1. Nuclear thermal capacity (P(th), MW(th)) Reactor nuclear thermal capacity
(as derived from a heat balance measurement on the reactor primary coolant system).
2. Maximum electrical capacity of a nuclear station (P
gor P
n, MW(e))
The 'maximum capacity of a nuclear station' is the maximum power that could be maintained or is authorized to be maintained throughout a period of continuous operation, in practice 15 hours or longer. It is specified that this value must remain constant for a given unit unless, following permanent modification, or a new permanent authorization, the management of the undertaking decides to amend the original value.
Electrical capacity may be gross of net:
– The gross capacity (P
g, MW(e)) is deemed to be measured at the output terminals of all generator sets in the station; it includes therefore the power taken by the station auxiliaries and losses in transformers that are considered integral parts of the station.
– The net capacity (P
n, MW(e)), indicating the maximum power that can be supplied, is measured at the station outlet terminals, i.e. after deducting the power taken by station auxiliaries and the losses in the transformers that are considered integral parts of the station.
It is recognized that the maximum capacity may be set by an authorized maximum thermal capacity and in these cases the 'reference' maximum net electrical capacities corresponding to the authorized maximum thermal capacity should be used for simplicity in the calculations.
3. Reference period (T, hours)
For units in power ascension at the end of the period, the clock hours from the beginning of the period or the first electrical production, whichever comes last, to the end of the period.
For units in commercial operation at the end of the period, the clock hours from the beginning of the period or of commercial operation, whichever comes last, to the end of the period or permanent shutdown, whichever comes first.
4. On-line hours (t, hours)
The total clock hours in the reference period during which the unit operated with breakers closed to the station bus.
5. Maximum net energy produced (E
m,MW(e)·h)
Net electrical energy which would have been produced at maximum capacity
under continuous operation during the whole of the reference period.
Electrical output of the unit during the reference period as measured at the station outlet terminals, i.e. after deducting the electrical energy taken by station auxiliaries and the losses in the transformers that are considered integral parts of the station. If this quantity is less than zero, zero is reported.
7. Load factor (LF, %) E 100
= E LF
m
× E = net energy produced ((MW(e)·h)
E
m= maximum net energy produced (MW(e)·h) The load factor for a unit or station for a given period of time is the ratio of the energy that it produced during the period considered to the energy that it could have produced at maximum capacity under continuous operation during the whole of that period.
8. Operation factor (OF, %) T 100
= t
OF × t = number of hours on-line (h) (MW(e)·h) T = number of hours in the reference period (h)0 The operation factor is the ratio between the number of hours the unit or station was on-line and the total number of hours in the reference period.
9. Available capacity (P, MW)
The available capacity at a given moment is the maximum capacity at which the station can be or is authorized to be operated at a continuous rating under the prevailing conditions assuming unlimited transmission facilities.
10. Energy loss (EL, MW(e)·h)
Energy loss is the energy which could have been produced during the reference period by the unavailable capacity; it is categorized into three types – ELP, ELU and ELX – i.e. energy loss planned, energy loss unplanned due to causes in the plant and energy loss unplanned due to causes external to the plant.
11. Unavailability
Unavailability means that the available capacity is lower than the maximum capacity. Unavailability is classified as planned if it is foreseen at least 1–3 months in advance, generally at the time when the annual overhaul programme is established, and if the beginning of the unavailability period can be largely controlled and deferred by management. Unavailability is classified as unplanned when it is due either to causes in the plant or causes external to the plant. Power plant operation at lower than maximum capacity because of lower demand from the grid (other than stretch-out operations) but available to operate at the maximum capacity, does not constitute unavailability, either planned or unplanned.
12. Energy unavailability (EUF, %) E 100
= EL EUF
m
×
20
could have been produced during this period by a capacity equal to the unavailable capacity P and the energy E
mthat could have been produced during the same period by the maximum capacity.
The energy unavailability factor EUF over a specified period can be divided into:
PUF = planned unavailability factor
UUF = unplanned unavailability factor due to causes in the plant
XUF = unplanned unavailability factor due to causes external to the plant.
