Nuclear Power Acronyms

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Here you can find a list of Acronyms used in Nuclear Power Industry.

Organizations list is available - here

Acronyms used in Soviet and Russian Industry can be found - here



ABB A document classification code corresponding to reports and meeting minutes

ABWR Advanced Boiling Water Reactor Улучшенный кипящий водяной реактор

ADSR Accelerator Driven Subctritiacal Reactor Гибридный реактор: Подкритический реактор + источник нейтронов

AIMS Areva Infromation Management System

Organization (see *):

ANDRA - L'Agence nationale pour la gestion des déchets radioactifs Национальное агентство Франции по обращению с радиоактивными отходами

Organization (see *):


APC - AirPlane Crash

ASB - As-built

Organization (see *):

ASN - French Nuclear Safety Authority

ATWS - Anticipated Transient Without SCRAM

AVS Annulus Ventilation System



BDL Break Down Level

BLBase Load

Base load - wikipedia

BNI Balance of Nuclear Island

BNI Business Network International


BPW Burst Pressure Wave

BQ - Becquerel

1 bequerel = 1 nucleus decay per second

The becquerel (symbol Bq) is the SI derived unit of radioactivity. One becquerel is defined as the activity of a quantity of radioactive material in which one nucleus decays per second.

The becquerel is therefore equivalent to an inverse second, s−1. The becquerel is named after Henri Becquerel, who shared a Nobel Prize in Physics with Pierre and Marie Curie in 1903 for their work in discovering radioactivity.

Becquerel - wikipedia

BWB - Box Within a Box

The “box within a box” principle is to create a closed volume isolated from the main civil-engineering structure by intermediate elastic supports that damp the vibrations transmitted by neighbouring installations

BWR - Boiling Water Reactor

BWR is a type of light water nuclear reactor used for the generation of electrical power.

It is the second most common type of electricity-generating nuclear reactor after the pressurized water reactor (PWR), which is also a type of light water nuclear reactor.

The main difference between a BWR and PWR is that in a BWR, the reactor core heats water, which turns to steam and then drives a steam turbine. In a PWR, the reactor core heats water, which does not boil.

This hot water then exchanges heat with a lower pressure water system, which turns to steam and drives the turbine.

The BWR was developed by the Argonne National Laboratory and General Electric (GE) in the mid-1950s. The main present manufacturer is GE Hitachi Nuclear Energy, which specializes in the design and construction of this type of reactor.


CAE - Certified As Executed

CAR - Corrective Action Request

CC - Core Catcher

CC - Component Cooling

CCC - Commissioning Clearance Certificate

CCWS - Component Cooling Water System

CDF - Core Damage Frequency

CE - Commissioning Engineer

CE - Contract Effective (Date)

CEAR - Construction Erection All Risk

CED - Contract Effective Date

Organization (see *):

CEIP - Carnegie Endowment for International Peace

CEMDS - Condition of Equipment or Material upon Delivery on Site They are in the warehous drive site management 5-warehouse -material receiving inspection

CFC - Certified for Construction

Organization (see *):

CFS - Consortium Framatome – Siemens

Consortium AREVA NP GmbH – AREVA NP SAS – Siemens AG

CFT - Cold Functional Test

CFTRVO - Cold Functional Test with Reactor Vessel Open

CGCS - Combustible Gas Control System

Organization (see *):

CGN - China General Nuclear

Organization (see *):

CGNPC - China General Nuclear Power Group

China Guangdong Nuclear Power Holding

CHF - Critical Heat Flux

CHRS - Containment Heat Removal System

CHRSHE - Containment Heat Removal System Heat Exchanger

CHRSHX - Containment Heat Removal System Heat Exchanger

CI - Commissioning Instruction

CI - Construction Inspection

CI - Conventional Island

Ci - Curie

1 Curie = 3.7 × 10^10 decays per second (37 GBq)

The curie (symbol Ci) is a non-SI unit of radioactivity, named 'in honour of' Pierre Curie, according to his widow, the famed radiation researcher Marie Curie.

It was originally defined as

The quantity or mass of radium emanation in equilibrium with one gram of radium (element)

But is currently defined as:

1 Ci = 3.7 × 1010 decays per second

after more accurate measurements of the activity of 226Ra (which has a specific activity of 3.66 x 1010 Bq/g.)

