| AECL |
Atomic Energy of Canada Ltd. |
| AECB |
Atomic Energy Control Board |
| AESOP |
Atomic Energy Simulation of Optimization (computer code) |
| ASDV |
Atmospheric Steam Discharge Valve |
| ASSERT |
Advanced Solution of Subchannel Equations in Reactor Thermalhydraulics
(computer code) |
| ASTM |
American Society for Testing Materials |
| BLC |
Boiler Level Control |
| BLW |
Boiling Light Water |
| BPC |
Boiler Pressure Controller |
| CCP |
Critical Channel Power |
| CHF |
Critical Heat Flux |
| CPR |
Critical Power Ratio |
| CRL |
Chalk River Laboratories |
| CRT |
Cathode Ray Tube |
| CSA |
Canadian Standards Association |
| CSDV |
Condenser Steam Discharge Valve |
| CSNI |
Canadian Standards for the Nuclear Industry |
| DBE |
Design Base Earthquake |
| DCC |
Digital Control Computer |
| DF-ET |
Drift Flux-Equal Temperature |
| DF-UT |
Drift Flux-Unequal Temperature |
| DNB |
Departure from Nucleate Boiling |
| ECC |
Emergency Core Cooling |
| ECI |
Emergency Core Injection |
| EFPH |
Effective Full Power Hours |
| EVET |
Equal Velocity Equal Temperature |
| EVUT |
Equal Velocity-Unequal Temperature |
| EWS |
Emergency Water Supply |
| FBR |
Feed, Bleed and Relief |
| FP |
Full Power |
| HEM |
Homogeneous Equilibrium Model |
| HTS |
Heat Transport System |
| HWP |
Heavy Water Plant |
| HYDNA |
Hydraulic Network Analysis (extinct computer code) |
| I&C |
Instrumentation and Control |
| IBIF |
Intermittent Buoyancy Induced Flow |
| ICRP |
International Commission on Radiological Protection |
| LOC |
Loss of Coolant |
| LOCA |
Loss of Coolant Accident |
| LOC/LOECC |
Loss of Coolant with Coincident Loss of Emergency Core Cooling |
| LOP |
Loss of Pumping |
| LOR |
Loss of Regulation |
| MCCR |
Ministry of Corporate and Consumer Relations |
| MCS |
Maintenance Cooling System |
| MHD |
Magneto hydrodynamics |
| milli-k |
Unit of reactivity for reactor physics |
| NPD |
Nuclear Power Demonstration |
| NPSH |
Net Positive Suction Head |
| NUCIRC |
Nuclear Circuits (computer code) |
| OECD |
Organization for Economic Co-operation & Development |
| OH |
Ontario Hydro |
| PGSA |
Pickering Generating Station A |
| PHTS |
Primary Heat Transport System |
| PHW |
Pressurized Heavy Water |
| PHWR |
Pressurized Heavy Water Reactor |
| PRESCON2 |
Pressure Containment (computer code) |
| QA |
Quality Assurance |
| RAMA |
Reactor Analysis Implicit Algorithm |
| R&M |
Reliability and Maintainability |
| RB |
Reactor Building |
| RIH |
Reactor Inlet Header |
| ROH |
Reactor Outlet Header |
| RTD |
Resistance Temperature Detectors |
| SDM |
Safety Design Matrices |
| SOPHT |
Simulation of Primary Heat Transport (computer code) |
| SRV |
Safety Relief Valve |
| TMI |
Three Mile Island |
| TOFFEA |
Two Fluid Flow Equation Analysis (computer code) |
| UVUT |
Unequal Velocity Unequal Temperature |
| VB |
Vacuum Building |
| VC |
Vacuum Chamber |
| WRE |
Whiteshell Research Establishment |