13. Energy availability factor (EAF, %) EAF = 100 – EUF
14. Unit capability factor (UCF, %)
UCF = (REG - PEL - UEL) x 100 % REG
15. Construction start
Date when first major placing of concrete, usually for the base mat of the reactor building, is done.
16. First criticality
Date when the reactor is made critical for the first time.
17. Grid connection
Date when the plant is first connected to the electrical grid for supply of power.
18. Commercial operation
Date when the plant is handed over by the contractors to the owner and declared officially to be in commercial operation.
19. Shutdown
Date when the plant is officially declared shut down by the owner and taken out of operation permanently.
20. Significant outages
A significant outage is a power reduction resulting in a loss of energy corresponding to at least ten hours of continuous operation at maximum capacity.
(When reported to the IAEA, outages smaller than significant ones are also included in the report.)
21. Outage duration (hours)
The total clock hours of the outage measured from the beginning of the reference period or the outage, whichever comes last, to the end of the reference period or the outage, whichever comes first.
22. Factors refer to the plants which were in commercial operation during the whole of the reference period.
23. Cumulative factors are given for the plants which were in commercial operation
during full calendar years.
24. A blank and three periods (...), if used in tables, denote information that is not applicable or not available, respectively.
25. Types of outages
Outages or unavailabilities are categorized as full or partial. The outage/unavailability is considered full when net power is reduced to zero per cent. The outage/unavailability is considered partial when the available capacity is lower than the maximum net capacity. The following abbreviations are used to indicate the type of outage.
First digit:
P = planned outage U = unplanned outage
X = outage due to causes not attributable to the plant itself.
Examples:
– shortage of fuel – shortage of water
– special testing caused by experience at other plants – requirements of manufacturers, especially for new plants – staff shortages and strikes
– regulatory requirements.
Second digit:
F = full outage P = partial outage.
Third digit:
1 = Controlled shutdown or load reduction that could be deferred but had to be performed earlier than four weeks after the cause occurred or before the next refuelling outage, whatever comes first
2 = Controlled shutdown or load reduction that had to be performed in the next 24 hours after the cause occurred
3 = Outage extension
4 = Reactor scram, automatic 5 = Reactor scram, manual
26. Main causes of outages/unavailabilities (full or partial) (A) Plant equipment failure
(B) Refuelling without a maintenance
(C) Inspection, maintenance or repair combined with refuelling (D) Inspection, maintenance or repair without refuelling
(E) Testing of plant systems or components
(F) Major back-fitting, refurbishment or upgrading activities with refuelling (G) Major back-fitting, refurbishment or upgrading activities without refuelling (H) Nuclear regulatory requirements
(J) Grid failure or grid unavailability
(K) Load-following (frequency control, reserve shutdown due to reduced energy demand)
(L) Human factor related
(M) Governmental requirements or Court decisions
(N) Environmental conditions (flood, storm, lightning, lack of cooling water due to dry weather, cooling water temperature limits etc.)
(P) Fire
22
payments from customers, disputes in fuel industries, fuel-rationing, labour strike outside the plant
1, spare part delivery problems etc.)