In 1975 the General Conference on Weights and Measures gave the becquerel (Bq), defined as one nuclear decay per second, official status as the SI unit of activity.

Curie - wikipedia

CIAR - Construction Installation All Risk

CIB - Commissioning Inspections of NI Buildings

CID - Configuration Identification Document CID Review Sheet process

CIS - Core-internals storage

CIT - Conformed In Transit There are some missing documents so you can not take it from the warehouse



CMP - Configuration Management Plan

COEDM - Common Electronic Document Management

COM - Communications


COTC - Core Outlet Thermocouple

CP - Construction Plan

CR - Change Request

CR - Clarification Request

CR - Control Room

CR - Contract Resposible

CRDM - Control Rod Drive Mechanism

CS - Cover Sheet

CTCN - Consortium Technical Change Note

CTT - Containment Tightness Test

CVCS - Chemical and Volume Control System

cw - Calendar Week

CW - Civil Works

CWP - Customer witness point

CWS - Commissioning Worksheet


CYE Check Your Email


DAS - Document Approval Sheet

DBC - Design Basis Conditions

DC - Declaration of Conformity

DCC - Document Classification Code


DCR - Design Change Request Open Point type e.g.


DE - Design Earthquake

DEC - Design extension conditions (e.g. complex sequence of severe accidents)

DEN - Document Evolution Notice

DIR - Data Information Requests

DIS - Documents for Information and Scrutiny

DM - Design Manual (compilation of Design Procedures)

DMR - Design Modification Request

DMS - Document Management System

DNBI - Departure from Nucleate Boiling (Ration)

Organization (see *):

DOE - Department of Energy


DP - Design Procedure

DR - Deviation Report

DSA - Deterministic Safety Analysis

DT - Destructive Testing

DQM - Data Quality Monitor


EBITDA - Earnings before interest, taxes, depreciation and amortization EBITDA


EBS - Emergency Borating System

EBS - Extra Borating System

ECA - Emergency Control AreA

ECC - Erection Clearance Certificate

ECC - End of Construction Certificate

ECC - Erection Completion Certificates

ECC - Emergency Core Cooling

ECC - Engineered Cementitious Composites



EDF - Code System French Three-Letter Codes

Organization (see *):

EDF - Electricite de France


EDL - Engineer Discipline Leader

EDM - Electronic Document Management

EDMS - Electronic Document Management System

EDS - Electrical Distribution System

EEN - Engineering Evolution Note/Notice

EER - End of Erection Report

Same as TSE

EFS - Emergency Feedwater Systems

EFWS - Emergency Feed Water Systems

EIR - End of Installation Report

EITI - Extractive Industries Transparency Initiative

EM (-package) - Electromechanical (-package)

EM - Engineering Management

EOMM - Equipment Operation and Maintenance Manuals Same as TPM (Part of Equipment Documentation)

EOMP - End of Manufacturing Protocol Inside EOMR

EoMR - End of Manufacturing Report Same as TPQ (Part of Equipment Documentation)

EP - Erection Procedure

EPD - Electric Power Distribution

EPR - European Pressurized Water Reactor

EPSS - Emergency Power Supply System

EPW - Explosion Pressure Waves

ESW - Essential Service Water

ESWS - Essential Service Water System

ETA - Event Tree Analysis

ETCN - External Technical Change Note

EYT “Non-classified” safety class



FANP - Framatome-ANP

FAT - Factory Acceptance Tests

FAT - Final Acceptance Test

FA3 - Flamanville 3

FBR - Fast Breeder Reactor

In 2006 all large-scale fast breeder reactor (FBR) power stations were liquid metal fast breeder reactors (LMFBR) cooled by liquid sodium.

These have been of one of two designs:

Loop type, in which the primary coolant is circulated through primary heat exchangers outside the reactor tank (but inside the biological shield due to radioactive sodium-24 in the primary coolant)

Experimental Breeder Reactor II, which served as the prototype for the Integral Fast Reactor

Pool type, in which the primary heat exchangers and pumps are immersed in the reactor tank

FC - First Criticality

FCC - Fluid Catalytic Cracking

FC&LPT - First Criticality & Low Power Test

FCP - Field Change Process

FCR - Field Change Request Open Point type

FD - Final Documentation

FDC - Field Design Change

FDHO - Final Documentation Handover

FFAG - Fixed Field Alternating Gradient

FFTF - Fast Flux Test Facility FFTF

FG - Functional Group

FGM - Functional Group Manager

FIN - Final (Contract Status)

