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PWR Operator Manual · Open the simulator

10 — Glossary

Document: PWR-GL-01
Revision: 24

Terms used in the PWR manuals and on the simulator board. Acronym first, then plain meaning.


Plant MODES

Convention: write Mode N, Name (example: Mode 1, At Power).

MODEFull formShort definition
1Mode 1, At PowerCritical, thermal power > 5 %, RCS hot
2Mode 2, StartupCritical, power ≤ 5 %, RCS hot
3Mode 3, Hot StandbySubcritical, RCS hot (NOP T/P)
4Mode 4, Hot ShutdownSubcritical, intermediate RCS temperature
5Mode 5, Cold ShutdownSubcritical, RCS cold
6Mode 6, RefuelingCold, vessel head not fully tensioned (out of scope here)

Mode 5, Cold Shutdown → Mode 1, At Power and Mode 1, At Power → Mode 5, Cold Shutdown master procedures: 05_MODE_TRANSITIONS.md (PWR-T20, PWR-T21). Both run end to end on integrated physics — Mode 5 was restored 2026-08-31 when the water-property floor moved below its boundary (09 §11.0).

Not plant MODES: turbine load modes Follow / Manual / Disconnected.


A

TermDefinition
AC / DCAlternating-current / direct-current electrical power.
AFWAuxiliary Feedwater — backup water supply to the Steam Generators when main feed is lost.
ATWSAnticipated Transient Without Scram — event where the reactor should trip but rods fail to insert fully.
AUTO / MANAutomatic / manual control of a plant channel. AUTO reads instruments and issues commands to hold a setpoint; MAN leaves control to the operator.

B–C

TermDefinition
Borate / DiluteRaise / lower dissolved boron concentration via CVCS (adds / removes negative reactivity) — done by setting the BORON CONTROL target ppm (batch dose), not a live meter seek.
CHEM SAMPLE / chemistry sampleRCS grab sample analyzed by the lab; the result (posted after a real 30-minute lab turnaround) is the authoritative boron ppm — there is no online boron meter on the board.
BOPBalance of Plant — turbine, condenser, feedwater, and related secondary systems.
CVCSChemical & Volume Control System — charging, letdown, boron adjust, inventory make-up.
Critical / CriticalitySteady chain reaction: reactivity ≈ 0; power neither grows nor dies away on its own.
Cold ShutdownRCS cool and depressurized, RHR carrying the heat sink — Mode 5, Cold Shutdown. [sim]: a Free Play initial condition, and the full path to and from power runs on integrated physics (PWR-T20 / PWR-T21).

D

TermDefinition
Decay heatHeat from radioactive decay after fission stops (~7 % of rated after a power run, then falling).
RHRResidual Heat Removal — the low-pressure system that removes leftover decay heat after shutdown.
DNBDeparture from Nucleate Boiling — heat-transfer crisis; fuel temperature rises sharply.
DopplerNegative reactivity feedback from hotter fuel absorbing more neutrons (prompt stabilizer).
DPMDecades Per Minute — unit of Startup Rate (one decade = factor of ten in power).

E–F

TermDefinition
ECCSEmergency Core Cooling System — here, merged HPI/LPI plus passive accumulators.
ESFEngineered Safety Features — systems such as HPI and AFW with AUTO/MAN arms.
Follow (load mode)Turbine electrical load automatically tracks reactor power.

H

TermDefinition
Heat sinkWhere core heat goes — primarily the Steam Generators (secondary water/steam).
Hot Full Power (HFP)~100 % power, ~100 MWe, equilibrium — full-power Mode 1, At Power.
Hot StandbySubcritical, hot, at operating temperature and pressure — Mode 3, Hot Standby.
Hot ShutdownSubcritical with RCS not yet cold — commercial Mode 4, Hot Shutdown. [sim]: the trainer derives it from power, reactivity and Tavg, so it is what the board declares while transiting between Mode 3 and Mode 5, and what the hot_shutdown preset loads. A post-trip board still at operating temperature is Mode 3, Hot Standby by temperature class.
Cold ShutdownSubcritical and cold — Mode 5, Cold Shutdown. [sim] — see the Cold Shutdown entry under C.
HPI / LPIHigh- / Low-Pressure Injection — merged emergency injection with a two-segment pump curve.
HR1Simulator hard rule: protection and alarms read instruments, never true state.