(S) Fuel management limitation (including high flux tilt, stretch out or coast-down operation)
(T) Offsite heat distribution system unavailability
(U) Security and access control and other preventive shutdown due to external threats
(Z) Others
27. Plant systems affected Nuclear System
11 Reactor and accessories Includes:
Reactor vessel and main shielding Reactor core (including fuel assemblies0
Reactor internals (including steam separators/dryers) Auxiliary shielding and heat insulation
Moderator and auxiliaries (PHWR) Annulus gas system (PHWR/RBMK) Non of them above system
12 Reactor instrumentation and control (I&C) systems Includes:
Control and safety rods and drives
Neutron monitoring (in-core plus external) Reactor instrumentation (except neutron) Reactor control system
Reactor protection system Process computer
Reactor recirculation control (BWR) Non of them above system
13 Reactor Auxiliary Systems Includes:
Primary coolant treatment and cleanup system (BWR and GCR) Chemical and volume control system (PWR)
Residual heat removal system (including heat exchangers) Component cooling system
Gaseous, liquid and solid radwaste treatment
Nuclear building ventilation and containment inerting systems
Nuclear equipment venting and drainage system (including room floor drainage) Borated or refuelling water storage system
CO
2injection and storage system (GCR) Sodium heating system (FBR)
Primary pump oil system (including RCP or make-up pump oil) D
2O leakage collection and dryer system (PHWR)
Essential auxiliary system (GCR)
Non of them above system
Includes:
Emergency core cooling systems (including accumulators and core spray system) High pressure safety injection and emergency poisoning system
Auxiliary and emergency feedwater system Containment spray system (active)
Containment pressure suppression system (passive)
Containment isolation system (isolation valves, doors, locks and penetrations) Containment structures
Fire protection system None of the above systems 15 Reactor cooling system Includes:
Reactor coolant pumps/blowers and drives
Reactor coolant piping (including associated valves)
Reactor coolant safety and relief valves (including relief tank) Reactor coolant pressure control system
Main steam piping and isolation valves (BWR) None of the above systems
16 Steam generation system Includes:
Steam generator (PWR), boiler (PHWR, AGR), steam drum vessel (RBMK, BWR)
Steam generator blow-down system
Steam drum level control system (RBMK, BWR) None of the above systems
17 Safety I&C systems (excluding reactor I&C) Includes:
Engineered safeguard feature actuation system Fire detection system
Containment isolation function
Main steam/feedwater isolation function
Main steam pressure emergency control system (turbine bypass and steam dump valve control)
Failed fuel detection system (DN monitoring system for PHWR) RCS integrity monitoring system (RBMK)
None of the above systems
Fuel and Refuelling System
21 Fuel Handling and Storage Facilities Includes:
On-power refuelling machine Fuel transfer system
Storage facilities, including treatment plant and final loading and cask handling facilities
None of the above systems Secondary Plant System
31 Turbine and auxiliaries
24
Turbine
Moisture separator and re-heater Control valves and turbine stop valves Turbine control valves and stop valves Main condenser (including vacuum system) Turbine by-pass valves
Turbine auxiliaries (lubricating oil, gland steam, steam extraction) Turbine control and protection system
None of the above systems
32 Feedwater and Main Steam System Includes:
Main steam piping and valves Main steam safety and relief valves
Feedwater system (including feedwater tank, piping, pumps and heaters) Condensate system (including condensate pumps, piping and heaters) Condensate treatment system
None of the above systems 33 Circulating water system Includes:
Circulating water system (pumps and piping/ducts excluding heat sink system) Cooling towers / heat sink system
Emergency ultimate heat sink system None of the above systems
34 Miscellaneous systems Includes:
Compressed air (essential and non-essential / high-pressure and low-pressure) Gas storage, supply and cleanup systems (nitrogen, hydrogen, carbon dioxide etc.)
Service water / process water supply system (including water treatment) Demineralized water supply system (including water treatment)
Auxiliary steam supply system (including boilers and pressure control equipment)
Non-nuclear area ventilation (including main control room) Chilled water supply system
Chemical additive injection and makeup systems Non-nuclear equipment venting and drainage system Communication system
None of the above systems 35 All other I&C systems
Includes:
Plant process monitoring systems (excluding process computer) Leak monitoring systems
Alarm annunciation system Plant radiation monitoring system Plant process control systems None of the above systems Electrical System
41 Main generator
Includes:
Generator and exciter (including generator output breaker) Sealing oil system
Rotor cooling gas system 42 Electrical power supply systems Includes:
Main transformers
Unit self-consumption transformers (station, auxiliary, house reserve etc.) Vital AC and DC plant power supply systems (medium and low voltage) Non-vital AC plant power supply system (medium and low voltage)
Emergency power generation system (e.g. emergency diesel generator and auxiliaries)
Power supply system logics (including load shed logic, emergency bus transfer logic, load sequencer logic, breaker trip logic etc.)