FIP - Final Inspection Plan

FIT - Final Integration Test


FL - Fuel Loading

FLG - Fuel Loading

FMEA - Failure Modes and Effects analysis

Organization (see *):

FMEE - Finnish Ministry of Employment and Economy

FPCS - Fuel Pool Cooling System

FQP - Field Quality Plan

FRR - Field Revision Request

applicable for TI

FSAR - Final Safety Analysis Report

FTE - Full Time Equivalent

FUD - Follow-up Document

FW - Finishing Works



GIP - General Inspection Plan

GNS - General Nuclear Services


HBO - Home-Based Offices

HBS - Hardwire Back-up System


HDPE - High-Density PolyEthylene

HEPF-Filter - High-Efficiency Particulate Air Filter

HF - Human Factor

HFT - Hot Functional Test

HMI - Human Machine Interface

HO - Head Office

HP - Hold Point

HPEM - High Power Electromagnetic

HR - Human Resources

HSE - Health Safety Environment

HTP - Heat Treatment Plan

HVAC - Heating Ventilation and Air Conditioning

HVAC - High Voltage Alternating Current

HWBS - Hard Wired Backup System

HX - Heat Exchanger


I - Classified „non-nuclear“ according to YVL Guide 2.1

I&C - Instrumentation and Command

I&C - Instrumentation and Control

Organization (see *):

IAEA International Atomic Energy Agency (rus. МАГАТЭ)

IB - International Business

ICCR - Instrumentation & Control Clarification / Change Request

ICN - I&C Change Note

applicable for Siemencs EFIE

ICT - Information and Communication Technology

ILS - Instrumentation Lances Storage


Organization (see *):

INSAG - International Safety Advisory Group

IO - Inspection Organization (see *):

Organization (see *):

IOLM - International Organization of Legal Metrology

An intergovernmental organization, created in 1955 and based in Paris, to promote the global harmonization of the legal metrology procedures that underpin and facilitate international trade.

IO/M - Inspection Organization (see *):

(Notified Body) contracted by manufacturer(s)

IO/STUK - Inspection Organization (see *):

employed / assigned by STUK

IPI - Internal Project Instruction

IRWST - In-containment refuelling water storage tank

ISI - In-service Inspection

ISI - Internal Site Instruction

ISO - International Standardization Organization (see *):

ITP - Inspection and Test Plan




JEA - Steam generator

JEW -Reactor coolant pump seal injection and leak-off system

JDH - Extra borating system

JMA - Containment liner

JMQ - Containment heat removal system

JN - Safety injection and residual heat removal system

Organization (see *):

JNFL - Japan Nuclear Fuel Limited

JNG - Low head safety injection system

Organization (see *):

JSW - Japan Steel Works

JT - Jominty Test

Jominy Test measures Hardenability of steels. Hardenability is a measure of the capacity of a steel to be hardened in depth when quenched from its austenitizing temperature.

Hardenability of a steel should not be confused with the hardness of a steel.






KKS - German Three-Letter Codes – Kraftwerkskenn - zeichensystem – Plant Indetification System = Plant breakdown structure, Plant Codification System

KMS - Key Milestone Schedule

KO - protocol Report issued by STUK after a commissioning inspection

KOT - Commissioning inspection



Organization (see *):

KTA - Nuclear Safety Standards Commission

Organization (see *):

KURRI - Kyoto University Research Reactor Institute


LBE - Lead-bismuth Eutectic

LCOE - Levelized cost of energy

Cost of electricity by source

LMFBR - Liquid Metal Fast Breeder Reactors

LHSIS - Low Head Safety Injection System

LTIFR - Lost Time Injury Frequency Ratio

LOP - List of Open Points

LP - Large Projects

LPT - Low Power Test

LTA - Lost Time Accident

LV - Low Voltage

LWR - Light Water Reactor


MaDIT - Mass document import tool (DCTM)

MBIR - Multipurpose sodium-cooled fast neutron research reactor

RUS - МБИР - Многоцелевой Быстрый Исследовательский реактор

MCL - Main Coolant Line

MCR - Main Control Room

The MCR must remain available if there is an earthquake; MCR equipment required to ensure safety must operate during an earthquake (i.e. the SICS).