I–L

TermDefinition
Instrument / IndicationWhat the operator sees — lagged, noisy, possibly failed — not necessarily truth.
IRIntermediate Range — compensated ion chamber (amperes) from SR handoff up to ~10 % power.
LOCALoss-Of-Coolant Accident — primary coolant escaping the RCS.
LOFWLoss Of Feedwater — main feed to the SGs lost.
Load rejectionSudden loss of electrical load / turbine trip; steam demand collapses.

M–O

TermDefinition
MSIVMain Steam Isolation Valve — isolates Steam Generators from the turbine.
MTCModerator Temperature Coefficient — in a PWR, negative: hotter water → less reactivity.
MWe / MWtMegawatts electric (grid) / megawatts thermal (reactor heat).
Natural circulationFlow driven by density difference after pumps stop — weaker than forced RCP flow.
NOPNormal Operating Pressure/Temperature (hot operating conditions).

P

TermDefinition
P-6Permissive: intermediate range on scale (≥ 1e-10 A). Allows the source-range trip to be blocked, which also switches the detector off (Trip Blocks panel, SR HIGH FLUX); resets below 5e-11 A, clearing the block. See 09 §2.0.
P-10Nuclear at-power permissive (8 % on this plant, the same crossing as P-7) — allows blocking the intermediate-range and power-range low-setpoint trips, and revokes a standing block below itself.
pcmPercent millirho — unit of reactivity (1 pcm = 10⁻⁵ Δk/k).
POAHPoint of Adding Heat — power level where fission heat exceeds system losses.
PORVPower-Operated Relief Valve — controllable RCS pressure relief on the pressurizer.
PORV block valveIsolation valve upstream of the PORV; closes the relief line if the PORV sticks open.
PRPower Range — main power % neutron channels at power.
Primary / RCSReactor Coolant System — high-pressure water loop through the core.
PWRPressurized Water Reactor.
PZRPressurizer — steam/water vessel that sets primary pressure.

R

TermDefinition
RCPReactor Coolant Pump — forced circulation in the primary loop.
Reactivity (ρ)Tendency of the chain reaction to grow (+) or shrink (−); critical ≈ 0.
Reactor periodTime for power to change by a factor of e (~2.72); long period = slow change.
RPSReactor Protection System — automatic SCRAM logic.
Rod bank (control)Operable control rods for reactivity control.
Rod bank (shutdown)Scram rods, normally fully withdrawn; drive in on SCRAM.

S

TermDefinition
SBLOCASmall-Break LOCA — e.g. stuck-open PORV.
SBOStation Blackout — loss of all AC power (as modeled).
SCRAMRapid full insertion of control rods — emergency/automatic shutdown.
SecondarySteam side: SG secondary, turbine, condenser, feedwater.
Setpoint (SP)Value an automatic controller holds; often captured from the current reading when AUTO engages.
SGSteam Generator — heat exchanger boiling secondary water using primary heat.
SGTRSteam Generator Tube Rupture — primary-to-secondary leak.
Shrink and swellIndicated SG level moves “wrong way” briefly on fast power/load changes.
SRSource Range — startup neutron counter (counts per second).
Subcooling marginHow far primary coolant is below boiling temperature at current pressure — TMI truth-teller.
SURStartup Rate — how fast power is changing, in decades per minute (DPM).

T–X

TermDefinition
TavgAverage primary coolant temperature.
Thot / TcoldHot-leg / cold-leg temperatures.
TMIThree Mile Island (1979 accident).
True stateActual physics values in the model — hidden from normal operator view.
Void / void fractionSteam bubbles in the coolant; reduce heat transfer; affect inventory presentation.
Xenon (Xe-135)Strong neutron-absorbing fission product; builds after power drops; decays over hours.

These manuals are licensed CC BY 4.0 — see Legal. Training documents for an educational simulator, not licensing-basis documents for a real plant.