Plant switchyard equipment None of the above systems
26
0 2000 4000 6000 8000 10000
1958 1963 1968 1973 1978 1983 1988 1993 1998 2003
Cumulative Reactor-Years
The future potential
Data unavailable to the IAEA
Data available in IAEA PRIS
Figure 2 — Lifetime Energy Availability Factors up to 2003
(only reactors with capacity greater than 100 MW(e) and with more than one year of commercial operation)
Figure 3 — Reactors with High Availability Factors
13
42
3 0 0 2 3
1
20
72
61
13
0 0
20 40 60 80
< 30% 30 – 35% 35 – 40% 40 – 45% 45 – 50% 50 – 55% 55 – 60% 60 – 65% 65 – 70% 70 – 75% 75 – 80% 80 – 85% 85 – 90% 90 – 95% > 95%
Energy Availability Factor Range
Number of Reactors
0 20 40 60 80 100
1986 1988 1990 1992 1994 1996 1998 2000 2002
% of Reactors
70 – 79% 80 – 89% 90 – 100%
28
Figure 4 — Average Energy Availability Factors
79
81 82 83 84
81
73
75 74
72 73 74 74 74
76
79 78 77
0 10 20 30 40 50 60 70 80 90
1986 1988 1990 1992 1994 1996 1998 2000 2002
Energy Availability Factor (%)
Figure 5 — Number of Reactors in Operation (as of 1 January 2004)
Note: There were 6 reactors in operation in Taiwan, China.
Figure 6 — Number of Reactors by Age (as of 1 January 2004)
59 KOREA RP GERMANY CZECH R.
SLOVAKIA
Number of Reactors
2
Reactor Age (years)
Number of Reactors
30
5. ABBREVIATIONS
COUNTRY CODES
AM ARMENIA AR ARGENTINA BE BELGIUM BG BULGARIA BR BRAZIL CA CANADA CH SWITZERLAND CN CHINA
CZ CZECH REPUBLIC
DE GERMANY ES SPAIN FI FINLAND FR FRANCE
GB UNITED KINGDOM
HU HUNGARY IN INDIA JP JAPAN KR KOREA, REPUBLIC OF
KZ KAZAKHSTAN LT LITHUANIA, REPUBLIC OF MX MEXICO NL NETHERLANDS PK PAKISTAN RO ROMANIA
RU RUSSIAN FEDERATION
SE SWEDEN SI SLOVENIA
SK SLOVAK REPUBLIC
TW TAIWAN, CHINA
UA UKRAINE US UNITED STATES OF AMERICA
ZA SOUTH AFRICA
REACTOR TYPES
ABWR Advanced Boiling Light-Water-Cooled and Moderated Reactor AGR Advanced Gas-Cooled, Graphite-Moderated Reactor BWR Boiling Light-Water-Cooled and Moderated Reactor FBR Fast Breeder Reactor
GCR Gas-Cooled, Graphite-Moderated Reactor
HTGR High-Temperature Gas-Cooled, Graphite-Moderated Reactor HWGCR Heavy-Water-Moderated, Gas-Cooled Reactor
HWLWR Heavy-Water-Moderated, Boiling Light-Water-Cooled Reactor LWGR Light-Water-Cooled, Graphite-Moderated Reactor
PHWR Pressurized Heavy-Water-Moderated and Cooled Reactor PWR Pressurized Light-Water-Moderated and Cooled Reactor SGHWR Steam-Generating Heavy-Water Reactor
WWER Water Cooled Water Moderated Power Reactor
OPERATORS
AMEREN AMEREN AMERGEN AMERGEN ENERGY CO.
ANAV ASOCIACION NUCLEAR ASCO-VANDELLOS A.I.E.
(ENDESA/ID)
ANPP ARIZONA NUCLEAR POWER PROJECT
BE BRITISH ENERGY
BKAB BARSEBECK KRAFT AB BKW BKW ENERGIE AG
BNFL BRITISH NUCLEAR FUELS PLC
BRUCEPOW BRUCE POWER
CEA/EDF COMMISSARIAT A L'ENERGIE ATOMIQUE / ELECTRICITE DE FRANCE
CEZ CZECH POWER COMPANY , CEZ A.S.
CFE COMISION FEDERAL DE ELECTRICIDAD
CHUGOKU CHUGOKU ELECTRIC POWER CO.