Other areas may be non-operational, but must not prevent the MCR being used, or jeopardise installations with a safety function.

MDC - Minimum Drain Concept

Minimum Drain Concept KTC

Minimum Drain Concept GWH

Mgt Management

Organization (see *):

MHI - Mitsubishi Heavy Industries

MoM - Minute of Meeting MoM

MQD - Manufacturing Quality Documentation


Mtoe - Million of tonnes of oil equivalent

MTS - Main Time Schedule A part of the Plant Contract, the highest level schedule


NAB - Nuclear Auxiliary Building

NEA - Nuclear Energy Agency

NCBA - Not Conformed But Available

NCC - Nuclear Circuit Cleaning

NCR - Non Conformity/Conformance Report

NCI - Nuclear Cleanliness Implementation

NGPF - ??in the document name

NI - Nuclear Island

NP - Nuclear Power

Organization (see *):

NPCIL - Nuclear Power Corporation of IndiA

NPP - Nuclear Power Plant

NPPEPC - Nuclear Power Plant Exporters' Principles of Conduct

NR - Nonconformance Report

NRC - Nuclear Regulatory Comission

NSSS - Nuclear Steam Supply System

NTIW - No Tube In Windows

Organization (see *):

NUSSAG - Nuclear Safety Standards Advisory Group


Organization (see *):

OECD - Organisation for Economic Co-operation and Development

An intergovernmental economic organisation with 35 member countries, founded in 1960 to stimulate economic progress and world trade.


OIO - Operation Integrated Organization (see *):

OIO - Overseas Investment Office

Organization (see *):

OIML - French: Organisation Internationale de Métrologie Légale - OIML same as IOLM

OL3 - Olkiluoto 3

OLA - Operating License Application

OLG - Operating License Granted

OLAR - Operational License Application Radiness

OM - Operating Manual

OM - Operating Manager

ONR - Office for Nuclear Regulation Britain

OP - Open Point

OPMS - Open Point Management System

OTS - Overall Time Schedule


PA - Performance Appraisal

PAC - Preliminary (Provisional) Acceptance Certificate

PTO "Provisional Acceptance Certificate (PAC)

A Provisional Acceptance Certificate (PAC) is an owner’s acceptance certificate to contractor when the contractor achieves the requirements of provisional acceptance (PA) criteria in accordance of the contract terms and conditions.

(Refer to the Mechanical Completion (M/C), Provisional Acceptance (PC), Hand Over, Care, Custody and Control (CCC), Performance Test, Final Acceptance) "



PAR - Preventive Action Request

PCM - Product Change Management

PCS - Plant Codification System Same as KKS

PDMS - Plant Design Management System

PE - Power Escalation

PEHD - PolyEthylene High-Density


PERA - Probabilitic Environmental Risk Assessment

PG - Power Grid

Organization (see *):

PGHO - Приаргунское производственное горно-химическое объединение (ППГХО)

PI - Project Instructions

PIAP - Post Installed Anchor Plates

PIC - Product Item Code

PICS - Process Information and Control System

"Functions of the PICS The PICS has the following fundamental control and information functions:
- relaying digital and analogue information from the process,
- managing all the Unit actuators that can be controlled individually by commands from the MCR,
- displaying the progress and status of processes initiated by commands,
- controlling the I&C functions (automatic sequences, control loops, inputting settings, switching between automatic and manual modes, setting parameters and clearing memory) and displaying the corresponding action logs,
- annunciating and displaying alarms for functions and equipment that impact directly on the control of the process,
- tuning parameters at specific stages, where the tuning relates to the status of the process (if not, the maintenance service does the tuning),
- providing information on the availability and administrative status of actuators and sensors, and
- displaying alarms when equipment necessary to control the process fails, or when events occur that require special attention from the operator or require him to take action manually."


