology Systems Manual 19.0, ADAMS ML11223A342, App. 19-1 step 22: "Increase generator load at the desired rate while maintaining Tavg with manual rod control."). Mismatch floods or drains the SG.
These are never called Mode 1, At Power / Mode 5, Cold Shutdown.
7.0 What the operator never sees by default
| Hidden / diagnostic | Why it matters |
|---|---|
True porv_open vs commanded porv_indicator | TMI deception |
| True core inventory / void fraction | Level can rise while inventory falls |
| Fuel temperature (raw) | Shown only as contextual status in Learning mode |
| Physics Overlay fields | Reactivity pcm, period, etc. — Learning + overlay |
Golden rule: Trust subcooling margin and diverse indications more than any single light.
8.0 Deliberate simplifications (honest scope)
| Topic | Real plant | This trainer |
|---|---|---|
| Rod banks | Multiple banks + overlap | One control + one shutdown |
| RCS loops | Multi-loop with individual RCPs | Single lumped loop — and this plant genuinely is single-loop |
| Cold ops (Mode 5 / Mode 4) | Multi-hour heatup/cooldown | [sim] on integrated physics — Free Play can start in Mode 5, Cold Shutdown; the full loop is PWR-T20 / PWR-T21. Heatup pacing is real (ride at time acceleration); the cooldown depressurisation leg remains compressed. |
| Containment / dose | Full models | Partly modeled. Containment pressure, temperature and sump level exist — the building receives break and relief discharge, and break flow throttles against its rising pressure; hydrogen is generated by the oxidizing core and tracked in the building. Engineered safeguards are automatic only: safety injection backs up on 3.5 psig (18.1 psi absolute / 0.125 MPa) containment pressure, and the high-high at 30 psig (44.7 psi absolute / 0.308 MPa) starts containment spray, realigns the fan coolers and shuts the main steam isolation valve — no board controls, no player levers (09 §3.0, 12 §12.4d). What this plant still does not have: no hydrogen recombiners and no hydrogen burn — no source document gives their capacities, so none was invented (12 §12.4e). The building has a way down now, but a limited one: spray and the fan coolers are AC loads and stay dark in a station blackout, so an unpowered plant's containment still only heats and pressurizes. Nothing past fuel damage: no source term, no release, no dose. Core damage and melt are simulated — cladding failure at 2192 °F (1200 °C), fuel melt at 5072 °F (2800 °C) |
| Instrument channels | Redundant trains | Single sensors (can fail) — so instrument failures bite harder here than in a voting plant |
| Point kinetics | Spatial power shape | Point model (lumped) |
| Decay heat | Detailed groups | Two-term model (~7 % at scram after power run) |
| Natural circulation | Buoyancy-driven flow on pump loss | Modeled — the steam generators sit above the core, so the hot/cold density difference drives flow when the RCPs stop. Flow follows the cube root of core heat and is gated on a liquid-filled loop: a voided loop circulates nothing. Magnitude is fitted to this plant, not to a published figure |
Where the model understates reality, training commentary and these manuals say so.
This table is a summary. The full account — what the engine actually computes, every deliberate simplification, and everything that is not modeled at all — is 12_SIM_PHYSICS.md.
9.0 Flagship accident
Three Mile Island Unit 2 (1979) is hosted on this plant. Root teaching theme: an accident of information — a stuck-open PORV with an indicator that read closed, pressurizer level that rose while inventory fell, and operators who throttled High-Pressure Injection (HPI) based on the wrong story.
See 08_ACCIDENT_TMI.md and procedure PWR-X01.
10.0 Related documents
02_SIMULATOR_USER_GUIDE.md— using the trainer03_CONTROLS_AND_INDICATIONS.md— board inventory09_SETPOINTS_LIMITS.md— numbers10_GLOSSARY.md— terms
These manuals are licensed CC BY 4.0 — see Legal. Training documents for an educational simulator, not licensing-basis documents for a real plant.