CNAT CENTRALES NUCLEARES ALMARAZ- TRILLO(ID/UFG/ENDESA/HC/NUCLENOR ) CONST CONSTELLATION NUCLEAR GROUP DETED DETROIT EDISON CO.
DOMIN DOMINION VIRGINIA POWER DUKE DUKE POWER CO.
EBO ELECTROSTATION BOHUNICE
EDF ELECTRICITE DE FRANCE
ELECTRAB ELECTRABEL M. V. NUCLEAIRE PRODUKTIE ELETRONU ELETROBRAS TERMONUCLEAR SA –
ELETRONUCLEAR
EMO ELECTROSTATION MOCHOVCE
EnBW ENBW KRAFTWERK AG
ENERGYNW ENERGY NORTWEST
ENTERGY ENTERGY NUCLEAR
EON EON KERNKRAFT GES.M.B.H
EPZ N.V. ELEKTRICITEITS-PRODUKTIEMAATSCHAPPIJ ZUID-NEDERLAND
ESKOM ESKOM EXELON EXELON NUCLEAR CO.
FENOC FIRST ENERGY NUCLEAR OPERATING CO.
FKA FORSMARK KRAFTGRUPP AB
FORTUMPH FORTUM POWER AND HEAT OY (FORMER IVO) FPL FLORIDA POWER & LIGHT CO.
GNPJVC GUANDONG NUCLEAR POWER JOINT VENTURE COMPANY LIMITED(GNPJVC)
HEPCO HOKKAIDO ELECTRIC POWER CO.
HEW HAMBURGISCHE ELEKTRIZITAETSWERKE
HOKURIKU HOKURIKU ELECTRIC POWER CO.
HQ HYDRO QUEBEC
ID IBERDROLA, S.A.
IMPCO INDIANA MICHIGAN POWER CO.
INPP IGNALINA NUCLEAR POWER PLANT JAPCO JAPAN ATOMIC POWER CO.
JNC JAPAN NUCLEAR CYCLE DEVELOPEMENT INSTITUTE JSC JOINT STOCK COMPANY ARMENIA NPP
KEPCO KANSAI ELECTRIC POWER CO.
KHNP KOREA HYDRO AND NUCLEAR POWER CO.
KKG KERNKRAFTWERK GOESGEN-DAENIKEN AG
KKL KERNKRAFTWERK LEIBSTADT
KYUSHU KYUSHU ELECTRIC POWER CO.
LANPC LINGAO NUCLEAR POWER COMPANY LTD.
NASA NUCLEOELECTRICA ARGENTINA S.A.
NBEPC NEW BRUNSWICK ELECTRIC POWER COMMISSION NEC NATIONAL ELECTRICITY COMPANY, BRANCH NPP-
KOZLODUY
NEK NUKLEARNA ELEKTRARNA KRSKO
NNEGC NATIONAL NUCLEAR ENERGY GENERATING COMPANY <ENERGOATOM>
NOK NORDOSTSCHWEIZERISCHE KRAFTWERKE
NPCIL NUCLEAR POWER CORPORATION OF INDIA LTD.
NPPD NEBRASKA PUBLIC POWER DISTRICT
NPQJVC NUCLEAR POWER PLANT QINSHAN JOINT VENTURE COMPANY LTD.
NUCLENOR NUCLENOR, S.A.
NUCMAN NUCLEAR MANAGEMENT CO.
OKG OKG AKTIEBOLAG
OPG ONTARIO POWER GENERATION OPPD OMAHA PUBLIC POWER DISTRICT PAEC PAKISTAN ATOMIC ENERGY COMMISSION PAKS RT. PAKS NUCLEAR POWER PLANT LTD PGE PACIFIC GAS & ELECTRIC CO.
PP&L PENNSYLVANIA POWER & LIGHT CO.
PROGRESS PROGRESS ENERGY CORPORATION PSEG PUBLIC SERVICE ELECTRIC & GAS CO.
QNPC QINSHAN NUCLEAR POWER COMPANY
RAB RINGHALS AB
REA ROSENERGOATOM, CONSORTIUM
RGE ROCHESTER GAS & ELECTRIC CORP.