PICS TPX cabinetS

PL - Part List

PL - Punch List

A punch list is a document prepared near the end of a construction project listing work not conforming to contract specifications that the contractor must complete prior to final payment

Punch list

PLDL - Part List-Delivery List

PMCB - Project Management Change Board (Meeting)

POP - Plant Overview Panel

PP - Project Procedure

PP - Physical Protection


PRA - Probabilistic Risk Assessment

Probabilistic risk assessment (PRA) is a systematic and comprehensive methodology to evaluate risks associated with a complex engineered technological entity (such as an airliner or a nuclear power plant) or the effects of stressors on the environment (Probabilitic Environmental Risk Assessment - PERA)


PS - Project Specification

PS - Protection Systems

PSA - Probabilistic Safety Analysis

PSAR - Preliminary Safety Analysis Report

PSC - Plant Station Code Same as KKS

PSRV - Pressurizer Safety Relief Valve

PTO - Preliminary Take Over

PTO - Provisional Take Over

PTS - Partial Time Schedule

PW - Pressure Wave

PWR - Pressurized Water Reactor

PWR is a type of light-water nuclear reactor. PWRs constitute the large majority of the world's nuclear power plants (with notable exceptions being the UK, Japan and Canada).

In a PWR, the primary coolant (water) is pumped under high pressure to the reactor core where it is heated by the energy released by the fission of atoms.

The heated, high pressure water then flows to a steam generator, where it transfers its thermal energy to lower pressure water of a secondary system where steam is generated. The steam then drives turbines, which spin an electric generator.

In contrast to a boiling water reactor ( BWR), pressure in the primary coolant loop prevents the water from boiling within the reactor.

All light-water reactors use ordinary water as both coolant and neutron moderator. Most use anywhere from two to four vertically mounted steam generators; VVER reactors use horizontal steam generators.

PWRs were originally designed to serve as nuclear marine propulsion for nuclear submarines and were used in the original design of the second commercial power plant at Shippingport Atomic Power Station.

PWRs currently operating in the United States are considered Generation II reactors.

Russia's VVER reactors are similar to US PWRs, but the VVER-1200 is not considered Generation II.

France operates many PWRs to generate the bulk of its electricity.


QA - Quality Assurance


QC - Quality Control

QCATS - Quality Control Activities Time Schedule

QCP - Quality Control Plan

QCPCS - Quality Control Plan by Conctreting Section

QCR - Quality Control Records

QI - Quality Inspection

QR - Quality Requirements

QR - Quality Release

QRP - Quality Release Protocol


QMS - Quality Management System


RCP - Reactor Coolant Pump

"The RCPs are part of the Reactor Coolant System (RCS); they are located in the cold leg of each of the four primary loops. RCPs are essential mechanical components for the reactor’s safety.

They provide with a constant flow a forced circulation of water through the RCS. This water circulation removes heat from the reactor core to the steam generators.

The steam produced by the steam generators is then transferred to the turbine island and actuates the turbine to generate electricity. "

RCS - Reactor Coolant System

RFC - Ready for Construction

RFCC - Ready for Commissioning Certificate

RFCC - Residue Fluid Catalytic Cracking

RFE - Release for Execution

RFT - Ready For Testing

RFT - Ready For Training

RHO - Room HandOver

RHRS - Residual Heat Removal System

RMR - Reduced-moderaton Water Reactor

RPV - Reactor Pressure Vessel

(rus. Корпус Высокого Давления)

RPVI - Reactor Pressure Vessel Internals

RRRFR - Russian Research Reactor Fuel Return

RS - Review Sheet

RS - Release for Shipment

RS - Remote Shutdown

RSMS one of the tools management SEE Methods and tools workspace

RSS - Remote Shutdown Station

RSP - Remote Shutdown Panel

RtOM - Relevant to Operation and Maintenance


SBO - Station Black Out

SC - Supply Chain

SCAR - Supplier Corrective Action Request


SCN - Shipment number from VPRM

SCP - System Commissioning Program

SCOC - System Control and Operations Concept


SD - Site Documentation

SE - Safety Engineer

Organization (see *):

SEF - Siemence AG Power Generation

SG - Steam Generator

SICS (TXP SICS) - Safety Information and Control System

The MCR must remain available if there is an earthquake; MCR equipment required to ensure safety must operate during an earthquake (i.e. the SICS).

Other areas may be non-operational, but must not prevent the MCR being used, or jeopardise installations with a safety function.

SL - Surge Line


SPG - Siemence Power Generation

SRP - Standard Repair Plan

Every repair with approved SRP has to be documented. The reports have to be included in the correcponding FIP / FUD / ITP .

STAR - Stop Think Act Report

Organization (see *):

STUK - Radiation and Nuclear Safety Authority Finland (from Finnish Säteilyturvakeskus)


TA - Licensing Documentation Has integral structure, not subdivided into 1-8 groups

TAF - Operation License Documentation

TAP - Construction License Documentation

TBC - To Be Continued

tce - Tonne of coal equivalent Conventional value, based on the amount of energy released by burning one tonne of coal. 1 tce = 0.7 toe = 29,3076 GJ tce

TCM - Technical Coordination Management

TCN - Technical Change Note

TCP - Technical Change Process

TD - Design an Engineering Documentation (Part of Equipment Documentation)

TE - Erection and Commissioning Instructions

TEC - Commissioning Instructions /Programs

TEE - Erection Instructions

Organization (see *):

TEPCO - Tokyo Electric Power Company Holdings, InC

TFD - Test Flow Diagram


TI - Turbine Island

TID - Total Ionizing Dose Поглощённая доза TID


TO - Operation Manual (Overall Plant) Has integral structure, not subdivided into 1-8 groups

TOD - Time of Day

TOD - Terms of Delivery

TOD - Total Oxigen Demand

TOD - Test of Design

toe - Tonne of oil equivalent A unit of energy defined as the amount of energy released by burning one tonne of crude oil. It is approximately 42 gigajoules toe

TOP - Take Over Protocol TOTO Take Over to Temporary Operation

TM - Plant Testing Manual Has integral structure, not subdivided into 1-8 groups

TP - Operation and Maintenance Documentation

TPM - Technical Project Manager

TPM - Equipment Operation and Maintenance Documentation (EOMM)

TPQ - Manufacturing Quality Documentation (Quality Records) Same as EOMR; Final version is sent to TVO (Part of Equipment Documentation)

TS - Technical Specification

TSC - Commissioning Documentation \ activities_records

TSC - Technical Support Center

TSE - Site Erection Documentation

End of Erection Report Same as EER

TSN Taishan

TT - Training Manual

Organization (see *):

TVO - Teollisuuden Voima Oyj

English: Industrial Power Corporation

A Finnish nuclear power company owned by a consortium of power and industrial companies.

TXP ( I&C Operational platform (TXP cabinets))

TXS (I&C Operational platform (TXP cabinets))


Organization (see *):

UKAEA - UK Atomic Energy Authority

UCW - Ultimate Cooling Water


Organization (see *):

USEC - United States Enrichment Company


VA - Vibration Analysis

VC - Values Charter

VCS - Volume Control System


VPE - Vantage Plant Engineering

VPRM - Vantage Project Resouces Management

VT - Valve Team

Organization (see *):

VTT - Finnish Research Center

VVER - Vodo-vodyanoi Energetichesky Reaktor

The water-water energetic reactor (WWER), or VVER (from Russian: водо-водяной энергетический реактор; transliterates as vodo-vodyanoi energetichesky reaktor; water-water power reactor) is a series of pressurized water reactor designs originally developed in the Soviet Union, and now Russia, by OKB Gidropress.

The idea of such a reactor was proposed at the Kurchatov Institute by Savely Moiseevich Feinberg. VVER were originally developed before the 1970s, and have been continually updated.

As a result, the name VVER is associated with a wide variety of reactor designs spanning from generation I reactors to modern generation III+ reactor designs.

Power output ranges from 70 to 1300 MWe, with designs of up to 1700 MWe in development.

The first prototype VVER-210 was built at the Novovoronezh Nuclear Power Plant.

VVER power stations have been mostly installed in Russia and the former Soviet Union, but also in China, Czech Republic, Finland , Germany, Hungary, Slovakia, Bulgaria, India, and Iran.

Countries that are planning to introduce VVER reactors include Bangladesh, Egypt, Jordan, and Turkey.


WBS - Work Breakdown Structure A deliverable-oriented hierachical decomposition of the work to be executed by the project team to accomplish the project objectives and create the required deliverables. It organizes and defines the total scope of the project WBS

WD - Workshop Drawing

Organization (see *):

WENRA - Western European Nuclear Regulators Association

WO - Work Order

WPAR - Weldin Procedure Approval Record

WPS - Welding Procedure Specification

WPQR - Welding Procedure Quality Report

WR - Welding Record

WRSC - Welding Record Summary Certificate



YVL - Guides issued by STUK


List of acronyms used in USSR and Russia is available in - this article


Organizations list is available - here

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