RWE RWE ENERGIE AG
SCE SOUTHERN CALIFORNIA EDISON SCEG SOUTH CAROLINA ELECTRIC & GAS CO.
SHIKOKU SHIKOKU ELECTRIC POWER CO.
SNN SOCIETATEA NATIONALA NUCLEARELECTRICA S.A.
SOUTH SOUTHERN NUCLEAR OPERATING CO.
32
TEPCO TOKYO ELECTRIC POWER CO.
TOHOKU TOHOKU ELECTRIC POWER CO.
TPC TAI POWER CO.
TQNPC THE THIRD QINSHAN JOINTED VENTURE COMPANY LTD.
TVA TENNESSEE VALLEY AUTHORITY TVO TEOLLISUUDEN VOIMA OY TXU TXU ELECTRIC CO.
UFG UNION FENOSA GENERATION S.A.
WOLF WOLF CREEK NUCLEAR OPERATION CORP.
CONTRACTORS
AA ALSTHOM ATLANTIQUE
ABBATOM ABBATOM (formerly ASEA-ATOM)
ACECOWEN ACECOWEN ( ACEC-COCKERILL-WESTINGHOUSE ) ACLF (ACECOWEN - CREUSOT LOIRE - FRAMATOME) AECL ATOMIC ENERGY OF CANADA LTD.
AECL/DAE ATOMIC ENERGY OF CANADA Ltda AND DEPARTMENT OF ATOMIC ENERGY(INDIA)
AECL/DHI ATOMIC ENERGY OF CANADA LTD./DOOSAN HEAVY INDUSTRY &
CONSTRUCTION
AEE ATOMENERGOEXPORT APC ATOMIC POWER CONSTRUCTION LTD.
ASEASTAL ASEA-ATOM / STAL-LAVAL B&W BABCOCK & WILCOX CO.
BBC BROWN BOVERI ET CIE
CE COMBUSTION ENGINEERING CO.
CGE CANADIAN GENERAL ELECTRIC
CNCLNEY CNIM-CONSTRUCTIONS NAVALES ET INDUSTRIELLES DE MEDITERRANEE CL - CREUSOT LOIRE , NEY - NEYRPIC CNNC CHINA NATIONAL NUCLEAR CORPORATION
DHICKAEC DOOSAN HEAVY INDUSTRIES & CONSTRUCTION CO.LTD./KOREA ATOMICENERGY RESEARCH INSTITUTE/COMBUSTIONENGINEERING DHICKOPC DOOSAN HEAVY INDUSTRIES & CONSTRUCTION CO.LTD./KOREA
POWER ENGINEERING COMPANY/COMBUSTIONENGINEERING EE/B&W/T THE ENGLISH ELECTRIC CO. LTD / BABCOCK & WILCOX CO. /
TAYLOR WOODROW CONSTRUCTION LTD.
FRAM FRAMATOME
FRAMACEC FRAMACECO ( FRAMATOME-ACEC-COCKERILL ) GE GENERAL ELECTRIC COMPANY (US)
GEC GENERAL ELECTRIC COMPANY (UK)
GETSCO GENERAL ELECTRIC TECHNICAL SERVICES CO.
HITA/GE HITACHI LTD./GENERAL ELECTRIC CO.
HITACHI HITACHI LTD.
KWU SIEMENS KRAFTWERK UNION AG KWU/STOR KRAFTWERK UNION AG / STORK M MITSUBISHI HEAVY INDUSTRY LTD
MAEP MINATOMENERGOPROM, MINISTRY OF NUCLEAR POWER AND INDUSTRY
MNE MINISTRY OF NUCLEAR ENERGY OF RUSSIAN FEDERATION
NEI.P NEI PARSONS
NNC NATIONAL NUCLEAR CORPORATION NPC NUCLEAR POWER CO. LTD.
NPCIL NUCLEAR POWER CORPORATION OF INDIA LTD.
OH/AECL ONTARIO HYDRO / ATOMIC ENERGY OF CANADA LTD.
PAA PRODUCTION AMALGAMATION 'ATOMMASH', VOLGODONSK PAIP PRODUCTION AMALGAMATION IZHORSKY PLANT
ATOMMASH,VOLGODONSK,RUSSIA PPC PWR POWER PROJECTS
SIEM,KWU SIEMENS AG, KRAFTWERK UNION AG
SIEMENS SIEMENS AG
SKODA SKODA CONCERN NUCLEAR POWER PLANT WORKS TNPG THE NUCLEAR POWER GROUP LTD.
TOSHI/GE TOSHIBA CORPORATION/GENERAL ELECTRIC CO.
TOSHIBA TOSHIBA CORPORATION
UKAEA UNITED KINGDOM ATOMIC ENERGY AUTHORITY WEST WESTINGHOUSE ELECTRIC CORPORATION
6. DATA SHEETS ON
INDIVIDUAL NUCLEAR POWER STATIONS UNITS
1. 2.
Unit Capability Factor (in %)
Cumul.
Energy GW(e).h
Performance for Full Years of Commercial Operation
5600 63.9
1983
Energy Availability
Factor (in %) Load Factor (in %) Annual Time Online Capacity
MW(e)
Annual Cumul. Annual
77.8 59.8 77.7
1982 335.0 59.2 77.8 59.2
Annual Cumul. Hours of (%) 2666 hours
67.2%
Cumulative Load Factor:
Cumulative Unit Capability Factor:
Year
1753.6
31.2%
Total Off–line Time:
58066.2 GW(e).h 70.2%
19 Mar 1974
29.8%
Cumulative Energy Unavailability Factor:
Lifetime Generation:
Cumulative Energy Availability Factor:
77.1%
Historical Summary
Date of Commercial Operation:
Date of First Criticality:
Date of Grid Connection:
Date of Construction Start:
24 Jun 1974 01 Jun 1968 13 Jan 1974
2003 Monthly Performance Data
2003 Summary of Operation
7.2
UCLF replaces previously used UUF.
0.0 0.0 0.0 0.0
100.0 93.3 0.2 26.9
52.9 76.3 91.4 100.0 100.0 100.0 99.9 100.0 55.6 100.0 100.0 53.6 73.9 89.8 100.8 100.6 100.4 99.7 99.3
88.9 100.0 100.0 100.0
0.0 6.7 99.8 73.1
100.0 100.0 100.0 53.6 99.5
239.6 131.8 0.0 6.7 99.8 73.1 88.9 100.0 100.0
0.0 8.3 100.1
Nov Feb
0.0 16.0 239.8
0.0 6.4
250.7 242.0 248.7 Jan
0.0 184.2 216.6 251.3
0.0
May Jun Jul Aug Sep Oct Dec Annual
AR-1 ATUCHA-1
Operator:
Contractor: SIEMENS (SIEMENS AG)
NASA (NUCLEOELECTRICA ARGENTINA S.A.)
68.8%
68.9%
69.6%
Production Summary 2003
Energy Production: 2020.6 GW(e).h
Station Details
PHWR
Energy Availability Factor:
Design Discharge Burnup:
335.0 MW(e) 319.0 MW(e) 5600 MW.d/t
Load Factor:
Operating Factor:
Energy Unavailability Factor:
Type:
Maximum Net Capacity at the beginning of 2003:
Design Net Capacity:
EAF UCF
Mar Apr
0.0 0.0
2356.0 335.0 78.4 77.9 78.4 77.9 80.3 78.0 8101 92.5
1984 1706.1 335.0 98.7 80.0 98.7 80.0 58.0 75.9 8678 98.8
67.2 3030 34.6
68.9 67.2
72.3 68.8 70.2
6.
7.
A.
B.
C.
D.
E.
H.
J.
K.
8.
Date Hours GW(e).h Type Code 01 Jan 2112.0 707.5
2003 Outages
Description
PF D11 REPLACEMENT OF FUEL CHANNELS AND CONTROL RODS GUIDE TUBES, INSTALLATION
AR-1 ATUCHA-1
AND COMISSIONING OF A NEW EMERGENCY FEEDWATER SYSTEM AND TURBINE INSPECTION
AND COMISSIONING OF A NEW EMERGENCY FEEDWATER SYSTEM AND TURBINE INSPECTION